ML093200401

2009-08-FINAL Outlines

ML093200401
Person / Time
Site:	Wolf Creek
Issue date:	11/16/2009
From:	Apger G NRC Region 4
To:	Wolf Creek
References
50-482/09-301
Download: ML093200401 (29)

Text

ES-401 Written Examination Outline Form ES-401-2 Wolf Creek 2009 NRC Facility: Date of Exam: 8/17/2009 Examination RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4 *

1. 1 3 3 3 3 3 3 18 3 3 6 Emergency

& 2 2 2 1 1 2 1 9 2 2 4 Plant Tier Evolutions 5 5 4 4 5 4 27 5 5 10 Totals 1 2 2 2 3 2 2 3 3 3 3 3 28 2 3 5 2.

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

3. Generic Knowledge & Abilities 10 7 Categories 2 3 2 3 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 that are not included on the outline should be added. Refer to section D.1.b of ES-401, for guidance regarding 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 KAs 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 (IR) 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 10CFR55.43 1

ES-401 2 Form ES-401-2 Wolf Creek 2009 NRC Examination Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # / Name Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#

AA2.32 - Ability to determine and interpret the following as they apply to the Loss of 056 / Loss of Off-site Power / 6 X 4.3 76 Offsite Power: Transient trend of coolant temperature toward no-load T-ave EA2.14 - Ability to determine or interpret the following as they apply to a Large 011 / Large Break LOCA / 3 X 4.0 77 Break LOCA: Actions to be taken if limits for PTS are violated AA2.02 - Ability to determine and interpret the following as they apply to the Loss of 058 / Loss of DC Power / 6 X 3.6 78 DC Power: 125V dc bus voltage, low/critical low, alarm E05 / Inadequate Heat Transfer - 2.4.18 - Emergency Procedures / Plan:

X 4.0 79 Loss of Secondary Heat Sink / 4 Knowledge of the specific bases for EOPs.

2.1.25 - Conduct of Operations: Ability to 009 / Small Break LOCA / 3 X interpret reference materials, such as 4.2 80 graphs, curves, tables, etc.

2.4.2 - Emergency Procedures / Plan:

E12 / Steam Line Rupture - Knowledge of system set points, interlocks X 4.6 81 Excessive Heat Transfer / 4 and automatic actions associated with EOP entry conditions.

EK1.02 - Knowledge of the operational implications of the following concepts as 055 / Station Blackout / 6 X 4.1 39 they apply to the Station Blackout : Natural circulation cooling AK1.02 - Knowledge of the operational implications of the following concepts as 054 / Loss of Main Feedwater / 4 X they apply to Loss of Main Feedwater 3.6 40 (MFW): Effects of feedwater introduction on dry S/G EK1.01 - Knowledge of the operational implications of the following concepts as 011 / Large Break LOCA / 3 X they apply to the Large Break LOCA: 4.1 41 Natural circulation and cooling, including reflux boiling.

EK2.1 - Knowledge of the interrelations between the (Loss of Emergency Coolant Recirculation) and the following:

E11 / Loss of Emergency Coolant X Components, and functions of control and 3.6 42 Recirculation / 4 safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

EK2.1 - Knowledge of the interrelations between the (Uncontrolled Depressurization of all Steam Generators)

E12 / Steam Line Rupture - and the following: Components, and X 3.4 43 Excessive Heat Transfer / 4 functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

AK2.01 - Knowledge of the interrelations 008 / Pressurizer Vapor Space X between the Pressurizer Vapor Space 2.7 44 Accident / 3 Accident and the following: Valves EK3.01 - Knowledge of the reasons for the 007 / Reactor Trip - Stabilization -

X following as the apply to a reactor trip: 4.0 45 Recovery / 1 Actions contained in EOP for reactor trip AK3.01 - Knowledge of the reasons for the following responses as they apply to the 056 / Loss of Off-site Power / 6 X 3.5 46 Loss of Offsite Power: Order and time to initiation of power for the load sequencer

ES-401 3 Form ES-401-2 Wolf Creek 2009 NRC Examination Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # / Name Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#

EK3.4 - Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink) RO or SRO E05 / Inadequate Heat Transfer - function within the control room team as X 3.7 47 Loss of Secondary Heat Sink / 4 appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

EA1.2 - Ability to operate and / or monitor E04 / LOCA Outside Containment / the following as they apply to the (LOCA X 3.6 48 3 Outside Containment) Operating behavior characteristics of the facility.

