ML22179A343

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2018 PI Ile ES-401-2 & ES-401-3
ML22179A343
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 05/27/2018
From: Randy Baker
NRC/RGN-III/DRS/OLB
To:
Nuclear Management Co
Baker R
Shared Package
ML17165A321 List:
References
Download: ML22179A343 (21)
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Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Prairie Island Date of Exam: SEPTEMBER 10, 2018 RO K/A Category Points SRO-Only Points Tier Group Total K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* A2 G*

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 3 2 2 3 2 1 3 3 3 3 3 28 3 2 5 2.

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

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

P8184L-004 109 (R1)

Breakers, relays, and disconnects 008 Pressurizer Vapor Space Accident 000008 Pressurizer Vapor Space Accident / x AK3.03: 4.1 1 3 Knowledge of the reasons for the following responses as they apply to the Pressurizer Vapor Space Accident:

P8197L-012 259 (R2)

Actions contained in EOP for PZR vapor space accident/LOCA 009 Small Break LOCA 000009 Small Break LOCA / 3 x EA1.11: 4.1 1 Ability to operate and monitor the following as they apply to a P8180L-007 227 (R3) small break LOCA:

AFW/MFW 000011 Large Break LOCA / 3 015 RCP Malfunctions 000015 RCP Malfunctions / 4 x AA2.01: 3.0 1 Ability to determine and interpret the following as they apply to P8170L-002 151 (R4) the Reactor Coolant Pump Malfunctions:

Cause of RCP failure 000022 Loss of Rx Coolant Makeup / 2 000025 Loss of RHR System / 4 026 Loss of Component Cooling Water 000026 Loss of Component Cooling Water / x AK3.03: 4.0 1 8 Knowledge of the reasons for the following responses as they apply to the Loss of Component Cooling Water:

P8172L-002 205 (R5)

Guidance actions contained in EOP for Loss of CCW 027 Pressurizer Pressure Control System Malfunction 000027 Pressurizer Pressure Control x AK3.03: 3.7 1 System Malfunction / 3 Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control Malfunctions:

P8197L-011 143 (R6)

Actions contained in EOP for PZR PCS malfunction 029 ATWS 000029 ATWS / 1 x 2.1.20: 4.6 1 Ability to interpret and execute procedure steps P8197L-014 183 (R7) 038 Steam Generator Tube Rupture 000038 Steam Gen. Tube Rupture / 3 x EK1.01: 3.1 1 Knowledge of the operational implications of the following P8197L-013 121 (R8) concepts as they apply to the SGTR:

Use of steam tables Westinghouse E12 Uncontrolled Depressurization of all W/E12 Steam Line Rupture - Excessive x Steam Generators 3.6 1 Heat Transfer / 4 EA1.2:

Operating behavior characteristics of the facility P8197L-012 260 (R9)

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

  • 054 Loss of Main Feedwater (MFW) 000054 Loss of Main Feedwater / 4 x AA2.02: 4.1 1 Ability to determine and interpret the following as they apply to P8174L-003 123 (R10) the Loss of Main Feedwater(MFW):

Differentiation between loss of all MFW and trip of one MFW pump.

055 Loss of Offsite and Onsite Power (Station Blackout) 000055 Station Blackout / 6 x 2.4.49: 4.6 1 Ability to perform without reference to procedures those P8140L-224 006 (R11) actions that require immediate operation of system components and controls 056 Loss of Offsite Power 000056 Loss of Off-site Power / 6 x AK1.01: 3.1* 1 Knowledge of the operational implications of the following P8170L-003 224 (R12) concepts as they apply to Loss of Offsite Power:

Principle of cooling by natural convection.

000057 Loss of Vital AC Inst. Bus / 6 058 Loss of DC Power 000058 Loss of DC Power / 6 x AK2.02: 2.2* 1 Knowledge of the interrelations between the Loss of DC P8186L-005 044 (R13)

Power and the following:

Breakers, relays, and disconnects 062 Loss of Nuclear Service Water 000062 Loss of Nuclear Svc Water / 4 x AK3.02: 3.6 1 Knowledge of the reasons for the following responses as they P8176L-003 084 (R14) apply to the Loss of Nuclear Service Water:

The automatic actions (alignments) within the nuclear service water resulting from the actuation of the ESFAS 065 Loss of Instrument Air 000065 Loss of Instrument Air / 8 x AA1.05: 3.3* 1 Ability to operate and / or monitor the following as they apply P8178L-005 054 (R15) to the Loss of Instrument Air:

