ML041130154

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2004 - Draft Examination Outline
ML041130154
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 04/16/2004
From: Gody A
Operations Branch IV
To: Ridenoure R
Omaha Public Power District
References
50-285/04-301 50-285/04-301
Download: ML041130154 (45)
v • d • e


Text

Outline Development for 3/2004 Fort Calhoun NRC Exam This exam outline was developed in accordance with NUREG-1021, draft Rev 9. In addition, the NRC Region IV AGood Practices@ document was used as a reference.

Written Exam Outline Fort Calhoun has developed a methodology to ensure that the selection of K/A items for the written exam is random and unbiased. The written exam outline was developed using a Microsoft Access database. All K/A items from NUREG-1122, Rev 2 are contained in a table within the database. Items which clearly are not applicable to Fort Calhoun are assigned a flag to prevent them from being sampled. Flagged items are selected using guidance provided in ES-401, attachment 2. Flagged items include the Ice Condenser System K/A=s, Non-Combustion Engineering vender specific EPE/APE K/A=s, and K/A=s only associated with multi-unit plants. The sample plan is developed as follows:

$ A module is run that assigns a random number to each item in the K/A catalog. This module uses a Arandomize@ routine to ensure that the pattern of random numbers is unique.

$ A query is run that presents K/A items belonging to the tier and group being sampled ordered by their associated random number. Minimum and maximum numbers are assigned to topics and categories to prevent over and under sampling. Items are entered in the sample plan as ordered, subject to the pre-established minimums and maximums. If a sampled K/A item has an importance value less than 2.5 with no FCS specific priority, is not applicable to Fort Calhoun or not appropriate for the written exam, it will be tagged and included in the Record of Rejected K/As along with the reason for rejection. This sampling process is repeated until the tier/group has the required number of items.

$ This procedure is repeated for each tier/group combination.

$ Additional items are selected for the SRO only questions to meet the SRO tier/group requirements. These items are also presented in order of their associated random number. An additional requirement, for this step, is that the selected K/A items must be associated with 10 CFR 55.43 items.

In addition to the ES-401-2 and ES-401-3 forms, a more detailed listing of the selected K/A item including the full text and a cross reference to the applicable 10 CFR 55.41/43/45 items is provided.

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Operating Exam Outline The Fort Calhoun APRA Summary Notebook@ was used as a resource to ensure that risk-significant items identified in the Fort Calhoun IPE are reflected in the exam. The following risk significant initiating events are included in the operating exams:

$ Steam Generator Tube Rupture

$ Loss of offsite power

$ Total loss of feedwater

$ RCP seal failures It also resulted in the following risk-significant operator actions being evaluated:

$ Manually opening a Circulating Water Pump breaker to allow D/G to power vital bus.

$ Minimizing DC loads following a loss of offsite power.

$ Initiation of Once-Through Cooling

$ Initiation of simultaneous hot and cold leg injection All four simulator scenarios are new.

The development of the audit exam that will be given was completed prior to beginning work on this exam outline.

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ES-401 PWR Examination Outline Form ES-401-2 Facility: Fort Calhoun Printed: 11/12/2003 Date Of Exam: 03/12/2004 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total K A A2 G*

1. 1 3 3 3 3 3 3 18 0 0 0 0 0 Emergency 2 0 2 2 2 1 2 9 0 0 0 0 0 Abnormal Plant Tier 3 5 5 5 4 5 27 0 0 0 0 0 Evolutions Totals 1 3 2 2 3 3 1 3 3 2 3 3 28 0 0 0 0 0 2.

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

3. Generic Knowledge And 10 0 Abilities Categories 3 2 2 3 0 0 0 0 Note:
1. Ensure that at least two topics from every K/A category are sampled within each tier of the RO outline (i.e., the "Tier Totals" in each K/A category shall not be less than two). Refer to Section D.1.c for additional guidance regarding the SRO sampling.
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. Select topics from many systems and evolutions; avoid selecting more than two K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category /tier.

6.* 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. The SRO K/As must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7. 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 columns labeled "K" and "A".

Use duplicate pages for RO and SRO-only exams.

8. For Tier 3, enter the K/A numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.

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PWR RO Examination Outline Printed: 11/12/2003 Facility: Fort Calhoun ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # E/APE Name/Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 007 000007 Reactor Trip - Stabilization X EA2.03 - Reactor trip breaker position 4.2 1

- Recovery / 1 008 000008 Pressurizer Vapor Space X AK3.04 - RCP tripping requirements 4.2 1 Accident / 3 009 000009 Small Break LOCA / 3 X EA2.06 - Whether PZR water inventory 3.8 1 loss is imminent 009 000009 Small Break LOCA / 3 X EK3.21 - Actions contained in EOP for 4.2 1 small break LOCA/leak 015 000015 RCP Malfunctions / 4 X AK2.07 - RCP seals 2.9 1 026 000026 Loss of Component X AA1.07 - Flow rates to the components 2.9 1 Cooling Water / 8 and systems that are serviced by the CCWS; interactions among the components 027 000027 Pressurizer Pressure X 2.4.49 - Ability to perform without 4.0 1 Control System Malfunction / 3 reference to procedures those actions that require immediate operation of system components and controls.

029 000029 ATWS / 1 X EK2.06 - Breakers, relays, and 2.9* 1 disconnects 038 000038 Steam Gen. Tube Rupture / X EK3.03 - Automatic actions associated 3.6* 1 3 with high radioactivity in S/G sample lines 040 000040 Steam Line Rupture - X AK2.01 - Valves 2.6* 1 Excessive Heat Transfer / 4 040 000040 Steam Line Rupture - X AA1.24 - Main steam header pressure 3.8 1 Excessive Heat Transfer / 4 gauges 054 000054 Loss of Main Feedwater / X 2.4.50 - Ability to verify system alarm 3.3 1 4 setpoints and operate controls identified in the alarm response manual.

055 000055 Station Blackout / 6 X EK1.01 - Effect of battery discharge 3.3 1 rates on capacity 056 000056 Loss of Off-site Power / 6 X AA2.20 - AFW flow indicator 3.9 1 057 000057 Loss of Vital AC Inst. Bus X 2.4.50 - Ability to verify system alarm 3.3 1

/6 setpoints and operate controls identified in the alarm response manual.

057 000057 Loss of Vital AC Inst. Bus X AA1.02 - Manual control of PZR level 3.8 1

/6 E02 CE/E02 Reactor Trip - Stabilization X EK1.1 - Components, capacity, and 2.9 1

- Recovery / 1 function of emergency systems E06 CE/E06 Loss of Main Feedwater / X EK1.3 - Annunciators and conditions 3.2 1 4 indicating signals, and remedial actions associated with the (Loss of Feedwater) 1

PWR RO Examination Outline Printed: 11/12/2003 Facility: Fort Calhoun ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # E/APE Name/Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 2

PWR RO Examination Outline Printed: 11/12/2003 Facility: Fort Calhoun ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # E/APE Name/Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 024 000024 Emergency Boration / 1 X AK2.04 - Pumps 2.6 1 032 000032 Loss of Source Range NI / X AA1.01 - Manual restoration of power 3.1* 1 7

036 000036 Fuel Handling Accident / 8 X 2.4.49 - Ability to perform without 4.0 1 reference to procedures those actions that require immediate operation of system components and controls.

060 000060 Accidental Gaseous X AK2.01 - ARM system, including the 2.6 1 Radwaste Rel. / 9 normal radiation-level indications and the operability status 061 000061 ARM System Alarms / 7 X AA2.01 - ARM panel displays 3.5 1 068 000068 Control Room Evac. / 8 X AK3.17 - Injection of boric acid into the 3.7 1 RCS A11 CE/A11 RCS Overcooling - PTS / X 2.1.27 - Knowledge of system purpose 2.8 1 4 and or function.