EA1.19 - Ability to operate and monitor the 038 / Steam Generator Tube X following as they apply to a SGTR: MFW 3.4 49 Rupture / 3 System status indicator AA1.11 - Ability to operate and / or monitor 025 / Loss of Residual Heat the following as they apply to the Loss of X 2.9 50 Removal System / 4 Residual Heat Removal System: Reactor building sump level indicators AA2.13 - Ability to determine and interpret 027 / Pressurizer Pressure Control the following as they apply to the X 2.8 51 System Malfunction / 3 Pressurizer Pressure Control Malfunctions:

Seal return flow AA2.19 - Ability to determine and interpret the following as they apply to the Loss of 057 / Loss of Vital AC Electrical X Vital AC Instrument Bus: The plant 4.0 52 Instrument Bus / 6 automatic actions that will occur on the loss of a vital ac electrical instrument bus AA2.07 - Ability to determine and interpret the following as they apply to Generator 077 / Generator Voltage and X Voltage and Electric Grid Disturbances: 3.6 53 Electric Grid Disturbances Operational status of engineered safety features 2.1.23 - Conduct of Operations: Ability to 026 / Loss of Component Cooling perform specific system and integrated X 4.3 54 Water / 8 plant procedures during all modes of plant operation.

022 / Loss of Reactor Coolant 2.2.40 - Equipment Control: Ability to apply X 3.4 55 Makeup / 2 technical specifications for a system.

2.1.30 - Conduct of Operations: Ability to 029 / Anticipated Transient Without X locate and operate components, including 4.4 56 Scram (ATWS) / 1 local controls K/A Category Totals: 3 3 3 3 3/3 3/3 Group Point Total: 18/6

ES-401 4 Form ES-401-2 Wolf Creek 2009 NRC Examination Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE # / Name Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#

AA2.05 - Ability to determine and interpret 037 / Steam Generator Tube Leak / the following as they apply to the Steam X 3.3 82 3 Generator Tube Leak: Past history of leakage with current problem EA2.1 - Ability to determine and interpret the following as they apply to the (Natural E10 / Natural Circulation with Steam Circulation with Steam Void in Vessel X 3.9 83 Void in Vessel with/without RVLIS / 4 with/without RVLIS) Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

2.1.28 - Conduct of Operations: Knowledge E06 / Degraded Core Cooling / 4 X of the purpose and function of major system 4.1 84 components and controls.

2.4.4 - Emergency Procedures / Plan:

Ability to recognize abnormal indications for 076 / High Reactor Coolant Activity /

X system operating parameters which are 4.7 85 9

entry-level conditions for emergency and abnormal operating procedures.

AK1.01 - Knowledge of the operational 061 / Area Radiation Monitoring implications of the following concepts as X 2.5 57 (ARM) System Alarms / 7 they apply to Area Radiation Monitoring (ARM) System Alarms: Detector limitations AK2.01 - Knowledge of the interrelations 036 / Fuel Handling Incidents / 8 X between the Fuel Handling Incidents and 2.9 58 the following: Fuel handling equipment EK3.1 - Knowledge of the reasons for the following responses as they apply to the (High Containment Pressure) Facility operating characteristics during transient E14 / High Containment Pressure /

X conditions, including coolant chemistry and 3.2 59 5

the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.

AA1.04 - Ability to operate and / or monitor 051 / Loss of Condenser Vacuum / 4 X the following as they apply to the Loss of 2.5 60 Condenser Vacuum: Rod position AA2.04 - Ability to determine and interpret the following as they apply to the 059 / Accidental Liquid RadWaste X Accidental Liquid Radwaste Release: The 3.2 61 Release / 9 valve lineup for a release of radioactive liquid 2.2.39 - Equipment Control: Knowledge of 003 / Dropped Control Rod / 1 X less than one hour technical specification 3.9 62 action statements for systems.

AK2.01 - Knowledge of the interrelations 076 / High Reactor Coolant Activity / between the High Reactor Coolant Activity X 2.6 63 9 and the following: Process radiation monitors AA2.03 - Ability to determine and interpret the following as they apply to the 028 / Pressurizer Level Control X Pressurizer Level Control Malfunctions: 2.8 64 Malfunction / 2 Charging subsystem flow indicator and controller AK1.04 - Knowledge of the operational implications of the following concepts as 005 / Inoperable/Stuck Control Rod / they apply to Inoperable / Stuck Control X 3.0 65 1 Rod: Definitions of axial imbalance, neutron error, power demand, actual power tracking mode, ICS tracking

ES-401 5 Form ES-401-2 Wolf Creek 2009 NRC Examination Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE # / Name Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Q#

2/ 1/

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

ES-401 6 Form ES-401-2 Wolf Creek 2009 NRC Examination Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A A System # / Name G Imp. Q#

1 2 3 4 5 6 1 2 3 4 A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the P S; and (b) based 007 Pressurizer Relief/Quench X on those predictions, use procedures to 3.2 86 Tank correct, control, or mitigate the consequences of those malfunctions or operations: Abnormal pressure in PRT A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) 010 Pressurizer Pressure based on those predictions, use X 4.2 87 Control procedures to correct, control, or mitigate the consequences of those malfunctions or operations: PORV failures 2.4.9 - Emergency Procedures / Plan:

Knowledge of low power / shutdown 022 Containment Cooling X implications in accident (e.g., loss of 4.2 88 coolant accident or loss of residual heat removal) mitigation strategies.

