ML091811166
| ML091811166 | |
| Person / Time | |
|---|---|
| Site: | South Texas |
| Issue date: | 06/30/2009 |
| From: | Division of Reactor Safety IV |
| To: | |
| References | |
| Download: ML091811166 (37) | |
Text
NUREG-1021, Rev. 9, Supp.1 1
ES-401 Facility:
Callaway PWR Examination Outline Form ES-401-2 3
3 3
3 3
3 1
2 1
2 2
1 4
5 4
5 5
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
2 3
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:
06/19/2009 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
NUREG-1021, Rev. 9, Supp.1 2
K1 KA Topic Imp.
K2 K3 A1 A2 G
Points ES - 401 Facility:
Callaway E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 EK1.02 - Shutdown margin 3.4 1
X 000007 Reactor Trip - Stabilization - Recovery
/ 1 EK2.03 - S/Gs 3.0 1
X 000009 Small Break LOCA / 3 AK3.02 - CCW lineup and flow paths to RCP oil coolers 3.0 1
X 000015/000017 RCP Malfunctions / 4 AK1.03 - Relationship between charging flow and PZR level 3.0 1
X 000022 Loss of Rx Coolant Makeup / 2 AK3.01 - Shift to alternate flowpath 3.1 1
X 000025 Loss of RHR System / 4 AA1.05 - The CCWS surge tank, including level control and level alarms, and radiation alarm 3.1 1
X 000026 Loss of Component Cooling Water / 8 AK1.03 - Latent heat of vaporization/condensation 2.6 1
X 000027 Pressurizer Pressure Control System Malfunction / 3 2.1.20 - Ability to interpret and execute procedure steps.
4.6 1
X 000038 Steam Gen. Tube Rupture / 3 AK2.02 - Sensors and detectors 2.6*
1 X
000040 Steam Line Rupture - Excessive Heat Transfer / 4 AA1.31 - PZR heater group control switches 3.3 1
X 000056 Loss of Off-site Power / 6 AK3.01 - Actions contained in EOP for loss of vital ac electrical instrument bus 4.1 1
X 000057 Loss of Vital AC Inst. Bus / 6 AA1.03 - Vital and battery bus components 3.1 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 000062 Loss of Nuclear Svc Water / 4 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 000065 Loss of Instrument Air / 8 AA2.09 -Operational status of Emergency Diesel Generators 3.9 1
X 000077 Generator Voltage and Electric Grid Disturbances / 6 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 3.8 1
X W/E04 LOCA Outside Containment / 3
NUREG-1021, Rev. 9, Supp.1 3
K1 KA Topic Imp.
K2 K3 A1 A2 G
Points ES - 401 Facility:
Callaway E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 EA2.1 - Facility conditions and selection of appropriate procedures during abnormal and emergency operations 3.4 1
X W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 EA2.1 - Facility conditions and selection of appropriate procedures during abnormal and emergency operations 3.4 1
X W/E11 Loss of Emergency Coolant Recirc. / 4 18 3
3 3
3 3
3 K/A Category Totals:
Group Point Total:
NUREG-1021, Rev. 9, Supp.1 4
K1 KA Topic Imp.
K2 K3 A1 A2 G
Points ES - 401 Facility:
Callaway E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR RO Examination Outline Form ES-401-2 AK2.03 - Controllers and positioners 2.6 1
X 000028 Pressurizer Level Malfunction / 2 AK3.01 - Termination of startup following loss of intermediate-range instrumentation 3.2 1
X 000033 Loss of Intermediate Range NI / 7 AA2.08 - S/G pressure 3.9 1
X 000068 Control Room Evac. / 8 EA2.07 - The difference between a LOCA and inadequate core cooling, from trends and indicators 4.1 1
X 000074 Inad. Core Cooling / 4 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 EK1.3 - Annunciators and conditions indicating signals, and remedial actions associated with the Natural Circulation Operations 3.3 1
X W/E09 Natural Circ. / 4 2.1.7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
4.4 1
X W/E13 Steam Generator Over-pressure / 4 EA1.2 - Operating behavior characteristics of the facility 2.7 1
X W/E15 Containment Flooding / 5 EK2.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 3.0 1
X W/E16 High Containment Radiation / 9 9
1 2
1 2
2 1
K/A Category Totals:
Group Point Total:
NUREG-1021, Rev. 9, Supp.1 5
K1 KA Topic Imp.