A13 CE/A13 Natural Circ. / 4 X AK3.3 - Manipulation of controls 3.4 1 required to obtain desired operating results during abnormal, and emergency situations A16 CE/A16 Excess RCS Leakage / 2 X AA1.2 - Operating behavior 3.0 1 characteristics of the facility K/A Category Totals: 0 2 2 2 1 2 Group Point Total: 9 1

PWR RO Examination Outline Printed: 11/12/2003 Facility: Fort Calhoun ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Ev # System / Evolution Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 003 003 Reactor Coolant X A3.04 - RCS flow 3.6 1 Pump 003 003 Reactor Coolant X K1.08 - Containment 2.7* 1 Pump isolation 004 004 Chemical and X A2.09 - High primary and/or 3.0 1 Volume Control secondary activity 004 004 Chemical and X K6.15 - Reason for venting 2.8 1 Volume Control VCT and pump casings while filling: vents must connect to LRS 005 005 Residual Heat X A4.03 - RHR temperature, 2.8* 1 Removal PZR heaters and flow, and nitrogen 005 005 Residual Heat X K4.12 - Lineup for piggyback 3.1* 1 Removal mode with CSS 006 006 Emergency Core X 2.1.33 - Ability to recognize 3.4 1 Cooling indications for system operating parameters which are entry-level conditions for technical specifications.

006 006 Emergency Core X A2.12 - Conditions requiring 4.5 1 Cooling actuation of ECCS 007 007 Pressurizer X A2.02 - Abnormal pressure 2.6 1 Relief/Quench Tank in the PRT 007 007 Pressurizer X A4.10 - Recognition of 3.6 1 Relief/Quench Tank leaking PORV/code safety 008 008 Component Cooling X A3.01 - Setpoints on 3.2* 1 Water instrument signal levels for normal operations, warnings, and trips that are applicable to the CCWS 010 010 Pressurizer Pressure X K1.05 - PRTS 3.4 1 Control 010 010 Pressurizer Pressure X K5.01 - Determination of 3.5 1 Control condition of fluid in PZR, using steam tables 012 012 Reactor Protection X K1.08 - MFW 2.9* 1 012 012 Reactor Protection X K5.02 - Power density 3.1* 1 013 013 Engineered Safety X 2.1.32 - Ability to explain and 3.4 1 Features Actuation apply all system limits and precautions.

013 013 Engineered Safety X A1.02 - Containment 3.9 1 Features Actuation pressure, temperature, and humidity 026 026 Containment Spray X A1.04 - Containment 3.1 1 humidity 1

PWR RO Examination Outline Printed: 11/12/2003 Facility: Fort Calhoun ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Ev # System / Evolution Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 039 039 Main and Reheat X K4.08 - Interlocks on MSIV 3.3 1 Steam and bypass valves 039 039 Main and Reheat X K5.08 - Effect of steam 3.6 1 Steam removal on reactivity 059 059 Main Feedwater X A4.11 - Recovery from 3.1 1 automatic feedwater isolation 061 061 Auxiliary/Emergency X A1.02 - S/G pressure 3.3* 1 Feedwater 064 064 Emergency Diesel X K2.03 - Control power 3.2* 1 Generator 064 064 Emergency Diesel X K4.03 - Governor valve 2.5 1 Generator operation 073 073 Process Radiation X 2.4.50 - Ability to verify 3.3 1 Monitoring system alarm setpoints and operate controls identified in the alarm response manual.

076 076 Service Water X K2.01 - Service water 2.7* 1 076 076 Service Water X K3.07 - ESF loads 3.7 1 078 078 Instrument Air X K3.02 - Systems having 3.4 1 pneumatic valves and controls K/A Category Totals: 3 2 2 3 3 1 3 3 2 3 3 Group Point Total: 28 2

PWR RO Examination Outline Printed: 11/12/2003 Facility: Fort Calhoun ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Ev # System / Evolution Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 001 001 Control Rod Drive X K4.11 - Resetting of CRDM 2.7 1 circuit breakers 002 002 Reactor Coolant X A4.06 - Overflow level of the 2.9 1 RWST 011 011 Pressurizer Level X 2.1.2 - Knowledge of 3.0 1 Control operator responsibilities during all modes of plant operation.

015 015 Nuclear X K3.01 - RPS 3.9 1 Instrumentation 028 028 Hydrogen X A2.03 - The hydrogen air 3.4 1 Recombiner and Purge concentration in excess of Control limit flame propagation or detonation with resulting equipment damage in containment 029 029 Containment Purge X A3.01 - CPS isolation 3.8 1 033 033 Spent Fuel Pool X K1.02 - RHRS 2.5 1 Cooling 035 035 Steam Generator X A1.02 - S/G pressure 3.5 1 041 041 Steam Dump/Turbine X K5.02 - Use of steam tables 2.5 1 Bypass Control for saturation temperature and pressure 086 086 Fire Protection X K6.04 - Fire, smoke, and heat 2.6 1 detectors K/A Category Totals: 1 0 1 1 1 1 1 1 1 1 1 Group Point Total: 10 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 11/12/2003 Facility: Fort Calhoun Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.19 Ability to use plant computer to obtain and 3.0 1 evaluate parametric information on system or component status.

2.1.20 Ability to execute procedure steps. 4.3 1 2.1.28 Knowledge of the purpose and function of major 3.2 1 system components and controls.

Category Total: 3 Equipment Control 2.2.12 Knowledge of surveillance procedures. 3.0 1 2.2.13 Knowledge of tagging and clearance procedures. 3.6 1 Category Total: 2 Radiation Control 2.3.1 Knowledge of 10 CFR: 20 and related facility 2.6 1 radiation control requirements.

2.3.11 Ability to control radiation releases. 2.7 1 Category Total: 2 Emergency Procedures/Plan 2.4.17 Knowledge of EOP terms and definitions. 3.1 1 2.4.24 Knowledge of loss of cooling water procedures. 3.3 1 2.4.31 Knowledge of annunciators alarms and 3.3 1 indications, and use of the response instructions.

Category Total: 3 Generic Total: 10 1

Nov 12, 2003 7:10 PM PWR RO Written Examination Outline Summary Page 1 of 1 System/Mode System Title K1 K2 K3 A1 A2 G Points EPE/APE Tier 1 / Group 1 000007 Reactor Trip 1 1 000008 Pressurizer Vapor Space Accident 1 1 000009 Small Break LOCA 1 1 2 000017 Reactor Coolant Pump Malfunctions (Loss of RC Flow) 1 1 000026 Loss of Component Cooling Water 1 1 000027 Pressurizer Pressure Control System Malfunction 1 1 000029 Anticipated Transient Without Scram (ATWS) 1 1 000038 Steam Generator Tube Rupture 1 1 000040 Steam Line Rupture 1 1 2 000054 Loss of Main Feedwater 1 1 000055 Station Blackout 1 1 000056 Loss of Off-Site Power 1 1 000057 Loss of Vital AC Electrical Instrument Bus 1 1 2 CE-E02 Reactor Trip Recovery 1 1 CE-E06 Loss of Feedwater 1 1 3 3 3 3 3 3 18 EPE/APE Tier 1 / Group 2 000024 Emergency Boration 1 1 000032 Loss of Source Range Nuclear Instrumentation 1 1 000036 Fuel Handling Incidents 1 1 000060 Accidental Gaseous Radwaste Release 1 1 000061 Area Radiation Monitoring (ARM) System Alarms 1 1 000068 Control Room Evacuation 1 1 CE-A11 RCS Overcooling 1 1 CE-A13 Natural Circulation Operations 1 1 CE-A16 Excess RCS Leakage 1 1 2 2 2 1 2 9 Grand Total of EPE/APE K&A Selection: 3 5 5 5 4 5 27

