ML15126A185

2014 Prairie Island Nuclear Generating Plant Initial License Examination Forms Es 401-2 and Es 401-3

ML15126A185
Person / Time
Site:	Prairie Island
Issue date:	09/12/2014
From:	Bielby M NRC/RGN-III/DRS/OLB
To:	Nuclear Management Co
References
Download: ML15126A185 (20)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Prairie Island Date of Exam: 8/4/2014 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 2 2 1 N/A 1 1 N/A 2 9 2 2 4 Plant Evolutions Tier Totals 5 4 5 4 4 5 27 5 5 10 1 4 2 3 2 3 2 1 3 2 3 3 28 3 2 5 2.

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

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

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/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 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-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 2 007 Reactor Trip 000007 Reactor Trip - Stabilization - X EA2.03: 4.2 1 Recovery / 1 Ability to determine or interpret the following as they apply to a reactor trip:

P8184L-004 100 (R01)

Reactor trip breaker position 008 Pressurizer Vapor Space Accident 000008 Pressurizer Vapor Space X 2.4.47: 4.2 1 Accident / 3 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the P8197L-012 222 (R02) appropriate control room reference material.

009 Small Break LOCA 000009 Small Break LOCA / 3 X EK1.01: 4.2 1 Knowledge of the operational implications of the P8197L-012 013 (R03) following concepts as they apply to the small break LOCA:

Natural circulation and cooling, including reflux boiling 011 Large Break LOCA 000011 Large Break LOCA / 3 X EK2.02: 2.6* 1 Knowledge of the interrelations between the and P8180L-002 034 (R04) the following Large Break LOCA:

Pumps 015/017 Reactor Coolant Pump (RCP) 000015/17 RCP Malfunctions / 4 X Malfunctions 3.0 1 AK3.02:

P8170L-002 064 (R05)

Knowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow):

CCW lineup and flow paths to RCP oil coolers 022 Loss of Reactor Coolant Makeup 000022 Loss of Rx Coolant Makeup / 2 X AA1.09: 3.2 1 Ability to operate and / or monitor the following as P8170L-002 092 (R06) they apply to the Loss of Reactor Coolant Makeup:

RCP seal flows, temperatures, pressures, and vibrations 025 Loss of Residual Heat Removal System 000025 Loss of RHR System / 4 X (RHRS) 2.7 1 AA2.01:

P8197L-012 226 (R07)

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

Proper amperage of running LPI/decay heat removal/RHR pump(s) 026 Loss of Component Cooling Water 000026 Loss of Component Cooling X 2.2.38: 3.6 1 Water / 8 Knowledge of conditions and limitations in the facility license.

P8172L-002 088 (R08) 000027 Pressurizer Pressure Control System Malfunction / 3 029 Anticipated Transient Without Scram 000029 ATWS / 1 X (ATWS) 3.6 1 EK1.03:

P8197L-014 183 (R09)

Knowledge of the operational implications of the following concepts as they apply to the ATWS:

Effects of boron on reactivity 038 Steam Generator Tube Rupture (SGTR) 000038 Steam Gen. Tube Rupture / 3 X EK2.01: Knowledge of the interrelations between 2.2* 1 the and the following a SGTR: Valves P8197L-013 115 (R10)

Justification for K/A less than 2.5: The question used to meet this K/A requires RO knowledge of when to perform a RCS depressurization using pressurizer spray valves during a SGTR event.

Based on past experience at Prairie Island, this knowledge is important to ROs.

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 W/E12 Steam Line Rupture - Excessive Heat Transfer / 4 054 Loss of Main Feedwater (MFW) 000054 Loss of Main Feedwater / 4 X AK3.03: Knowledge of the reasons for the 3.8 1 following responses as they apply to the Loss of P8180L-007 110 (R11)

Main Feedwater (MFW):

Manual control of AFW flow control valves 055 Loss of Offsite and Onsite Power (Station 000055 Station Blackout / 6 X Blackout) 3.5 1 EA1.04:

P8186L-005 036 (R12)

Ability to operate and monitor the following as they apply to a Station Blackout:

Reduction of loads on the battery 056 Loss of Offsite Power 000056 Loss of Off-site Power / 6 X AA2.54: 2.9 1 Ability to determine and interpret the following as P8186L-008 047 (R13) they apply to the Loss of Offsite Power:

Breaker position (remote and local) 057 Loss of Vital AC Electrical Instrument Bus 000057 Loss of Vital AC Inst. Bus / 6 X 2.1.30: 4.4 1 Ability to locate and operate components, P8186L-015 026 (R14) including local controls.

