ML20245E558

ES-401-2, 3, 4, PWR Examination Outline

ML20245E558
Person / Time
Site:	Prairie Island
Issue date:	08/27/2020
From:	NRC/RGN-III/DRS/OLB
To:
Callaway G
Shared Package
ML19127A303	List: ML20245E545 ML20245E548 ML20245E558 ML20245E581 ML20245E582
References
50-282/20-01, 50-306/20-01, ES-401-2, ES-401-3, ES-401-4 50-282/OL-20, 50-306/OL-20
Download: ML20245E558 (22)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Prairie Island Date of Exam: AUGUST 28, 2020 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 3 3 3 3 3 18 3 3 6 Emergency

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

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

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

• EK1.05 000007 Reactor Trip - Stabilization - Knowledge of the operational implications of the 3.3 1 Recovery / 1 X following concepts as they apply to the reactor trip:

Decay power as a function of time.

(R16) PI-OPS-GFE-192008 003 AK1.01 000008 Pressurizer Vapor Space Accident Knowledge of the operational implications of the 3.2 1

/3 following concepts as they apply to Pressurizer Vapor (R2) P8170L-003 107 X Space Accident:

Thermodynamics and flow characteristics of open or leaking valves.

2.4.21 000009 Small Break LOCA / 3 Emergency Procedures / Plan 4.0 1 Knowledge of the parameters and logic used to assess the (R3) P8140L-224 006 X status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

EA1.11 000011 Large Break LOCA / 3 Ability to operate and monitor the following as they apply 4.2 1 (R4) P8197L-012 220 X to a Large Break LOCA:

Long term core cooling.

AA1.10 000015 RCP Malfunctions / 4 Ability to operate and / or monitor the following as they 2.7 1 X apply to the Reactor Coolant Pump Malfunctions (Loss of (R5) P8170L-002 017 RC Flow):

RCP ammeter and trip alarm.

AA2.02 000022 Loss of Rx Coolant Makeup / 2 Ability to determine and interpret the following as they 3.2 1 (R6) P8172L-001A 157 X apply to the Loss of Reactor Coolant Makeup:

Charging pump problems.

AK1.01 000025 Loss of RHR System / 4 Knowledge of the operational implications of the 3.9 1 X following concepts as they apply to Loss of Residual Heat (R7) P8180L-003 075 Removal System:

Loss of RHR system during all modes of operation.

AK3.03 000026 Loss of Component Cooling Water / Knowledge of the reasons for the following responses as 4.0 1 8 X they apply to the Loss of Component Cooling Water.

Guidance actions contained in EOP for Loss of CCW.

(R8) P8172L-002 205 AK2.03 000027 Pressurizer Pressure Control Knowledge of the interrelations between the Pressurizer 2.6 1 System Malfunction / 3 X Pressure Control Malfunctions and the following:

Controllers and positioners (R9) P8170L-005 082 EK3.10 000029 ATWS / 1 Knowledge of the reasons for the following responses as 4.1 1 (R10) P8197L-014 071 X they apply to the ATWS:

Manual rod insertion.

EK3.01 000038 Steam Gen. Tube Rupture / 3 Knowledge of the reasons for the following responses as 4.1 1 X they apply to the SGTR:

(R11) P8197L-013 120 Equalizing pressure on primary and secondary sides of ruptured S/G.

EK2.1 W/E12 Steam Line Rupture - Excessive Knowledge of the interrelations between the 3.4 1 Heat Transfer / 4 (Uncontrolled Depressurization of all Steam Generators)

X and the following:

(R12) P8197L-012 221 Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

2.4.20 000054 Loss of Main Feedwater / 4 Knowledge of operational implications of EOP warnings, 3.8 1 X cautions, and notes.

(R13) P8180L-007 129

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

• 000055 Station Blackout / 6 AA1.33 000056 Loss of Off-site Power / 6 Ability to operate and/or monitor the following as they 3.3 1 (R14) P8197L-011 240 X apply to the LOOP:

PORV block valve control switch.

