ML092180043
| 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 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G* Total A2 G* Total 1 4 2 33 3 3 3 18 3 3 6 2 1 1 22 1 2 2 9 2 2 4
- 1. Emergency & Abnormal Plant Evolutions Tier Totals 5 3 5 5 N/A 4 5 N/A 5 27 5 5 10 1 2 2 3 3 3 3 3 3 2 2 2 28 3 2 5 2 1 0 1 1 1 1 1 1 1 1 1 10 2 1 3
- 2. Plant Systems Tier Totals 3 2 4 4 4 4 4 4 3 3 3 38 5 3 8 1 2 3 4 1 2 3 4 3. Generic Knowledge and Abilities Categories 3 2 2 3 10 2 2 2 1 7 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 t he 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 descripti on 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-401-2Emergency 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 Trip - Stabilization - Recovery / 1 01 Actions Contained in EOP for Reactor Trip 4.0 1 000008 Pressurizer Vapor Space Accident / 3 01 Pzr Spray Block Valve and PORV Block Valve 4.2 1 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 Coolant Systems 2.8 1 000038 Steam Gen. Tube Rupture / 3 06 Actions contained in EOP for RCS water inventory balance, S/G tube rupture, and plant shutdown procedures.
4.2 1 000040 (BW/E05; CE/E05; W/E12) Steam Line Rupture - Excessive Heat Transfer / 4 07 Steam Pressure and Flow Rates Via Computer, Safety Parameter Display System, and other Indications 3.4 1 000054 (CE/E06) Loss of Main Feedwater / 4 01 Occurrence of reactor and/or turbine trip. 4.3 1 000055 Station Blackout / 6 X (2.4.50) Ability to Verify System Alarrn Setpoints and Operate Controls Identified in the Alarm Response Manual 3.3 1 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 Procedures Are Used in Conjunction with the Symptom-Based EOPs 3.0 1 W/E04 LOCA Outside Containment / 3 01 Components, and Functions of Control and Safety Systems, Including Instrumentation, Signals, Interlocks, Failure Modes, and Automatic and Manual Features 3.5 1 W/E11 Loss of Emergency Coolant Recirc. / 4 01 Components, and Functions of Control and Safety Systems, Including Instrumentation, Signals, Interlocks, Failure Modes, and Automatic and Manual Features 3.6 1 BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 02 Normal, Abnormal and Emergency Operating Procedures Associated with (Loss of Secondary Heat Sink) 3.9 1 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 Radiation and Guard Against Personnel Exposure 3.3 1 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 Condenser Is not Available/ (2.3.6) Knowledge of the Requirements for Reviewing and Approving Release Permits 4.4/3.1 2 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-401-2Emergency 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 Judgments Based on Operating Characteristics, Reactor Behavior, and Instrument Interpretation 3.7 1 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 Limits 3.4 1 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 Control Requirements 3.0 1 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 Precautions 3.8 1 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-401-2Plant Systems - Tier 2/Group 1 (RO / SRO) System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G K/A Topic(s) IR # 003 Reactor Coolant Pump 01 02 Relationship between the RCPS Flow Rate and the Nuclear Reactor Core Operating Parameters/ RCP Seals and Seal Water Supply 3.3/2.7 2 004 Chemical and Volume Control 09 10 Thermal Shock: High Component Stress Due to Rapid Temperature Change / Boric Acid Storage Tank/Boron Injection Tank Recirculation Flow Path 3.7/2.7 2 005 Residual Heat Removal 02 04 RHR Flow Rate/ RHR Valve Malfunction 3.3/
2.9 2 006 Emergency Core Cooling 01 02 High Bearing Temperature / Pumps 2.9/
4.1 2 007 Pressurizer Relief/Quench Tank 04 PZR Vent Valve 2.6 1 008 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 Actuation 01 Fuel 4.4 1 022 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 Feedwater 01 Controllers and Positioners 2.5 1 062 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 action statements.
3.8 1 073 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 Cooling Water 2.5/3.5 2 078 Instrument Air 03 01 Cross-tied Units / Manual/Automatic Transfers of Control 3.0/
2.7 2 103 Containment 04 01 Personnel Access Hatch and Emergency Access Hatch / Containment Pressure, Temperature, and Humidity 2.5/3.7 2 006 Emergency Core Cooling 10 (SRO) Safety Injection Tank Heating System 2.8 1 007 Pressurizer Relief/Quench Tank X (SRO) (2.4.6) Knowledge of symptom based EOP mitigation strategies.
4.0 1 010 Pressurizer Pressure Control 01 (SRO) Heater Failures 3.9 1 026 Containment Spray X (SRO) (2.2.22) Knowledge of Limiting Conditions for Operations and Safety Limits.
4.1 1 103 Containment 03 (SRO) Phase A and B isolation. 3.8 1 K/A Category Point Totals: 2 2 3 3 3 3 3 3/3 2 2 2/2 Group Point Total: 28/
5 ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2Plant Systems - Tier 2/Group 2 (RO / SRO) System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G K/A Topic(s) IR # 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, and Radioactive Liquids 3.4 1 071 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 Assess the Status of Safety Functions 4.3 1 K/A Category Point Totals: 1 0 1 1 1 1 1 1/2 1 1 1/1 Group Point Total: 10/
3 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date of Exam: RO SRO-Only Category K/A # Topic IR # IR # 2.1.2 Knowledge of Operator Responsibilities during all Modes of Plant Operation 4.0 1 2.1.20 Ability to Execute Procedure Steps 4.2 1 2.1.24 Ability to Obtain and Interpret Station Electrical and Mechanical Drawings 2.8 1 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 Technical Specifications 3.4 1 2.1. 1. Conduct of Operations Subtotal 3 2 2.2.1 Ability to Perform Pre-Startup Procedures for the Facility, Including Operating those Controls Associated with Plant Equipment that Could Affect Reactivity. 3.7 1 2.2.5 Knowledge of the Process for Making Changes in the Facility as Described in the Safety Analysis Report 2.7 1 2.2.18 Knowledge of the Process for Managing Troubleshooting Activities 3.3 1 2.2.33 Knowledge of Control Rod Programming 2.5 1 2.2. 2.2. 2. Equipment Control 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 2.3.10 Ability to Perform Procedures to Reduce Excessive Levels of Radiation and Guard Against Personnel Exposure 2.9 1 2.3.11 Ability to Control Radiation Releases 2.7 1 2.3. 3. Radiation Control 2.3.
Subtotal 2 2 2.4.7 Knowledge of Event Based EOP Mitigation Strategies 3.8 1 2.4.12 Knowledge of General Operating Crew Responsibilities during Emergency Operations 3.4 1 2.4.24 Knowledge of Loss of Cooling Water Procedures 3.3 1 2.4.39 Knowledge of the RO's Responsibilities in Emergency Plan Implementation 3.3 1 2.4. 2.4. 4. Emergency Procedures /
Plan Subtotal 3 1 Tier 3 Point Total 10 7