PWR RO Written Examination Outline Summary Nov 12, 2003 7:10 PM Page 1 of 1 System/Mode System Title K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Points Plant System Tier 2 / Group 1 003000 Reactor Coolant Pump System 1 1 2 004000 Chemical and Volume Control System 1 1 2 005000 Residual Heat Removal System 1 1 2 006000 Emergency Core Cooling System 1 1 2 007000 Pressurizer Relief Tank / Quench Tank System 1 1 2 008000 Component Cooling Water System 1 1 010000 Pressurizer Pressure Control System 1 1 2 012000 Reactor Protection System 1 1 2 013000 Engineered Safety Features Actuation System 1 1 2 026000 Containment Spray System 1 1 039000 Main and Reheat Steam System 1 1 2 059000 Main Feedwater System 1 1 061000 Auxiliary / Emergency Feedwater System 1 1 064000 Emergency Diesel Generators 1 1 2 073000 Process Radiation Monitoring System 1 1 076000 Service Water System 1 1 2 078000 Instrument Air System 1 1 3 1 2 3 3 1 3 3 3 3 3 28 Plant System Tier 2 / Group 2 001000 Control Rod Drive System 1 1 002000 Reactor Coolant System 1 1 011000 Pressurizer Level Control System 1 1 015000 Nuclear Instrumentation System 1 1 028000 Hydrogen Recombiner and Purge Control System 1 1 029000 Containment Purge System 1 1 033000 Spent Fuel Pool Cooling System 1 1 035000 Steam Generator System 1 1 041000 Steam Dump System and Turbine Bypass Control 1 1 086000 Fire Protection System 1 1 1 1 1 1 1 1 1 1 1 1 10 Grand Total of Plant System K&A Selection: 4 1 3 4 4 2 4 4 4 4 4 38

Nov 12, 2003 7:11 PM PWR RO Written Examination Outline Summary Page 1 of 1 System/Mode System Title Cat 1 Cat 2 Cat 3 Cat 4 Points Generic Knowledge and Abilities Tier 3 000000 Generic Knowledges and Abilities 3 2 2 3 10 3 2 2 3 10 Grand Total of Generic K&A Selection: 3 2 2 3 10

PWR RO Written Examination Outline Nov 12, 2003 7:11 PM Page 1 of 8 System/Mode System Title KA Number Title RO Value 10 CFR 55 Tier 1 Group 1 000007 Reactor Trip EA2.03 Ability to determine or interpret the following as they apply to a reactor trip:: Reactor trip breaker 4.2 41.7 / 45.5 /

position 45.6 000008 Pressurizer Vapor Space Accident AK3.04 Knowledge of the reasons for the following responses as they apply to the Pressurizer Vapor 4.2 41.5 / 41.10 /

Space Accident:: RCP tripping requirements 45.6 / 45.13 000009 Small Break LOCA EA2.06 Ability to determine or interpret the following as they apply to a small break LOCA:: Whether PZR 3.8 43.5 / 45.13 water inventory loss is imminent 000009 Small Break LOCA EK3.21 Knowledge of the reasons for the following responses as the apply to the small break LOCA:: 4.2 41.5 / 41.10 /

Actions contained in EOP for small break LOCA/leak 45.6 / 45.13 000017 Reactor Coolant Pump Malfunctions AK2.07 Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC 2.9 41.7 / 45.7 (Loss of RC Flow) Flow) and the following:: RCP seals 000026 Loss of Component Cooling Water AA1.07 Ability to operate and / or monitor the following as they apply to the Loss of Component Cooling 2.9 41.7 / 45.5 /

Water:: Flow rates to the components and systems that are serviced by the CCWS; interactions 45.6 among the components 000027 Pressurizer Pressure Control System 2.4.49  : Ability to perform without reference to procedures those actions that require immediate operation 4.0 41.10 / 43.2 /

Malfunction of system components and controls. 45.6 000029 Anticipated Transient Without Scram EK2.06 Knowledge of the interrelations between the and the following an ATWS:: Breakers, relays, and 2.9* 41.7 / 45.7 (ATWS) disconnects 000038 Steam Generator Tube Rupture EK3.03 Knowledge of the reasons for the following responses as the apply to the SGTR:: Automatic 3.6* 41.5 / 41.10 /

actions associated with high radioactivity in S/G sample lines 45.6 / 45.13 000040 Steam Line Rupture AA1.24 Ability to operate and / or monitor the following as they apply to the Steam Line Rupture:: Main 3.8 41.7 / 45.5 /

steam header pressure gauges 45.6 000040 Steam Line Rupture AK2.01 Knowledge of the interrelations between the Steam Line Rupture and the following:: Valves 2.6* 41.7 / 45.7

PWR RO Written Examination Outline (Continued)

Nov 12, 2003 7:11 PM Page 2 of 8 System/Mode System Title KA Number Title RO Value 10 CFR 55 000054 Loss of Main Feedwater 2.4.50  : Ability to verify system alarm setpoints and operate controls identified in the alarm response 3.3 45.3 manual.

000055 Station Blackout EK1.01 Knowledge of the operational implications of the following concepts as they apply to the Station 3.3 41.8 / 41.10 /

Blackout :: Effect of battery discharge rates on capacity 45.3 000056 Loss of Off-Site Power AA2.20 Ability to determine and interpret the following as they apply to the Loss of Offsite Power:: AFW 3.9 43.5 / 45.13 flow indicator 000057 Loss of Vital AC Electrical Instrument 2.4.50  : Ability to verify system alarm setpoints and operate controls identified in the alarm response 3.3 45.3 Bus manual.

000057 Loss of Vital AC Electrical Instrument AA1.02 Ability to operate and / or monitor the following as they apply to the Loss of Vital AC Instrument 3.8 41.7 / 45.5 /

Bus Bus:: Manual control of PZR level 45.6 CE-E02 Reactor Trip Recovery EK1.01 Knowledge of the operational implications of the following concepts as they apply to the (Reactor 2.9 41.8 / 41.10 /

Trip Recovery): Components, capacity, and function of emergency systems. 45.3 CE-E06 Loss of Feedwater EK1.03 Knowledge of the operational implications of the following concepts as they apply to the (Loss of 3.2 41.8 / 41.10 /

Feedwater): Annunciators and conditions indicating signals, and remedial actions associated with 45.3 the (Loss of Feedwater).

