Text

2005 NRC Hot License Exam Outline
	ML052300129
Person / Time
Site:	Fort Calhoun
Issue date:	02/25/2006
From:	; Division of Reactor Safety IV
To:	;
References
	50-285/05-301
	Download: ML052300129 (86)
	v • d • e

Fort Calhoun Station 2005 NRC Hot License Exam Outline Submitted to Mr. Tom McKernon, Chief Examiner Scheduled Exam Dates : 7/8/05 - 7/15/05

Contents of Outline Proposed Schedule Outline Introduction Written Exam Outline

$ RO Written Exam Sample Plan (ES-401-2 and ES-401-3 forms, standard and enhanced versions)

$ SRO Written Exam Sample Plan (ES-401-2 and ES-401-3 forms, standard and enhanced versions)

$ Record of Rejected K/As (enhanced form for ES-401-4)

Administrative Topics Outline

$ Form ES-301-1 (RO)

$ Form ES-301-1 (SRO)

Walk-Through Test Outline

$ RO Form ES-301-2

$ SRO-I Form ES-301-2

$ SRO-U Form ES-301-2 Simulator Scenario Outline

$ ES-D-1 forms for all scenarios

$ ES-301-5 forms

$ ES-301-6 forms Copy of Form ES 201 -3 security agreement as it exists to date Form ES-201-2 Examination Outline Quality Checklist 2

Preliminary Schedule for FCS Exam Friday - 07/08/05 0800- 1300 All take written exam Monday - 07/11/05 1300 - 1500 Simulator Scenario One ( USRO1, RO1, RO3) 1500 - 1700 Simulator Scenario One ( USRO2, RO4, RO6) 1700 - 1900 Simulator Scenario One ( ISRO2, ISRO1, ISRO3)

Tuesday - 07/12/05 0700 - 0900 Simulator Scenario Two (USRO1, RO2, RO1) 0900 - 1100 Simulator Scenario Two (USRO2, RO5, RO4) 1100 - 1200 Lunch 1200 - 1500 RO Admin 1500 - 1700 Simulator Scenario Two (ISRO3, ISRO2, ISRO1)

Wedensday - 07/13/05 0700 - 0900 Simulator Scenario Three (USRO1, RO3, RO2) 0900 - 1100 Simulator Scenario Three (USRO2, RO6, RO5) 1100 - 1200 Lunch 1200 - 1500 SRO Admin 1500 - 1700 Simulator Scenario Three (ISRO1, ISRO3, ISRO2)

Thursday - 07/14/05 3

0700 - 0900 Simulator JPM set 1 (RO1, RO2) 0900 - 1100 Simulator JPM set 1 (RO3, RO4) 1100 - 1200 Lunch 1200 - 1400 Simulator JPM set 1 (RO5, RO6) 1400 - 1600 Simulator JPM set 1 (USRO1, USRO2) 1600 - 1800 Simulator JPM set 1 (ISRO1, ISRO2) 1800 - 1900 Simulator JPM set 1 (ISRO3)

Friday - 07/15/05 0700 - 0900 Simulator JPM set 1 (RO1, RO2) In-Plant JPMs (USRO1, USRO2) 0900 - 1100 Simulator JPM set 1 (RO3, RO4) In-Plant JPMs (RO1, RO2) 1100 - 1200 Lunch 1200 - 1400 Simulator JPM set 1 (RO5, RO6) In-Plant JPMs (RO3, RO4) 1400 - 1600 Simulator JPM set 1 (ISRO1, ISRO2) In-Plant JPMs (RO5, RO6) 1600 - 1800 Simulator JPM set 1 (ISRO3) In Plant JPMs (ISRO1, ISRO2) 1800 - 1900 In-Plant JPMs (ISRO3) 4

Outline Development for 7/2005 Fort Calhoun NRC Exam This exam outline was developed in accordance with NUREG-1021, Rev 9.

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

$ Station Blackout

$ Loss of Coolant Accident It also resulted in the following risk-significant operator actions being evaluated:

$ Manually opening a closed breaker to allow D/G to power vital bus.

$ Minimizing DC loads following a loss of offsite power.

$ Emergency Boration

$ Emergency Start of a Diesel-Generator

$ Determination of minimum HPSI flow in response to a clogged containment sump strainer All four simulator scenarios are new.

Audit Exam There will be no duplication of questions, scenarios, system JPMs or administrative JPMs between the audit exam and the license exam.

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ES-401 PWR Examination Outline Form ES-401-2 l Facility: Fort Calhoun Date of Exam: 07/11/05 RO K/A Category Points SRO-Only Points l Tier Group K K K K K K A A A A G A2 G* Total l 1 2 3 4 5 6 1 2 3 4

Total

1. 1 2 1 4 4 3 4 18 6 l Emergency &

Abnormal 2 1 3 1 N/A 2 0 N/A 2 9 4 l Plant Evolutions Tier Totals 3 4 5 6 3 6 27 10 l 1 3 1 2 3 2 1 3 3 4 3 3 28 5 l 2.

