ML091490505

2009-03 - Final Outlines

ML091490505
Person / Time
Site:	Fort Calhoun
Issue date:	03/27/2009
From:	Brian Larson Operations Branch IV
To:	Omaha Public Power District
References
50-285/09-301, ES-401, ES-401-2 50-285/09-301
Download: ML091490505 (23)

Text

ES-401 PWR Examination Outline - Rev 2 FORM ES-401-2 Facility Name: Fort Calhoun Date of Exam:3/30/2009 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 2 1 4 3 6 2 18 4 2 6

1. Emergency Abnormal 2 2 1 1 N/A 2 1 N/A 2 9 1 3 4 Plant Evolutions Tier Totals 4 2 5 5 7 4 27 5 5 10 1 3 2 2 3 2 1 2 4 2 3 4 28 4 1 5 2.

2 1 0 2 3 1 1 0 1 0 0 1 10 0 1 2 3 Plant Systems Tier Totals 4 2 4 6 3 2 2 5 2 3 5 38 5 3 8 1 2 3 4 1 2 3 4

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

Note: 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.

Note: 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 the elimination of inappropriate K/A statements.

Note: 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.

Note: 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.

Note: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

Note: 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.

Note: 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.

Note: 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, 22 of 34

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

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

1 2 3 1 2 000007 Reactor Trip / 1 1

0 CE/E02 Reactor Trip Recovery / 1 Operating behavior characteristics of the facility. 3.3 2

0 000008 Pressurizer Vapor Space Accident / 3 Actions contained in EOP for PZR vapor space accident/LOCA 4.1 1 3

0 The time available for action before PZR is empty, given the rate 000009 Small Break LOCA / 3 3.4 1 5 of decrease of PZR level 000011 Large Break LOCA / 3 0 02.

000015 RCP Malfunctions / 4 Knowledge of limiting conditions for operations and safety limits. 4 22 1

000017 RCP Malfunctions (Loss of RC Flow) / 4 000022 Loss of Rx Coolant Makeup / 2 0 0

000025 Loss of RHR System / 4 LPI or Decay Heat Removal/RHR pumps 3.2 1 2

01. Ability to perform specific system and integrated plant 000026 Loss of Component Cooling Water / 8 4.3 1 23 procedures during all modes of plant operation.

000027 Pressurizer Pressure Control System 0 Why, if PZR level is lost and then restored, that pressure 2.8 1 Malfunction / 3 4 recovers much more slowly 0

000029 ATWS / 1 Closing the main steam isolation valve 3.6 1 8

0 000038 Steam Gen. Tube Rupture / 3 Plant conditions, from survey of control room indications 4.4 1 7

000040 Steam Line Rupture / 4 1

0 Desired operating results during abnormal and emergency CE/E05 Excessive Steam Demand / 4 3.4 3 situations.

0 000054 Loss of Main Feedwater / 4 Effects of feedwater introduction on dry S/G 3.6 2

1 CE/E06 Loss of Feedwater / 4 0

000055 Station Blackout / 6 Actions necessary to restore power 3.9 1 3

0 000056 Loss of Off-site Power / 6 Principle of cooling by natural convection 3.7 1 1

0 Actions contained in EOP for loss of vital ac electrical instrument 000057 Loss of Vital AC Inst. Bus / 6 4.1 1 1 bus 0

000058 Loss of DC Power / 6 Cross-tie of the affected dc bus with the alternate supply 3.4 1 1

0 The valve lineups necessary to restart the SWS while bypassing 000062 Loss of Nuclear Svc Water / 4 2.6 1 3 the portion of the system causing the abnormal condition 0

000065 Loss of Instrument Air / 8 Failure modes of air-operated equipment 2.9 1 8

000077 Generator Voltage and Electric 1 Generator overheating and the required actions 3.6 1 Grid Disturbances / 6 0 K/A Category Totals: 2 1 4 3 6 2 Group Point Total: 18 ES-401, 23 of 34

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

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

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 0 000003 Dropped Control Rod / 1 0 000005 Inoperable/Stuck Control Rod / 1 03 Metroscope 3.1 1 Ability to interpret reference materials, such as graphs, curves, 000024 Emergency Boration / 1 01.25 tables, etc.