PWR RO Written Examination Outline (Continued)

Nov 12, 2003 7:11 PM Page 3 of 8 System/Mode System Title KA Number Title RO Value 10 CFR 55 Tier 1 Group 2 000024 Emergency Boration AK2.04 Knowledge of the interrelations between the Emergency Boration and the following:: Pumps 2.6 41.7 / 45.7 000032 Loss of Source Range Nuclear AA1.01 Ability to operate and / or monitor the following as they apply to the Loss of Source Range Nuclear 3.1* 41.7 / 45.5 /

Instrumentation Instrumentation:: Manual restoration of power 45.6 000036 Fuel Handling Incidents 2.4.49  : Ability to perform without reference to procedures those actions that require immediate operation 4.0 41.10 / 43.2 /

of system components and controls. 45.6 000060 Accidental Gaseous Radwaste Release AK2.01 Knowledge of the interrelations between the Accidental Gaseous Radwaste Release and the 2.6 41.7 / 45.7 following:: ARM system, including the normal radiation-level indications and the operability status 000061 Area Radiation Monitoring (ARM) AA2.01 Ability to determine and interpret the following as they apply to the Area Radiation Monitoring 3.5 43.5 / 45.13 System Alarms (ARM) System Alarms:: ARM panel displays 000068 Control Room Evacuation AK3.17 Knowledge of the reasons for the following responses as they apply to the Control Room 3.7 41.5 / 41.10 /

Evacuation:: Injection of boric acid into the RCS 45.6 / 45.13 CE-A11 RCS Overcooling 2.1.27  : Knowledge of system purpose and or function. 2.8 41.7 CE-A13 Natural Circulation Operations AK3.03 Knowledge of the reasons for the following responses as they apply to the (Natural Circulation 3.4 41.5 / 41.10 /

Operations): Manipulation of controls required to obtain desired operating results during abnormal, 45.6 / 45.13 and emergency situations.

CE-A16 Excess RCS Leakage AA1.02 Ability to operate and / or monitor the following as they apply to the (Excess RCS Leakage): 3.0 41.7 / 45.5 /

Operating behavior characteristics of the facility. 45.6

PWR RO Written Examination Outline (Continued)

Nov 12, 2003 7:11 PM Page 4 of 8 System/Mode System Title KA Number Title RO Value 10 CFR 55 Tier 2 Group 1 003000 Reactor Coolant Pump System A3.04 Ability to monitor automatic operation of the RCPS, including:: RCS flow 3.6 41.7 / 45.5 003000 Reactor Coolant Pump System K1.08 Knowledge of the physical connections and/or cause-effect relationships between the RCPS and 2.7* 41.2 to 41.9 /

the following systems:: Containment isolation 45.7 to 45.8 004000 Chemical and Volume Control System A2.09 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) 3.0 41.5 / 43.5 /

based on those predictions, use procedures to correct, control, or mitigate the consequences of 45.3 / 45.5 those malfunctions or operations:: High primary and/or secondary activity 004000 Chemical and Volume Control System K6.15 Knowledge of the effect of a loss or malfunction on the following CVCS components:: Reason for 2.8 41.7 / 45.7 venting VCT and pump casings while filling: vents must connect to LRS 005000 Residual Heat Removal System A4.03 Ability to manually operate and/or monitor in the control room:: RHR temperature, PZR heaters 2.8* 41.7 / 45.5 to and flow, and nitrogen 45.8 005000 Residual Heat Removal System K4.12 Knowledge of RHRS design feature(s) and/or interlock(s) which provide or the following:: Lineup 3.1* 41.7 for piggyback mode with CSS 006000 Emergency Core Cooling System 2.1.33  : Ability to recognize indications for system operating parameters which are entry-level conditions 3.4 43.2 / 43.3 /

for technical specifications. 45.3 006000 Emergency Core Cooling System A2.12 Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) 4.5 41.5 / 45.5 based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:: Conditions requiring actuation of ECCS 007000 Pressurizer Relief Tank / Quench Tank A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the P S; and (b) 2.6 41.5 / 43.5 /

System based on those predictions, use procedures to correct, control, or mitigate the consequences of 45.3 / 45.13 those malfunctions or operations:: Abnormal pressure in the PRT 007000 Pressurizer Relief Tank / Quench Tank A4.10 Ability to manually operate and/or monitor in the control room:: Recognition of leaking PORV/code 3.6 41.7 / 45.5 to System safety 45.8 008000 Component Cooling Water System A3.01 Ability to monitor automatic operation of the CCWS, including:: Setpoints on instrument signal 3.2* 41.7 / 45.5 levels for normal operations, warnings, and trips that are applicable to the CCWS

PWR RO Written Examination Outline (Continued)

Nov 12, 2003 7:11 PM Page 5 of 8 System/Mode System Title KA Number Title RO Value 10 CFR 55 010000 Pressurizer Pressure Control System K1.05 Knowledge of the physical connections and/or cause-effect relationships between the PZR PCS 3.4 41.2 to 41.9 /

and the following systems:: PRTS 45.7 to 45.8 010000 Pressurizer Pressure Control System K5.01 Knowledge of the operational implications of the following concepts as the apply to the PZR PCS:: 3.5 41.5 / 45.7 Determination of condition of fluid in PZR, using steam tables 012000 Reactor Protection System K1.08 Knowledge of the physical connections and/or cause effect relationships between the RPS and the 2.9* 41.2 to 41.9 /

following systems:: MFW 45.7 to 45.8 012000 Reactor Protection System K5.02 Knowledge of the operational implications of the following concepts as the apply to the RPS:: 3.1* 41.5 / 45.7 Power density 013000 Engineered Safety Features Actuation 2.1.32  : Ability to explain and apply all system limits and precautions. 3.4 41.10 / 43.2 /

System 45.12 013000 Engineered Safety Features Actuation A1.02 Ability to predict and/or monitor changes in parameters (to Prevent exceeding design limits) 3.9 41.5 / 45.5 System associated with operating the ESFAS controls including:: Containment pressure, temperature, and humidity 026000 Containment Spray System A1.04 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 3.1 41.5 / 45.5 associated with operating the CSS controls including:: Containment humidity 039000 Main and Reheat Steam System K4.08 Knowledge of MRSS design feature(s) and/or interlock(s) which provide for the following:: 3.3 41.7 Interlocks on MSIV and bypass valves 039000 Main and Reheat Steam System K5.08 Knowledge of the operational implications of the following concepts as the apply to the MRSS:: 3.6 41.5 / 45.7 Effect of steam removal on reactivity 059000 Main Feedwater System A4.11 Ability to manually operate and monitor in the control room:: Recovery from automatic feedwater 3.1 41.7 / 45.5 to isolation 45.8 061000 Auxiliary / Emergency Feedwater A1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 3.3* 41.5 / 45.5 System associated with operating the AFW controls including:: S/G pressure

PWR RO Written Examination Outline (Continued)

Nov 12, 2003 7:11 PM Page 6 of 8 System/Mode System Title KA Number Title RO Value 10 CFR 55 064000 Emergency Diesel Generators A3.12 Ability to monitor automatic operation of the ED/G system, including:: Purpose of automatic load 3.3* 41.7 / 45.5 sequencer 064000 Emergency Diesel Generators K4.03 Knowledge of ED/G system design feature(s) and/or interlock(s) which provide for the following:: 2.5 41.7 Governor valve operation 073000 Process Radiation Monitoring System 2.4.50  : Ability to verify system alarm setpoints and operate controls identified in the alarm response 3.3 45.3 manual.