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

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

l Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO l and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals l in each K/A category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points. l

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply l at the facility should be deleted and justified; operationally important, site-specific systems that are not included l on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination l of inappropriate K/A statements. l

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group l before selecting a second topic for any system or evolution. l

5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. l Use the RO and SRO ratings for the RO and SRO-only portions, respectively. l

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories. l 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 l must be relevant to the applicable evolution or system. l

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) l for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals l for each category in the table above. Use duplicate pages for RO and SRO-only exams. l

9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, l and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43. l ES-401, Page 21 of 33

PWR RO Examination Outline Printed: 03/29/2005 Facility: Fort Calhoun ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000008 Pressurizer Vapor Space Accident / X AA1.06 - Control of PZR level 3.6 1 3

000009 Small Break LOCA / 3 X EA2.08 - Letdown isolation valve 2.9* 1 position indication 000011 Large Break LOCA / 3 X 2.4.6 - Knowledge symptom based EOP 3.1 1 mitigation strategies.

000015 RCP Malfunctions / 4 X AA1.16 - Low-power reactor trip block 3.2* 1 status lights 000022 Loss of Rx Coolant Makeup / 2 X AA1.03 - PZR level trend 3.2 1 000025 Loss of RHR System / 4 X AK2.03 - Service water or closed 2.7 1 cooling water pumps 000026 Loss of Component Cooling Water / X AK3.02 - The automatic actions 3.6 1 8 (alignments) within the CCWS resulting from the actuation of the ESFAS 000027 Pressurizer Pressure Control System X AA2.07 - Makeup flow indication 3.1 1 Malfunction / 3 000038 Steam Gen. Tube Rupture / 3 X EK1.03 - Natural circulation 3.9 1 000054 Loss of Main Feedwater / 4 X 2.4.50 - Ability to verify system alarm 3.3 1 setpoints and operate controls identified in the alarm response manual.

000055 Station Blackout / 6 X 2.1.23 - Ability to perform specific 3.9 1 system and integrated plant procedures during all modes of plant operation.

000056 Loss of Off-site Power / 6 X AA1.02 - ESF bus synchronization 4.0* 1 select switch to close bus tie breakers 000057 Loss of Vital AC Inst. Bus / 6 X AA2.01 - Safety injection tank pressure 3.7 1 and level indicators 000058 Loss of DC Power / 6 X 2.4.4 - Ability to recognize abnormal 4.0 1 indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

000062 Loss of Nuclear Svc Water / 4 X AK3.02 - The automatic actions 3.6 1 (alignments) within the nuclear service water resulting from the actuation of the ESFAS 000065 Loss of Instrument Air / 8 X AK3.08 - Actions contained in EOP for 3.7 1 loss of instrument air 1

PWR RO Examination Outline Printed: 03/29/2005 Facility: Fort Calhoun ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points CE/E02 Reactor Trip - Stabilization - X EK3.1 - Facility operating 3.2 1 Recovery / 1 characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics CE/E05 Steam Line Rupture - Excessive X EK1.1 - Components, capacity, and 3.0 1 Heat Transfer / 4 function of emergency systems K/A Category Totals: 2 1 4 4 3 4 Group Point Total: 18 2

PWR RO Examination Outline Printed: 03/29/2005 Facility: Fort Calhoun ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000001 Continuous Rod Withdrawal / 1 X AK2.08 - Individual rod display lights 3.1 1 and indications 000024 Emergency Boration / 1 X AK1.04 - Low temperature limits for 2.8 1 boron concentration 000037 Steam Generator Tube Leak / 3 X AA1.13 - S/G blowdown radiation 3.9 1 monitors 000060 Accidental Gaseous Radwaste Rel. / X AK2.02 - Auxiliary building ventilation 2.7 1 9 system 000068 Control Room Evac. / 8 X AK2.02 - Reactor trip system 3.7 1 000074 Inad. Core Cooling / 4 X EA1.05 - PORV 3.9 1 CE/A11 RCS Overcooling - PTS / 4 X 2.2.22 - Knowledge of limiting 3.4 1 conditions for operations and safety limits.

CE/A16 Excess RCS Leakage / 2 X 2.1.30 - Ability to locate and operate 3.9 1 components, including local controls.