3.9 1 000028 Pressurizer Level Malfunction / 2 0 000032 Loss of Source Range NI / 7 0 Equivalency between source-range, intermediate-range, and 000033 Loss of Intermediate Range NI / 7 01 power-range channel readings 3 1 000036 Fuel Handling Accident / 8 0 000037 Steam Generator Tube Leak / 3 0 000051 Loss of Condenser Vacuum / 4 0 Types of radiation, their units of intensity and the location of the 000059 Accidental Liquid RadWaste Rel. / 9 01 sources of radiation in a nuclear power plant 2.7 1 Types of radiation, their units of intensity and the location of 000060 Accidental Gaseous Radwaste Rel. / 9 01 sources of radiation in a nuclear reactor power plant 2.5 1 000061 ARM System Alarms / 7 0 000067 Plant Fire On-site / 9 8 04 Actions contained in EOP for plant fire on site 3.3 1 000068 Control Room Evac. / 8 0 000069 Loss of CTMT Integrity / 5 0 000074 Inad. Core Cooling / 4 25 Atmospheric dump valve controllers and indicators 3.8 1 Ability to recognize abnormal indications for system operating 000076 High Reactor Coolant Activity / 9 04.04 parameters that are entry-level conditions for emergency and 4.5 1 CE/A11 RCS Overcooling / 4 0 Desired operating results during abnormal and emergency CE/A16 Excess RCS Leakage / 2 03 situations.

3 1 CE/E09 Functional Recovery 0 0

0 0

0 0

0 0

0 0

0 K/A Category Totals: 2 1 1 2 1 2 Group Point Total: 9 ES-401, 24 of 34

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline - Rev 2 Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)

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

1 2 3 4 5 6 1 2 3 4 01.

003 Reactor Coolant Pump Ability to interpret and execute procedure steps. 4.6 1 20 2 3 Effect and detection of leaking PORV or relief on PZR level 3.4; 004 Chemical and Volume Control and pressure, including VCT makeup activity in automatic 2 9 0 mode; Reduction of boron concentration in the letdown 3.3 0

005 Residual Heat Removal RHR heat exchanger 2.5 1 3

0 Brittle fracture, including causes and preventative actions;

02. 2.9; 006 Emergency Core Cooling Ability to determine operability and/or availability of safety 2 4 37 related equipment. 3.6 Method of forming a steam bubble in the PZR; Ability to 0 01. 3.1; 007 Pressurizer Relief/Quench Tank evaluate plant performance and make operational 2 2 07 judgments based on operating characteristics, reactor 4.4 0 04. Startup of a CCW pump when the system is shut down; 2.6; 008 Component Cooling Water Ability to verify that the alarms are consistent with the plant 2 4 46 conditions. 4.2 0

010 Pressurizer Pressure Control PZR spray valve 3.7 1 1

0 0 125V dc system; RPS channels, components, and 3.4; 012 Reactor Protection interconnections 2

2 1 3.3 013 Engineered Safety Features 0 LOCA 4.6 1 Actuation 1 0

022 Containment Cooling Cooling of control rod drive motors 2.8 1 4

025 Ice Condenser N0 Ice Condenser at FCS 0 0

026 Containment Spray Adequate level in containment sump for suction (interlock) 3.8 1 7

0 039 Main and Reheat Steam Main steam pressure 3 1 6

0 059 Main Feedwater Programmed levels of the S/G 2.9 1 2

0 061 Auxiliary/Emergency Feedwater RCS 4.4 1 1

1 062 AC Electrical Distribution Degraded system voltages 2.5 1 6

0 0 Grounds; Meters, annunciators, dials, recorders, and 2.5; 063 DC Electrical Distribution indicating lights 2

1 1 2.7 0

064 Emergency Diesel Generator ESFAS controlled or actuated systems 4.2 1 2

0 073 Process Radiation Monitoring Radiation levels 3.2 1 1

1 0 3.6; 076 Service Water ESF; Service water 2 6 1 2.7 0

078 Instrument Air Pressure gauges 3.1 1 1

0 103 Containment Personnel access hatch and emergency access hatch 2.5 1 4

K/A Category Totals: 3 2 2 3 2 1 2 4 2 3 4 Group Point Total: 28 ES-401, 25 of 35

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

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

1 2 3 4 5 6 1 2 3 4 9

001 Control Rod Drive 7

Relationship of T-ave. to T-ref 3.3 1 002 Reactor Coolant 0 04.

