ML102220046
| ML102220046 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/21/2010 |
| From: | Division of Nuclear Materials Safety III |
| To: | |
| References | |
| Download: ML102220046 (1) | |
Text
04/12/2010 Printed: ES-401 Facility: Cook Nuclear Plant PWR Examination Outline Form ES-401-2 3 3 3 3 3 3 2 2 1 2 1 1 5 5 4 5 4 4 3 2 3 3 2 2 3 3 2 2 3 1 1 0 1 1 1 1 1 1 1 1 4 3 3 4 3 3 4 4 3 3 4 3 2 3 2 RO K/A Category Points Tier Group Total K1 K2 K3 K4 K5 A1 A2 A3 A4 K6 G*1.Emergency&Abnormal Plant Evolutions 1 1 2 2 Tier Totals Tier Totals 2.Plant Systems 1 2 3 4 3. Generic Knowledge And Abilities Categories 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.
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.
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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
5.Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
Note: Date Of Exam:
06/21/2010 28 18 9 27 10 38 10 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).
7.*The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
SRO-Only Points A2 G* 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 2 3 4 0 0 0 0 0 0 0 9.For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.
Limit SRO selections to K/As that are linked to 10 CFR 55.43.
6.Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
N/A N/A Total 0 0 1 04/12/2010 9:22:52 am 04/12/2010 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:
ES - 401 Facility: Cook Nuclear Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 AK2.01 - Valves 2.7*1 X 000008 Pressurizer Vapor Space Accident /
3 EA2.38 - Existence of head bubble 3.9 1 X 000009 Small Break LOCA / 3 EA1.05 - Manual and/or automatic transfer of suction of charging pumps to borated source 4.3 1 X 000011 Large Break LOCA / 3 AK1.04 - Basic steady state thermodynamic relationship between RCS loops and S/Gs resulting from unbalanced RCS flow 2.9 1 X 000015/000017 RCP Malfunctions / 4 AA1.09 - LPI pump switches, ammeter, discharge pressure gauge, flow meter, and indicators 3.2 1 X 000025 Loss of RHR System / 4 2.2.40 - Ability to apply Technical Specifications for a system.
3.4 1 X 000027 Pressurizer Pressure Control System Malfunction / 3 EK2.06 - Breakers, relays, and disconnects 2.9*1 X 000029 ATWS / 1 AK3.04 - Actions contained in EOPs for loss of MFW 4.4 1 X 000054 Loss of Main Feedwater / 4 EK3.02 - Actions contained in EOP for loss of offsite and onsite power 4.3 1 X 000055 Station Blackout / 6 AK1.03 - Definition of subcooling: use of steam tables to determine it 3.1*1 X 000056 Loss of Off-site Power / 6 AA1.02 - Manual control of PZR level 3.8 1 X 000057 Loss of Vital AC Inst. Bus / 6 2.4.20 - Knowledge of operational implications of EOP warnings, cautions, and notes.
3.8 1 X 000058 Loss of DC Power / 6 2.4.8 - Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
3.8 1 X 000065 Loss of Instrument Air / 8 AA2.07 - Operational status of engineered safety features 3.6 1 X 000077 Generator Voltage and Electric Grid Disturbances / 6 EK2.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 3.5 1 X W/E04 LOCA Outside Containment / 3 EK3.3 - Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations 4.0 1 X W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 1 04/12/2010 9:22:19 am 04/12/2010 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:
ES - 401 Facility: Cook Nuclear Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 3.4 1 X W/E11 Loss of Emergency Coolant Recirc. /
4 EK1.2 - Normal, abnormal and emergency operating procedures associated with Uncontrolled Depressurization of all Steam Generators 3.5 1 X W/E12 - Steam Line Rupture - Excessive Heat Transfer / 4 18 3 3 3 3 3 3 K/A Category Totals:
Group Point Total:
2 04/12/2010 9:22:19 am 04/12/2010 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:
ES - 401 Facility: Cook Nuclear Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR RO Examination Outline Form ES-401-2 AA1.04 - Rod position 2.5*1 X 000051 Loss of Condenser Vacuum / 4 AK1.02 - Biological effects on humans of various types of radiation, exposure levels that are acceptable for nuclear power plant personnel, and the units used for radiation-intensity measurements and for radiation exposure levels 2.6 1 X 000059 Accidental Liquid RadWaste Rel. /
9 2.2.36 - Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.
