ML120880601
ML120880601 | |
Person / Time | |
---|---|
Site: | Diablo Canyon ![]() |
Issue date: | 03/09/2012 |
From: | NRC Region 4 |
To: | Pacific Gas & Electric Co |
References | |
50-275/12-401, 50-323/12-401, ES-401, ES-401-2 | |
Download: ML120880601 (15) | |
Text
09/29/2011 Printed:
ES-401 Facility:
Diablo Canyon PWR Examination Outline Form ES-401-2 3
3 3
3 3
3 2
2 1
1 2
1 5
5 4
4 5
4 3
2 3
3 3
2 2
3 2
2 3
1 1
1 1
0 1
1 1
1 1
1 4
3 4
4 3
3 3
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:
02/03/2012 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
09/29/2011 11:12:04 am
09/29/2011 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
ES - 401 Facility:
Diablo Canyon E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 EK3.01 - Actions contained in EOP for reactor trip 4.0 1
X 000007 Reactor Trip - Stabilization -
Recovery / 1 AK2.02 - Sensors and detectors 2.7*
1 X
000008 Pressurizer Vapor Space Accident /
3 EK1.02 - Use of steam tables 3.5 1
X 000009 Small Break LOCA / 3 2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc.
3.9 1
X 000015/000017 RCP Malfunctions / 4 AA1.05 - RCP seal back pressure regulator valves and flow indicators 2.9*
1 X
000022 Loss of Rx Coolant Makeup / 2 AK2.05 - Reactor building sump 2.6 1
X 000025 Loss of RHR System / 4 AK3.04 - Effect on the CCW flow header of a loss of CCW 3.5 1
X 000026 Loss of Component Cooling Water /
8 AK1.02 - Expansion of liquids as temperature increases 2.8 1
X 000027 Pressurizer Pressure Control System Malfunction / 3 AA2.04 - Proper operation of AFW pumps and regulating valves 4.2 1
X 000054 Loss of Main Feedwater / 4 AA2.07 - Operational status of emergency feedwater pump (motor driven) 4.2 1
X 000056 Loss of Off-site Power / 6 2.1.30 - Ability to locate and operate components, including local controls.
4.4 1
X 000057 Loss of Vital AC Inst. Bus / 6 AK3.01 - Use of dc control power by ED/Gs 3.4*
1 X
000058 Loss of DC Power / 6 AA2.04 - The normal values and upper limits for the temperatures of the components cooled by SWS 2.5 1
X 000062 Loss of Nuclear Svc Water / 4 AA1.01 - Remote manual loaders 2.7*
1 X
000065 Loss of Instrument Air / 8 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 2.4.20 - Knowledge of operational implications of EOP warnings, cautions, and notes.
3.8 1
X W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 EA1.3 - Desired operating results during abnormal and emergency situations 3.7 1
X W/E11 Loss of Emergency Coolant Recirc. /
4 EK1.1 - Components:, capacity, and function of emergency systems 3.4 1
X W/E12 - Steam Line Rupture - Excessive Heat Transfer / 4 1
09/29/2011 11:11:30 am
09/29/2011 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
ES - 401 Facility:
Diablo Canyon E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 18 3
3 3
3 3
3 K/A Category Totals:
Group Point Total:
2 09/29/2011 11:11:30 am
09/29/2011 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
ES - 401 Facility:
Diablo Canyon E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR RO Examination Outline Form ES-401-2 AK2.06 - T-ave./ref. deviation meter 3.0*
1 X
000001 Continuous Rod Withdrawal / 1 AK1.01 - Relationship between boron addition and change in T-ave 3.4 1
X 000024 Emergency Boration / 1 AA1.01 - Manual restoration of power 3.1*
1 X
000032 Loss of Source Range NI / 7 AA2.01 - ARM system indications 3.2 1
X 000036 Fuel Handling Accident / 8 AK1.02 - 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 levels 2.5 1
X 000060 Accidental Gaseous Radwaste Rel. /
9 2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
4.5 1
X 000068 Control Room Evac. / 8 EK3.4 - RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated 3.5 1
X W/E02 SI Termination / 3 EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 3.5 1
X W/E03 LOCA Cooldown - Depress. / 4 EK2.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 3.6 1
X W/E06 Inad. Core Cooling / 4 9
2 2
1 1
2 1
K/A Category Totals:
Group Point Total:
1 09/29/2011 11:11:37 am
09/29/2011 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
Diablo Canyon PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 K5.05 - The dependency of RCS flow rates upon the number of operating RCPs 2.8 1
X 003 Reactor Coolant Pump K3.03 - Feedwater and emergency feedwater 2.8 1
X 003 Reactor Coolant Pump K5.50 - Design basis letdown system temperatures: resin integrity 2.6 1
X 004 Chemical and Volume Control K4.05 - Relation between RHR flowpath and refueling cavity 2.5 1
X 005 Residual Heat Removal A1.19 - Subcooling 4.0 1
X 006 Emergency Core Cooling K4.01 - Quench tank cooling 2.6 1
X 007 Pressurizer Relief/Quench Tank K1.04 - RCS, in order to determine source(s) of RCS leakage into the CCWS 3.3 1
X 008 Component Cooling Water K5.01 - Determination of condition of fluid in PZR, using steam tables 3.5 1
X 010 Pressurizer Pressure Control K2.01 - RPS channels, components, and interconnections 3.3 1