CE/E09 Functional Recovery X EK3.2 - Normal, abnormal and 3.2 1 emergency operating procedures associated with (Functional Recovery)

K/A Category Totals: 1 3 1 2 0 2 Group Point Total: 9 1

PWR RO Examination Outline Printed: 03/29/2005 Facility: Fort Calhoun ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump X A1.08 - Seal water 2.5 1 temperature 003 Reactor Coolant Pump X A3.04 - RCS flow 3.6 1 004 Chemical and Volume Control X A2.16 - T-ave. and T-ref. 3.2 1 deviations 004 Chemical and Volume Control X A4.12 - Boration/dilution 3.8 1 batch control 005 Residual Heat Removal X K4.02 - Modes of operation 3.2 1 005 Residual Heat Removal X K5.02 - Need for adequate 3.4 1 subcooling 006 Emergency Core Cooling X A3.06 - Valve lineups 3.9 1 007 Pressurizer Relief/Quench X K5.02 - Method of forming 3.1 1 Tank a steam bubble in the PZR 008 Component Cooling Water X K3.02 - CRDS 2.9 1 010 Pressurizer Pressure Control X A1.09 - Tail pipe 3.4 1 temperature and acoustic monitors 012 Reactor Protection X 2.1.32 - Ability to explain 3.4 1 and apply all system limits and precautions.

013 Engineered Safety Features X 2.1.2 - Knowledge of 3.0 1 Actuation operator responsibilities during all modes of plant operation.

013 Engineered Safety Features X K1.12 - ED/G 4.1 1 Actuation 022 Containment Cooling X A2.04 - Loss of service 2.9* 1 water 026 Containment Spray X K1.02 - Cooling water 4.1 1 039 Main and Reheat Steam X K4.05 - Automatic isolation 3.7 1 of steam line 059 Main Feedwater X K4.18 - Automatic 2.8* 1 feedwater reduction on plant trip 059 Main Feedwater X A3.06 - Feedwater isolation 3.2* 1 061 Auxiliary/Emergency X A1.04 - AFW source tank 3.9 1 Feedwater level 062 AC Electrical Distribution X 2.4.50 - Ability to verify 3.3 1 system alarm setpoints and operate controls identified in the alarm response manual.

063 DC Electrical Distribution X A4.03 - Battery discharge 3.0* 1 rate 063 DC Electrical Distribution X K1.02 - AC electrical 2.7 1 system 1

PWR RO Examination Outline Printed: 03/29/2005 Facility: Fort Calhoun ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 064 Emergency Diesel Generator X K6.07 - Air receivers 2.7 1 064 Emergency Diesel Generator X A2.11 - Conditions 2.6 1 (minimum load) required for unloading an ED/G 073 Process Radiation Monitoring X A4.03 - Check source for 3.1 1 operability demonstration 076 Service Water X K2.01 - Service water 2.7* 1 078 Instrument Air X K3.02 - Systems having 3.4 1 pneumatic valves and controls 103 Containment X A3.01 - Containment 3.9 1 isolation K/A Category Totals: 3 1 2 3 2 1 3 3 4 3 3 Group Point Total: 28 2

PWR RO Examination Outline Printed: 03/29/2005 Facility: Fort Calhoun ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 001 Control Rod Drive X K1.05 - NIS and RPS 4.5 1 002 Reactor Coolant X K6.03 - Reactor vessel level 3.1 1 indication 011 Pressurizer Level Control X K2.01 - Charging pumps 3.1 1 014 Rod Position Indication X A4.02 - Control rod 3.4 1 mode-select switch 017 In-core Temperature Monitor X K1.01 - Plant computer 3.2* 1 033 Spent Fuel Pool Cooling X A1.02 - Radiation 2.8 1 monitoring systems 035 Steam Generator X A2.06 - Small break LOCA 4.5 1 041 Steam Dump/Turbine Bypass X 2.4.4 - Ability to recognize 4.0 1 Control abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

045 Main Turbine Generator X K3.01 - Remainder of the 2.9 1 plant 086 Fire Protection X K6.04 - Fire, smoke, and 2.6 1 heat detectors K/A Category Totals: 2 1 1 0 0 2 1 1 0 1 1 Group Point Total: 10 1

PWR RO Examination Outline Printed: 03/29/2005 Facility: Fort Calhoun ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 001 Control Rod Drive X K1.05 - NIS and RPS 4.5 1 002 Reactor Coolant X K6.03 - Reactor vessel level 3.1 1 indication 011 Pressurizer Level Control X K2.01 - Charging pumps 3.1 1 014 Rod Position Indication X A4.02 - Control rod 3.4 1 mode-select switch 017 In-core Temperature Monitor X K1.01 - Plant computer 3.2* 1 033 Spent Fuel Pool Cooling X A1.02 - Radiation 2.8 1 monitoring systems 035 Steam Generator X A2.06 - Small break LOCA 4.5 1 041 Steam Dump/Turbine Bypass X 2.4.4 - Ability to recognize 4.0 1 Control abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

045 Main Turbine Generator X K3.01 - Remainder of the 2.9 1 plant 086 Fire Protection X K6.04 - Fire, smoke, and 2.6 1 heat detectors K/A Category Totals: 2 1 1 0 0 2 1 1 0 1 1 Group Point Total: 10 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 03/29/2005 Facility: Fort Calhoun Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.2 Knowledge of operator responsibilities during all 3.0 1 modes of plant operation.