011 Pressurizer Level Control Knowledge of EOP mitigation strategies. 3.7 1 06 0

014 Rod Position Indication 3

Rod bottom lights 3.2 1 015 Nuclear Instrumentation 0 016 Non-nuclear Instrumentation 0 017 In-core Temperature Monitor 0 027 Containment Iodine Removal 0 028 Hydrogen Recombiner and Purge 0

Control 0

029 Containment Purge 2

Containment entry 2.9 1 0

033 Spent Fuel Pool Cooling 2

RHRS 2.5 1 034 Fuel Handling Equipment 0 035 Steam Generator 0 0

041 Steam Dump/Turbine Bypass Control 3

Controller and positioners, including ICS, S/G, CRDS 2.7 1 045 Main Turbine Generator 0 0

055 Condenser Air Removal 1

Main condenser 2.5 1 0

056 Condensate 4

Loss of condensate pumps 2.6 1 068 Liquid Radwaste 0 0

071 Waste Gas Disposal 1

Pressure capability of the waste gas decay tank 2.6 1 072 Area Radiation Monitoring 0 075 Circulating Water 0 079 Station Air 0 0

086 Fire Protection Detection and location of fires 3.1 1 3

K/A Category Totals: 1 0 2 3 1 1 0 1 0 0 1 Group Point Total: 10 ES-401, 26 of 34

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

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

1 2 3 1 2 000007 Reactor Trip / 1 1

02. Knowledge of the bases in Technical Specifications for limiting CE/E02 Reactor Trip Recovery / 1 4.2 25 conditions for operations and safety limits.

000008 Pressurizer Vapor Space Accident / 3 0 000009 Small Break LOCA / 3 0 1

000011 Large Break LOCA / 3 Actions to be taken if limits for PTS are violated 4 1 4

000015 RCP Malfunctions / 4 1

0 000017 RCP Malfunctions (Loss of RC Flow) / 4 Cause of RCP failure 3.5 1

000022 Loss of Rx Coolant Makeup / 2 0 000025 Loss of RHR System / 4 0 000026 Loss of Component Cooling Water / 8 0 000027 Pressurizer Pressure Control System 0

Malfunction / 3 000029 ATWS / 1 0 000038 Steam Gen. Tube Rupture / 3 0 000040 Steam Line Rupture / 4 0

CE/E05 Excessive Steam Demand / 4 0

000054 Loss of Main Feedwater / 4 Steam flow-feed trend recorder 3.3 8

1 CE/E06 Loss of Feedwater / 4 000055 Station Blackout / 6 0 000056 Loss of Off-site Power / 6 0 000057 Loss of Vital AC Inst. Bus / 6 0 000058 Loss of DC Power / 6 0 000062 Loss of Nuclear Svc Water / 4 0 04.

000065 Loss of Instrument Air / 8 Knowledge of EOP mitigation strategies. 4.7 1 06 000077 Generator Voltage and Electric 0 Voltage outside the generator capability curve 3.6 1 Grid Disturbances / 6 2 K/A Category Totals: 0 0 0 0 4 2 Group Point Total: 6 ES-401, 23 of 34

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

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

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 0 Dropped rod, using in-core/ex-core instrumentation, in-core or loop 000003 Dropped Control Rod / 1 03 temperature measurements 3.8 1 000005 Inoperable/Stuck Control Rod / 1 0 000024 Emergency Boration / 1 0 000028 Pressurizer Level Malfunction / 2 0 000032 Loss of Source Range NI / 7 0 01.

000033 Loss of Intermediate Range NI / 7 Ability to explain and apply system limits and precautions. 4 1 32

04. Knowledge of low power/shutdown implications in accident (e.g.,

000036 Fuel Handling Accident / 8 loss of coolant accident or loss of residual heat removal) mitigation 4.2 1 09 strategies

04. Ability to diagnose and recognize trends in an accurate and timely 000037 Steam Generator Tube Leak / 3 manner utilizing the appropriate control room reference material.