2.4.30 - Emergency procedures/plan:

Knowledge of events related to system operation / status that must be reported 003 Reactor Coolant Pump X 4.1 89 to internal organizations or external agencies, such as the state, the NRC, or the transmission system operator.

2.1.25 - Conduct of Operations: Ability 039 Main and Reheat Steam X to interpret reference materials, such 4.2 90 as graphs, curves, tables, etc.

K1.08 - Knowledge of the physical connections and/or cause-effect 103 Containment X relationships between the containment 3.6 1 system and the following systems: SIS, including action of safety injection reset K1.08 - Knowledge of the physical 010 Pressurizer Pressure connections and/or cause-effect X 3.2 2 Control relationships between the PZR PCS and the following systems: PZR LCS K2.01 - Knowledge of bus power 003 Reactor Coolant Pump X 3.1 3 supplies to the following: RCPS K2.02 - Knowledge of bus power 006 Emergency Core Cooling X supplies to the following: Valve 2.5 4 operators for accumulators K3.01 - Knowledge of the effect that a 073 Process Radiation loss or malfunction of the PRM system X 3.6 5 Monitoring will have on the following: Radioactive effluent releases K3.01 - Knowledge of the effect that a 064 Emergency Diesel loss or malfunction of the ED/G system X 3.8 6 Generator will have on the following: Systems controlled by automatic loader K4.02 - Knowledge of SWS design feature(s) and/or interlock(s) which 076 Service Water X provide for the following: Automatic 2.9 7 start features associated with SWS pump controls

ES-401 7 Form ES-401-2 Wolf Creek 2009 NRC Examination Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A A System # / Name G Imp. Q#

1 2 3 4 5 6 1 2 3 4 K4.01 - Knowledge of CCWS design 008 Component Cooling feature(s) and/or interlock(s) which X 3.1 8 Water provide for the following: Automatic start of standby pump K5.09 - Knowledge of the operational implications of the following concepts 005 Residual Heat Removal X 3.2 9 as they apply the RHRS: Dilution and boration considerations K5.03 - Knowledge of the operational 061 Auxillary/Emergency implications of the following concepts X 2.6 10 Feedwater as the apply to the AFW: Pump head effects when control valve is shut K6.13 - Knowledge of the effect of a loss or malfunction on the following 004 Chemical and Volume X CVCS components: Purpose and 3.1 11 Control function of the boration/dilution batch controller K6.01 - Knowledge of the effect of a 013 Engineered Safety loss or malfunction on the following will X 2.7 12 Features Actuation have on the ESFAS: Sensors and detectors A1.01 - Ability to predict and/or monitor Changes in parameters (to prevent 012 Reactor Protection X exceeding design limits) associated 2.9 13 with operating the RPS controls including: Trip setpoint adjustment A1.01 - Ability to predict and/or monitor changes in parameters associated with 063 DC Electrical Distribution X operating the dc electrical system 2.5 14 controls including: Battery capacity as it is affected by discharge rate A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures 059 Main Feedwater X 3.4 15 to correct, control, or mitigate the consequences of those malfunctions or operations: Feedwater Actuation of AFW System A2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based 022 Containment Cooling X on those predictions, use procedures to 2.9 16 correct, control, or mitigate the consequences of those malfunctions or operations: Loss of service water A3.02 - Ability to monitor automatic 039 Main and Reheat Steam X operation of the MRSS, including: 3.1 17 Isolation of the MRSS A3.01 - Ability to monitor automatic 026 Containment Spray X operation of the CSS, including: Pump 4.3 18 starts and correct MOV positioning A4.01 - Ability to manually operate and/or monitor in the control room: All 062 AC Electrical Distribution X 3.3 19 breakers (including available switchyard)

A4.01 - Ability to manually operate 078 Instrument Air X and/or monitor in the control room: 3.1 20 Pressure gauges

ES-401 8 Form ES-401-2 Wolf Creek 2009 NRC Examination Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A A System # / Name G Imp. Q#

1 2 3 4 5 6 1 2 3 4 2.4.50 - Emergency Procedures / Plan:

007 Pressurizer Relief/Quench Ability to verify system alarm setpoints X 4.2 21 Tank and operate controls identified in the alarm response manual.

2.4.6 - Emergency Procedures / Plan:

063 DC Electrical Distribution X Knowledge of EOP mitigation 3.7 22 strategies.

A3.01 - Ability to monitor automatic 078 Instrument Air X operation of the IAS, including: Air 3.1 23 pressure A1.02 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated 076 Service Water X 2.6 24 with operating the SWS controls including: Reactor and turbine building closed cooling water temperatures.

