ML092180043

2008 Byron Station Initial License Examination ES-401-2 and Es 401-3 Forms

ML092180043
Person / Time
Site:	Byron
Issue date:	05/19/2008
From:	Operations Branch III
To:	Exelon Generation Co
References
ES-401, ES-401-2
Download: ML092180043 (9)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Byron RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total

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

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

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

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 2 2 2 1 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).

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

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

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

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

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

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals

(#) for each system and category. Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO-only exams.

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

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

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) IR #

000007 (BW/E02&E10; CE/E02) Reactor 01 Actions Contained in EOP for Reactor Trip 4.0 1 Trip - Stabilization - Recovery / 1 000008 Pressurizer Vapor Space 01 Pzr Spray Block Valve and PORV Block Valve 4.2 1 Accident / 3 000009 Small Break LOCA / 3 13 Charging Pump Flow Indication 3.4 1 000022 Loss of Rx Coolant Makeup / 2 X (2.1.30) Ability to Locate and Operate Components, Including Local Controls 3.9 1 000015/17 RCP Malfunctions / 4 02 Consequences of an RCPS Failure 3.7 1 000029 ATWS / 1 05 Definition of Negative Temperature Coefficient as Applied to Large PWR 2.8 1 Coolant Systems 000038 Steam Gen. Tube Rupture / 3 06 Actions contained in EOP for RCS water inventory balance, S/G tube rupture, 4.2 1 and plant shutdown procedures.

000040 (BW/E05; CE/E05; W/E12) 07 Steam Pressure and Flow Rates Via Computer, Safety Parameter Display 3.4 1 Steam Line Rupture - Excessive Heat System, and other Indications Transfer / 4 000054 (CE/E06) Loss of Main 01 Occurrence of reactor and/or turbine trip. 4.3 1 Feedwater / 4 000055 Station Blackout / 6 X (2.4.50) Ability to Verify System Alarrn Setpoints and Operate Controls 3.3 1 Identified in the Alarm Response Manual 000056 Loss of Off-site Power / 6 01 Principle of Cooling by Natural Convection 3.7 1 000057 Loss of Vital AC Inst. Bus / 6 01 Actions Contained in EOP for Loss of Vital AC Electrical Instrument Bus 4.1 1 000058 Loss of DC Power / 6 01 Cross-tie of the Affected DC Bus with the Alternate Supply 3.4 1 000062 Loss of Nuclear Svc Water / 4 01 Location of a Leak in the SWS 2.9 1 000065 Loss of Instrument Air / 8 X (2.4.2) Knowledge of How the Event-Based Emergency/Abnormal Operating 3.0 1 Procedures Are Used in Conjunction with the Symptom-Based EOPs W/E04 LOCA Outside Containment / 3 01 Components, and Functions of Control and Safety Systems, Including 3.5 1 Instrumentation, Signals, Interlocks, Failure Modes, and Automatic and Manual Features

W/E11 Loss of Emergency Coolant 01 Components, and Functions of Control and Safety Systems, Including 3.6 1 Recirc. / 4 Instrumentation, Signals, Interlocks, Failure Modes, and Automatic and Manual Features BW/E04; W/E05 Inadequate Heat 02 Normal, Abnormal and Emergency Operating Procedures Associated with 3.9 1 Transfer - Loss of Secondary Heat Sink / 4 (Loss of Secondary Heat Sink) 000015/17 RCP Malfunctions / 4 11 (SRO) When to Jog RCPs during ICC 3.8 1 000011 Large Break LOCA / 3 X (SRO) (2.3.10) Ability to Perform Procedures to Reduce Excessive Levels of 3.3 1 Radiation and Guard Against Personnel Exposure 000029 ATWS / 1 07 (SRO) Reactor Trip Breaker Indication Lights 4.3 1 000038 Steam Gen. Tube Rupture / 3 08 X (SRO) Viable Alternatives for Placing Plant in Safe Condition when 4.4/ 2 Condenser Is not Available/ (2.3.6) Knowledge of the Requirements for 3.1 Reviewing and Approving Release Permits 000056 Loss of Off-site Power / 6 X (SRO) (2.1.20) Ability to Execute Procedure Steps 4.2 1 K/A Category Totals: 4 2 3 3 3/3 3/3 Group Point Total: 18/