RPS 077 Generator Voltage and Electric Grid Distrurbances 000077 Generator Voltage and Electric Grid x AA2.07: 3.6 1 Disturbances / 6 Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances:

P8186L-009 011 (R16)

Operational status of engineered safety features W/E04 LOCA Outside Containment / 3 Westinghouse E11 Loss of Emergency Coolant Recirc W/E11 Loss of Emergency Coolant Recirc. / x 2.2.38: 3.6 1 4 Knowledge of conditions and limitations in the facility license P8197L-012 261 (R17)

Westinghouse E05 Loss of Secondary Heat Sink W/E05 Inadequate Heat Transfer - Loss x EK1.2: 3.9 1 of Secondary Heat Sink / 4 Knowledge of the operational implications of the following concepts as they apply to the (Loss of Secondary Heat Sink)

P8197L-014 208 (R18)

Normal, abnormal, and emergency operating procedures associated with (Loss of Secondary Heat Sink)

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

ES-401 4 Form ES-401-2 ES-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

3.6 1 P8184L-005 095 (R19) Ability to operate and / or monitor the following as they apply to the Dropped Control Rod:

Rod control switches 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 028 Pressurizer (PZR) Level Control Malfunction 000028 Pressurizer Level Malfunction / 2 x AK1.01 2.8* 1 P8170L-006 065 (R20) Knowledge of the operational implications of the following concepts as they apply to Pressurizer Level Control Malfunctions:

PZR reference leak abnormalities 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 Fuel Handling Incidents / 8 000037 Steam Generator Tube Leak / 3 051 Loss of Condenser Vacuum 000051 Loss of Condenser Vacuum / 4 x AA2.02 3.9 1 P8174L-005 029 (R21) Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum:

Conditions requiring reactor and / or turbine trip 000059 Accidental Liquid Radwaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. /

9 061 Area Radiation Monitoring (ARM) System Alarms 000061 ARM System Alarms / 7 x 2.1.32: 3.8 1 P8182L-002 059 (R22) Ability to explain and apply system limits and precautions 000067 Plant Fire On-site / 8 068 Control Room Evacuation 000068 Control Room Evac. / 8 x AA1.29 3.1* 1 P8197L-008 016 (R23) Ability to operate and / or monitor the following as they apply to the Control Room Evacuation:

Calculation of boron needed for xenon-free shutdown.

W/E14 Loss of CTMT Integrity / 5

ES-401 5 Form ES-401-2 ES-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

  • Westinghouse E06 Degraded Core Cooling W/E06 & E07 Inad. Core Cooling / 4 x EA2.2:

3.5 1 P8197L-014 216 (R24) Ability to determine and interpret the following as they apply to the (Degraded Core Cooling)

Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments 076 High Reactor Coolant Activity 000076 High Reactor Coolant Activity / 9 x 2.1.27 3.9 1 P8172L-001A 148 (R25) Knowledge of system purpose and / or function.

000078 RCS Leak / 3 Westinghouse E01 Rediagnosis W/E01 & E02 Rediagnosis & SI Termination x EK2.2 3.5 1

/3 Knowledge of the interrelations between the (Reactor Trip or P8180L-007 106 (R26) Safety Injection/Rediagnosis) and the following:

Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 W/E16 High Containment Radiation / 9 W/E03 LOCA Cooldown - Depress. / 4 W/E09 & E10 Natural Circ. / 4 Westinghouse E08 Pressurized Thermal Shock W/E08 RCS Overcooling - PTS / 4 x EK3.1 3.4 1 P8197L-014 217 (R27) Knowledge of the reasons for the following responses as they apply to the (Pressurized Thermal Shock)

Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.

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

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

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

1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump 003 Reactor Coolant Pump x x K3.04 3.6* 2 Knowledge of the effect that a loss or P8184L-004 114 (R28) malfunction of the RCPS will have on the following:

RPS A2.01 P8172L-002 103 (R29) Ability to (a) predict the impacts of the following 3.5 malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Problems with RCP seals, especially rates of seal leak-off 004 Chemical and Volume Control System 004 Chemical and Volume Control x (CVCS) 2.8 1 K4.03 P8172L-001A 040 (R30) Knowledge of CVCS design feature(s) and / or Interlock(s) which provide for the following:

Protection of ion exchangers (high letdown temperature will isolate ion exchangers) 005 Residual Heat Removal System (RHRS) 005 Residual Heat Removal x K5.03 2.9* 1 Knowledge of the operational implications of the P8140L-204 035 (R31) following concepts as they apply the RHRS:

Reactivity effects of RHR fill water Emergency Core Cooling System (ECCS) 006 Emergency Core Cooling x K6.03 3.6 1 Knowledge of the effect of a loss or malfunction P8180L-004 060 (R32) on the following will have on the ECCS:

Safety Injection Pumps 007 Pressurizer Relief Tank/Quench Tank 007 Pressurizer Relief/Quench Tank x System (PRTS) 2.9 1 A1.01 P8170L-003 129 (R33) Ability to predict and / or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS controls including:

Maintaining quench tank water level within limits 008 Component Cooling Water System 008 Component Cooling Water x x (CCWS) 3.3 2 A2.01 P8172L-002 105 (R34) Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures P8172L-002 104 (R35) to correct, control, or mitigate the consequences of those malfunctions or operations:

Loss of CCW pump A3.04 Ability to monitor automatic operation of the 2.9 CCWS, including:

Requirements on and for the CCWS for different conditions of the power plant

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

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

1 2 3 4 5 6 1 2 3 4 010 Pressurizer Pressure Control System 010 Pressurizer Pressure Control x (PZR PCS) 3.0 1 A3.02 P8170L-005 075 (R36) Ability to monitor automatic operation of the PZR PCS, including:

PZR pressure.

012 Reactor Protection System 012 Reactor Protection x A4.07 3.9* 1 Ability to manually operate and / or monitor in P8184L-004 115 (R37) the control room:

M/G set breakers 013 Engineered Safety Features Actuation 013 Engineered Safety Features x System (ESFAS) 4.2 1 Actuation 2.4.46 Ability to verify that the alarms are consistent P8180L-006 051 (R38) with the plant conditions 022 Containment Cooling System (CCS) 022 Containment Cooling x K1.04 2.9* 1 Knowledge of the physical connections and / or P8440L-401C 006 (R39) cause - effect relationships between the CCS and the following systems:

Chilled Water 026 Containment Spray System (CSS) 026 Containment Spray x x K2.01 3.4* 2 Knowledge of bus power supplies to the P8180L-002 077 (R40) following:

Containment Spray pumps P8180L-002 050 (R41) A4.01 4.5 Ability to manually operate and / or monitor in the control room:

CSS controls 039 Main and Reheat Steam System (MRSS) 039 Main and Reheat Steam x x K3.03 3.2* 2 Knowledge of the effect that a loss or P8174L-001 042 (R42) malfunction of the MRSS will have on the following:

AFW Pumps P8174L-001 043 (R43) 2.1.23 Ability to perform specific system and integrated 4.3 plant procedures during all modes of plant operation 059 Main Feedwater (MFW) System 059 Main Feedwater x K4.02 3.3 1 Knowledge of MFW design feature(s) and / or P8174l-003 083 (R44) interlock(s) which provide for the following:

Automatic turbine/reactor trip runback 061 Auxiliary / Emergency Feedwater (AFW) 061 Auxiliary/Emergency Feedwater x System 2.6 1 K5.03 P8180L-007 228 (R45) Knowledge of the operational implications of the following concepts as the apply to the AFW:

Pump head effects when control valve is shut

ES-401 8 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)

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

1 2 3 4 5 6 1 2 3 4 062 A.C. Electrical Distribution 062 AC Electrical Distribution x X K1.04 3.7 2 Knowledge of the physical connections and / or P8186L-002 036 (R46) cause-effect relationships between the ac distribution system and the following systems:

Off-site power sources P8186L-003B 012 (R47)

K4.03 Knowledge of ac distribution system design 2.8*

feature(s) and / or interlock(s) which provide for the following:

Interlocks between automatic bus transfer and breakers 063 D.C. Electrical Distribution 063 DC Electrical Distribution x A1.01 2.5 1 Ability to predict and / or monitor changes in P8186L-005 043 (R48) parameters associated with operating the DC electrical system controls including:

Battery capacity as it is affected by discharge rate 064 Emergency Diesel Generator 064 Emergency Diesel Generator x x K2.01 2.7* 2 Knowledge of bus power supplies to the P8186L-004 049 (R49) following:

Air compressor P8186L-004 050 (R50) A2.03 3.1 Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Parallel operation of ED/Gs 073 Process Radiation Monitoring (PRM) 073 Process Radiation Monitoring x System 3.7 1 A4.02 P8182L-002 094 (R51) Ability to manually operate and / or monitor in the control room:

Radiation monitoring system control panel 076 Service Water System (SWS) 076 Service Water x A3.02 3.7 1 Ability to monitor automatic operation of the P8176L-003 085 (R52) SWS, including:

Emergency heat loads 078 Instrument Air System (IAS) 078 Instrument Air x 2.4.47 4.2 1 Ability to diagnose and recognize trends in an P8178L-005 055 (R53) accurate and timely manner utilizing the appropriate control room reference material

ES-401 9 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)

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

1 2 3 4 5 6 1 2 3 4 103 Containment System 103 Containment x x K1.05 2.8* 2 Knowledge of the physical connections and / or P8180L-001 037 (R54) cause-effect relationships between the containment system and the following systems:

Personnel access hatch and emergency access P8180L-002 024 (R55) hatch A1.01 3.7 Ability to predict and / or monitor changes in parameters (to prevent exceeding design limits) associated with operating the containment system controls including:

Containment pressure, temperature and humidity 053 Integrated Control K/A Category Point Totals: 3 2 2 3 2 1 3 3 3 3 3 Group Point Total: 28

ES-401 10 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO)

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

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control 011 Pressurizer Level Control x A2.03: 3.8 1 Ability to (a) predict the impacts of the following P8170L-006 068 (R56) malfunctions or operations on the RCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Loss of PRZR level 014 Rod Position Indication 015 Nuclear Instrumentation System 015 Nuclear Instrumentation x K3.01 3.9 1 Knowledge of the effect that a loss or malfunction P8184L-002 026 (R57) of the NIS will have on the following:

RPS 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor 028 Hydrogen Recombiner and Purge Control 028 Hydrogen Recombiner x System (HRPS) 3.3 1 and Purge Control K3.01 Knowledge of the effect that a loss or malfunction P8180L-008 007 (R58) of the HRPS will have on the following:

Hydrogen concentration in containment 029 Containment Purge 033 Spent Fuel Pool Cooling System (SFPCS) 033 Spent Fuel Pool Cooling x K4.01 3.1 1 Knowledge of design feature(s) and / or interlock(s)

P8182L-004 029 (R59) which provide for the following:

Maintenance of Spent Fuel Pool Level 034 Fuel Handling Equipment 035 Steam Generator System (S/GS) 035 Steam Generator x K6.02 3.1 1 Knowledge of the effect of a loss or malfunction on P8174L-001 027 (R60) the following will have on the S/GS:

Secondary PORV

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

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

1 2 3 4 5 6 1 2 3 4 041 Steam Dump System (SDS) and Turbine 041 Steam Dump/Turbine Bypass x Bypass Control 3.1 1 Control A1.02 Ability to predict and / or monitor changes in P8174L-002 090 (R61) parameters (to prevent exceeding design limits) associated with operating the SDS controls including:

Steam pressure 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal 071 Waste Gas Disposal x A3.03: 3.6 1 Ability to monitor automatic operation of the Waste P8182L-002 090 (R62) Gas Disposal System including:

Radiation monitoring system alarm and actuating signals 072 Area Radiation Monitoring (ARM) System 072 Area Radiation Monitoring x A4.03 3.1 1 Ability to manually operate and / or monitor in the P8182L-002 019 (R63) control room:

Check source for operability demonstration 075 Circulating Water 075 Circulating Water x 2.1.25 3.9 1 Ability to interpret reference materials, such as P8176L-002A 024 (R64) graphs, curves, tables, etc.

079 Station Air System (SAS) 079 Station Air x K1.01 3.0 1 Knowledge of the physical connections and / or P8178L-005 008 (R65) cause-effect relationships between the SAS and the following systems:

IAS 086 Fire Protection 050 Control Room Ventilation K/A Category Point Totals: 1 0 2 1 0 1 1 1 1 1 1 Group Point Total: 10

ES-401 12 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 000007 Reactor Trip - Stabilization -

Recovery / 1 000008 Pressurizer Vapor Space Accident / 3 000009 Small Break LOCA / 3 011 Large Break LOCA 000011 Large Break LOCA / 3 x EA2.09 4.3 1 Ability to determine or interpret the following as P8197L-012 257 (S76) they apply to a Large Break LOCA:

Existence of adequate natural circulation 000015 RCP Malfunctions / 4 022 Loss of Reactor Coolant Makeup 000022 Loss of Rx Coolant Makeup / 2 x 2.2.42 4.6 1 Ability to recognize system parameters that are P8180L-005 016 (S77) entry-level conditions for technical specifications 025 Loss of Residual Heat Removal System 000025 Loss of RHR System / 4 x (RHRS) 3.8 1 AA2.03 P8180L-003 075 (S78)

Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System:

Increasing reactor building sump level 026 Loss of Component Cooling Water (CCW) 000026 Loss of Component Cooling x 2.2.40 4.7 Water / 8 Ability to apply Technical Specifications for a system.