K2 K3 A1 A2 G
Points K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
Callaway PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 K4.02 - Prevention of cold water accidents or transients 2.5 1
X 003 Reactor Coolant Pump K2.01 - Boric acid makeup pumps 2.9 1
X 004 Chemical and Volume Control K2.03 - RCS pressure boundary motor-operated valves 2.7*
1 X
005 Residual Heat Removal K6.01 - BIT/borated water sources 3.4 1
X 006 Emergency Core Cooling A3.05 - Safety Injection Pumps 4.2 1
X 006 Emergency Core Cooling K5.02 - Method of forming a steam bubble in the PZR 3.1 1
X 007 Pressurizer Relief/Quench Tank 2.1.28 - Knowledge of the purpose and function of major system components and controls.
4.1 1
X 007 Pressurizer Relief/Quench Tank A1.01 - CCW flow rate 2.8 1
X 008 Component Cooling Water K4.01 - Spray valve warm-up 2.7 1
X 010 Pressurizer Pressure Control 2.1.17 - Ability to make accurate, clear, and concise verbal reports.
3.9 1
X 012 Reactor Protection K3.04 - ESFAS 3.8*
1 X
012 Reactor Protection K6.01 - Sensors and detectors 2.7*
1 X
013 Engineered Safety Features Actuation K1.01 - SWS/cooling system 3.5 1
X 022 Containment Cooling A2.03 - Failure of ESF 4.1 1
X 026 Containment Spray A1.09 - Main steam line radiation monitors 2.5*
1 X
039 Main and Reheat Steam K3.02 - AFW System 3.6 1
X 059 Main Feedwater A4.12 - Initiation of automatic feedwater isolation 3.4 1
X 059 Main Feedwater K5.02 - Decay heat sources and magnitude 3.2 1
X 061 Auxiliary/Emergency Feedwater A3.01 - Vital ac bus amperage 3.0 1
X 062 AC Electrical Distribution A1.03 - Effect on instrumentation and controls of switching power supplies 2.5 1
X 062 AC Electrical Distribution K1.03 - Battery charger and battery 2.9 1
X 063 DC Electrical Distribution K1.05 - Starting air system 3.4 1
X 064 Emergency Diesel Generator
NUREG-1021, Rev. 9, Supp.1 6
K1 KA Topic Imp.
K2 K3 A1 A2 G
Points K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
Callaway PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 A2.02 - Detector failure 2.7 1
X 073 Process Radiation Monitoring A2.01 - Loss of SWS 3.5*
1 X
076 Service Water A4.01 - Pressure gauges 3.1 1
X 078 Instrument Air K3.01 - Containment air system 3.1*
1 X
078 Instrument Air 2.4.14 - Knowledge of general guidelines for EOP usage.
3.8 1
X 103 Containment K4.01 - Vacuum breaker protection 3.0*
1 X
103 Containment 28 3
2 3
3 3
3 K/A Category Totals:
3 2
2 2
2 Group Point Total:
NUREG-1021, Rev. 9, Supp.1 7
K1 KA Topic Imp.
K2 K3 A1 A2 G
Points K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
Callaway PWR RO Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 A1.11 - Relative level indications in the RWST, the refueling cavity, the PZR and the reactor vessel during preparation for refueling 2.7 1
X 002 Reactor Coolant K1.08 - RCS (pump start) 2.6*
1 X
015 Nuclear Instrumentation A2.01 - High temperature in the filter system 3.0*
1 X
027 Containment Iodine Removal K6.01 - Hydrogen recombiners 2.6 1
X 028 Hydrogen Recombiner and Purge Control A3.01 - CPS isolation 3.8 1
X 029 Containment Purge 2.4.11 - Knowledge of abnormal condition procedures.
4.0 1
X 033 Spent Fuel Pool Cooling A4.02 - Fill of dry S/G 2.7 1
X 035 Steam Generator K5.03 - Units of radiation, dose, and dose rate 2.6 1
X 068 Liquid Radwaste K2.03 - Emergency/essential SWS pumps 2.6*
1 X
075 Circulating Water K4.03 - Detection and location of fires 3.1 1
X 086 Fire Protection 10 1
1 0
1 1
1 K/A Category Totals:
1 1
1 1
1 Group Point Total:
NUREG-1021, Rev. 9, Supp.1 8
Facility:
Callaway Generic Category KA KA Topic Imp.
Points Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 PWR RO Examination Outline 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
3.9 1
Conduct of Operations 2.1.29 Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.
4.1 1
2.1.32 Ability to explain and apply system limits and precautions.
3.8 1
3 Category Total:
2.2.14 Knowledge of the process for controlling equipment configuration or status.
3.9 1
Equipment Control 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
2 Category Total:
2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
3.2 1
Radiation Control 2.3.5 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personal monitoring equipment, etc.