6

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

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) IR #

000003 Dropped Control Rod / 1 04 Rod Motion Stops Due to Dropped Rod 3.4 1 000005 Inoperable/Stuck Control Rod / 1 X (2.1.7) Ability to Evaluate Plant Performane and Make Operational 3.7 1 Judgments Based on Operating Characteristics, Reactor Behavior, and Instrument Interpretation 000024 Emergency Boration / 1 01 Relationship Between Boron Addition and Change in T-ave 3.4 1 000028 Pressurizer Level Malfunction / 2 03 Controllers and Positioners 2.6 1 000032 Loss of Source Range NI / 7 01 Startup Termination on Source-Range Loss 3.2 1 000033 Loss of Intermediate Range NI / 7 03 Manual Restoration of Power 3.0 1 000061 ARM System Alarms / 7 03 Setpoints for Alert and High Alarms 3.0 1 000037 Steam Generator Tube Leak / 3 X (2.2.22) Knowledge of Limiting Conditions for Operations and Safety 3.4 1 Limits 000051 Loss of Condenser Vacuum / 4 01 Loss of Steam Dump Capability upon Loss of Condenser Vacuum 2.8 1 000059 Accidental Liquid RadWaste Rel. / 9 X (SRO) (2.3.1) Knowledge of 10 CFR 20 and Related Facility Radiation 3.0 1 Control Requirements 000036 (BW/A08) Fuel Handling Accident / 8 02 (SRO) Occurrence of a Fuel Handling Incident 4.1 1 000069 (W/E14) Loss of CTMT Integrity / 5 01 (SRO) Loss of Conatinment Integrity 4.3 1 W/E13 Steam Generator Over-pressure / 4 X (SRO) (2.1.32) Ability to Explain and Apply all System Limits and 3.8 1 Precautions K/A Category Point Totals: 1 1 2 1 2 2 Group Point Total: 9/4

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

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

1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump 01 02 Relationship between the RCPS Flow Rate and the Nuclear 3.3/ 2 Reactor Core Operating Parameters/ RCP Seals and Seal Water 2.7 Supply 004 Chemical and Volume 09 10 Thermal Shock: High Component Stress Due to Rapid 3.7/ 2 Control Temperature Change / Boric Acid Storage Tank/Boron Injection 2.7 Tank Recirculation Flow Path 005 Residual Heat Removal 02 04 RHR Flow Rate/ RHR Valve Malfunction 3.3/ 2 2.9 006 Emergency Core Cooling 01 02 High Bearing Temperature / Pumps 2.9/ 2 4.1 007 Pressurizer Relief/Quench 04 PZR Vent Valve 2.6 1 Tank 008 Component Cooling Water X (2.1.20) Ability to execute procedure steps. 4.2 1 010 Pressurizer Pressure Control 05 PRTS 3.4 1 012 Reactor Protection 01 RPS Channels, Components, and Interconnections 3.3 1 013 Engineered Safety Features 01 Fuel 4.4 1 Actuation 022 Containment Cooling 01 Cooling of Containment Penetrations 2.5 1 026 Containment Spray 01 Containment Pressure 3.9 1 039 Main and Reheat Steam 08 Effect of Steam Removal on Reactivity 3.6 1 059 Main Feedwater 05 Rupture in MFW Suction or Discharge Line 3.1 1 061 Auxiliary/Emergency 01 Controllers and Positioners 2.5 1 Feedwater 062 AC Electrical Distribution 05 Safety-Related Indicators and Controls 3.5 1 063 DC Electrical Distribution 02 Battery Voltage Indicator 2.8 1

064 Emergency Diesel Generator X (2.1.11) Knowledge of less than one hour technical specification 3.8 1 action statements.

073 Process Radiation Monitoring 01 Those Systems Served by PRMs 3.6 1 076 Service Water 04 03 Reactor Building Closed Cooling Water / Reactor Building Closed 2.5/ 2 Cooling Water 3.5 078 Instrument Air 03 01 Cross-tied Units / Manual/Automatic Transfers of Control 3.0/ 2 2.7 103 Containment 04 01 Personnel Access Hatch and Emergency Access Hatch / 2.5/ 2 Containment Pressure, Temperature, and Humidity 3.7 006 Emergency Core Cooling 10 (SRO) Safety Injection Tank Heating System 2.8 1 007 Pressurizer Relief/Quench X (SRO) (2.4.6) Knowledge of symptom based EOP mitigation 4.0 1 Tank strategies.