P8172L-002 134 (S79) 000027 Pressurizer Pressure Control System Malfunction / 3 000029 ATWS / 1 000038 Steam Gen. Tube Rupture / 3 W/E12 Steam Line Rupture - Excessive Heat Transfer / 4 000054 Loss of Main Feedwater / 4 000055 Station Blackout / 6 000056 Loss of Off-site Power / 6

ES-401 13 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 2 057 Loss of Vital AC Electrical Instrument Bus 000057 Loss of Vital AC Inst. Bus / 6 x AA2.08 3.5* 1 Ability to determine and interpret the following as P8186L-015 029 (S80) they apply to the Loss of Vital AC Instrument Bus:

Reactor power digital display and remote flux meter 000058 Loss of DC Power / 6 000062 Loss of Nuclear Svc Water / 4 000065 Loss of Instrument Air / 8 000077 Generator Voltage and Electric Grid Disturbances / 6 Westinghouse E04 LOCA Outside W/E04 LOCA Outside Containment / 3 x Containment 3.9 1 2.4.3 P8140L-233 007 (S81)

Ability to identify post-accident instrumentation W/E11 Loss of Emergency Coolant Recirc. / 4 W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 K/A Category Totals: 3 3 Group Point Total: 6

ES-401 14 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 000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 033 Loss of Intermediate Range 000033 Loss of Intermediate Range NI / 7 x Nuclear Instrumentation 4.2 1 P7410L-034 027 (S82) AA2.07 Ability to determine and interpret the following as they apply to the Loss of Intermediate Range Nuclear Instrumentation:

Confirmation of reactor trip 036 Fuel Handling Incidents 000036 Fuel Handling Incidents / 8 x 2.4.41 4.6 1 P8182L-004 028 (S83) Knowledge of the emergency action level thresholds and classifications.

000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 000061 ARM System Alarms / 7 067 Plant fire on site 000067 Plant Fire On-site / 8 x AA2.05 3.6 1 P8140L-229 005 (S84) Ability to determine and interpret the following as they apply to the Plant Fire on Site:

Ventilation alignment necessary to secure affected area.

000068 Control Room Evac. / 8 W/E14 Loss of CTMT Integrity / 5 W/E06 & E07 Inad. Core Cooling / 4 000076 High Reactor Coolant Activity / 9

ES-401 15 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 000078 RCS Leak / 3 W/E01 & E02 Rediagnosis & SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 W/E16 High Containment Radiation / 9 Westinghouse E03 LOCA Cooldown W/E03 LOCA Cooldown - Depress. / 4 x and Depressurization 4.0 1 P8197L-012 255 (S85) 2.4.18 Knowledge of the specific bases for EOPs W/E09 & E10 Natural Circ. / 4 W/E08 RCS Overcooling - PTS / 4 K/A Category Point Totals: 2 2 Group Point Total: 4

ES-401 16 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)

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

1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump 004 Chemical and Volume Control 005 Residual Heat Removal 005 Residual Heat Removal x A2.01 2.9* 1 Ability to (a) predict the impacts of the P8197L-012 262 (S86) following malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Failure modes for pressure, flow, pump motor amps, motor temperature, and tank level instrumentation 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 010 Pressurizer Pressure Control 012 Reactor Protection 013 Engineered Safety Features 013 Engineered Safety Features x Actuation System (ESFAS) 4.4 1 Actuation 2.2.44 Ability to interpret control room (S87) P7410L-034 026 indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions 022 Containment Cooling 026 Containment Spray System (CSS) 026 Containment Spray x A2.08 3.7 1 Ability to (a) predict the impacts of the P8180L-002 051 (S88) 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 039 Main and Reheat Steam 059 Main Feedwater

ES-401 17 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)