4.2 1 47 000051 Loss of Condenser Vacuum / 4 0 000059 Accidental Liquid RadWaste Rel. / 9 0 000060 Accidental Gaseous Radwaste Rel. / 9 0 000061 ARM System Alarms / 7 0 000067 Plant Fire On-site / 9 8 0 000068 Control Room Evac. / 8 0 000069 Loss of CTMT Integrity / 5 0 000074 Inad. Core Cooling / 4 0 000076 High Reactor Coolant Activity / 9 0 CE/A11 RCS Overcooling / 4 0 CE/A16 Excess RCS Leakage / 2 0 CE/E09 Functional Recovery 0 K/A Category Totals: 0 0 0 0 1 3 Group Point Total: 4 ES-401, 24 of 34

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline - Rev 2 Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)

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

1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump 0 0

004 Chemical and Volume Control Inadvertent boration/dilution 4.3 1 6

005 Residual Heat Removal 0 0

006 Emergency Core Cooling High bearing temperature 3.1 1 1

007 Pressurizer Relief/Quench Tank 0 008 Component Cooling Water 0 010 Pressurizer Pressure Control 0 012 Reactor Protection 0 013 Engineered Safety Features 0

Actuation 022 Containment Cooling 0 025 Ice Condenser 0 Knowledge of the parameters and logic used to assess the 04.

026 Containment Spray status of safety functions, such as reactivity control, core 4.6 1 21 cooling and heat removal, reactor coolant system integrity, 039 Main and Reheat Steam 0 1

059 Main Feedwater Failure of feedwater regulating valves 3.4 1 2

061 Auxiliary/Emergency Feedwater 0 062 AC Electrical Distribution 0 063 DC Electrical Distribution 0 064 Emergency Diesel Generator 0 073 Process Radiation Monitoring 0 0

076 Service Water Loss of SWS 3.7 1 1

078 Instrument Air 0 103 Containment 0 K/A Category Totals: 0 0 0 0 0 0 0 4 0 0 1 Group Point Total: 5 ES-401, 25 of 34

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

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

1 2 3 4 5 6 1 2 3 4

02. Ability to recognize system parameters that are entry-level 001 Control Rod Drive 4.6 1 42 conditions for Technical Specifications.

002 Reactor Coolant 0 011 Pressurizer Level Control 0 014 Rod Position Indication 0 015 Nuclear Instrumentation 0 016 Non-nuclear Instrumentation 0 017 In-core Temperature Monitor 0 027 Containment Iodine Removal 0 028 Hydrogen Recombiner and Purge 01. Ability to interpret reference materials, such as graphs, 4.2 1 Control 25 curves, tables, etc.

029 Containment Purge 0 033 Spent Fuel Pool Cooling 0 034 Fuel Handling Equipment 0 035 Steam Generator 0 041 Steam Dump/Turbine Bypass Control 0 045 Main Turbine Generator 0 055 Condenser Air Removal 0 056 Condensate 0 068 Liquid Radwaste 0 071 Waste Gas Disposal 0 072 Area Radiation Monitoring 0 0

075 Circulating Water 1

Loss of intake structure 3.2 1 079 Station Air 0 086 Fire Protection 0 K/A Category Totals: 0 0 0 0 0 0 0 1 0 0 2 Group Point Total: 3 ES-401, 26 of 34

ES-401 Generic Knowledge and Abilities Outline (Tier 3) - Rev 2 Form ES-401-3 Facility Name: Fort Calhoun Date of Exam:3/30/2009 RO SRO-Only Category K/A # Topic IR # IR #

2.1. 21 Ability to verify the controlled procedure copy. 3.5 1 2.1. 42 Knowledge of new and spent fuel movement procedures. 2.5 1

1. 2.1. 34 Knowledge of primary and secondary plant chemistry limits. 3.5 1 Conduct of 2.1. 40 Knowledge of refueling administrative requirements. 3.9 1 Operations 2.1.

2.1.

Subtotal 2 2 2.2. 12 Knowledge of surveillance procedures. 3.7 1 Ability to interpret control room indications to verify the status and operation of a system, 2.2. 44 and understand how operator actions and directives affect plant and system conditions. 4.2 1 Ability to analyze the effect of maintenance activities, such as degraded power sources, on

2. 2.2. 36 the status of limiting conditions for operations. 3.1 1 Equipment 2.2. 37 Ability to determine operability and/or availability of safety related equipment. 4.6 1 Control 2.2.

2.2.

Subtotal 3 1 Knowledge of radiological safety principles pertaining to licensed operator duties, such as 2.3. 12 containment entry requirements, fuel handling responsibilities, access to locked high- 3.2 1 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3. 05 portable survey instruments, personnel monitoring equipment, etc. 2.9 1

3. 2.3. 11 Ability to control radiation releases. 3.8 1 Radiation 2.3. 15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, 3.1 1 portable survey instruments, personnel monitoring equipment, etc.