AA2.04 000057 Loss of Vital AC Inst. Bus / 6 X Ability to determine and interpret the following as they 3.7 1 apply to the Loss of Vital AC Instrument Bus:

(R15) P8186L-015 32 ESF system panel alarm annunciators and channel status indicators.

000058 Loss of DC Power / 6 2.1.7 000062 Loss of Nuclear Svc Water / 4 X Ability to evaluate plant performance and make operational 4.4 1 judgments based on operating characteristics, reactor (R01) P8176L-003 088 behavior, and instrument interpretation.

AA2.08:

000065 Loss of Instrument Air / 8 X Ability to determine and interpret the following as they 2.9 1 apply to the Loss of Instrument Air:

(R17) P8178L-005 012 Failure modes of air operated equipment.

000077 Generator Voltage and Electric Grid Disturbances / 6 W/E04 LOCA Outside Containment / 3 W/E11 Loss of Emergency Coolant Recirc. /

4 EK2.2 W/E05 Inadequate Heat Transfer - Loss X Knowledge of the interrelations between Loss of Heat 3.9 1 of Secondary Heat Sink / 4 Sink and the following:

Facilitys heat removal systems, including primary coolant, (R18) P8197L-014 226 emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

K/A Category Totals: 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 2.4.18 000003 Dropped Control Rod / 1 X Knowledge of the specific bases for EOPs. 3.3 1 (R19) P8184L-005 146 AA1.03 000005 Inoperable/Stuck Control Rod / 1 X 3.4 1 Ability to operate and/or monitor the following as they (R20) P8184L-005 148 apply to the Inoperable/Stuck Rod:

Metroscope 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 AA2.04 000033 Loss of Intermediate Range NI / 7 X 3.2 1 Ability to determine and interpret the following as they (R21) P8184L-002 120 apply to the Loss of Intermediate Range Nuclear Instrumentation:

Satisfactory overlap between source range, intermediate range, and power range instrumentation.

AK3.02 000036 Fuel Handling Incidents / 8 X 2.9 1 Knowledge of the reasons for the following responses as (R22) P8182L-003 105 they apply to the Fuel Handling incidents:

Interlocks associated with fuel handling equipment.

AK1.01 000037 Steam Generator Tube Leak / 3 X 2.9 1 Knowledge of the operational implications of the (R23) P8140L-242 123 following concepts as they apply to Steam Generator Tube Leak:

Use of steam tables.

AA2.02 000051 Loss of Condenser Vacuum / 4 X 3.9 1 Ability to determine and interpret the following as they (R24) P8174L-005 051 apply to the Loss of Condenser Vacuum:

Conditions requiring reactor and/or turbine trip.

AK1.01 000059 Accidental Liquid Radwaste Rel. / 9 X 2.7 1 Knowledge of the operational implications of the (R25) P8182L-001A 072 following concepts as they apply to Accidental Liquid Radwaste Release:

Types of radiation, their units of intensity, and the location of the sources of radiation in a nuclear power plant.

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

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

• 000076 High Reactor Coolant Activity / 9 000078 RCS Leak / 3 W/E01 & E02 Rediagnosis & SI Termination

/3 W/E13 Steam Generator Over-pressure / 4 EA1.1 W/E15 Containment Flooding / 5 X 2.9 1 Ability to operate and/or monitor the following as they (R26) P8176L-003 089 apply to the (Containment Flooding):

Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

W/E16 High Containment Radiation / 9 EK2.2 W/E03 LOCA Cooldown - Depress. / 4 X 3.7 1 Knowledge of the interrelations between the (LOCA (R27) P8197L-012 007 Cooldown and Depressurization) 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/E09 & E10 Natural Circ. / 4 W/E08 RCS Overcooling - PTS / 4 K/A Category Point Totals: 2 1 1 2 2 1 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 2.1.32 003 Reactor Coolant Pump X Ability to explain and apply all system limits and 3.8 1 precautions.

(R28) P8140L-209 012 A1.12 004 Chemical and Volume Control X Ability to predict and/or monitor changes in 2.8 2 parameters (to prevent exceeding design (R29) P8172L-001A 156 limits) associated with operating the CVCS controls including:

Rate of boron concentration reduction in RCS as a function of letdown flow while deborating demineralizer is in service.