076000 Service Water System K2.01 Knowledge of bus power supplies to the following:: Service water 2.7* 41.7 076000 Service Water System K3.07 Knowledge of the effect that a loss or malfunction of the SWS will have on the following:: ESF 3.7 41.7 / 45.6 loads 078000 Instrument Air System K3.02 Knowledge of the effect that a loss or malfunction of the IAS will have on the following:: Systems 3.4 41.7 / 45.6 having pneumatic valves and controls

PWR RO Written Examination Outline (Continued)

Nov 12, 2003 7:11 PM Page 7 of 8 System/Mode System Title KA Number Title RO Value 10 CFR 55 Tier 2 Group 2 001000 Control Rod Drive System K4.11 Knowledge of CRDS design feature(s) and/or interlock(s) which provide for the following:: 2.7 41.7 Resetting of CRDM circuit breakers 002000 Reactor Coolant System A4.06 Ability to manually operate and/or monitor in the control room:: Overflow level of the RWST 2.9 41.7 / 45.5 to 45.8 011000 Pressurizer Level Control System 2.1.02  : Knowledge of operator responsibilities during all modes of plant operation. 3.0 41.10 / 45.13 015000 Nuclear Instrumentation System K3.01 Knowledge of the effect that a loss or malfunction of the NIS will have on the following:: RPS 3.9 41.7 / 45.6 028000 Hydrogen Recombiner and Purge A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the HRPS; and (b) 3.4 41.5 / 43.5 /

Control System based on those predictions, use procedures to correct, control or mitigate the consequences of 45.3 / 45.13 those malfunctions or operations:: The hydrogen air concentration in excess of limit flame propagation or detonation with resulting equipment damage in containment 029000 Containment Purge System A3.01 Ability to monitor automatic operation of the Containment Purge System including:: CPS isolation 3.8 41.7 / 45.5 033000 Spent Fuel Pool Cooling System K1.02 Knowledge of the physical connections and/or cause-effect relationships between the Spent Fuel 2.5 41.2 to 41.9 /

Pool Cooling System and the following systems:: RHRS 45.7 to 45.8 035000 Steam Generator System A1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 3.5 41.5 / 45.5 associated with operating the S/GS controls including:: S/G pressure 041000 Steam Dump System and Turbine K5.02 Knowledge of the operational implications of the following concepts as the apply to the SDS:: Use 2.5 41.5 / 45.7 Bypass Control of steam tables for saturation temperature and pressure 086000 Fire Protection System K6.04 Knowledge of the effect of a loss or malfunction on the Fire Protection System following will have 2.6 41.7 / 45.7 on the :: Fire, smoke, and heat detectors

PWR RO Written Examination Outline (Last Page)

Nov 12, 2003 7:11 PM Page 8 of 8 System/Mode System Title KA Number Title RO Value 10 CFR 55 Tier 3 Group 4 000000 Generic Knowledges and Abilities 2.1.19  : Ability to use plant computer to obtain and evaluate parametric information on system or 3.0 45.12 component status.

000000 Generic Knowledges and Abilities 2.1.20  : Ability to execute procedure steps. 4.3 41.10 / 43.5 /

45.12 000000 Generic Knowledges and Abilities 2.1.28  : Knowledge of the purpose and function of major system components and controls. 3.2 41.7 000000 Generic Knowledges and Abilities 2.2.12  : Knowledge of surveillance procedures. 3.0 41.10 / 45.13 000000 Generic Knowledges and Abilities 2.2.13  : Knowledge of tagging and clearance procedures. 3.6 41.10 / 45.13 000000 Generic Knowledges and Abilities 2.3.01  : Knowledge of 10CFR20 and related facility radiation control requirements. 2.6 41.12 / 43.4 /

45.9 / 45.10 000000 Generic Knowledges and Abilities 2.3.11  : Ability to control radiation releases. 2.7 45.9 / 45.10 000000 Generic Knowledges and Abilities 2.4.17  : Knowledge of EOP terms and definitions. 3.1 41.10 / 45.13 000000 Generic Knowledges and Abilities 2.4.24  : Knowledge of loss of cooling water procedures. 3.3 41.10 / 45.13 000000 Generic Knowledges and Abilities 2.4.31  : Knowledge of annunciators alarms and indications, and use of the response instructions. 3.3 41.10 / 45.3

ES-401 PWR Examination Outline Form ES-401-2 Facility: Fort Calhoun Printed: 11/12/2003 Date Of Exam: 03/12/2004 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total K A A2 G*

1. 1 3 3 3 3 3 3 18 0 0 4 3 7 Emergency 2 0 2 2 2 1 2 9 0 0 2 3 5 Abnormal Plant Tier 3 5 5 5 4 5 27 0 0 6 6 12 Evolutions Totals 1 3 2 2 3 3 1 3 3 2 3 3 28 0 0 2 2 4 2.

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

3. Generic Knowledge And 10 7 Abilities Categories 3 2 2 3 1 2 2 2 Note:
1. Ensure that at least two topics from every K/A category are sampled within each tier of the RO outline (i.e., the "Tier Totals" in each K/A category shall not be less than two). Refer to Section D.1.c for additional guidance regarding the SRO sampling.
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. Select topics from many systems and evolutions; avoid selecting more than two K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category /tier.

6.* 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. The SRO K/As must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7. 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 columns labeled "K" and "A".

Use duplicate pages for RO and SRO-only exams.

8. For Tier 3, enter the K/A numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.

1

PWR SRO Examination Outline Printed: 11/12/2003 Facility: Fort Calhoun ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # E/APE Name/Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 008 000008 Pressurizer Vapor Space X AA2.22 - Consequences of loss of 4.2 1 Accident / 3 pressure in RCS; methods for evaluating pressure loss 015 000015 RCP Malfunctions / 4 X AA2.07 - Calculation of expected values 2.9 1 of flow in the loop with RCP secured 022 000022 Loss of Rx Coolant X 2.1.14 - Knowledge of system status 3.3 1 Makeup / 2 criteria which require the notification of plant personnel.

025 000025 Loss of RHR System / 4 X 2.4.49 - Ability to perform without 4.0 1 reference to procedures those actions that require immediate operation of system components and controls.

038 000038 Steam Gen. Tube Rupture / X EA2.08 - Viable alternatives for placing 4.4 1 3 plant in safe condition when condenser is not available 055 000055 Station Blackout / 6 X EA2.02 - RCS core cooling through 4.6 1 natural circulation cooling to S/G cooling 056 000056 Loss of Off-site Power / 6 X 2.1.33 - Ability to recognize indications 4.0 1 for system operating parameters which are entry-level conditions for technical specifications.

K/A Category Totals: 0 0 0 0 4 3 Group Point Total: 7 1

PWR SRO Examination Outline Printed: 11/12/2003 Facility: Fort Calhoun ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # E/APE Name/Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 051 000051 Loss of Condenser X AA2.01 - Cause for low vacuum 2.7* 1 Vacuum / 4 condition 069 000069 Loss of CTMT Integrity / X AA2.01 - Loss of containment integrity 4.3 1 5

074 000074 Inad. Core Cooling / 4 X 2.4.6 - Knowledge symptom based EOP 4.0 1 mitigation strategies.

076 000076 High Reactor Coolant X 2.1.32 - Ability to explain and apply all 3.8 1 Activity / 9 system limits and precautions.

E09 CE/E09 Functional Recovery X 2.2.25 - Knowledge of bases in technical 3.7 1 specifications for limiting conditions for operations and safety limits.

K/A Category Totals: 0 0 0 0 2 3 Group Point Total: 5 1

PWR SRO Examination Outline Printed: 11/12/2003 Facility: Fort Calhoun ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Ev # System / Evolution Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 022 022 Containment Cooling X 2.1.14 - Knowledge of 3.3 1 system status criteria which require the notification of plant personnel.

059 059 Main Feedwater X A2.04 - Feeding a dry S/G 3.4* 1 062 062 AC Electrical X A2.08 - Consequences of 3.0* 1 Distribution exceeding voltage limitations 063 063 DC Electrical X 2.4.6 - Knowledge symptom 4.0 1 Distribution based EOP mitigation strategies.

K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 2 Group Point Total: 4 1

PWR SRO Examination Outline Printed: 11/12/2003 Facility: Fort Calhoun ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Ev # System / Evolution Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 016 016 Non-nuclear X 2.2.25 - Knowledge of bases 3.7 1 Instrumentation in technical specifications for limiting conditions for operations and safety limits.