Control Knowledge of radiological safety procedures pertaining to licensed operator duties, such 2.3. 13 as response to radiation monitor alarms, containment entry requirements, fuel handling 3.8 1 2.3.

Subtotal 3 2 2.4. 03 Ability to identify post-accident instrumentation. 3.7 1 Knowledge of system set points, interlocks and automatic actions associated with EOP 2.4. 02 entry conditions. 4.5 1 Knowledge of EOP implementation hierarchy and coordination with other support

4. 2.4. 16 procedures or guidelines such as, operating procedures, abnormal operating procedures, 4.4 1 Emergency Procedures 2.4. 18 Knowledge of the specific bases for EOPs. 4 1

/ Plan 2.4.

2.4.

Subtotal 2 2 Tier 3 Point Total 10 7

ES-401 RO Exam Record of Rejected K/As-Rev 2 Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/1 000025 K2.08 Low Importance - No Plant Specific Priority 1/1 000025 K2.12 Low Importance - No Plant Specific Priority 1/1 000025 K2.04 Low Importance - No Plant Specific Priority 1/1 000025 K2.11 Low Importance - No Plant Specific Priority 1/1 000025 K2.06 Low Importance - No Plant Specific Priority 1/1 000015 02.38 No related license conditions 1/1 000065 K2.02 Low Importance - No Plant Specific Priority 1/1 000065 K2.01 Low Importance - No Plant Specific Priority 1/1 000065 K2.05 Low Importance - No Plant Specific Priority 1/1 000065 K2.04 Low Importance - No Plant Specific Priority 1/1 000065 K2.03 Low Importance - No Plant Specific Priority 1/1 000065 K1.01 Low Importance - No Plant Specific Priority 1/1 000058 K2.01 Low Importance - No Plant Specific Priority 1/1 000058 K2.02 Low Importance - No Plant Specific Priority 1/2 000059 K1.05 ROs do not calculate offsite doses at FCS 1/2 000076 K2.03 Low Importance - No Plant Specific Priority 1/2 000032 K1.01 Generic Fundamentals Topic 1/2 000060 K1.03 Low Importance - No Plant Specific Priority 2/1 006000 K5.11 Generic Fundamentals Topic 2/1 006000 K5.12 Low Importance - No Plant Specific Priority 2/1 008000 02.39 No "less than 1 hr" Tech Specs associated with CCW 2/1 059000 K2.02 Low Importance - No Plant Specific Priority 2/1 059000 K2.01 Low Importance - No Plant Specific Priority 2/1 059000 A3.05 Low Importance - No Plant Specific Priority 2/1 059000 A3.07 ICS is a B&W system N/A to FCS 2/1 026000 K6.05 Low Importance - No Plant Specific Priority

ES-401 RO Exam Record of Rejected K/As-Rev 2 Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 2/1 026000 K6.03 Low Importance - No Plant Specific Priority 2/1 026000 K6.02 Low Importance - No Plant Specific Priority 2/1 026000 K6.01 Low Importance - No Plant Specific Priority 2/1 026000 K6.04 Low Importance - No Plant Specific Priority 2/1 026000 K5.02 Low Importance - No Plant Specific Priority 2/1 026000 K5.04 Low Importance - No Plant Specific Priority 2/1 026000 K5.03 Low Importance - No Plant Specific Priority 2/1 026000 K5.01 Low Importance - No Plant Specific Priority 2/1 005000 K6.09 Low Importance - No Plant Specific Priority 2/1 005000 K6.02 Low Importance - No Plant Specific Priority 2/1 005000 K6.05 Low Importance - No Plant Specific Priority 2/1 005000 K6.06 Low Importance - No Plant Specific Priority 2/1 005000 K6.10 Low Importance - No Plant Specific Priority 2/1 005000 K6.08 Low Importance - No Plant Specific Priority 2/1 022000 K4.01 No plant specific penetration cooling system at FCS 2/1 022000 K4.02 No fan speed or flowpath change with pressure at FCS 2/1 063000 A2.02 Low Importance - No Plant Specific Priority 2/1 007000 K5.06 Low Importance - No Plant Specific Priority 2/1 007000 K5.03 Low Importance - No Plant Specific Priority 2/1 007000 K5.05 Low Importance - No Plant Specific Priority 2/1 007000 K5.01 Low Importance - No Plant Specific Priority 2/1 007000 K5.04 Low Importance - No Plant Specific Priority 2/2 055000 K3.04 Low Importance - No Plant Specific Priority 2/2 055000 K3.03 Low Importance - No Plant Specific Priority 2/2 041000 K6.04 Low Importance - No Plant Specific Priority 2/2 041000 K6.05 Low Importance - No Plant Specific Priority