K5.15 (R30) P8172L-001A 160 X Knowledge of the operational implications of 3.3 the following concepts as they apply to the CVCS:

Boron and control rod reactivity effects as they relate to MTC.

K5.05 005 Residual Heat Removal X Knowledge of the operational implications of 2.7 1 the following concepts as they apply to the (R31) P8197L-006 027 RHRS:

Plant response during solid plant pressure change due to the relative incompressibility of water.

K4.30 006 Emergency Core Cooling X Knowledge of ECCS design feature(s) and/or 3.6 1 interlock(s) which provide for the following:

(R32) P8180L-006 081 Containment isolation Ability to (a) predict the impacts of the 007 Pressurizer Relief/Quench Tank X following malfunctions or operations on the 2.6 2 PRTS; and (b) based on those predictions, (R33) use procedures to correct, control, or P8170L-003 115 mitigate the consequences of those malfunctions or operations:

A2.02 Abnormal pressure in the PRT A3.01 2.7 (R34) P8170L-003 225 X Ability to monitor automatic operation of the PRTS, including:

Components which discharge to the PRT K3.03 008 Component Cooling Water X Knowledge of the effect that a loss or 4.1 1 malfunction of the CCWS will have on the (R35) P8172L-002 107 following:

RCP A4.02 010 Pressurizer Pressure Control X Ability to manually operate and/or monitor in 3.6 1 the control room:

(R36) P8170L-005 084 PZR Heaters K6.02 012 Reactor Protection X Knowledge of the effect of a loss or malfunction 2.9 1 of the following will have on the RPS:

(R37) P8170L-006 074 Redundant channels

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 K2.01:

013 Engineered Safety Features X Knowledge of bus power supplies to the 3.6 2 Actuation following:

ESFAS / Safeguards Equipment Control (R38) P8186L-009 011 2.9 (R39) P8180L-006 044 X K5.02:

Knowledge of the operation implications of the following concepts as they apply to the ESFAS:

Safety system logic and reliability A3.01 022 Containment Cooling X Ability to monitor automatic operation of the 4.1 1 CCS, including:

(R40) P8180L-009H 057 Initiation of safeguards mode of operations.

K1.02 026 Containment Spray X Knowledge of the physical connections and/or 4.1 2 cause-effect relationships between the CSS and (R41) P8180L-002 049 the following systems:

(R42) P8180L-002 052 Cooling Water 2.7 X

K2.02 Knowledge of bus power supplies to the following:

MOVs 2.2.22 039 Main and Reheat Steam X Knowledge of limiting conditions for operations 4.0 2 and safety limits.

(R43) P8174L-001 043 X K4.07 (R44) P8174L-001 012 Knowledge of MRSS design feature(s) and/or 3.4 interlock(s) which provide for the following:

Reactor building isolation.

K3.03 059 Main Feedwater X Knowledge of the effect that a loss or 3.5 1 malfunction of the MFW will have on the (R45) P8174L-003 031 following:

S/Gs A2.05 061 Auxiliary/Emergency Feedwater X Ability to (a) predict the impacts of the following 3.1 2 malfunctions or operations on the AFW; and (b)

(R46) P8180L-007 223 based on those predictions, use procedures to (R47) P8180L-007 128 correct, control, or mitigate the consequences of 2.5 X those malfunctions or operations:

Automatic control malfunction K6.01 Knowledge of the effect of a loss or malfunction of the following will have on the AFW components:

Controllers and positioners A1.03 062 AC Electrical Distribution X Ability to predict and/or monitor changes in 2.5 1 parameters (to prevent exceeding design limits)

(R48) P8186L-008 067 associated with operating the AC distribution system controls including:

Effect on instrumentation and controls of switching power supplies.