X 012 Reactor Protection K6.01 - Sensors and detectors 2.7*
1 X
013 Engineered Safety Features Actuation 2.4.9 - Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.
3.8 1
X 013 Engineered Safety Features Actuation A2.04 - Loss of service water 2.9*
1 X
022 Containment Cooling 2.4.34 - Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects.
4.2 1
X 022 Containment Cooling A4.05 - Containment spray reset switches 3.5 1
X 026 Containment Spray K4.02 - Utilization of T-ave.
program control when steam dumping through atmospheric relief/dump valves, including T-ave.
limits 3.1 1
X 039 Main and Reheat Steam A4.08 - Feed regulating valve controller 3.0*
1 X
059 Main Feedwater 1
09/29/2011 11:11:45 am
09/29/2011 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
Diablo Canyon PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 A2.11 - Failure of feedwater control system 3.0*
1 X
059 Main Feedwater K2.01 - AFW system MOVs 3.2*
1 X
061 Auxiliary/Emergency Feedwater A3.01 - AFW startup and flows 4.2 1
X 061 Auxiliary/Emergency Feedwater A2.12 - Restoration of power to a system with a fault on it 3.2 1
X 062 AC Electrical Distribution K1.03 - Battery charger and battery 2.9 1
X 063 DC Electrical Distribution 2.1.30 - Ability to locate and operate components, including local controls.
4.4 1
X 064 Emergency Diesel Generator K6.08 - Fuel oil storage tanks 3.2 1
X 064 Emergency Diesel Generator K3.01 - Radioactive effluent releases 3.6 1
X 073 Process Radiation Monitoring K3.07 - ESF loads 3.7 1
X 076 Service Water K1.05 - MSIV air 3.4*
1 X
078 Instrument Air A3.01 - Air pressure 3.1 1
X 078 Instrument Air A1.01 - Containment pressure, temperature, and humidity 3.7 1
X 103 Containment 28 3
2 3
2 3
3 K/A Category Totals:
3 3
2 2
2 Group Point Total:
2 09/29/2011 11:11:45 am
09/29/2011 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
Diablo Canyon PWR RO Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 A4.02 - Boration/dilution 4.1 1
X 001 Control Rod Drive K1.05 - PRT 3.2 1
X 002 Reactor Coolant K6.04 - Operation of PZR level controllers 3.1 1
X 011 Pressurizer Level Control K4.03 - Rod bottom lights 3.2 1
X 014 Rod Position Indication A3.01 - Automatic selection of NNIS inputs to control systems 2.9*
1 X
016 Non-nuclear Instrumentation K2.01 - Hydrogen recombiners 2.5*
1 X
028 Hydrogen Recombiner and Purge Control A1.02 - Radiation levels 3.4 1
X 029 Containment Purge 2.4.49 - Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
4.6 1
X 045 Main Turbine Generator K3.05 - ARM and PRM systems 3.2 1
X 071 Waste Gas Disposal A2.01 - Loss of intake structure 3.0*
1 X
075 Circulating Water 10 1
1 1
1 1
1 K/A Category Totals:
1 0
1 1
1 Group Point Total:
1 09/29/2011 11:11:52 am
Facility:
Diablo Canyon Generic Category KA KA Topic Imp.
Points Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 09/29/2011 Printed:
PWR RO Examination Outline 2.1.26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).
3.4 1
Conduct of Operations 2.1.40 Knowledge of refueling administrative requirements.
2.8 1
2.1.45 Ability to identify and interpret diverse indications to validate the response of another indication.
4.3 1
3 Category Total:
2.2.6 Knowledge of the process for making changes to procedures.
3.0 1
Equipment Control 2.2.35 Ability to determine Technical Specification Mode of Operation.
3.6 1
2 Category Total:
2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.
3.5 1
Radiation Control 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
3.4 1
2 Category Total:
2.4.19 Knowledge of EOP layout, symbols, and icons.
3.4 1
Emergency Procedures/Plan 2.4.28 Knowledge of procedures relating to a security event (non-safeguards information).