2.1.3 Knowledge of shift turnover practices. 3.0 1 2.1.29 Knowledge of how to conduct and verify valve 3.4 1 lineups.

Category Total: 3 Equipment Control 2.2.13 Knowledge of tagging and clearance procedures. 3.6 1 2.2.30 Knowledge of RO duties in the control room 3.5 1 during fuel handling such as alarms from fuel handling area, communication with fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

Category Total: 2 Radiation Control 2.3.1 Knowledge of 10 CFR: 20 and related facility 2.6 1 radiation control requirements.

2.3.2 Knowledge of facility ALARA program. 2.5 1 Category Total: 2 Emergency Procedures/Plan 2.4.6 Knowledge symptom based EOP mitigation 3.1 1 strategies.

2.4.15 Knowledge of communications procedures 3.0 1 associated with EOP implementation.

2.4.23 Knowledge of the bases for prioritizing 2.8 1 emergency procedure implementation during emergency operations.

Category Total: 3 Generic Total: 10 1

EPE/APE Tier 1 / Group 1 000008 Pressurizer Vapor Space Accident 1 1 000009 Small Break LOCA 1 1 000011 Large Break LOCA 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 000038 Steam Generator Tube Rupture 1 1 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 000058 Loss of DC Power 1 1 000062 Loss of Nuclear Service Water 1 1 000065 Loss of Instrument Air 1 1 CE-E02 Reactor Trip Recovery 1 1 CE-E05 Excess Steam Demand 1 1 2 1 4 4 3 4 18 EPE/APE Tier 1 / Group 2 000001 Continuous Rod Withdrawal 1 1 000024 Emergency Boration 1 1 000037 Steam Generator Tube Leak 1 1 000060 Accidental Gaseous Radwaste Release 1 1 000068 Control Room Evacuation 1 1 000074 Inadequate Core Cooling 1 1 CE-A11 RCS Overcooling 1 1 CE-A16 Excess RCS Leakage 1 1 CE-E09 Functional Recovery 1 1 1 3 1 2 2 9 Grand Total of EPE/APE K&A Selection: 3 4 5 6 3 6 27

Mar 29, 2005 10:47 AM PWR RO Written Examination Outline Summary 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 007000 Pressurizer Relief Tank / Quench Tank System 1 1 008000 Component Cooling Water System 1 1 010000 Pressurizer Pressure Control System 1 1 012000 Reactor Protection System 1 1 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 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 2 064000 Emergency Diesel Generators 1 1 2 073000 Process Radiation Monitoring System 1 1 076000 Service Water System 1 1 078000 Instrument Air System 1 1 103000 Containment System 1 1 3 1 2 3 2 1 3 3 4 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 014000 Rod Position Indication System 1 1 017000 In-Core Temperature Monitor 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 045000 Main Turbine Generator System 1 1 086000 Fire Protection System 1 1 2 1 1 2 1 1 1 1 10 Grand Total of Plant System K&A Selection: 5 2 3 3 2 3 4 4 4 4 4 38

Mar 29, 2005 10:47 AM 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 Mar 29, 2005 10:47 AM Page 1 of 8 System/Mode System Title KA Number Title RO Value 10 CFR 55 Tier 1 Group 1 000008 Pressurizer Vapor Space Accident AA1.06 Ability to operate and / or monitor the following as they apply to the Pressurizer Vapor Space 3.6 41.7 / 45.5 /

Accident:: Control of PZR level 45.6 000009 Small Break LOCA EA2.08 Ability to determine or interpret the following as they apply to a small break LOCA:: Letdown 2.9* 43.5 / 45.13 isolation valve position indication 000011 Large Break LOCA 2.4.06 : Knowledge symptom based EOP mitigation strategies. 3.1 41.10 / 43.5 /

45.13 000017 Reactor Coolant Pump Malfunctions AA1.16 Ability to operate and / or monitor the following as they apply to the Reactor Coolant Pump 3.2* 41.7 / 45.5 /

(Loss of RC Flow) Malfunctions (Loss of RC Flow):: Low-power reactor trip block status lights 45.6 000022 Loss of Reactor Coolant Makeup AA1.03 Ability to operate and / or monitor the following as they apply to the Loss of Reactor Coolant Pump 3.2 41.7 / 45.5 /

Makeup:: PZR level trend 45.6 000025 Loss of Residual Heat Removal System AK2.03 Knowledge of the interrelations between the Loss of Residual Heat Removal System and the 2.7 41.7 / 45.7 following:: Service water or closed cooling water pumps 000026 Loss of Component Cooling Water AK3.02 Knowledge of the reasons for the following responses as they apply to the Loss of Component 3.6 41.5 / 41.10 /