ES-401 RO Exam Record of Rejected K/As-Rev 2 Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 2/2 041000 K6.06 Low Importance - No Plant Specific Priority 2/2 041000 K6.01 Low Importance - No Plant Specific Priority 2/2 041000 K6.02 Low Importance - No Plant Specific Priority 2/2 033000 K1.01 Low Importance - No Plant Specific Priority 2/2 033000 K1.07 Low Importance - No Plant Specific Priority 2/2 033000 K1.03 Low Importance - No Plant Specific Priority 2/2 068000 A1.01 Low Importance - No Plant Specific Priority 2/2 068000 A1.02 Low Importance - No Plant Specific Priority 2/2 068000 K3.02 Low Importance - No Plant Specific Priority 2/2 068000 K3.01 Low Importance - No Plant Specific Priority 2/2 068000 K6.04 Low Importance - No Plant Specific Priority 2/2 068000 K6.08 Low Importance - No Plant Specific Priority 2/2 068000 K6.07 Low Importance - No Plant Specific Priority 2/2 068000 K6.06 Low Importance - No Plant Specific Priority 2/2 068000 K6.03 Low Importance - No Plant Specific Priority 2/2 068000 K6.11 Low Importance - No Plant Specific Priority 2/2 068000 K6.02 Low Importance - No Plant Specific Priority 2/2 068000 K6.06 Low Importance - No Plant Specific Priority 2/2 068000 K6.01 Low Importance - No Plant Specific Priority 2/2 079000 A3.01 Low Importance - No Plant Specific Priority 2/2 079000 A3.03 Low Importance - No Plant Specific Priority 2/2 079000 A3.02 Low Importance - No Plant Specific Priority 2/2 079000 K4.02 Low Importance - No Plant Specific Priority 2/2 079000 K6.04 Low Importance - No Plant Specific Priority 2/2 079000 K6.02 Low Importance - No Plant Specific Priority 2/2 079000 K6.05 Low Importance - No Plant Specific Priority

ES-401 RO Exam Record of Rejected K/As-Rev 2 Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 2/2 079000 K6.07 Low Importance - No Plant Specific Priority 2/2 079000 K6.04 Low Importance - No Plant Specific Priority 2/2 079000 K6.01 Low Importance - No Plant Specific Priority 2/2 079000 K6.06 Low Importance - No Plant Specific Priority 2/2 079000 K6.03 Low Importance - No Plant Specific Priority 2/2 079000 K5.01 Low Importance - No Plant Specific Priority 2/2 079000 K5.02 Low Importance - No Plant Specific Priority 2/2 056000 A2.09 Low Importance - No Plant Specific Priority 2/2 056000 A2.03 Low Importance - No Plant Specific Priority 1/1 00062 AA2.06 No procedure or reference to support question 1/2 000076 AK2.01 Radiation Monitors not used to detect high RCS activity 1/2 000076 AK2.06 Low Importance - No Plant Specific Priority 1/2 000076 AK2.05 Low Importance - No Plant Specific Priority 1/2 000076 AK2.04 Low Importance - No Plant Specific Priority 1/2 000076 AK2.02 Low Importance - No Plant Specific Priority 2/1 026000 K4.05 No procedure or reference to support question 2/2 079000 A4.01 Not a Fort Calhoun Design Feature 2/2 079000 all Low Importance - No Plant Specific Priority remaining 1/2 000032 AK3.01 Overlap with SRO question 2/1 073000 K4.01 Overlap with Audit Exam 2/1 073000 K4.02 Not a Fort Calhoun Design Feature 2/2 068000 K6.10 Overlap with Audit Exam 2/2 086000 K1.02 Overlap with SRO question

ES-401 SRO EXAM Record of Rejected K/As-Rev 2 Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/1 000054 A2.07 Not a design feature of FCS 2/2 079000 A2.01 Not a design feature of FCS 2/2 075000 A2.05 Low Importance, No plant specific priority

ES-301 Administrative Topics Outline Form ES-301-1 Facility: __Fort Calhoun______________ Date of Examination: __3/30/09_____