2.9 1
2 Category Total:
2.4.5 Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.
3.7 1
Emergency Procedures/Plan 2.4.11 Knowledge of abnormal condition procedures.
4.0 1
2.4.43 Knowledge of emergency communications systems and techniques.
3.2 1
3 Category Total:
10 Generic Total:
NUREG-1021, Rev. 9, Supp.1 9
ES-401 Facility:
Callaway PWR Examination Outline Form ES-401-2 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
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:
06/19/2009 0
0 0
0 0
0 0
- 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*
3 3
2 2
5 5
3 2
1 1
3 1
2 2
2 1
2 3
4 10 4
6 5
3 8
7
- 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 1
5
NUREG-1021, Rev. 9, Supp.1 10 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points ES - 401 Facility:
Callaway E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR SRO Examination Outline Form ES-401-2 AA2.14 - Saturation temperature monitor 4.4 1
X 000008 Pressurizer Vapor Space Accident / 3 2.3.4 - Knowledge of radiation exposure limits under normal or emergency conditions.
3.7 1
X 000011 Large Break LOCA / 3 EA2.03 - Centrifugal charging pump ammeter 3.1*
1 X
000029 ATWS / 1 2.1.6 - Ability to manage the control room crew during plant transients.
4.8 1
X 000054 Loss of Main Feedwater / 4 EA2.04 - Instruments and controls operable with only dc battery power available 4.1 1
X 000055 Station Blackout / 6 2.4.44 - Knowledge of emergency plan protective action recommendations.
4.4 1
X W/E12 - Steam Line Rupture - Excessive Heat Transfer / 4 6
0 0
0 0
3 3
K/A Category Totals:
Group Point Total:
NUREG-1021, Rev. 9, Supp.1 11 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points ES - 401 Facility:
Callaway E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR SRO Examination Outline Form ES-401-2 2.2.22 - Knowledge of limiting conditions for operations and safety limits.
4.7 1
X 000001 Continuous Rod Withdrawal / 1 AA2.17 - Systems that may be affected by the fire 3.5 1
X 000067 Plant Fire On-site / 9 2.4.1 - Knowledge of EOP entry conditions and immediate action steps.
4.8 1
X W/E06 Inad. Core Cooling / 4 EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 3.8 1
X W/E14 Loss of CTMT Integrity / 5 4
0 0
0 0
2 2
K/A Category Totals:
Group Point Total:
NUREG-1021, Rev. 9, Supp.1 12 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
Callaway PWR SRO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 A2.02 - Failure of automatic recirculation transfer 4.4*
1 X
026 Containment Spray A2.03 - Loss of dc power 3.4 1
X 061 Auxiliary/Emergency Feedwater A2.02 - Loss of ventilation during battery charging 3.1 1
X 063 DC Electrical Distribution 2.4.45 - Ability to prioritize and interpret the significance of each annunciator or alarm.
4.3 1
X 064 Emergency Diesel Generator 2.1.28 - Knowledge of the purpose and function of major system components and controls.
4.1 1
X 073 Process Radiation Monitoring 5
0 0
0 0
3 2
K/A Category Totals:
0 0
0 0
0 Group Point Total:
NUREG-1021, Rev. 9, Supp.1 13 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
Callaway PWR SRO Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 A2.02 - Loss of power supply 3.2*
1 X
016 Non-nuclear Instrumentation K1.03 - CVCS 2.7*
1 X
034 Fuel Handling Equipment 2.4.16 - Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.
4.4 1
X 055 Condenser Air Removal 3
1 0
0 0
1 1
K/A Category Totals:
0 0
0 0
0 Group Point Total:
NUREG-1021, Rev. 9, Supp.1 14 Facility:
Callaway Generic Category KA KA Topic Imp.
Points Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 PWR SRO Examination Outline 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.
3.9 1
Conduct of Operations 1
Category Total:
2.2.15 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tagouts, etc.
4.3 1
Equipment Control 2.2.40 Ability to apply Technical Specifications for a system.
4.7 1
2 Category Total:
2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
3.8 1
Radiation Control 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
3.8 1
2 Category Total:
2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
4.6 1
Emergency Procedures/Plan 2.4.46 Ability to verify that the alarms are consistent with the plant conditions.
4.2 1
2 Category Total:
7 Generic Total:
ES-401 Record of Rejected K/As Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection 2 / 1 026 A2.03 No plant reference to support 026 A2.01. Randomly selected from within 026 A2 1 / 1 077 AA2.09 No plant reference to support AA2.08. Randomly selected from within 077 AA2