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 2.4.3 063 DC Electrical Distribution X Ability to identify post-accident instrumentation. 3.7 2 (R49) P8186L-005 112 (R50) P8186L-005 107 K4.04 2.6 X Knowledge of DC electrical system design feature(s) and/or interlock(s) which provide for the following:

Trips K1.05 064 Emergency Diesel Generator X Knowledge of the physical connections and/or 3.4 1 cause-effect relationship between the ED/G (R51) P8186L-004 054 system and the following systems:

Starting air system A2.01 073 Process Radiation Monitoring X Ability to (a) predict the impacts of the following 2.5 1 malfunctions or operations on the PRM system; (R52) P8182L-002 014 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.

K2.04 076 Service Water X Knowledge of bus power supplies to the 2.5 1 following:

(R53) P8176L-003 010 Reactor building closed cooling water.

A4.01 078 Instrument Air X Ability to manually operate and/or monitor in the 3.1 1 control room:

(R54) P8178L-005 041 Pressure gauges A3.01 103 Containment X Ability to monitor automatic operation of the 3.9 1 containment system, including:

(R55) P8180L-006 080 Containment isolation 053 Integrated Control K/A Category Point Totals: 2 3 2 3 3 2 2 3 3 2 3 Group Point Total: 28 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 K6.12 002 Reactor Coolant X Knowledge of the effect of a loss or malfunction of 3.0 1 the following RCS Components:

(R56) P8170L-003 063 Code safety valves 011 Pressurizer Level Control

ES-401 9 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 K4.06 014 Rod Position Indication X Knowledge of RPIS design feature(s) and/or 3.4 1 interlock(s) which provide for the following:

(R57) P8184L-005 144 Individual and group misalignment A2.04 015 Nuclear Instrumentation X Ability to (a) predict the impacts of the following 3.3 1 malfunctions or operations on the NIS; and (b)

(R58) P8140L-200 ATT 23 013 based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Effects on axial flux density of control rod alignment and sequencing, xenon production and decay, and boron vs. control rod reactivity changes.

2.1.19 016 Non-nuclear Instrumentation X Ability to use plant computer to evaluate system or 3.9 1 component status.

(R59) P8180L-003 079 017 In-core Temperature Monitor K2.01 028 Hydrogen Recombiner X Knowledge of bus power supplies to the following: 2.5* 1 and Purge Control Hydrogen recombiners (R60) P8180L-008 009 K3.02 029 Containment Purge X Knowledge of the effect that a loss or malfunction 2.9* 1 of the CPS will have on the following:

(R63) P8130L-003 050 Containment entry 033 Spent Fuel Pool Cooling A1.02 034 Fuel Handling Equipment X Ability to predict and/or monitor changes in 2.9 1 parameters (to prevent exceeding design limits)

(R61) P8182L-003 104 associated with operating the Fuel Handling System Controls including:

Water level in the refueling canal 035 Steam Generator 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste

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 A4.14 071 Waste Gas Disposal X WGDS system alarms 2.8 1 (R62) P8182L-001C 020 072 Area Radiation Monitoring rejected 075 Circulating Water K1.01 079 Station Air X Knowledge of the physical connections and/or 3.0 1 cause-effect relationship between SAS and the (R64) P8178L-005 008 following systems:

IAS K5.04 086 Fire Protection X Knowledge of the operational implication of the 2.9 1 following concepts as they apply to the Fire (R65) P8178L-002 050 Protection System:

Hazards to personnel as a result of fire type and methods of protection 050 Control Room Ventilation K/A Category Point Totals: 1 1 1 1 1 1 1 1 0 1 1 Group Point Total: 9

ES-401 11 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 000015 RCP Malfunctions / 4 000022 Loss of Rx Coolant Makeup / 2 000025 Loss of RHR System / 4 000026 Loss of Component Cooling Water / 8 000027 Pressurizer Pressure Control System Malfunction / 3 000029 ATWS / 1 000038 Steam Gen. Tube Rupture / 3 AA2.05 W/E12 Steam Line Rupture - Excessive X Ability to determine and interpret the 4.5 1 Heat Transfer / 4 following as they apply to the Steam line Rupture:

(S76) P8140L-239 1 When ESFAS systems may be secured.