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

1 2 3 4 5 6 1 2 3 4 061 Auxiliary / Emergency Feedwater 061 Auxiliary/Emergency x (AFW) System 3.4* 1 Feedwater A2.05 Ability to (a) predict the impacts of the P8197L-014 215 (S89) following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Automatic control malfunction 062 AC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generators 064 Emergency Diesel Generator x (ED/G) 4.3 1 2.4.20 P8197L-011 242 (S90) Knowledge of the operational implications of EOP warnings, cautions, and notes 073 Process Radiation Monitoring 076 Service Water 078 Instrument Air 103 Containment 053 Integrated Control K/A Category Point Totals: 3 2 Group Point Total: 5

ES-401 18 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO)

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

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive 002 Reactor Coolant System (RCS) 002 Reactor Coolant x A2.04 4.6 1 Ability to (a) predict the impacts of the P8197L-014 214 (S91) following malfunctions or operations on the RCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Loss of Heat sinks 011 Pressurizer Level Control 014 Rod Position Indication 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator (MT/G) 045 Main Turbine Generator x System 4.7 1 2.2.22 P8140L-246 029 (S92) Knowledge of limiting conditions for operations and safety limits 055 Condenser Air Removal 056 Condensate

ES-401 19 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO)

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

1 2 3 4 5 6 1 2 3 4 068 Liquid Radwaste Systems (LRS) 068 Liquid Radwaste x A2.04 3.3 1 Ability to (a) predict the impacts of the P8182L-001A 011 (S93) following malfunctions or operations on 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 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air 086 Fire Protection 050 Control Room Ventilation K/A Category Point Totals: 2 1 Group Point Total: 3

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

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

Ability to make accurate, clear, and concise logs, records, status 2.1.18 boards, and reports 3.6 1 PI-OPS-GFE-038L 022 (R66)

1. Ability to evaluate plant performance and make operational Conduct 2.1.7 judgments based on operating characteristics, reactor behavior, 4.4 1 of Operations and instrument interpretation P8140L-233 006 (R67)

Knowledge of the purpose and function of major system 2.1.28 components and controls 4.1 1 P8180L-002 053 (R68)

Subtotal 3 Ability to analyze the effect of maintenance activities, such as 2.2.36 degraded power sources, on the status of limiting conditions for 3.1 1 operations P8186L-005 105 (R69)

2. Ability to determine operability and / or availability of safety Equipment 2.2.37 related equipment 3.6 1 Control P8180L-009H 020 (R70)

Knowledge of the process used to track inoperable alarms 2.2.43 P9150L-024 043 (R71) 3.0 1 Subtotal 3 Ability to comply with radiation work permit requirements during normal or abnormal conditions 3.5 1 2.3.7 P9130L-003 056 (R72) 3.

Radiation Control Subtotal 1 Knowledge of general operating crew responsibilities during 2.4.12 emergency operations 4.0 1 P8197L-012 253 (R73)

4. Knowledge of how abnormal operating procedures are used in Emergency 2.4.8 conjunction with EOPs 3.8 1 Procedures / P8197L-011 243 (R74)

Plan Knowledge of fire in the plant procedures 2.4.27 P8197L-009 034 (R75) 3.4 1 Subtotal 3 Tier 3 Point Total Tier 3 10 Point Total

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

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

Ability to perform specific system and integrated plant 2.1.23 procedures during all modes of plant operation 4.4 1 P8140L-231 004 (S94)

1. Knowledge of criteria or conditions that require plant-wide Conduct 2.1.14 announcements, such as pump starts, reactor trips, mode 3.1 1 of Operations changes etc.

P7410L-035 005 (S95)

Subtotal 2 Knowledge of the process for managing maintenance activities 2.2.17 during power operations, such as risk assessments, work 3.8 1 prioritization, and coordination with the transmission system operator.

2. P9150L-005 018 (S96)

Equipment Ability to determine the expected plant configuration using design 2.2.15 and configuration control documentation, such as drawings, line- 4.3 1 Control ups, tag-outs, etc.

P8180L-003 076 (S97)

Subtotal 2 Knowledge of radiological safety principles pertaining to licensed 2.3.12 operator duties, such as containment entry requirements, fuel 3.7 1 handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

3. P9130L-003 054 (S98)

Radiation Control Subtotal 1 Knowledge of EOP implementation hierarchy and 2.4.16 4.4 1 coordination with other support procedures or guidelines such as, operating procedures, abnormal operating 4.

procedures, and sever accident management guidelines Emergency P8140L-228 002 (S99)

Procedures / Knowledge of the bases for prioritizing emergency procedure Plan 2.4.23 implementation during emergency operations 4.4 1 P8197L-014 191 (S100)

Subtotal 2 Tier 3 Point Total Tier 3 7 Point Total

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