058 Loss of DC Power 000058 Loss of DC Power / 6 X AK1.01: 2.8 1 Knowledge of the operational implications of the P8186L-005 035 (R15) following concepts as they apply to Loss of DC Power:

Battery charger equipment and instrumentation 000062 Loss of Nuclear Svc Water / 4 065 Loss of Instrument Air 000065 Loss of Instrument Air / 8 X AK3.03: 2.9 1 Knowledge of the reasons for the following P8178L-005 012 (R16) responses as they apply to the Loss of Instrument Air:

Knowing effects on plant operation of isolating certain equipment from instrument air.

W/E04 LOCA Outside Containment / 3 W/E11 Loss of Emergency Coolant Recirc. / 4 E05 Loss of Secondary Heat Sink W/E05 Inadequate Heat Transfer - Loss X EK3.2: 3.7 1 of Secondary Heat Sink / 4 Knowledge of the reasons for the following responses as they apply to the (Loss of P8197L-014 190 (R17)

Secondary Heat Sink):

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

077 Generator Voltage and Electric Grid 000077 Generator Voltage and Electric X Disturbances 3.6 1 Grid Disturbances / 6 AA1.01:

Ability to operate and/or monitor the following as P8186L-001 019 (R18) they apply to Generator Voltage and Electric Grid Disturbances:

Grid frequency and voltage 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 000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 032 Loss of Source Range Nuclear 000032 Loss of Source Range NI / 7 X Instrumentation 2.5 1 P8184L-002 102 (R19) AK1.01:

Knowledge of the operational implications of the following concepts as they apply to Loss of Source Range Nuclear Instrumentation:

Effects of voltage changes on performance 000033 Loss of Intermediate Range NI / 7 036 Fuel Handling Incidents 000036 Fuel Handling Accident / 8 X AK2.02:

3.4 1 P8178L-001B 008 (R20) Knowledge of the interrelations between the Fuel Handling Incidents and the following:

Radiation monitoring equipment (portable and installed) 000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid RadWaste Rel. / 9 060 Accidental Gaseous Radwaste 000060 Accidental Gaseous Radwaste Rel. / 9 X Release 3.8 1 P8182L-001C 030 (R21) 2.1.32:

Ability to explain and apply system limits and precautions.

000061 ARM System Alarms / 7 067 Plant fire on site 000067 Plant Fire On-site / 8 X AK1.02:

3.1 1 P8178L-002 048 (R22) Knowledge of the operational implications of the following concepts as they apply to Plant Fire on Site:

Fire fighting 000068 Control Room Evac. / 8 W/E14 Loss of CTMT Integrity / 5 W/E06 & E07 Inad. Core Cooling / 4 076 High Reactor Coolant Activity 000076 High Reactor Coolant Activity / 9 X AK2.01:

2.6 1 P8172L-001A 134 (R23) Knowledge of the interrelations between the High Reactor Coolant Activity and the following:

Process radiation monitors W/E01 & E02 Rediagnosis & SI Termination / 3 W/E13 Steam Generator Over-pressure / 4

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 E15 Containment Flooding W/E15 Containment Flooding / 5 X EK3.3:

2.9 1 P8178L-002 027 (R24) Knowledge of the reasons for the following responses as they apply to the (Containment Flooding):

Manipulation of controls required to obtain desired operating results during abnormal and emergency situations.

E16 High Containment Radiation W/E16 High Containment Radiation / 9 X EA1.2:

2.9 1 P8180L-009 020 (R25) Ability to operate and / or monitor the following as they apply to the (High Containment Radiation):

Operating behavior characteristics of the facility.

E03 LOCA Cooldown and W/E03 LOCA Cooldown - Depress. / 4 X Depressurization 3.5 1 P8197L-012 135 (R26) EA2.2:

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

Adherence to appropriate procedures and operation within the limitations in the Facilitys license and amendments.