000054 Loss of Main Feedwater / 4 EA2.03 000055 Station Blackout / 6 X Ability to determine or interpret the following 4.7 1 as they apply to a Station Blackout:

(S77) P8197L-011 206 Actions necessary to restore power.

000056 Loss of Off-site Power / 6 2.2.40 000057 Loss of Vital AC Inst. Bus / 6 X Ability to apply technical specifications for a 4.7 1 system.

(S78) P8186L-015 031

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 2.4.41 000058 Loss of DC Power / 6 X Emergency Procedures / Plan: 4.6 1 Knowledge of the emergency action level (S79) P7410-034 146 thresholds and classifications.

000062 Loss of Nuclear Svc Water / 4 000065 Loss of Instrument Air / 8 2.1.23 000077 Generator Voltage and Electric X Conduct of Operations: 4.4 1 Grid Disturbances / 6 Ability to perform specific system and integrated plant procedures during all modes of plant (S80) P8186L-002 091 operation.

EA2.2 W/E04 LOCA Outside Containment / 3 X Ability to determine and interpret the 4.2 1 following as they apply to the (LOCA Outside (S81) P8171L-014 058 Containment):

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

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 13 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 A2.12 000028 Pressurizer Level Malfunction / 2 X 3.5 1 Ability to determine and interpret the (S82) P8140L-237 001 following as they apply to the Pressurizer Level Control Malfunctions:

Cause for PZR level deviation alarm:

Controller malfunction or other instrumentation malfunction A2.02 000032 Loss of Source Range NI / 7 X 3.9 1 Ability to determine and interpret the (S83) P8184L-002 143 following as they apply to the Loss of Source Range Nuclear Instrumentation:

Expected change in source range count rate when rods are moved.

000033 Loss of Intermediate Range NI / 7 000036 Fuel Handling Incidents / 8 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 2.4.30 000067 Plant Fire On-site / 8 X 4.1 1 Emergency Procedures / Plan (S84) P8140L-229 005 Knowledge of events related to system operations / status that must be reported to internal organizations or outside agencies such as the State, the NRC, or the transmission system operator.

000068 Control Room Evac. / 8 W/E14 Loss of CTMT Integrity / 5

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 W/E06 & E07 Inad. Core Cooling / 4 000076 High Reactor Coolant Activity / 9 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 W/E03 LOCA Cooldown - Depress. / 4 2.2.44 W/E09 & E10 Natural Circ. / 4 X 4.4 1 Equipment Control (S85) P8197-011 239 Ability to interpret control room indications to verify the status and operation of a system and understand how operator actions and directives affect plant and system conditions.

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 004 Chemical and Volume Control 005 Residual Heat Removal A2.02 006 Emergency Core Cooling X Ability to (a) predict the impacts of 4.3 1 the following malfunctions on the (S86) P8197L-012 242 ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Loss of flow path 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 010 Pressurizer Pressure Control A2.06 012 Reactor Protection X Ability to (a) predict the impacts of 4.7 1 the following malfunctions on the (S87) P7410L-034 030 RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Failure of RPS signal to trip the reactor 013 Engineered Safety Features Actuation A2.05 022 Containment Cooling X Ability to (a) predict the impacts of 3.5 1 the following malfunctions on the (S88) P8180L-009H 054 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 039 Main and Reheat Steam 2.4.6 059 Main Feedwater X Knowledge of EOP mitigation strategies. 4.7 1 (S89) P8140L-241 001

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 4 061 Auxiliary/Emergency Feedwater 062 AC Electrical Distribution 063 DC Electrical Distribution 2.2.25 064 Emergency Diesel Generator X Knowledge of the bases in technical 4.2 1 specifications for limiting conditions for (S90) P8186L-014 084 operations and safety limits.

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 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 A2.07 001 Control Rod Drive X Ability to (a) predict the impacts of the 4.4 1 following malfunctions on the CRDS; (S91) P8140L-224 005 and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Effect of reactor trip on primary and secondary parameters and systems.