K4.06 - Knowledge of RHRS design feature(s) and/or interlock(s) which 005 Residual Heat Removal X 2.7 25 provide or the following: Function of RHR pump miniflow recirculation 2.1.20 - Conduct of Operations: Ability 026 Containment Spray X to interpret and execute procedure 4.6 26 steps..

A2.05 - Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to 012 Reactor Protection X 3.1 27 correct, control, or mitigate the consequences of those malfunctions or operations: Faulty or erratic operation of detectors and function generators A4.18 - Ability to manually operate 004 Chemical and Volume X and/or monitor in the control room: 4.3 28 Control Emergency borate valve 3 3 K/A Category Totals: 2 2 2 3 2 2 3 / 3 3 / Group Point Total: 28/5 2 3

ES-401 9 Form ES-401-2 Wolf Creek 2009 NRC Examination Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A A System # / Name G Imp. Q#

1 2 3 4 5 6 1 2 3 4 A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those 075 Circulating Water X 3.2 91 predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Loss of intake structure 2.1.28 - Conduct of Operations:

Knowledge of the purpose and function 011 Pressurizer Level Control X 4.1 92 of major system components and controls.

A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the RCS; and (b) based on those predictions, use 002 Reactor Coolant X 4.3 93 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of forced circulation A4.01 - Ability to manually operate 014 Rod Position Indication X and/or monitor in the control room: Rod 3.3 29 selection control K6.02 - Knowledge of the effect of a loss or malfunction on the following will 015 Nuclear Instrumentation X 2.6 30 have on the NIS:

Discriminator/compensation circuits 2.4.6 - Emergency Procedures / Plan:

016 Non-nuclear X Knowledge of EOP mitigation 3.7 31 Instrumentation strategies.

K4.02 - Knowledge of MT/G system design feature(s) and/or inter-lock(s) which provide for the following:

045 Main Turbine Generator X 2.5 32 Automatic shut of reheat stop valves as well as main control valves when tripping turbine 027 Containment Iodine K2.01 - Knowledge of bus power X 3.1 33 Removal supplies to the following: Fans K1.07 - Knowledge of the physical connections and/or cause effect X relationships between the Liquid 068 Liquid Radwaste 2.7 34 Radwaste System and the following systems: Sources of liquid wastes for LRS A1.02 - Ability to predict and/or monitor changes in parameter (to prevent 028 Hydrogen Recombiner and X exceeding design limits) associated 3.4 35 Purge Control with operating the HRPS controls including: Containment pressure A4.01 - Ability to manually operate 086 Fire Protection X and/or monitor in the control room: Fire 3.3 36 Water pumps A3.02 - Ability to monitor automatic operation of the ITM system including:

017 In-core Temperature X Measurement of in-core thermocouple 3.4 37 Monitor temperatures at panel outside control room

ES-401 10 Form ES-401-2 Wolf Creek 2009 NRC Examination Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A A System # / Name G Imp. Q#

1 2 3 4 5 6 1 2 3 4 A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the SDS; and (b) 041 Steam Dump/Turbine X based on those predictions or mitigate 3.6 38 Bypass Control the consequences of those malfunctions or operations: Steam valve stuck open 1 1 K/A Category Totals: 1 1 0 1 0 1 1 / 1 2 / Group Point Total: 10/3 2 1

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Wolf Creek 2009 NRC Examination Date: 8/17/2009 RO SRO-Only Category K/A # Topic IR Q# IR Q#

Knowledge of procedures and limitations 2.1.36 4.1 94 involved in core alterations.

1.

Ability to interpret reference materials, such as Conduct 2.1.25 3.9 66 graphs, curves, tables, etc.

of Operations Knowledge of facility requirements for controlling 2.1.13 2.5 67 vital / controlled access.

Subtotal 2 1 Knowledge of the process used to track 2.2.43 3.3 95 inoperable alarms.

Knowledge of the process for making changes to 2.2.6 3.6 98 procedures.

Ability to determine Technical Specification 2.2.35 3.6 68

2. Mode of Operation.

Equipment Ability to analyze the effect of maintenance Control 2.2.36 activities, such as degraded power sources, on 3.1 69 the status of limiting conditions for operations.

Ability to perform pre-startup procedures for the facility, including operating those controls 2.2.1 4.5 75 associated with plant equipment that could affect reactivity.

Subtotal 3 2 Knowledge of Radiological Safety Procedures pertaining to licensed operator duties, such as 3.

response to radiation monitor alarms, Radiation 2.3.13 3.8 96 containment entry requirements, fuel handling Control responsibilities, access to locked high radiation areas, aligning filters, etc.

Knowledge of radiation exposure limits under 2.3.4 3.7 99 normal or emergency conditions.

Knowledge of radiation or contamination hazards 2.3.14 that may arise during normal, abnormal, or 3.4 70 emergency conditions or activities.

Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable 2.3.15 2.9 71 survey instruments, personnel monitoring equipment, etc.