071 071 Waste Gas Disposal X A2.05 - Power failure to the 2.6 1 ARM and PRM Systems K/A Category Totals: 0 0 0 0 0 0 0 1 0 0 1 Group Point Total: 2 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Printed: 11/12/2003 Facility: Fort Calhoun Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.11 Knowledge of less than one hour technical 3.8 1 specification action statements for systems.

Category Total: 1 Equipment Control 2.2.18 Knowledge of the process for managing 3.6 1 maintenance activities during shutdown operations.

2.2.28 Knowledge of new and spent fuel movement 3.5 1 procedures.

Category Total: 2 Radiation Control 2.3.4 Knowledge of radiation exposure limits and 3.1 1 contamination control, including permissible levels in excess of those authorized.

2.3.8 Knowledge of the process for performing a 3.2 1 planned gaseous radioactive release.

Category Total: 2 Emergency Procedures/Plan 2.4.8 Knowledge of how the event-based 3.7 1 emergency/abnormal operating procedures are used in conjunction with the symptom-based EOPs.

2.4.33 Knowledge of the process used track inoperable 2.8 1 alarms.

Category Total: 2 Generic Total: 7 1

Nov 12, 2003 9:06 PM PWR SRO Written Examination Outline Summary Page 1 of 1 System/Mode System Title K1 K2 K3 A1 A2 G Points EPE/APE Tier 1 / Group 1 000007 Reactor Trip 1 1 000008 Pressurizer Vapor Space Accident 1 1 2 000009 Small Break LOCA 1 1 2 000015 Reactor Coolant Pump Malfunctions 1 1 000017 Reactor Coolant Pump Malfunctions (Loss of RC Flow) 1 1 000022 Loss of Reactor Coolant Makeup 1 1 000025 Loss of Residual Heat Removal System 1 1 000026 Loss of Component Cooling Water 1 1 000027 Pressurizer Pressure Control System Malfunction 1 1 000029 Anticipated Transient Without Scram (ATWS) 1 1 000038 Steam Generator Tube Rupture 1 1 2 000040 Steam Line Rupture 1 1 2 000054 Loss of Main Feedwater 1 1 000055 Station Blackout 1 1 2 000056 Loss of Off-Site Power 1 1 2 000057 Loss of Vital AC Electrical Instrument Bus 1 1 2 CE-E02 Reactor Trip Recovery 1 1 CE-E06 Loss of Feedwater 1 1 3 3 3 3 7 6 25 EPE/APE Tier 1 / Group 2 000024 Emergency Boration 1 1 000032 Loss of Source Range Nuclear Instrumentation 1 1 000036 Fuel Handling Incidents 1 1 000051 Loss of Condenser Vacuum 1 1 000060 Accidental Gaseous Radwaste Release 1 1 000061 Area Radiation Monitoring (ARM) System Alarms 1 1 000068 Control Room Evacuation 1 1 000069 Loss of Containment Integrity 1 1 000074 Inadequate Core Cooling 1 1 000076 High Reactor Coolant Activity 1 1 CE-A11 RCS Overcooling 1 1 CE-A13 Natural Circulation Operations 1 1 CE-A16 Excess RCS Leakage 1 1 CE-E09 Functional Recovery 1 1 2 2 2 3 5 14 Grand Total of EPE/APE K&A Selection: 3 5 5 5 10 11 39

PWR SRO Written Examination Outline Summary Nov 12, 2003 9:07 PM Page 1 of 1 System/Mode System Title K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Points Plant System Tier 2 / Group 1 003000 Reactor Coolant Pump System 1 1 2 004000 Chemical and Volume Control System 1 1 2 005000 Residual Heat Removal System 1 1 2 006000 Emergency Core Cooling System 1 1 2 007000 Pressurizer Relief Tank / Quench Tank System 1 1 2 008000 Component Cooling Water System 1 1 010000 Pressurizer Pressure Control System 1 1 2 012000 Reactor Protection System 1 1 2 013000 Engineered Safety Features Actuation System 1 1 2 022000 Containment Cooling System 1 1 026000 Containment Spray System 1 1 039000 Main and Reheat Steam System 1 1 2 059000 Main Feedwater System 1 1 2 061000 Auxiliary / Emergency Feedwater System 1 1 062000 A.C. Electrical Distribution 1 1 063000 D.C. Electrical Distribution 1 1 064000 Emergency Diesel Generators 1 1 2 073000 Process Radiation Monitoring System 1 1 076000 Service Water System 1 1 2 078000 Instrument Air System 1 1 3 1 2 3 3 1 3 5 3 3 5 32 Plant System Tier 2 / Group 2 001000 Control Rod Drive System 1 1 002000 Reactor Coolant System 1 1 011000 Pressurizer Level Control System 1 1 015000 Nuclear Instrumentation System 1 1 016000 Non-Nuclear Instrumentation System 1 1 028000 Hydrogen Recombiner and Purge Control System 1 1 029000 Containment Purge System 1 1 033000 Spent Fuel Pool Cooling System 1 1 035000 Steam Generator System 1 1 041000 Steam Dump System and Turbine Bypass Control 1 1 071000 Waste Gas Disposal System 1 1 086000 Fire Protection System 1 1 1 1 1 1 1 1 2 1 1 2 12 Grand Total of Plant System K&A Selection: 4 1 3 4 4 2 4 7 4 4 7 44

Nov 12, 2003 9:07 PM PWR SRO Written Examination Outline Summary Page 1 of 1 System/Mode System Title Cat 1 Cat 2 Cat 3 Cat 4 Points Generic Knowledge and Abilities Tier 3 000000 Generic Knowledges and Abilities 4 4 4 5 17 4 4 4 5 17 Grand Total of Generic K&A Selection: 4 4 4 5 17

PWR SRO Only Written Examination Outline Nov 12, 2003 7:12 PM Page 1 of 5 System/Mode System Title KA Number Title SRO Value 10 CFR 55 Tier 1 Group 1 000008 Pressurizer Vapor Space Accident AA2.22 Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space 4.2 43.5 / 45.13 Accident:: Consequences of loss of pressure in RCS; methods for evaluating pressure loss 000015 Reactor Coolant Pump Malfunctions AA2.07 Ability to determine and interpret the following as they apply to the Reactor Coolant Pump 2.9 43.5 / 45.13 Malfunctions (Loss of RC Flow):: Calculation of expected values of flow in the loop with RCP secured 000022 Loss of Reactor Coolant Makeup 2.1.14  : Knowledge of system status criteria which require the notification of plant personnel. 3.3 43.5 / 45.12 000025 Loss of Residual Heat Removal System 2.4.49  : Ability to perform without reference to procedures those actions that require immediate operation 4.0 41.10 / 43.2 /

of system components and controls. 45.6 000038 Steam Generator Tube Rupture EA2.08 Ability to determine or interpret the following as they apply to a SGTR:: Viable alternatives for 4.4 43.5 / 45.13 placing plant in safe condition when condenser is not available 000055 Station Blackout EA2.02 Ability to determine or interpret the following as they apply to a Station Blackout:: RCS core 4.6 43.5 / 45.13 cooling through natural circulation cooling to S/G cooling 000056 Loss of Off-Site Power 2.1.33  : Ability to recognize indications for system operating parameters which are entry-level conditions 4.0 43.2 / 43.3 /

for technical specifications. 45.3

PWR SRO Only Written Examination Outline (Continued)

Nov 12, 2003 7:12 PM Page 2 of 5 System/Mode System Title KA Number Title SRO Value 10 CFR 55 Tier 1 Group 2 000051 Loss of Condenser Vacuum AA2.01 Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum:: 2.7* 43.5 / 45.13 Cause for low vacuum condition 000069 Loss of Containment Integrity AA2.01 Ability to determine and interpret the following as they apply to the Loss of Containment Integrity:: 4.3 43.5 / 45.13 Loss of containment integrity 000074 Inadequate Core Cooling 2.4.06  : Knowledge symptom based EOP mitigation strategies. 4.0 41.10 / 43.5 /

45.13 000076 High Reactor Coolant Activity 2.1.32  : Ability to explain and apply all system limits and precautions. 3.8 41.10 / 43.2 /

45.12 CE-E09 Functional Recovery 2.2.25  : Knowledge of bases in technical specifications for limiting conditions for operations and safety 3.7 43.2 limits.