3.1 1 X 000061 ARM System Alarms / 7 AK1.02 - Fire fighting 3.1 1 X 000067 Plant Fire On-site / 9 AK2.07 - ED/G 3.3 1 X 000068 Control Room Evac. / 8 EA1.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 4.0 1 X W/E03 LOCA Cooldown - Depress. / 4 EK3.2 - Normal, abnormal and emergency operating procedures associated with Natural Circulation Operations 3.2 1 X W/E09 Natural Circ. / 4 EK2.2 - Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility 3.4 1 X W/E14 Loss of CTMT Integrity / 5 EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 3.0 1 X W/E16 High Containment Radiation / 9 9 2 2 1 2 1 1 K/A Category Totals:
Group Point Total:
1 04/12/2010 9:22:26 am 04/12/2010 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
Cook Nuclear Plant PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 K2.02 - CCW pumps 2.5*1 X 003 Reactor Coolant Pump 2.4.47 - Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.4.2 1 X 004 Chemical and Volume Control K3.08 - RCP seal injection 3.6 1 X 004 Chemical and Volume Control K6.03 - RHR heat exchanger 2.5 1 X 005 Residual Heat Removal K1.11 - CCWS 2.8 1 X 006 Emergency Core Cooling A4.10 - Recognition of leaking PORV/code safety 3.6 1 X 007 Pressurizer Relief/Quench Tank A2.05 - Effect of loss of instrument and control air on the position of the CCW valves that are air operated 3.3*1 X 008 Component Cooling Water A2.01 - Heater failures 3.3 1 X 010 Pressurizer Pressure Control A3.04 - Circuit breaker 2.8*1 X 012 Reactor Protection K6.02 - Redundant channels 2.9 1 X 012 Reactor Protection K5.02 - Safety system logic and reliability 2.9 1 X 013 Engineered Safety Features Actuation K4.04 - Auxiliary feed actuation signal 4.3*1 X 013 Engineered Safety Features Actuation K3.02 - Containment instrumentation readings 3.0 1 X 022 Containment Cooling A1.03 - Glycol flow to ice condenser air handling units 2.5*1 X 025 Ice Condenser K2.02 - MOVs 2.7*1 X 026 Containment Spray K5.08 - Effect of steam removal on reactivity 3.6 1 X 039 Main and Reheat Steam A1.07 - Feed Pump speed, including normal control speed for ICS 2.5*1 X 059 Main Feedwater A4.03 - Feedwater control during power increase and decrease 2.9*1 X 059 Main Feedwater K3.02 - S/G 4.2 1 X 061 Auxiliary/Emergency Feedwater K1.03 - DC distribution 3.5 1 X 062 AC Electrical Distribution K4.04 - Trips 2.6?1 X 063 DC Electrical Distribution 2.4.50 - Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
4.2 1 X 064 Emergency Diesel Generator K4.04 - Overload ratings 3.1 1 X 064 Emergency Diesel Generator 1 04/12/2010 9:22:33 am 04/12/2010 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
Cook Nuclear Plant PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 A2.01 - Erratic or failed power supply 2.5 1 X 073 Process Radiation Monitoring A1.02 - Reactor and turbine building closed cooling water temperatures 2.6*1 X 076 Service Water 2.4.6 - Knowledge of EOP mitigation strategies.
3.7 1 X 076 Service Water A3.01 - Air pressure 3.1 1 X 078 Instrument Air K1.02 - Containment isolation/containment integrity 3.9 1 X 103 Containment 28 3 2 3 3 3 3 K/A Category Totals:
3 2 2 2 2 Group Point Total:
2 04/12/2010 9:22:33 am 04/12/2010 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
Cook Nuclear Plant PWR RO Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 K5.05 - Interrelation of indicated charging flow rate with volume of water required to bring PZR level back to programmed level hot/cold 2.8 1 X 011 Pressurizer Level Control A4.01 - Rod selection control 3.3 1 X 014 Rod Position Indication K1.04 - MFW System 2.7*1 X 016 Non-nuclear Instrumentation A2.03 - Startup operations and the associated required valve lineups 2.7 1 X 029 Containment Purge K6.02 - Secondary PORV 3.1 1 X 035 Steam Generator K2.01 - ICS, normal and alternate power supply 2.8*1 X 041 Steam Dump/Turbine Bypass Control 2.2.44 - Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
4.2 1 X 056 Condensate K4.01 - Safety and environmental precautions for handling hot, acidic, and radioactive liquids 3.4 1 X 068 Liquid Radwaste A3.01 - Changes in ventilation alignment 2.9*1 X 072 Area Radiation Monitoring A1.03 - Fire doors 2.7 1 X 086 Fire Protection 10 1 1 0 1 1 1 K/A Category Totals:
1 1 1 1 1 Group Point Total:
1 04/12/2010 9:22:40 am