W/E09 & E10 Natural Circ. / 4 E08 Pressurized Thermal Shock CE/A11; W/E08 RCS Overcooling - PTS / 4 X 2.4.9: 3.8 1 P8197L-014 184 (R27) Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies K/A Category Point Totals: 2 2 1 1 1 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 System 003 Reactor Coolant Pump X (RCPS) 2.9 1 A4.02:

P8170L-002 091 (R28)

Ability to manually operate and/or monitor in the control room:

RCP motor parameters 004 Chemical and Volume Control 004 Chemical and Volume X System (CVCS) 2.5 1 Control K6.20:

Knowledge of the effect of a loss or P8172L-001A 045 (R29) malfunction on the following CVCS components:

Function of demineralizer, including boron loading and temperature limits 004 Chemical and Volume Control 3.7 1 P8197L-010 052 (R30)

X System (CVCS) 2.4.6:

Knowledge of EOP mitigation strategies 005 Residual Heat Removal System 005 Residual Heat Removal X (RHRS) 2.7 1 K1.08:

P8180L-003 059 (R31)

Knowledge of the physical connections and/or cause effect relationships between the RHRS and the following systems:

SWS X 005 Residual Heat Removal System P8197L-006 014 (R32) (RHRS) 2.7* 1 K5.05:

Knowledge of the operational implications of the following concepts as they apply the RHRS:

Plant response during "solid plant" pressure change due to the relative incompressibility of water 006 Emergency Core Cooling System 006 Emergency Core Cooling X (ECCS) 3.6 1 K2.01:

P8180L-004 049 (R33)

Knowledge of bus power supplies to the following:

ECCS pumps 007 Pressurizer Relief Tank/Quench 007 Pressurizer Relief/Quench X Tank System (PRTS) 3.3 1 Tank K3.01:

Knowledge of the effect that a loss or P8170L-003 100 (R34) malfunction of the PRTS will have on the following:

Containment 007 Pressurizer Relief Tank/Quench P8170L-003 115 (R35) X Tank System (PRTS)

A2.02: 2.6 1 Ability to (a) predict the impacts of the following malfunctions or operations on the P S; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Abnormal pressure in the PRT

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 4 008 Component Cooling Water 008 Component Cooling Water X System (CCWS) 3.1 1 K4.01:

P8172L-002 090 (R36) Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following:

Automatic start of standby pump 010 Pressurizer Pressure Control 010 Pressurizer Pressure Control X System (PZR PCS) 4.0 1 K3.03:

P8170L-005 063 (R37) Knowledge of the effect that a loss or malfunction of the PZR PCS will have on the following:

ESFAS P8197L-012 073 (R38) 010 Pressurizer Pressure Control X System (PZR PCS)

K5.02: 2.6 1 Knowledge of the operational implications of the following concepts as the apply to the PZR PCS:

Constant enthalpy expansion through a valve 012 Reactor Protection System 012 Reactor Protection X K6.02: 2.9 1 Knowledge of the effect of a loss or P8184L-004 002 (R39) malfunction of the following will have on the RPS:

Redundant channels 013 Engineered Safety Features 013 Engineered Safety Features X Actuation System (ESFAS) 3.6 1 Actuation A1.07:

Ability to predict and/or monitor changes P8180L-006 079 (R40) in parameters (to Prevent exceeding design limits) associated with operating the ESFAS controls including:

Containment radiation 022 Containment Cooling System 022 Containment Cooling X (CCS) 3.1 1 A2.05:

P8180L-009H 052 (R41)

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

Major leak in CCS 026 Containment Spray System (CSS) 026 Containment Spray X K1.02: 4.1 1 Knowledge of the physical connections P8172L-002 040 (R42) and/or cause effect relationships between the CSS and the following systems:

Cooling water 026 Containment Spray System (CSS)

X A3.01:

P8180L-002 006 (R43) Ability to monitor automatic operation of 4.3 1 the CSS, including:

Pump starts and correct MOV positioning 039 Main and Reheat Steam System 039 Main and Reheat Steam X (MRSS) 2.9* 1 A4.01:

P8174L-001 032 (R44) Ability to manually operate and/or monitor in the control room:

Main steam supply valves

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 4 059 Main Feedwater 059 Main Feedwater X 2.4.35: 3.8 1 Knowledge of local auxiliary operator P8174L-006 035 (R45) tasks during an emergency and the resultant operational effects.