11

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Subtotal 2 2 Knowledge of the organization of the operating 2.4.5 procedures network for normal, abnormal, and 4.3 97 emergency evolutions.

Ability to prioritize and interpret the significance 2.4.45 4.3 100 of each annunciator or alarm.

4.

Emergency Procedures / 2.4.25 Knowledge of fire protection procedures. 3.3 72 Plan 2.4.11 Knowledge of abnormal condition procedures. 4.0 73 Knowledge of RO tasks performed outside the 2.4.34 main control room during an emergency and the 4.2 74 resultant operational effects.

Subtotal 3 2 Tier 3 Point Total 10 7 12

ES-401 Record of Rejected K/As Form ES-401-4 Randomly Selected Tier / Group Reason for Rejection K/A 065 / 2.1.30 Excessive similar topic coverage for Instrument Air 1/1 replaced by 029 system

/ 2.1.30 103 / K1.07 2/1 replaced by 103 System does not exist at this facility

/ K1.08 005 / K4.12 2/1 replaced by 005 Piggyback mode not used at facility

/ K4.06 014 / A4.03 Operationally insignificant and indication is not available 2/2 replaced by 014 in control room

/ A4.01 072 / K1.03 No interface between ARMs and FHB Ventilation at this 2/2 replaced by 072 facility

/ A4.01 072 / K1.02 This was a replacement for K1.03 but this is also not 2/2 replaced by 072 supported at facility.

/ A4.01 072 / K4.02 This topic was a random reselection but topic not 2/2 replaced by 072 supported by facility design

/ A4.01 059 / A2.04 Original topic was direct overlap with another test item on 2/1 replaced by 059 exam (Question 40)

/ A2.01 Original topic not operationally significant and no facility 068 K5.04 reference to support a test item at the license level 2/2 replaced by 068 required for examination K1.07 Original topic operationally insignificant and function not 072 A4.01 performed by operations staff. No operations references 2/2 replaced by 086 support topic.

A4.01 Formation of a pressurizer bubble has no impact on the 007 A2.06 PRT, and the PRT is not used in any way for bubble 2/1 replaced by 007 formation at this facility.

A2.02 There is no LCO related to component related to 003 G2.2.36 degraded power sources, and the reference for 2/1 replaced by 003 degraded power sources is very limited, resulting in G2.4.30 overlap with Question 53.

026 G2.2.22 Could not develop question at appropriate license level 2/1 replaced by 026 for selected topic 13

ES-401 Record of Rejected K/As Form ES-401-4 G2.1.20 Could not develop question at appropriate license level G2.2.7 replaced 3/2 for selected topic by G2.2.1 14

ES-301, Rev. 9 Administrative Topics Outline Final Form ES-301-1

{PRIVATE }Facility: ______Wolf Creek________ Date of Examination: __Aug 31 - Sept 4, 2009___

Examination Level: RO SRO X Operating Test Number: __________

Administrative Topic Type Code* Describe activity to be performed (see Note)

Complete a 1/M plot and determine the estimated critical Conduct of Operations R, M position and required actions.

(S.A.1.a) 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of operation. (CFR 41.10 / 43.5 /

45.2 / 45.6) (RO/SRO IR = 4.3 / 4.4)

Review completed dilution requirement calculation for one hour Conduct of Operations after a power reduction.

N, R (S.A.1.b) 2.1.37 Knowledge of procedures, guidelines or limitations associated with reactivity management. (CFR 41.1 / 43.6 /

45.6) (RO /SRO IR = 4.3 / 4.6)

Using a completed surveillance (STS AL-101, MDAFW Pump Equipment Control A Inservice Pump Test), evaluate acceptance criteria.

R, N (S.A.2) 2.2.12 Knowledge of surveillance procedures (CFR 41.10 /

45.13) (RO / SRO IR = 3.7 / 4.1)

Given a Liquid Release Permit determine if it is ready to be Radiation Control authorized for release to the environment.

N, R (S.A.3) 2.3.6 Ability to approve release permits. (CFR 41.13 / 43.4 /

45.10) (RO / SRO IR = 2.0 / 3.8)

In the simulator setting, perform the E-Plan classification.

Emergency Plan S, N 2.4.41 Knowledge of the emergency action level thresholds and classifications. (CFR 41.10 / 43.5 / 45.11) (RO/SRO IR = 2.9 /

(S.A.4) 4.6)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1

{PRIVATE }Facility: ______Wolf Creek________ Date of Examination: __Aug 31 - Sept 4, 2009___

Examination Level: RO x SRO Operating Test Number: __________

Administrative Topic Type Code* Describe activity to be performed (see Note)

Complete 1/M plot and determine the estimated critical Conduct of Operations position.

R, M (R.A.1.a) 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of operation. (CFR 41.10 / 43.5 /

45.2 / 45.6) (RO/SRO IR = 4.3 / 4.4)

Determine dilution requirements for one hour after a power Conduct of Operations reduction.