010 Pressurizer Pressure Control 01 (SRO) Heater Failures 3.9 1 026 Containment Spray X (SRO) (2.2.22) Knowledge of Limiting Conditions for Operations 4.1 1 and Safety Limits.

103 Containment 03 (SRO) Phase A and B isolation. 3.8 1 K/A Category Point Totals: 2 2 3 3 3 3 3 3/ 2 2 2/ Group Point Total: 28/

3 2 5

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

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

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive 05 Effect on T-ave, of Dilution without Rod Motion Compensation 3.4 1 002 Reactor Coolant 01 Loss of Coolant Inventory 4.3 1 011 Pressurizer Level Control 03 Charging and letdown 3.2 1 014 Rod Position Indication 01 Rod Selection Control 3.3 1 015 Nuclear Instrumentation X (2.1.33) 016 Non-nuclear Instrumentation 08 Pzr PCS 3.4 1 055 Condenser Air Removal 01 Main Condenser 2.5 1 068 Liquid Radwaste 01 Safety and Environmental Precautions for Handling Hot, Acidic, 3.4 1 and Radioactive Liquids 071 Waste Gas Disposal 04 Relationship of Hydrogen/Oxygen Concentrations to Flammability 2.5 1 086 Fire Protection 04 Fire, Smoke, and Heat Detectors 2.6 1 001 Control Rod Drive 09 (SRO) Station Blackout 4.0 1 011 Pressurizer Level Control 04 (SRO) Loss of One, Two or Three Charging Pumps 3.7 1 035 Steam Generator X (SRO) (2.4.21) Knowledge of the Parameters and Logic Used to 4.3 1 Assess the Status of Safety Functions K/A Category Point Totals: 1 0 1 1 1 1 1 1/ 1 1 1/ Group Point Total: 10/

2 1 3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date of Exam:

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

2.1.2 Knowledge of Operator Responsibilities during all Modes of Plant Operation 4.0 1

1. 2.1.20 Ability to Execute Procedure Steps 4.2 1 Conduct of 2.1.24 Ability to Obtain and Interpret Station Electrical and Mechanical Drawings 2.8 1 Operations 2.1.32 Ability to Explain and Apply all System Limits and Precautions 3.4 1 2.1.33 Ability to Recognize Indications for System Operating Parameters which are Entry-Level Conditions for 3.4 1 Technical Specifications 2.1.

Subtotal 3 2 2.2.1 Ability to Perform Pre-Startup Procedures for the Facility, Including Operating those Controls Associated with 3.7 1 Plant Equipment that Could Affect Reactivity.

2. 2.2.5 Knowledge of the Process for Making Changes in the Facility as Described in the Safety Analysis Report 2.7 1 Equipment 2.2.18 Knowledge of the Process for Managing Troubleshooting Activities 3.3 1 Control 2.2.33 Knowledge of Control Rod Programming 2.5 1 2.2.

2.2.

Subtotal 2 2 2.3.5 Knowledge of Use and Function of Personnel Monitoring Equipment 2.5 1 2.3.7 Knowledge of the Process for Preparing a Radiation Work Permit 3.3 1

3. 2.3.10 Ability to Perform Procedures to Reduce Excessive Levels of Radiation and Guard Against Personnel 2.9 1 Radiation Exposure Control 2.3.11 Ability to Control Radiation Releases 2.7 1 2.3.

2.3.

Subtotal 2 2 2.4.7 Knowledge of Event Based EOP Mitigation Strategies 3.8 1

4. 2.4.12 Knowledge of General Operating Crew Responsibilities during Emergency Operations 3.4 1 Emergency 2.4.24 Knowledge of Loss of Cooling Water Procedures 3.3 1 Procedures /

Plan 2.4.39 Knowledge of the ROs Responsibilities in Emergency Plan Implementation 3.3 1 2.4.

2.4.

Subtotal 3 1 Tier 3 Point Total 10 7