061 Auxiliary / Emergency Feedwater 061 Auxiliary/Emergency X (AFW) System 3.5 1 Feedwater K1.03:

Knowledge of the physical connections P8180L-007 037 (R46) and/or cause effect relationships between the AFW and the following systems:

Main steam system 062 A.C. Electrical Distribution 062 AC Electrical Distribution X K2.01: 3.3 1 Knowledge of bus power supplies to the P8186L-002 032 (R47) following:

Major system loads 063 D.C. Electrical Distribution 063 DC Electrical Distribution X K3.02: 3.5 1 Knowledge of the effect that a loss or P8186L-005 012 (R48) malfunction of the DC electrical system will have on the following:

Components using DC control power 064 Emergency Diesel Generators 064 Emergency Diesel Generator X (ED/G) 3.5 1 K4.11:

P8186L-008 048 (R49) Knowledge of ED/G system design feature(s) and/or interlock(s) which provide for the following:

Automatic load sequencer: safeguards 073 Process Radiation Monitoring 073 Process Radiation X (PRM) System 2.5 1 Monitoring K5.01:

Knowledge of the operational P8182L-002 053 (R50) implications as they apply to concepts as they apply to the PRM system:

Radiation theory, including sources, types, units, and effects P8182L-002 091 (R51) X 073 Process Radiation Monitoring (PRM) System 3.1 1 A4.03:

Ability to manually operate and/or monitor in the control room:

Check source for operability demonstration 076 Service Water System (SWS) 076 Service Water X A2.02: 2.7 1 Ability to (a) predict the impacts of the P8176L-003 071 (R52) following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Service water header pressure

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 4 078 Instrument Air System (IAS) 078 Instrument Air X K1.03: 3.3* 1 Knowledge of the physical connections P8178L-005 045 (R53) and/or cause-effect relationships between the IAS and the following systems:

Containment Air 078 Instrument Air System (IAS) 2.4.47:

Ability to diagnose and recognize trends P8178L-005 049 (R54) X in an accurate and timely manner 4.2 1 utilizing the appropriate control room reference material.

103 Containment System 103 Containment X A3.01: 3.9 1 Ability to monitor automatic operation of P8180L-009F 006 (R55) the containment system, including:

Containment isolation K/A Category Point Totals: 4 2 3 2 3 2 1 3 2 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 System 001 Control Rod Drive X A2.17: 3.3 1 Ability to (a) predict the impacts of the P8184L-005 035 (R56) following malfunction or operations on the CRDS- and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Rod-misalignment alarm 002 Reactor Coolant 011 Pressurizer Level Control 014 Rod Position Indication 015 Nuclear Instrumentation System 015 Nuclear Instrumentation X A3.04: 3.3 1 Ability to monitor automatic operation of the P8184L-002 104 (R57) NIS, including:

Maximum disagreement allowed between channels 016 Non-Nuclear Instrumentation 016 Non-nuclear Instrumentation X System (NNIS) 2.7 1 A4.02:

P8184L-003 042 (R58) Ability to manually operate and/or monitor in the control room:

Recorders 017 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge 028 Hydrogen Recombiner X Control System (HRPS) 2.5* 1 and Purge Control K1.01:

Knowledge of the physical connections P8180L-001 032 (R59) and/or cause effect relationships between the HRPS and the following systems:

Containment annulus ventilation system (including pressure limits) 029 Containment Purge 033 Spent Fuel Pool Cooling System 033 Spent Fuel Pool Cooling X (SFPCS) 4.1 1 2.1.28 P8182L-004 021 (R60) Knowledge of the purpose and function of major system components and controls.

034 Fuel Handling Equipment 035 Steam Generator System (S/GS) 035 Steam Generator X K3.02: 4.0 1 Knowledge of the effect that a loss or P8180L-006 084 (R61) malfunction of the S/GS will have on the following:

ECCS 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator (MT/G) 045 Main Turbine Generator X System 2.6 1 K4.13:

P8176L-001 069 (R62)

Knowledge of MT/G system design feature(s) and/or interlock(s) which provide for the following:

Overspeed protection

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 4 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring (ARM) 072 Area Radiation Monitoring X System 2.5 1 K5.02:

PI-OPS-GFE-044L 002 (R63)

Knowledge of the operational implications of the following concepts as they apply to the ARM system:

Radiation intensity changes with source distance 075 Circulating Water System 075 Circulating Water X K2.03 2.6* 1 Knowledge of bus power supplies to the P8176L-003 054 (R64) following:

Emergency/essential SWS pumps 079 Station Air 086 Fire Protection System (FPS) 086 Fire Protection X A1.01: 2.9 1 Ability to predict and/or monitor changes in P8178L-002 024 (R65) parameters (to prevent exceeding design limits) associated with Fire Protection System operating the controls including:

Fire header pressure K/A Category Point Totals: 1 1 1 1 1 0 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 000011 Large Break LOCA / 3 015/017 Reactor Coolant Pump (RCP) 000015/17 RCP Malfunctions / 4 X Malfunctions 3.7 1 AA2.10:

Ability to determine and interpret the following as P8170L-002 136 (S76) they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow):