R, N (R.A.1.b) 2.1.37 Knowledge of procedures, guidelines or limitations associated with reactivity management. (CFR 41.1 / 43.6 /

45.6) (RO /SRO IR = 4.3 / 4.6)

Complete the calculation for surveillance STS AL-101, Equipment Control MDAFW Pump A Inservice Pump Test, evaluate/recommend N, R operable/inoperable and required actions.

(R.A.2) 2.2.12 Knowledge of surveillance procedures (CFR 41.10 /

45.13) (RO / SRO IR = 3.7 / 4.1)

Given radiological conditions evaluate the most efficient Radiation Control method to limit radiological exposure based on DAC hours.

R, N (R.A.3) 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR 41.12 / 45.9 /

45.10) (RO/SRO IR = 3.2 / 3.7)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

ES-301 Control Room/In-Plant Systems Outline Final Form ES-301-2 Facility: Wolf Creek Date of Examination: Aug. 31 -

Sept. 4, 2009 Examination Level: RO SRO Operating Test Number:

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Bolded font = alternate path System / JPM Title Type Code* Safety Function

a. 014 - Rod Position Indication System N, E, S 1 S1 -- Perform actions to retrieve a dropped or misaligned control rod.

(A2.04)

RO/SRO-I

b. 013 - Engineered Safety Features Actuation System (ESFAS) N, EN, S, A 2 S2 -- Perform actions to ensure CSAS actuated correctly. (Auto CSAS failed, candidate manually initiates CSAS)

(A4.01)

PRA: ESFAS is a Top 10 Risk Significant System at Wolf Creek RO/SRO-I/SRO-U

c. 006 - Emergency Core Cooling System (ECCS) M, A, S, E 3 S3 -- Perform action to ensure transfer of ECCS flowpath. (EJ HIS-8840 fails to open)

(A3.08)

PRA: BN & EJ are Top 10 Risk Significant System.

RO/SRO-I

d. 076 - Service Water System (SWS) N, S, A 4S S4 -- Perform actions to start Service Water pump or an Essential Service Water pump. (Service water pumps fail to start)

(A2.01)

PRA: Core Damage Frequency by Initiating Event (Loss of Service Water)

RO/SRO-I

e. 071 - Waste Gas Disposal System (WGDS) N, S 9 S5 -- Perform actions to set process radiation monitor alarm setpoints for Vent Release Permit for Waste Gas Decay Tank.

(A4.25)

RO/SRO-I/SRO-U

f. 016 - Non-Nuclear Instrumentation System N, A, S 7 S6 -- Perform actions to manually trip the Main Turbine. (Auto Turbine trip fails)

(K4.03)

RO/SRO-U

g. 029 - Containment Purge System (CPS) N, A, S 8 S7 -- Perform actions to ensure Containment Purge System isolation. (Auto CPIS fails, manual action required)

(A3.01)

RO/SRO-I

h. 007 - Pressurizer Relief Tank (PRT) N, S 5 S8 -- Perform actions to identify and isolate stuck open PORV.

(A2.01)

RO/SRO-I

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. 063 - DC Electrical Distribution System D, P, L, E 6 P1 -- Perform actions of EMG C-0 Attachment C, DC Load Shed for NK11, NK12, NK13 and NK14.

(K2.01)

PRA: Risk significant system (NK); Core Damaging Frequency by Initiating Event (Loss of Offsite Power); CD Events - LERF (P = 2004 NRC exam)

RO/SRO-I/SRO-U

j. 061 - Auxiliary / Emergency Feedwater (AFW) System N, EN, L 4S P2 -- Perform actions to cooldown the TDAFWP piping to restore AFW to > 270,000 LBM per hour.

(A2.06)

PRA: Risk significant system (AL)

RO/SRO-I

k. 006 - Emergency Core Cooling System (ECCS) N, R, E 3 P3 -- Perform Attachment B of OFN BG-045, Gas Binding of CCPs or SI Pumps - vent the SI pump due to gas binding.

(A2.04)

SOER 97-1, Potential Loss of High Pressure Injection and Charging Capability from Gas Intrusion RO/SRO-I/SRO-U

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility: __Wolf Creek_______ Scenario No.: ___1____ Op-Test No.: _______

Examiners: ____________________________ Operators: __________________________

Initial Conditions: The plant is at 100% power. The A ESW pump and the A EDG are tagged out of service.

Turnover: The A ESW pump is OOS for an upper motor bearing replacement, which causes the A EDG to be OOS. The National Weather Service has issued a Severe Thunderstorm Warning for Shawnee and Butler counties. Topeka System Dispatch (TSD) has notified WC of abnormal grid conditions based on weather conditions. TSD reports that under the current grid conditions, predicted grid voltage is 98.7% if WC were to come offline. OFN AF-025 Unit Limitations has been completed for the current plant conditions, and no further actions are required.