002 Reactor Coolant 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 055 Condenser Air Removal 056 Condensate

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 4 068 Liquid Radwaste 071 Waste Gas Disposal A2.03 072 Area Radiation Monitoring X Ability to (a) predict the impacts of the 2.9 1 following malfunctions on the ARM (S92) P8182L-002 090 system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Blown power supply fuses 075 Circulating Water 079 Station Air 2.2.4 086 Fire Protection X Ability to explain the variations in control 3.6 1 board layouts, systems, instrumentation, (S93) P8197L-009 036 and procedural actions between units at a facility. (multi unit) 050 Control Room Ventilation 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:

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

Knowledge of conduct of operations requirements.

2.1.1 (R66) P8140L-201 068 3.8 1 Knowledge of primary and secondary chemistry limits.

1. 2.1.34 (R67) P8180L-005 019 2.7 1 Conduct Ability to use procedures to determine the effects on reactivity of of Operations 2.1.43 plant changes. 4.1 1 (R68) PI-OPS-GFE-192004 001 Subtotal 3 Knowledge of the process for conducting special or infrequent 2.2.7 tests. 2.9 1 (R69) P8140L-201 071 Knowledge of tagging and clearance procedures.

2. 2.2.13 (R70) FL-WMN-SHE-002L 001 4.1 1 Equipment Control Subtotal 2 Ability to use radiation monitoring systems.

2.3.5 (R71) P8182L-002 091 2.9 1 Ability to comply with radiation work permit requirements during normal or abnormal conditions. 3.5 1 2.3.7

3. (R72) P8182L-005 002 Radiation Control Subtotal 2 Knowledge of general guidelines for EOP usage.

2.4.14 (R73) P8197L-010 037 3.5 1 Knowledge of RO tasks performed outside the main control room

4. 2.4.34 during an emergency and the resultant operational effects. 4.2 1 Emergency (R74) P8197L-009 037 Procedures / Ability to prioritize and interpret the significance of each Plan 2.4.45 annunciator or alarm. 4.1 1 (R75) P8197L-012 250 Subtotal 3 Tier 3 Point Total Tier 3 Point 10 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 #

Knowledge of refueling administrative requirements.

2.1.40 (S94) P8182L-003 056 3.9 1 Knowledge of how to conduct system lineups, such as valves,

1. 2.1.29 breakers, and switches, etc. 4.0 1 Conduct (S95) P9150L-024 044 of Operations Subtotal 2 Ability to track Technical Specification limiting conditions for 2.2.23 operations. 4.6 1 (S96) P8171L-014 060 Ability to determine operability and/or availability of safety related

2. 2.2.37 equipment. 4.6 1 Equipment (S97) P8171L-009 009 Control Subtotal 2 Knowledge of radiation or contamination hazards that may arise 2.3.14 during normal, abnormal, or emergency conditions or activities. 3.8 1 (S98) P8182L-002 001 3.

Radiation Control Subtotal 1 Knowledge of the lines of authority during implementation of an 2.4.37 emergency plan. 4.1 1 (S99) FL-BEP-ORO-001F 001

4. Knowledge of emergency communications systems and Emergency 2.4.43 techniques. 3.8 1 Procedures / (S100) P7410L-034 145 Plan Subtotal 2 Tier 3 Point Total Tier 3 7 Point Total

ES-401 Record of Rejected K/As (RO) Form ES-401-4 Tier / Randomly Selected Reason for Rejection Group K/A 2/2 075 K3.07 Unable to develop Q to match K/A w/o adding multiple levels of difficulty beyond what K/A requires. Replaced with 029 CTMT Purge System K3.02 2/1 007 A2.06 Low operational validity. Pulling bubble in PRZE does not impact the PRT.

Replaced with 007 PRTS A2.04 1/2 059 AK1.05 Low operational validity; replaced with 059 K1.05 2/1 007 A2.04 Low operational validity; replaced with 007 A2.02

ES-401 Record of Rejected K/As (SRO) Form ES-401-4 Tier / Randomly Selected Reason for Rejection Group K/A 1/2 032 A2.02 At Prairie Island this is RO only knowledge 3 2.1.45 Unable to write Q w/o using system specific information. Replaced with 2.1.29