PWR SRO Only Written Examination Outline (Continued)

Nov 12, 2003 7:12 PM Page 3 of 5 System/Mode System Title KA Number Title SRO Value 10 CFR 55 Tier 2 Group 1 022000 Containment Cooling System 2.1.14  : Knowledge of system status criteria which require the notification of plant personnel. 3.3 43.5 / 45.12 059000 Main Feedwater System A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) 3.4* 41.5 / 43.5 /

based on those predictions, use procedures to correct, control, or mitigate the consequences of 45.3 / 45.13 those malfunctions or operations:: Feeding a dry S/G 062000 A.C. Electrical Distribution A2.08 Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution 3.0* 41.5 / 43.5 /

system; and (b) based on those predictions, use procedures to correct, control, or mitigate the 45.3 / 45.13 consequences of those malfunctions or operations:: Consequences of exceeding voltage limitations 063000 D.C. Electrical Distribution 2.4.06  : Knowledge symptom based EOP mitigation strategies. 4.0 41.10 / 43.5 /

45.13

PWR SRO Only Written Examination Outline (Continued)

Nov 12, 2003 7:12 PM Page 4 of 5 System/Mode System Title KA Number Title SRO Value 10 CFR 55 Tier 2 Group 2 016000 Non-Nuclear Instrumentation System 2.2.25  : Knowledge of bases in technical specifications for limiting conditions for operations and safety 3.7 43.2 limits.

071000 Waste Gas Disposal System A2.05 Ability to (a) predict the impacts of the following malfunctions or operations on the Waste Gas 2.6 41.5 / 43.5 /

Disposal System ; and (b) based on those predictions, use procedures to correct, control, or 45.3 / 45.13 mitigate the consequences of those malfunctions or operations:: Power failure to the ARM and PRM Systems

PWR SRO Only Written Examination Outline (Last Page)

Nov 12, 2003 7:12 PM Page 5 of 5 System/Mode System Title KA Number Title SRO Value 10 CFR 55 Tier 3 Group 4 000000 Generic Knowledges and Abilities 2.1.11  : Knowledge of less than one hour technical specification action statements for systems. 3.8 43.2 / 45.13 000000 Generic Knowledges and Abilities 2.2.18  : Knowledge of the process for managing maintenance activities during shutdown operations. 3.6 43.5 / 45.13 000000 Generic Knowledges and Abilities 2.2.28  : Knowledge of new and spent fuel movement procedures. 3.5 43.7 / 45.13 000000 Generic Knowledges and Abilities 2.3.04  : Knowledge of radiation exposure limits and contamination control, including permissible levels in 3.1 43.4 / 45.10 excess of those authorized.

000000 Generic Knowledges and Abilities 2.3.08  : Knowledge of the process for performing a planned gaseous radioactive release. 3.2 43.4 / 45.10 000000 Generic Knowledges and Abilities 2.4.08  : Knowledge of how the event-based emergency/abnormal operating procedures are used in 3.7 41.10 / 43.5 /

conjunction with the symptom-based EOPs. 45.13 000000 Generic Knowledges and Abilities 2.4.33  : Knowledge of the process used track inoperable alarms. 2.8 41.10 / 43.5 /

45.13

ES-401 Record of Rejected K/As Form ES-401-4 Tier ROGroup System/Mode KA Number Reason for Rejection 1 1 000015 AA2.07 RO imp:2.1 No FCS specific priority Used for SRO exam 1 1 000038 EK2.02 RO Imp:2.4 No FCS specific priority 1 1 000057 AA2.10 RO imp:2.3 No FCS specific priority 2 2 001000 K4.06 No First Out panel at FCS - reject from RO 2 1 003000 K4.10 RO Imp:2.3 No FCS specific priority 2 1 005000 K2.02 RO Imp:2.4 No FCS specific priority 2 1 010000 K6.07 RO Imp:2.3 No FCS specific priority 2 2 014000 K6.01 RO Imp:2.3 No FCS specific priority 2 2 033000 K1.07 RO Imp:2.4 No FCS specific priority 2 1 039000 K3.04 RO: No turbine driven MFW pumps at FCS 2 1 056000 K5.03 RO Imp:2.2 No FCS specific priority 2 1 062000 K5.03 RO Imp:2.4 No FCS specific priority 2 1 063000 K5.02 RO Imp:2.2 No FCS specific priority 2 2 068000 K1.05 RO Imp:2.3 No FCS specific priority 2 2 071000 K6.10 RO Imp:2.3 No FCS specific priority 2 2 075000 K2.03 RO: Redundant to 076000 K2 2 1 078000 K6.01 RO Imp:2.4 No FCS specific priority 1 1 CE-E05 2.4.30 RO imp:2.2 No FCS specific priority Wednesday, November 12, 2003 Page 1 of 1

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Fort Calhoun Date of Examination: 3/12/04 Examination Level: RO / SRO Operating Test Number: _____________

Administrative Topic Describe activity to be performed (See Note)

Manually determine dilution volume needed to raise power level.

Conduct of Operations (K/A 2.1.25 - Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.

RO Imp: 2.8; CFR: 41.10/43.5/45.12)

Determine maximum allowable Diesel/Generator load based on weather Conduct of Operations conditions.

(K/A 2.1.32 - Ability to explain and apply all system limits and precautions. RO Imp: 3.4; CFR: 41.10/43.2/45.12)

Use P&IDs to determine equipment affected by closure of instrument air Equipment Control valve.

(K/A 2.2.13 - Knowledge of tagging and clearance procedures. RO Imp:

3.6; CFR 41.10/45.13)

High Radiation Area entry and exit with EAD alarm.

Radiation Control (K/A 2.3.1 - Knowledge of 10 CFR:20 and related facility radiation control requirements. RO Imp: 2.6; CFR: 41.12/43.4/45.9/45.10)

Emergency 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 5 are required.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Fort Calhoun Date of Examination: 3/12/04 Examination Level: RO / SRO Operating Test Number: _____________

Administrative Topic Describe activity to be performed (See Note)

SRO Review of shutdown margin calculation with inoperable CEA.

Conduct of Operations (K/A: 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation; SRO Imp: 3.7; CFR: 43.5/45.12/45.13)

Determine Raw Water system operability based on technical specifications Conduct of Operations and TDB III.41.

(K/A: 2.1.12 - Ability to apply technical specifications for a system; SRO Imp: 4.0; CFR: 43.2/43.5/45.3)

SRO Review of Surveillance Test results.