Cooling Water:: The automatic actions (alignments) within the CCWS/nuclear service water 45.6 / 45.13 resulting from the actuation of the ESFAS 000027 Pressurizer Pressure Control System AA2.07 Ability to determine and interpret the following as they apply to the Pressurizer Pressure Control 3.1 43.5 / 45.13 Malfunction Malfunctions:: Makeup flow indication 000038 Steam Generator Tube Rupture EK1.03 Knowledge of the operational implications of the following concepts as they apply to the SGTR:: 3.9 41.8 / 41.10 /

Natural circulation 45.3 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 2.1.23 : Ability to perform specific system and integrated plant procedures during all modes of plant 3.9 45.2 / 45.6 operation.

PWR RO Written Examination Outline (Continued)

Mar 29, 2005 10:47 AM Page 2 of 8 System/Mode System Title KA Number Title RO Value 10 CFR 55 000056 Loss of Off-Site Power AA1.02 Ability to operate and / or monitor the following as they apply to the Loss of Offsite Power:: ESF 4.0* 41.7 / 45.5 /

bus synchronization select switch to close bus tie breakers 45.6 000057 Loss of Vital AC Electrical Instrument AA2.01 Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument 3.7 43.5 / 45.13 Bus Bus:: Safety injection tank pressure and level indicators 000058 Loss of DC Power 2.4.04 : Ability to recognize abnormal indications for system operating parameters which are entry-level 4.0 41.10 / 43.2 /

conditions for emergency and abnormal operating procedures. 45.6 000062 Loss of Nuclear Service Water AK3.02 Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear 3.6 41.4,41.8/45.7 Service Water: The automatic actions (alignments) within the nuclear service water resulting from the actuation of the ESFAS 000065 Loss of Instrument Air AK3.08 Knowledge of the reasons for the following responses as they apply to the Loss of Instrument Air:: 3.7 41.5 / 41.10 /

Actions contained in EOP for loss of instrument air 45.6 / 45.13 CE-E02 Reactor Trip Recovery EK3.01 Knowledge of the reasons for the following responses as they apply to the (Reactor Trip 3.2 41.5 / 41.10 /

Recovery): Facility operating characteristics during transient conditions, including coolant 45.6 / 45.13 chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.

CE-E05 Excess Steam Demand EK1.01 Knowledge of the operational implications of the following concepts as they apply to the (Excess 3.0 41.8 / 41.10 /

Steam Demand): Components, capacity, and function of emergency systems. 45.3

PWR RO Written Examination Outline (Continued)

Mar 29, 2005 10:47 AM Page 3 of 8 System/Mode System Title KA Number Title RO Value 10 CFR 55 Tier 1 Group 2 000001 Continuous Rod Withdrawal AK2.08 Knowledge of the interrelations between the Continuous Rod Withdrawal and the following:: 3.1 41.7 / 45.7 Individual rod display lights and indications 000024 Emergency Boration AK1.04 Knowledge of the operational implications of the following concepts as they apply to Emergency 2.8 41.8 / 41.10 /

Boration:: Low temperature limits for boron concentration 45.3 000037 Steam Generator Tube Leak AA1.13 Ability to operate and / or monitor the following as they apply to the Steam Generator Tube Leak:: 3.9 41.7 / 45.5 /

S/G blowdown radiation monitors 45.6 000060 Accidental Gaseous Radwaste Release AK2.02 Knowledge of the interrelations between the Accidental Gaseous Radwaste Release and the 2.7 41.7 / 45.7 following:: Auxiliary building ventilation system 000068 Control Room Evacuation AK2.02 Knowledge of the interrelations between the Control Room Evacuation and the following:: Reactor 3.7 41.7 / 45.7 trip system 000074 Inadequate Core Cooling EA1.05 Ability to operate and monitor the following as they apply to a Inadequate Core Cooling:: PORV 3.9 41.7 / 45.5 /

45.6 CE-A11 RCS Overcooling 2.2.22 : Knowledge of limiting conditions for operations and safety limits. 3.4 43.2 / 45.2 CE-A16 Excess RCS Leakage 2.1.30 : Ability to locate and operate components, including local controls. 3.9 41.7 / 45.7 CE-E09 Functional Recovery EK3.02 Knowledge of the reasons for the following responses as they apply to the (Functional Recovery): 3.0 41.5 / 41.10 /

Normal, abnormal and emergency operating procedures associated with (Functional Recovery). 45.6 / 45.13

PWR RO Written Examination Outline (Continued)