When to secure RCPs on loss of cooling or seal injection 022 Loss of Reactor Coolant Makeup 000022 Loss of Rx Coolant Makeup / 2 X 2.4.8: 4.5 1 Knowledge of how abnormal operating P8172L-001A 133 (S77) procedures are used in conjunction with EOPs 025 Loss of Residual Heat Removal System 000025 Loss of RHR System / 4 X (RHRS) 3.7 1 AA2.07:

Ability to determine and interpret the following as P8180L-003 058 (S78) they apply to the Loss of Residual Heat Removal System:

Pump cavitation 000026 Loss of Component Cooling Water / 8 000027 Pressurizer Pressure Control System Malfunction / 3 000029 ATWS / 1 000038 Steam Gen. Tube Rupture / 3 E12 Uncontrolled Depressurization of all W/E12 Steam Line Rupture - Excessive X Steam Generators 4.4 1 Heat Transfer / 4 2.2.44:

Ability to interpret control room indications to verify the status and operation of a system, and P8197L-012 219 (S79) understand how operator actions and directives affect plant and system conditions.

000054 Loss of Main Feedwater / 4 055 Loss of Offsite and Onsite Power (Station 000055 Station Blackout / 6 X Blackout) 4.7 1 EA2.03:

Ability to determine or interpret the following as P8197L-011 105 (S80) they apply to a Station Blackout:

Actions necessary to restore power 000056 Loss of Off-site Power / 6 000057 Loss of Vital AC Inst. Bus / 6 000058 Loss of DC Power / 6 000062 Loss of Nuclear Svc Water / 4 000065 Loss of Instrument Air / 8 E04 LOCA Outside Containment W/E04 LOCA Outside Containment / 3 X 2.4.18: 4.0 1 Knowledge of the specific bases for EOPs P8197L-011 017 (S81)

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 W/E11 Loss of Emergency Coolant Recirc. / 4 W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 000077 Generator Voltage and Electric Grid Disturbances / 6 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 000033 Loss of Intermediate Range NI / 7 036 Fuel Handling Accident 000036 Fuel Handling Accident / 8 X 2.4.4: 4.7 1 Ability to recognize abnormal indications for system operating parameters that are entry P8182L-003 030 (S82) level conditions for emergency and abnormal operating procedures.

037 Steam Generator (S/G) Tube Leak 000037 Steam Generator Tube Leak / 3 X AA2.10:

4.1 1 Ability to determine and interpret the following as they apply to the Steam P8171L-007 071 (S83)

Generator Tube Leak:

Tech-Spec limits for RCS leakage 000051 Loss of Condenser Vacuum / 4 059 Accidental Liquid Radwaste Release 000059 Accidental Liquid RadWaste Rel. / 9 X 2.2.38: 4.5 1 P8182L-002 001 (S84) Knowledge of conditions and limitations in the facility license 000060 Accidental Gaseous Radwaste Rel. / 9 000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8 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 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 E03 LOCA Cooldown and W/E03 LOCA Cooldown - Depress. / 4 X Depressurization 4.2 1 EA2.1:

Ability to determine and interpret the P8197L-012 225 (S85) following as they apply to the (LOCA Cooldown and Depressurization) Facility conditions and selection of appropriate procedures during abnormal and emergency operations 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 15 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 System 003 Reactor Coolant Pump X (RCPS) 4.7 1 2.1.7:

Ability to evaluate plant performance and P8197L-014 116 (S86) make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation 004 Chemical and Volume Control 005 Residual Heat Removal 006 Emergency Core Cooling System 006 Emergency Core Cooling X (ECCS) 4.2 1 A2.13:

Ability to (a) predict the impacts of the P8180L-004 024 (S87) following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Inadvertent SIS actuation 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 010 Pressurizer Pressure Control 012 Reactor Protection 013 Engineered Safety Features Actuation 022 Containment Cooling System 022 Containment Cooling X (CCS) 4.7 1 2.2.22:

P8180L-009H 048 (S88) Knowledge of limiting conditions for operations and safety limits.