Equipment Control (K/A: 2.2.12 - Knowledge of surveillance procedures; SRO Imp: 3.4; CFR:

41.10/45.13)

Determine primary to secondary leakage from plant parameters and actions Radiation Control required to control offsite releases (K/A: 2.3.11 - Ability to control radiation releases; SRO Imp: 3.2; CFR 45.9/45.10)

Emergency event classification and Protective Action Recommendations Emergency Plan (K/A 2.4.41 - Knowledge of the emergency action level thresholds and classifications. SRO Imp: 4.1; CFR 43.5/45.11) (K/A 2.4.44 - Knowledge of emergency plan protective action recommendations SRO Imp: 4.0; CFR 43.5/45.11)

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Fort Calhoun Date of Examination: 3/12/04 Exam Level: RO / SRO(I) / SRO(U) Operating Test No. _____________

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title Type Code* Safety Function

a. Establish Simultaneous Hot and Cold leg injection - new N, E, A 2 (K/A 006000 A4.05 3.9/3.8)
b. Shutdown a Reactor Coolant Pump - 0613 (modified) M, A, L 4P (K/A 003000 A4.06 2.9/2.9)
c. Operate Containment Hydrogen Analyzer - 0156 D, E 5 (K/A 028000 A1.01 3.4/3.8) d.Restoration of offsite electrical power following loss of offsite D, E 6 power - 0026 (K/A 064000 A4.07 3.4/3.4)
e. Perform manual trip check - 0654 D, L 7 (K/A 012000 A4.01 4.5/4.5)
f. Raise RCS Pressure with PORV Open Failure - 0621 D, A 3 (K/A 010000 A2.03 4.1/4.2)
g. Recover misaligned Control Rod - new N, A 1 (K/A 001000 A2.03 3.5/4.2)
h. Startup Containment Purge - 0704 (modified) M, A, L 8 (K/A 029000 A2.03 2.7/3.1)

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

a. Establish RW Backup to SI Pumps - 0010-RW D, R, E 4S (K/A 076000 A4.04 3.5/3.5)
b. Emergency Start of Diesel Fire Pump - 0450 D, E 8 (K/A 086000 A4.01 3.3/3.3)
c. Minimize DC Loads - 0304 (time critical) D, E 6 (K/A 063000 A1.01 2.5/3.3)
  • Type Codes: (D)irect from bank, (M)odified from Bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA , (E)mergency or abnormal condition

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Fort Calhoun Date of Examination: 3/12/04 Exam Level: RO / SRO(I) / SRO(U) Operating Test No. _____________

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title Type Code* Safety Function

a. Establish Simultaneous Hot and Cold leg injection - new N, E, A 2 (K/A 006000 A4.05 3.9/3.8)
b. Shutdown a Reactor Coolant Pump - 0613 (modified) M, A, L 4P (K/A 003000 A4.06 2.9/2.9)
c. Operate Containment Hydrogen Analyzer - 0156 D, E 5 (K/A 028000 A1.01 3.4/3.8) d.Restoration of offsite electrical power following loss of offsite D, E 6 power - 0026 (K/A 064000 A4.07 3.4/3.4) e.
f. Raise RCS Pressure with PORV Open Failure - 0621 D, A 3 (K/A 010000 A2.03 4.1/4.2)
g. Recover misaligned Control Rod - new N, A 1 (K/A 001000 A2.03 3.5/4.2)
h. Startup Containment Purge - 0704 (modified) M, A, L 8 (K/A 029000 A2.03 2.7/3.1)

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

a. Establish RW Backup to SI Pumps - 0010-RW D, R, E 4S (K/A 076000 A4.04 3.5/3.5)
b. Emergency Start of Diesel Fire Pump - 0450 D, E 8 (K/A 086000 A4.01 3.3/3.3)
c. Minimize DC Loads - 0304 (time critical) D, E 6 (K/A 063000 A1.01 2.5/3.3)
  • Type Codes: (D)irect from bank, (M)odified from Bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA , (E)mergency or abnormal condition

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Fort Calhoun Date of Examination: 3/12/04 Exam Level: RO / SRO(I) / SRO(U) Operating Test No. _____________

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title Type Code* Safety Function

a. Establish Simultaneous Hot and Cold leg injection - new N, E, A 2 (K/A 006000 A4.05 3.9/3.8)
b. Shutdown a Reactor Coolant Pump - 0613 (modified) M, A, L 4P (K/A 003000 A4.06 2.9/2.9) c.

d.

e.

f.

g.

h.

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

a. Establish RW Backup to SI Pumps - 0010-RW D, R, E 4S (K/A 076000 A4.04 3.5/3.5)
b. Emergency Start of Diesel Fire Pump - 0450 D, E 8 (K/A 086000 A4.01 3.3/3.3)
c. Minimize DC Loads - 0304 (time critical) D, E 6 (K/A 063000 A1.01 2.5/3.3)
  • Type Codes: (D)irect from bank, (M)odified from Bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA , (E)mergency or abnormal condition

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 1 Op-Test No. ___________

Examiners: _________________________ Operators: _________________________

Initial Conditions: 100% Power MOC Turnover: Diesel Generator DG-1 and Charging Pump CH-1B are out of service. Maintain full power operation.

Event Malf Event Event No. No. Type* Description 1 I - sec S/G steam flow transmitter output fails high 2 I - pri Hot leg RTD fails high (tech spec entry) 3 C - sec Heater Drain Pump trips 4 C - pri CEA drop (tech spec entry) 5 R - pri T. S. required power reduction N - sec 6 I - pri VCT level transmitter fails low 7 C - pri CCW pump trips (tech spec entry) 8 C - pri Second CEA drops - Manual Reactor Trip Required 9 M - all Steam Generator Tube Rupture 10 C - sec MSIV on ruptured S/G will not close

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

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2 Op-Test No. ___________

Examiners: _________________________ Operators: _________________________

Initial Conditions: 100% Power MOC Turnover: Diesel driven FW pump, FW-54 and charging pump CH-1B are Out of Service.

Maintain power.

Event Malf Event Event No. No. Type* Description 1 I - sec PT-910 fails high causing turbine bypass valve to open 2 C - pri Charging Pump Trips (tech spec entry) 3 C - sec High turbine vibration caused by inadequate oil cooling 4 I - pri Wide Range NI channel D fails (tech spec entry) 5 I - pri Pressurizer Pressure channel fails low 6 M - all Loss of Offsite Power 7 M - all ATWS - manual trip required 8 C - sec Emergency Feedwater Storage Tank line is blocked causing a total loss of Feedwater (once-through cooling required)

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

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 3 Op-Test No. ___________

Examiners: _________________________ Operators: _________________________

Initial Conditions: 50% Power, FW-54 Out of Service Turnover: Diesel drive FW pump, FW-54 is out of service. Maintain power Scenario objective: Evaluate ISRO candidates in the primary and secondary positions with a surrogate acting as SRO Event Malf Event Event No. No. Type* Description 1 I - pri Controlling pressurizer level channel fails low 2 I - sec Steam generator level channel fails high 3 C - pri Reactor Coolant Pump lower seal failure 4 I - pri Letdown pressure transmitter PCV-210 fails low 5 C - pri Reactor Coolant Pump middle seal failure 6 R - pri Emergency shutdown N - sec 7 C - sec Running Bearing water pump trips 8 M - all Loss of Coolant Accident 9 C - sec Turbine trip failure 10 C - pri HPSI loop injection valves fail to open

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

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 4 (spare) Op-Test No. ___________

Examiners: _________________________ Operators: _________________________

Initial Conditions: 100% Power MOC Turnover: LPSI pump SI-1B is Out of Service for bearing replacement Event Malf Event Event No. No. Type* Description 1 I - pri Power range nuclear instrumentation channel fails (tech spec entry) 2 I - sec FW flow channel fails low 3 C - sec Diesel Generator, D/G-1, radiator leak (tech spec entry) 4 I - pri Letdown HX CCW outlet temperature transmitter fails low 5 C -sec Loss of 161 KV 6 M - all Steam line break inside containment 7 C -sec CW-1C breaker fails to trip preventing D/G-2 breaker from closing 8 C - pri CPHS fails to actuate

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