Mar 29, 2005 10:47 AM 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 A1.08 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 2.5 41.5 / 45.5 associated with operating the RCPS controls including:: Seal water temperature 003000 Reactor Coolant Pump System A3.04 Ability to monitor automatic operation of the RCPS, including:: RCS flow 3.6 41.7 / 45.5 004000 Chemical and Volume Control System A2.16 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) 3.2 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:: T-ave. and T-ref. deviations 004000 Chemical and Volume Control System A4.12 Ability to manually operate and/or monitor in the control room:: Boration/dilution batch control 3.8 41.7 / 45.5 to 45.8 005000 Residual Heat Removal System K4.02 Knowledge of RHRS design feature(s) and/or interlock(s) which provide or the following:: Modes 3.2 41.7 of operation 005000 Residual Heat Removal System K5.02 Knowledge of the operational implications of the following concepts as they apply the RHRS:: 3.4 41.5 / 45.7 Need for adequate subcooling 006000 Emergency Core Cooling System A3.06 Ability to monitor automatic operation of the ECCS, including:: Valve lineups 3.9 41.7 / 45.5 007000 Pressurizer Relief Tank / Quench Tank K5.02 Knowledge of the operational implications of the following concepts as the apply to PRTS:: 3.1 41.5 / 45.7 System Method of forming a steam bubble in the PZR 008000 Component Cooling Water System K3.02 Knowledge of the effect that a loss or malfunction of the CCWS will have on the following:: CRDS 2.9 41.7 / 45.6 010000 Pressurizer Pressure Control System A1.09 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 3.4 41.5 / 45.5 associated with operating the PZR PCS controls including:: Tail pipe temperature and acoustic monitors 012000 Reactor Protection System 2.1.32 : Ability to explain and apply all system limits and precautions. 3.4 41.10 / 43.2 /

45.12

PWR RO Written Examination Outline (Continued)

Mar 29, 2005 10:47 AM Page 5 of 8 System/Mode System Title KA Number Title RO Value 10 CFR 55 013000 Engineered Safety Features Actuation 2.1.02 : Knowledge of operator responsibilities during all modes of plant operation. 3.0 41.10 / 45.13 System 013000 Engineered Safety Features Actuation K1.12 Knowledge of the physical connections and/or cause effect relationships between the ESFAS and 4.1 41.2 to 41.9 /

System the following systems:: ED/G 45.7 to 45.8 022000 Containment Cooling System A2.04 Ability to (a) predict the impacts of the following malfunctions or operationson the CCS; and (b) 2.9* 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:: Loss of service water 026000 Containment Spray System K1.02 Knowledge of the physical connections and/or cause-effect relationships between the CSS and 4.1 41.2 to 41.9 /

the following systems:: Cooling water 45.7 to 45.8 039000 Main and Reheat Steam System K4.05 Knowledge of MRSS design feature(s) and/or interlock(s) which provide for the following:: 3.7 41.7 Automatic isolation of steam line 059000 Main Feedwater System A3.06 Ability to monitor automatic operation of the MFW, including:: Feedwater isolation 3.2* 41.7 / 45.5 059000 Main Feedwater System K4.18 Knowledge of MFW design feature(s) and/or interlock(s) which provide for the following:: 2.8* 41.7 Automatic feedwater reduction on plant trip 061000 Auxiliary / Emergency Feedwater A1.04 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 AFW controls including:: AFW source tank level 062000 A.C. Electrical Distribution 2.4.50 : Ability to verify system alarm setpoints and operate controls identified in the alarm response 3.3 45.3 manual.

063000 D.C. Electrical Distribution A4.03 Ability to manually operate and/or monitor in the control room:: Battery discharge rate 3.0* 41.7 / 45.5 to 45.8 063000 D.C. Electrical Distribution K1.02 Knowledge of the physical connections and/or cause-effect relationships between the dc electrical 2.7 41.2 to 41.9 /

system and the following systems:: AC electrical system 45.7 to 45.8

PWR RO Written Examination Outline (Continued)

Mar 29, 2005 10:47 AM Page 6 of 8 System/Mode System Title KA Number Title RO Value 10 CFR 55 064000 Emergency Diesel Generators A2.11 Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; 2.6 41.5 / 43.5 /

and (b) based on those predictions, use procedures to correct, control, or mitigate the 45.3 / 45.13 consequences of those malfunctions or operations:: Conditions (minimum load) required for unloading an ED/G 064000 Emergency Diesel Generators K6.07 Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system:: 2.7 41.7 / 45.7 Air receivers 073000 Process Radiation Monitoring System A4.03 Ability to manually operate and/or monitor in the control room:: Check source for operability 3.1 41.7 / 45.5 to demonstration 45.8 076000 Service Water System K2.01 Knowledge of bus power supplies to the following:: Service water 2.7* 41.7 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 103000 Containment System A3.01 Ability to monitor automatic operation of the containment system, including:: Containment isolation 3.9 41.7 / 45.5

PWR RO Written Examination Outline (Continued)