Examination Level: RO Revision Number: 3 Administrative Topic Type Describe activity to be performed (see Note) Code*

A-1 M, R Calculate Shutdown Margin with inoperable CEAs Conduct of Operations KA 2.1.37 (RO Imp 4.3)

A-2 N, R Determine Pressurizer Level During Cooldown Conduct of Operations KA 2.1.25 (RO Imp 3.9)

A-3 N, R Determine Equipment Lost by Tagout of an MCC Equipment Control KA 2.2.41 (RO Imp 3.5)

A-4 D RCA Entry and Exit with PCM Alarms Radiation Control KA 2.3.13 (RO Imp 3.4)

Emergency Procedures/Plan 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 Administrative Topics Outline Form ES-301-1 Facility: __Fort Calhoun_______________ Date of Examination: _3/30/09____

Examination Level: SRO Revision Number: 3 Administrative Topic Type Describe activity to be performed (see Note) Code*

A-5 M, R Review Shutdown Margin Calculation with inoperable CEAs Conduct of Operations KA 2.1.37 (SRO Imp 4.6)

A-6 M, R Determine Shift Staffing Conduct of Operations KA 2.1.5 (SRO Imp 3.9)

A-7 D, R Determine RW System Operability Equipment Control KA 2.2.37 (SRO Imp 4.6)

A-8 D, R Authorize Release of Monitor Tank WD-22B Radiation Control KA 2.3.6 (SRO Imp 3.6)

A-9 M, R Emergency Classification and PARs Emergency Procedures/Plan KA's 2.4.41 (SRO Imp 4.6) and 2.4.44 (SRO Imp 4.4)

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 Form ES-301-2 Facility: __Fort Calhoun_____________________ Date of Examination: 3/30/09__

Exam Level: RO Revision Number.: 3 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S-1. 001000 A4.03 / Control Element Assembly Movement Test S, N, A 1 S-2. 004000 A4.08 / Establish Charging Flow via HPSI Header S, N 2 S-3 006000 A1.11 / Simultaneous Hot and Cold Leg Injection S,A, M, EN, L 3 S-4. 003000 A4.06 / Start a Reactor Coolant Pump S, A, L,M 4P S-5 061000 A2.04 / Initiate AFW to SGs S, EN, A, N, L 4S S-6 028000 A1.01 / Operate the Containment Hydrogen Analyzer S, D 5 S-7 062000 A4.01 / Transfer 4160 V buses from 345 KV to 161 KV S, D 6 S-8. 012000 A4.02 / RPS Power Adjustment S, N 7 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P-1 022000 A2.05 / Provide Raw Water Backup Cooling to E,R,M 5 Containment Coolers P-2 000055 EA1.07 / Energize 480 V buses from 13.8 KV E, N 6 P-3 086000 A2.04 / Local Emergency Manual Start of Diesel Fire E,A,D 8 Pump

@ 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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __Fort Calhoun_____________________ Date of Examination: 3/30/09__

Exam Level: ISRO Revision Number.: 3 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S-1. 001000 A4.03 / Control Element Assembly Movement Test S, N, A 1 S-2. 004000 A4.08 / Establish Charging Flow via HPSI Header S, N 2 S-3 006000 A1.11 / Simultaneous Hot and Cold Leg Injection S,A, M, EN, L 3 S-4. 003000 A4.06 / Start a Reactor Coolant Pump S, A, L,M 4P S-5 061000 A2.04 / Initiate AFW to SGs S, EN, A, N, L 4S S-7 062000 A4.01 / Transfer 4160 V buses from 345 KV to 161 KV S, D 6 S-8. 012000 A4.02 / RPS Power Adjustment S, N 7 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P-1 022000 A2.05 / Provide Raw Water Backup Cooling to E,R,M 5 Containment Coolers P-2 000055 EA1.07 / Energize 480 V buses from 13.8 KV E, N 6 P-3 086000 A2.04 / Local Emergency Manual Start of Diesel Fire E,A,D 8 Pump

@ 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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __Fort Calhoun_____________________ Date of Examination: 3/30/09__

Exam Level: USRO Revision Number.: 3 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S-3 006000 A1.11 / Simultaneous Hot and Cold Leg Injection S,A, M, EN, L 3 S-5 061000 A2.04 / Initiate AFW to SGs S, EN, A, N, L 4S In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P-1 022000 A2.05 / Provide Raw Water Backup Cooling to E,R,M 5 Containment Coolers P-2 000055 EA1.07 / Energize 480 V buses from 13.8 KV E, N 6 P-3 086000 A2.04 / Local Emergency Manual Start of Diesel Fire E,A,D 8 Pump

@ 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: Fort Calhoun Scenario No: 2009-2 Revision: 3 Examiners: _________________________ Operators: _________________________

Initial Conditions: 100% Power DG-1 Out of Service replacing contactors for 2CR relays.