Event Malf. No. Event Event No. Type* Description Power range instrument SE NI-42B fails high. Rods step 1 mSE03B I - ATC, t+1 BOP, in. Manual Rod Control must be selected (or the reactor SRO trips).

Pressurizer Pressure Channel 456 fails high (PORV 456 2 mBB21B I - ATC, t+9 fails to SRO cycles) 2508 psig Loss of 345 kV Benton line. TSD will request Wolf 3 mSY03F R -- ATC t+16 Creek to lower load to 950 MWe. (~78-80% power)

N - BOP, SRO Grid voltage droops to 89.9% (310kV). Class 1E busses 4 IRF C -- All t+25 pMA02 to NB01/2 voltage will decrease to the point where the 310 kV degraded voltage alarms come in.

After a 94 sec time delay, the busses will shed and mNE04B attempt to repower on the EDGs. Both EDGs are inoperable at this point.

The TDAFP fails to start in Auto, but can be started in 5 mAL01 C - BOP, t+28 SRO manual. (CT Manually start the Turbine Driven Auxiliary Feed Pump)

Loss All AC Power. The crew will enter EMG C-0, Loss 6 mSY01 M -- All t+28 of All AC Power, as neither safeguards bus is energized.

(CT Depressurize intact Steam Generator(s) at maximum rate)

Final Revision 1

NB01/2 bus is restored (EDG B supplying NB02 bus) 7 Delete t+35 mNE04B

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Final Revision 2

Appendix D Scenario Outline Form ES-D-1 Facility: __Wolf Creek________________ Scenario No.: ___2____ Op-Test No.: _____

Examiners: ____________________________ Operators: _____________________

Initial Conditions: The plant is restarting after a forced outage that lasted 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />. The Main Turbine is synchronized to the grid. The plant is at BOL conditions. RCS boron concentration is @ 2022 ppm. Rod Control is in Manual with bank D at 183 steps. GEN 00-003, Hot Standby to Minimum Load, is complete to step 6.42.

Turnover: Shift orders are to continue the plant startup. Continue the start up per Step 6.42 of GEN 00-003. Fuel conditioning limits are not in effect. The B Stator Cooling water pump is Out of Service for a rework condition following the outage. It is currently in PMT and is expected back in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

Event Event Malf. No. Event Description No. Type*

1 mBG01A R -- ATC Volume Control Tank Level control channel BG LI-112 fails low. The result is a 1/2 swapover from the VCT to the t+1 I -- SRO RWST.

2 mAE15A I - BOP, Steam Generator Level Control channel AE LI-551 fails 4 SRO low.

t + 16 3 mAC06H C -- All The turbine trips on HI-HI bearing vibration.

t + 25 4 mAE14A C -- All A feedwater leak (8E6 lbm/hr) in Containment develops on the A Steam Generator feedline. (CT Isolate faulted t + 32 Steam Generator) 5 mSF17A M -- All Failure of the RX to trip in Auto and Manual (CT Direct local Reactor Trip) t + 32 mSF17B 6 mAL04A C - BOP, Post trip malfunction SRO t + 32 Failure of the A MDAFP to auto start 7 mSA27A C - BOP, Post trip malfunction B08, 09, SRO t + 32 10 & 07 Failure of the MSIVs to auto close (CT Manually close the MSIVs)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Final Revision 1

Appendix D Scenario Outline Form ES-D-1 Facility: __Wolf Creek________________ Scenario No.: ___3____ Op-Test No.: _____

Examiners: ____________________________ Operators: _______________________

Initial Conditions: ____100% power,_EOL_______________________________________

Turnover: EDG B out of service for MTN PMs - expected back in six hours. TS 3.8.1 conditions A & B entered; STS NB-005, Breaker Alignment Verification has been completed

- due in seven hours.

MDAFW pump B tagged out/out of service for due to Emergent work (SM Concern).

Expected return is six hours. TS 3.7.5 condition B entered.

Event Malf. Event Event No. No. Type* Description 1 mBB22 I -- PZR level channel BB LI-459A failure high.

A ATC, OFN SB-008, Instrument Malfunctions, Attachment J t+2 SRO 2 bkrDPA R- Condensate pump A trip D01A ATC t+8 OFN AF-025, Unit Limitations, Attachment A C-BOP, OFN MA-038, Rapid Plant Shutdown SRO 3 ANN- M- All Seismic event followed by a Reactor trip occurs.

E098 EMG E-0, Reactor Trip or Safety Injection t+25 ANN-D099 This event series sets up the scenario for the Major event ANN- EMG FR-H1, Response to Loss of Secondary Heat Sink.

C098 mSF15A mSF15B Final Revision 1

4 mNB01 (Post Reactor trip) NB01 & NB02 trip mNB02 t+25 mNE02 C -- (Post reactor trip) EDG A autostart feature disabled - manual A ATC, available SRO (CT - start EDG A in order to energize NB01 bus)

Recall NB02 bus unavailable because EDG B out of service as part of Turnover item.