Mar 29, 2005 10:47 AM 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 K1.05 Knowledge of the physical connections and/or cause-effect relationships between the CRDS and 4.5 41.2 to 41.9 /

the following systems:: NIS and RPS 45.7 to 45.8 002000 Reactor Coolant System K6.03 Knowledge of the effect or a loss or malfunction on the following RCS components:: Reactor 3.1 41.7 / 45.7 vessel level indication 011000 Pressurizer Level Control System K2.01 Knowledge of bus power supplies to the following:: Charging pumps 3.1 41.7 014000 Rod Position Indication System A4.02 Ability to manually operate and/or monitor in the control room:: Control rod mode-select switch 3.4 41.7 / 45.5 to 45.8 017000 In-Core Temperature Monitor System K1.01 Knowledge of the physical connections and/or cause-effect relationships between the ITM system 3.2* 41.2 to 41.9 /

and the following systems:: Plant computer 45.7 to 45.8 033000 Spent Fuel Pool Cooling System A1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 2.8 41.5 / 45.5 associated with Spent Fuel Pool Cooling System operating the controls including:: Radiation monitoring systems 035000 Steam Generator System A2.06 Ability to (a) predict the impacts of the following malfunctions or operations on the GS; and (b) 4.5 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:: Small break LOCA 041000 Steam Dump System and Turbine 2.4.04 : Ability to recognize abnormal indications for system operating parameters which are entry-level 4.0 41.10 / 43.2 /

Bypass Control conditions for emergency and abnormal operating procedures. 45.6 045000 Main Turbine Generator System K3.01 Knowledge of the effect that a loss or malfunction of the MT/G system will have on the following:: 2.9 41.7 / 45.6 Remainder of the plant 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)

Mar 29, 2005 10:47 AM 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 2.1.02 : Knowledge of operator responsibilities during all modes of plant operation. 3.0 41.10 / 45.13 000000 Generic Knowledges and Abilities 2.1.03 : Knowledge of shift turnover practices. 3.0 41.10 / 45.13 000000 Generic Knowledges and Abilities 2.1.29 : Knowledge of how to conduct and verify valve lineups. 3.4 41.10 / 45.1 /

45.12 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 2.2.30 : Knowledge of RO duties in the control room during fuel handling such as alarms from fuel 3.5 45.12 handling area, communication with fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

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 2.3.02 : Knowledge of facility ALARA program. 2.5 41.12 / 43.4 /

45.9 / 45.10 000000 Generic Knowledges and Abilities 2.4.06 : Knowledge symptom based EOP mitigation strategies. 3.1 41.10 / 43.5 /

45.13 000000 Generic Knowledges and Abilities 2.4.15 : Knowledge of communications procedures associated with EOP implementation. 3.0 41.10 / 45.13 000000 Generic Knowledges and Abilities 2.4.23 : Knowledge of the bases for prioritizing emergency procedure implementation during emergency 2.8 41.10 / 45.13 operations.

Enhanced Form ES-401-4 Record of Rejected K/As from RO Outline 3/29/2005 Tier/Group Randomly Selected K/A Description Reason for Rejection 1/1 000025 AA1.13 Ability to operate and / or monitor the following as No Raw Water Rad monitor in service at FCS they apply to the Loss of Residual Heat Removal System:SWS radiation monitors 1/1 000025 AA1.19 Ability to operate and / or monitor the following as Not a FCS design feature they apply to the Loss of Residual Heat Removal System:Block orifice bypass valve controller and indicators 1/1 000029 EA1.05 Ability to operate and monitor the following as they No BIT at FCS apply to a ATWS:BIT outlet valve switches 1/1 000029 EK1.02 Knowledge of the operational implications of the GFE Topic following concepts as they apply to the ATWS:Definition of reactivity 1/1 000029 EK1.05 Knowledge of the operational implications of the GFE Topic following concepts as they apply to the ATWS:Definition of negative temperature coefficient as applied to large PWR coolant systems Page 1

Enhanced Form ES-401-4 Record of Rejected K/As from RO Outline 3/29/2005 Tier/Group Randomly Selected K/A Description Reason for Rejection 1/1 000038 EA2.03 Ability to determine or interpret the following as they Will be evaluated during operating exam.

apply to a SGTR:Which S/G is ruptured 1/1 000038 EA1.37 Ability to operate and monitor the following as they No specific concern at FCS apply to a SGTR:Controlling of thermal shock during PZR spray operation 1/1 000038 EA1.08 Ability to operate and monitor the following as they Core cooling monitor?

apply to a SGTR:Core cooling monitor 1/1 000062 AA2.06 Ability to determine and interpret the following as No specified time limits at FCS they apply to the Loss of Nuclear Service Water:The length of time after the loss of SWS flow to a component before that component may be damaged 1/2 000001 AA1.01 Ability to operate and / or monitor the following as Redundant to sampled K/A 014000 A4.02 they apply to the Continuous Rod Withdrawal:Bank select switch Page 2