026 Containment Spray 039 Main and Reheat Steam System 039 Main and Reheat Steam X (MRSS) 3.7 1 A2.03:

Ability to (a) predict the impacts of the P8182L-002 136 (S89) following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Indications and alarms for main steam and area radiation monitors (during SGTR) 059 Main Feedwater 061 Auxiliary/Emergency Feedwater 062 AC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator

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 4 073 Process Radiation Monitoring 073 Process Radiation X (PRM) System 3.2 1 Monitoring A2.02:

Ability to (a) predict the impacts of the following malfunctions or operations on P8182L-002 137 (S90) the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Detector failure 076 Service Water 078 Instrument Air 103 Containment K/A Category Point Totals: 3 2 Group Point Total: 5

ES-401 17 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 011 Pressurizer Level Control System 011 Pressurizer Level Control X (PZR LCS) 3.9 1 A2.03:

Ability to (a) predict the impacts of the P8170L-006 058 (S91) following malfunctions or operations on the PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Loss of PZR level 014 Rod Position Indication 015 Nuclear Instrumentation 015 Nuclear Instrumentation X 2.2.12 4.1 1 Knowledge of surveillance procedures.

P8184L-002 081 (S92) 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor 027 Containment Iodine Removal 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 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring (ARM) 072 Area Radiation Monitoring X System 2.9 1 A2.01:

Ability to (a) predict the impacts of the P8182L-002 089 (S93) following malfunctions or operations on the ARM system- and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Erratic or failed power supply 075 Circulating Water

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 4 079 Station Air 086 Fire Protection K/A Category Point Totals: 2 1 Group Point Total: 3

ES-401 Generic Knowledge and Abilities Outline (Tier 3 - RO) Form ES-401-3 Facility: Prairie Island Date of Exam: 8/4/2014 Category K/A # Topic RO SRO-Only IR # IR #

Knowledge of shift or short-term relief turnover practices.

2.1.3 P8140L-201 007 (R66) 3.7 1 Ability to make accurate, clear, and concise logs, records, status

1. 2.1.18 boards, and reports. 3.6 1 Conduct PI-OPS-GFE-038L 020 (R67) of Operations Knowledge of refueling administrative requirements.

2.1.40 P8184L-002 070 (R68) 2.8 1 Subtotal 3 Knowledge of the process for controlling equipment configuration 2.2.14 or status. 3.9 1 P9150L-024 039 (R69)

Ability to apply Technical Specifications for a system.

2. 2.2.40 P8170L-001 020 (R70) 3.4 1 Equipment Control Subtotal 2 Knowledge of radiological safety principles pertaining to licensed 2.3.12 operator duties, such as containment entry requirements, fuel 3.2 1

3. handling responsibilities, access to locked high-radiation areas, Radiation aligning filters, etc.

P9130L-003 017 (R71)

Control Knowledge of radiological safety procedures pertaining to 2.3.13 licensed operator duties, such as response to radiation monitor 3.4 1 alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

P9130L-003 075 (R72)

Knowledge of radiation monitoring systems, such as fixed 2.3.15 radiation monitors and alarms, portable survey instruments, 2.9 1 personnel monitoring equipment, etc.

P8182L-002 088 (R73)

Subtotal 3 Knowledge of the organization of the operating procedures 2.4.5 network for normal, abnormal, and emergency evolutions. 3.7 1 P8197L-010 027 (R74)

4. Knowledge of the bases for prioritizing emergency procedure Emergency 2.4.23 implementation during emergency operations. 3.4 1 Procedures / P8197L-011 117 (R75)

Plan Subtotal 2 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: 8/4/2014 Category K/A # Topic RO SRO-Only IR # IR #

Ability to evaluate plant performance and make operational 2.1.7 judgments based on operating characteristics, reactor behavior, 4.7 1 and instrument interpretation.

1. P8184L-002 103 (S94)

Conduct of Operations Subtotal 1 Knowledge of the process for making design or operating 2.2.5 changes to the facility. 3.2 1 P9150L-024 038 (S95)

Ability to interpret control room indications to verify the status

2. 2.2.44 and operation of a system, and understand how operator actions 4.4 1 Equipment and directives affect plant and system conditions.

Control P7410L-002 048 (S96)

Subtotal 2 Ability to approve release permits.

2.3.6 P8182L-001C 137 (S97) 3.8 1 Knowledge of radiation or contamination hazards that may arise 2.3.14 during normal, abnormal, or emergency conditions or activities. 3.8 1

3. P8197L-013 114 (S98)

Radiation Control Subtotal 2 Knowledge of EOP layout, symbols, and icons.

2.4.19 P8197L-011 116 (S99) 4.1 1 Knowledge of SRO responsibilities in emergency plan

4. 2.4.40 implementation. 4.5 1 Emergency P9150L-011 003 (S100)

Procedures /

Plan Subtotal 2 Tier 3 Point Total Tier 3 7 Point Total