5 mAL02 TDAFW pump trip (broken linkage) t+25 mtrDPA MDAFW pump A trip (shaft seizure)

L01A mBG13 CCP A trips due to overcurrent A

M- Loss of all Auxiliary Feedwater All EMG FR-H1, Response to Loss of Secondary Heat Sink (CT - Establish RCS bleed and feed before Steam Generators dry out)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Final Revision 2

Appendix D Scenario Outline Form ES-D-1 Facility: __Wolf Creek________________ Scenario No.: ___4____ Op-Test No.: _____

Examiners: ____________________________ Operators: ______________________

Initial Conditions: 65% power Turnover: Load reduction in progress per GEN 00-004, Power Operations, section 6.2, in order to remove A Main Feed pump from service due to high vibration. Main Feed Pump A is not expected to be out of service very long.

Use SYS AE-320, Turbine Driven Main Feedwater Pump Shutdown.

Event Malf. Event Event No. No. Type* Description 1 R- Reduce power using GEN 00-004, Power Operations and ATC remove A Main Feed Pump from service using SYS AE-t+1 320, Turbine Driven Main Feedwater Pump Shutdown N- (crew may reference / enter OFN AF-025, Unit Limitations, BOP, also)

SRO 2 mBB23 I- Pressurizer Spray valve (BB PCV-455B) fails open because A ATC, PZR Spray Controller BB PK-455B fails high - manual t+15 SRO control available OFN SB-008, Instrument Malfunctions, Attachment V 3 mAE15 I -- S/G C level AE LI-553 failure high C4 BOP, OFN SB-008, Instrument Malfunctions, Attachment F t+20 SRO ALR 00-110C, SG C Flow Mismatch ALR 00-110B, SG C Lev Dev 4 mBG13 C -- Normal Charging Pump (NCP) trip; a Centrifugal Charging C ATC, Pump must be started, letdown restored etc t+27 SRO ALR 00-042A, Charging Line Flow HiLo (SYS BG-120, CVCS Startup or SYS BG-201, Shifting Charging Pumps -

either may be used to restore letdown)

ALR 00-042E, Charging Pump Trouble (Step 7 re-establishes letdown)

Final Revision 1

5 mBB02 M -- All 500 gpm Steam Generator Tube Rupture on S/G A B OFN BB-07A, Steam Generator Tube Leakage (eventually t+35 EMG E-0, Reactor Trip or Safety Injection & EMG E-3, Steam Generator Tube Rupture) 5 EMG E-3, Steam Generator Tube Rupture actions:

CT - Isolate feed flow to the ruptured SG before Steam Generator overfills.

CT - Cooldown & Depressurize RCS to minimize RCS inventory leakage into the ruptured Steam Generator.

6 mSA27 C- Post trip: BIT outlet valves (EM HIS-8801A and EM HIS-EM01 ATC, 8801B) do not open. Manual open available t+43 and SRO mSA27 CT - Open BIT outlet valves (EM HIS-8801A and EM EM02 HIS-8801B) before the end of the scenario or before needless Red or Orange path occurs.

EMG E-0, Reactor Trip or Safety Injection, Attachment F or allowed post Immediate Action completion

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Final Revision 2

ES-301 Transient and Event Checklist Final Form ES-301-5 Facility: Wolf Creek Date of Exam: Aug 31 - Sept 4 Operating Test No.:

A E Scenarios P V 1 2 3 (BU) 4 (BU) T M P E O I L N CREW CREW CREW CREW T N I T POSITION POSITION POSITION POSITION A I

M C S A B S A B S A B S A B L U A T R T O R T O R T O R T O M(*)

N Y O C P O C P O C P O C P R I U T P E

RO RX 0 1 1 1 1 0 NOR 3 0 1 1 1 1 SRO-I I/C 145 34 5 4 4 2 SRO-U MAJ 67 5 3 2 2 1 TS 0 0 0 0 2 2 RO RX 3 0 1 1 1 0 NOR 0 0 0 1 1 1 SRO-I I/C 124 1234 9 4 4 2 67 SRO-U MAJ 67 5 3 2 2 1 TS 0 12 2 0 2 2 RO RX 0 0 0 1 1 0 NOR 3 0 1 1 1 1 SRO-I I/C 1245 234 9 4 4 2 67 SRO-U MAJ 67 5 3 2 2 1 TS 12 0 2 0 2 2 RO RX 0 2 0 0 1 0 1 1 0 NOR 0 0 0 1 0 1 1 1 1 SRO-I I/C 124 14 2 2346 246 3 4 4 2 SRO-U MAJ 35 35 35 5 5 5 2 2 1 TS 1 0 0 3 0 0 0 2 2

Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.

If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.