Turnover: Rotate Condenser Evacuation Pumps, then rotate Containment Cooling Units.

Event Malf Event Event No. No. Type* Description 1 N-BOPO Rotate Condenser Evacuation Pumps per OI-CE-1, Attachment (2 min) 3.

2 N-ATCO Rotate Containment Cooling Units In accordance with OI-VA-1.

(10 min) 3 C-ATCO Dropped CEA - Tech Spec Entry.

LE CUE C-BOPO 4 R-ATCO AOP-05 shutdown to 70% Power.

N-BOPO 5 I-ATCO Controlling Pressurizer Pressure Transmitter, PT-103Y, Fails LE CUE High.

6 C-BOPO Loss of 161 KV - Tech Spec Entry.

LE CUE 7 C-ATCO Another Dropped CEA - Manual Reactor Trip Required.

LE CUE 8 M-ALL Circulating Water Pump, CW-1C, Breaker fails to open preventing DG from loading onto bus 1A4 - Station Blackout.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (5-8) 5

2. Malfunctions after EOP entry (1-2) 1

3. Abnormal events (2-4) 3

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 1

6. EOP contingencies requiring substantive actions (0-2) 1

7. Critical tasks (2-3) 2

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2009-4 Revision: 5 Examiners: _________________________ Operators: _________________________

Initial Conditions: 50% Power, Diesel Driven AFW Pump, FW-54, Out of Service, Main Feed Pumps, FW-4A and FW-4C, Out of Service.

Turnover: Maintain 50% operation. Rotate CCW Pumps.

Event Malf Event Event No. No. Type* Description 1 N-ATCO Rotate CCW Pumps.

(2 min) 2 C-BOPO Isolated Phase Bus Duct Cooling Fan Motor Trips.

LE CUE 3 I-ATCO Pressurizer Pressure Safety Channel fails Low - Tech Spec LE CUE TS-CRS Entry.

4 I-BOPO Steam header pressure transmitter, PT-910 Fails High.

LE CUE 5 C - ATCO 10-15 gpm leak to containment - Tech Spec Entry.

LE CUE TS-CRS 6 C - ATCO Feedwater Pump Trips, Reactor Trip.

LE CUE 7 C-BOPO Blowdown fails to isolate automatically.

8 M - ALL Pipe from EFWST to FW-6 and FW-10 breaks. Total Loss of LE CUE Feedwater.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (5-8) 7

2. Malfunctions after EOP entry (1-2) 2

3. Abnormal events (2-4) 2

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 1

6. EOP contingencies requiring substantive actions (0-2) 1

7. Critical tasks (2-3) 2 or 3

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2009-1 (SPARE) Revision: 3 Examiners: _________________________ Operators: _________________________

Initial Conditions: 100% Power. Diesel Driven AFW Pump, FW-54, is out of service. Air Compressor, CA-1A, is out of service.

Turnover: Transfer Letdown Control Valves from LCV-101-1 to LCV-101-2. After that rotate running EHC Pumps.

Event Malf Event Event No. No. Type* Description 1 N-ATCO Transfer Letdown Flow Control Valves.

(2 min) 2 N-BOPO Rotate EHC Pumps.

(14 min) 3 I-ATCO Power Range NI Channel B fails - Tech Spec Entry.

LE CUE 4 C-BOPO Running Bearing Cooling Water Pump, AC-9A, trips.

LE CUE 5 I-ATCO Loop Two Hot Leg RTD, TT-122H, Fails High - Tech Spec LE CUE Entry 6 C-All Loss of Instrument Air.

LE CUE 7 C-ATCO Manual Reactor Trip Required.

8 M-All Steam Generator Safety Valve Fails Open.

LE CUE

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (5-8) 5

2. Malfunctions after EOP entry (1-2) 1

3. Abnormal events (2-4) 2

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 1

6. EOP contingencies requiring substantive actions (0-2) 1

7. Critical tasks (2-3) 3