3.2 1
2.4.46 Ability to verify that the alarms are consistent with the plant conditions.
4.2 1
3 Category Total:
10 Generic Total:
1 09/29/2011 11:11:59 am
12/07/2011 Printed:
ES-401 Facility:
DCPP 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:
02/03/2012 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
2 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 0
5 1
12/07/2011 10:52:16 am
12/07/2011 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
ES - 401 Facility:
DCPP E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR SRO Examination Outline Form ES-401-2 EA2.03 - Consequences of managing LOCA with loss of CCW 4.2 1
X 000011 Large Break LOCA / 3 2.4.49 - Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
4.4 1
X 000015/000017 RCP Malfunctions / 4 EA2.11 - Local radiation reading on main steam lines 3.9*
1 X
000038 Steam Gen. Tube Rupture / 3 AA2.02 - Conditions requiring a reactor trip 4.7 1
X 000040 Steam Line Rupture - Excessive Heat Transfer / 4 2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
4.7 1
X 000055 Station Blackout / 6 2.4.20 - Knowledge of operational implications of EOP warnings, cautions, and notes.
4.3 1
X 000062 Loss of Nuclear Svc Water / 4 6
0 0
0 0
3 3
K/A Category Totals:
Group Point Total:
1 12/07/2011 10:45:33 am
12/07/2011 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
ES - 401 Facility:
DCPP E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR SRO Examination Outline Form ES-401-2 AA2.04 - Ammeters and running indicators for CVCS charging pumps 3.1 1
X 000028 Pressurizer Level Malfunction / 2 AA2.01 - Cause for low vacuum condition 2.7*
1 X
000051 Loss of Condenser Vacuum / 4 2.4.6 - Knowledge of EOP mitigation strategies.
4.7 1
X W/E01 Rediagnosis / 3 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
X W/E09 Natural Circ. / 4 4
0 0
0 0
2 2
K/A Category Totals:
Group Point Total:
1 12/07/2011 10:45:40 am
12/07/2011 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
DCPP PWR SRO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 2.4.8 - Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
4.5 1
X 003 Reactor Coolant Pump A2.04 - RHR valve malfunction 2.9 1
X 005 Residual Heat Removal A2.04 - Malfunctioning steam dump 3.7 1
X 039 Main and Reheat Steam A2.07 - Air or MOV failure 3.5 1
X 061 Auxiliary/Emergency Feedwater 2.2.25 - Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
4.2 1
X 076 Service Water 5
0 0
0 0
3 2
K/A Category Totals:
0 0
0 0
0 Group Point Total:
1 12/07/2011 10:45:46 am
12/07/2011 K1 KA Topic Imp.
K2 K3 A1 A2 G
Points Printed:
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
DCPP PWR SRO Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 A2.02 - Loss of coolant pressure 4.4 1
X 002 Reactor Coolant 2.4.49 - Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
4.4 1
X 015 Nuclear Instrumentation A2.04 - Loss of condensate pumps 2.8*
1 X
056 Condensate 3
0 0
0 0
2 1
K/A Category Totals:
0 0
0 0
0 Group Point Total:
1 12/07/2011 10:45:52 am
Facility:
DCPP Generic Category KA KA Topic Imp.
Points Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 12/07/2011 Printed:
PWR SRO Examination Outline 2.1.6 Ability to manage the control room crew during plant transients.
4.8 1
Conduct of Operations 1
Category Total:
2.2.7 Knowledge of the process for conducting special or infrequent tests.
3.6 1
Equipment Control 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
2 Category Total:
2.3.6 Ability to approve release permits.
3.8 1
Radiation Control 2.3.11 Ability to control radiation releases.
4.3 1
2 Category Total:
2.4.41 Knowledge of the emergency action level thresholds and classifications.
4.6 1
Emergency Procedures/Plan 2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.
4.3 1
2 Category Total:
7 Generic Total:
1 12/07/2011 10:45:59 am
ES-401 Record of Rejected K/As Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection RO -
T1/G1 EPE029 G2.2.25 KA asks for the bases in Technical Specifications for LCO and safety limits. Not applicable to ATWS or RO Randomly replaced with APE015/017 G2.1.25 RO -
T1/G2 APE059AA1.03 Adequately covered by system KA 071; randomly replaced this KA with APE060 AK1.02 RO -
T1/G2 APE060AK3.02 Oversampling of effects of accidental rad waste. Kept system KA 073 and randomly replaced this KA with W/E02 EK3.4 RO -
T2/G1 073 A4.01 Oversampled system and not monitored in the Control Room by the RO. Randomly replaced KA with 003 K5.05 SRO -
T1/G1 APE 077 G2.4.50 Unable to generate SRO level question. Alarm response would be handled by RO. Randomly replaced KA with APE 062 G2.4.20 SRO -
T2/G1 062 A2.07 Not SRO level knowledge. Randomly replaced KA with 061 A2.07 SRO -
T2/G2 041 A2.02 KA very similar to KA 039 A2.04. Randomly replaced KA with 002 A2.02