Enhanced Form ES-401-4 Record of Rejected K/As from RO Outline 3/29/2005 Tier/Group Randomly Selected K/A Description Reason for Rejection 1/2 000001 AK1.19 Knowledge of the operational implications of the GFE Topic following concepts as they apply to Continuous Rod Withdrawal:Voids coefficient 1/2 000001 AK2.02 Knowledge of the interrelations between the Rod control is manual only Continuous Rod Withdrawal and the following:Controllers and positioners 1/2 000003 AK1.13 Knowledge of the operational implications of the No ICS at FCS following concepts as they apply to Dropped Control Rod:Interaction of ICS control stations as well as purpose, function, and modes of operation of ICS 1/2 000003 AK1.22 Knowledge of the operational implications of the GFE Topic following concepts as they apply to Dropped Control Rod:Calculation of power defect: algebraic sum of moderator temperature and fuel temperature defects 1/2 000003 AK1.05 Knowledge of the operational implications of the Low Importance, no FCS specific priority following concepts as they apply to Dropped Control Rod:CVCS response to dropped rod Page 3

Enhanced Form ES-401-4 Record of Rejected K/As from RO Outline 3/29/2005 Tier/Group Randomly Selected K/A Description Reason for Rejection 1/2 000005 AA2.04 Ability to determine and interpret the following as Not used by operators to determine dropped they apply to the Inoperable / Stuck Control rod location Rod:Interpretation of computer in-core TC map for dropped rod location 1/2 000060 AK1.02 Knowledge of the operational implications of the Not an RO task related to event following concepts as they apply to Accidental Gaseous Radwaste Release:Biological effects on humans of the various types of radiation, exposure levels that are acceptable for personnel in a nuclear reactor power plant; the units used for radiation intensity measurements and for radiation exposure 1/2 000060 AA2.03 Ability to determine and interpret the following as Difficult to provide P&IDs of required size in they apply to the Accidental Gaseous Radwaste:The written exam setting steps necessary to isolate a given radioactive-gas leak, using P&IDs 1/2 000067 AA1.04 Ability to operate and / or monitor the following as Not an FCS design feature they apply to the Plant Fire on Site:Bypass of a heat detector 2/1 059000 K4.19 Knowledge of MFW design feature(s) and/or Redundant to sampled K/A 059000 A3.06 interlock(s) which provide for the following:Automatic feedwater isolation of MFW Page 4

Enhanced Form ES-401-4 Record of Rejected K/As from RO Outline 3/29/2005 Tier/Group Randomly Selected K/A Description Reason for Rejection 2/1 076000 K3.02 Knowledge of the effect that a loss or malfunction of No relationship the SWS will have on the following:Secondary closed cooling water 2/1 076000 K1.09 Knowledge of the physical connections and/or No separate reactor building CCW system at cause- effect relationships between the SWS and FCS the following systems:Reactor building closed cooling water 2/2 041000 A4.02 Ability to manually operate and/or monitor in the Not an FCS design feature control room:Cooldown valves 2/2 045000 K4.44 Knowledge of MT/G system design feature(s) and/or Not used at FCS interlock(s) which provide for the following:Impulse pressure mode control of steam dumps 2/2 071000 A4.19 Ability to manually operate and/or monitor in the Not performed from control room control room:Bringing an empty WDGS decay tank on line and shutting down a full tank Page 5

Enhanced Form ES-401-4 Record of Rejected K/As from RO Outline 3/29/2005 Tier/Group Randomly Selected K/A Description Reason for Rejection 2/2 072000 K4.02 Knowledge of ARM system design feature(s) and/or Not part of FCS design interlock(s) which provide for the following:Fuel building isolation 2/2 086000 2.4.49 Ability to perform without reference to procedures No immediate actions that would be those actions that require immediate operation of performed prior to implementing procedure system components and controls. for this system Page 6

ES-401 PWR Examination Outline Form ES-401-2 l Facility: Fort Calhoun Date of Exam: 07/11/05 RO K/A Category Points SRO-Only Points l Tier Group K K K K K K A A A A G A2 G* Total l 1 2 3 4 5 6 1 2 3 4

Total

1. 1 2 1 4 4 3 4 18 3 3 6 l Emergency &

Abnormal 2 1 3 1 N/A 2 0 N/A 2 9 3 1 4 l Plant Evolutions Tier Totals 3 4 5 6 3 6 27 6 4 10 l 1 3 1 2 3 2 1 3 3 4 3 3 28 2 3 5 l 2.

2 2 1 1 0 0 2 1 1 0 1 1 10 1 &K4FH 1 3 l Plant Systems 5 2 3 3 2 3 4 4 4 4 4 4 4 Tier Totals 38 8 l

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