Text

2012-03-FINAL-Outlines
	ML120880627
Person / Time
Site:	Diablo Canyon
Issue date:	03/09/2012
From:	; Division of Reactor Safety IV
To:	; Pacific Gas & Electric Co
References
	DC-2012-03, ES-401, ES-401-2
	Download: ML120880627 (15)
	v • d • e

ES-401 PWR Examination Outline Form ES-401-2 Facility: DCPP Printed: 03/27/2012 Date Of Exam: 02/03/2012 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 3 3 3 3 3 3 18 0 0 0 Emergency 2 2 2 1 N/A 1 2 1 9 0 0 0

& N/A Abnormal Tier Plant Totals 5 5 4 4 5 4 27 0 0 0 Evolutions 1 3 2 3 3 3 2 2 3 2 2 3 28 0 0 0 2.

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

3. Generic Knowledge And 10 0 Abilities Categories 3 2 2 3 0 0 0 0 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/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.

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.

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.

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. 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.

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.

03/27/2012 8:37:32 am 1

PWR RO Examination Outline Printed: 03/27/2012 Facility: DCPP ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000007 Reactor Trip - Stabilization - X EK3.01 - Actions contained in EOP for 4.0 1 Recovery / 1 reactor trip 000008 Pressurizer Vapor Space Accident / X AK2.02 - Sensors and detectors 2.7* 1 3

000009 Small Break LOCA / 3 X EK1.02 - Use of steam tables 3.5 1 000015/000017 RCP Malfunctions / 4 X 2.1.25 - Ability to interpret reference 3.9 1 materials, such as graphs, curves, tables, etc.

000022 Loss of Rx Coolant Makeup / 2 X AA1.05 - RCP seal back pressure 2.9* 1 regulator valves and flow indicators 000025 Loss of RHR System / 4 X AK2.05 - Reactor building sump 2.6 1 000026 Loss of Component Cooling Water / X AK3.04 - Effect on the CCW flow 3.5 1 8 header of a loss of CCW 000027 Pressurizer Pressure Control System X AK1.02 - Expansion of liquids as 2.8 1 Malfunction / 3 temperature increases 000054 Loss of Main Feedwater / 4 X AA2.04 - Proper operation of AFW 4.2 1 pumps and regulating valves 000055 Station Blackout / 6 X EA1.01 - In-core thermocouple 3.7 1 temperatures 000056 Loss of Off-site Power / 6 X AA2.07 - Operational status of 4.2 1 emergency feedwater pump (motor driven) 000057 Loss of Vital AC Inst. Bus / 6 X 2.1.30 - Ability to locate and operate 4.4 1 components, including local controls.

000058 Loss of DC Power / 6 X AK3.01 - Use of dc control power by 3.4* 1 ED/Gs 000062 Loss of Nuclear Svc Water / 4 X AA2.04 - The normal values and upper 2.5 1 limits for the temperatures of the components cooled by SWS W/E04 LOCA Outside Containment / 3 X EK2.2 - Facility's heat removal systems, 3.8 1 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 W/E05 Inadequate Heat Transfer - Loss of X 2.4.20 - Knowledge of operational 3.8 1 Secondary Heat Sink / 4 implications of EOP warnings, cautions, and notes.

W/E11 Loss of Emergency Coolant Recirc. / X EA1.3 - Desired operating results 3.7 1 4 during abnormal and emergency situations 03/27/2012 8:36:52 am 1

PWR RO Examination Outline Printed: 03/27/2012 Facility: DCPP ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points W/E12 - Steam Line Rupture - Excessive X EK1.1 - Components:, capacity, and 3.4 1 Heat Transfer / 4 function of emergency systems K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 03/27/2012 8:36:52 am 2

PWR RO Examination Outline Printed: 03/27/2012 Facility: DCPP ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000001 Continuous Rod Withdrawal / 1 X AK2.06 - T-ave./ref. deviation meter 3.0* 1 000024 Emergency Boration / 1 X AK1.01 - Relationship between boron 3.4 1 addition and change in T-ave 000032 Loss of Source Range NI / 7 X AA1.01 - Manual restoration of power 3.1* 1 000036 Fuel Handling Accident / 8 X AA2.01 - ARM system indications 3.2 1 000060 Accidental Gaseous Radwaste Rel. / X AK1.02 - Biological effects on humans 2.5 1 9 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 000068 Control Room Evac. / 8 X 2.4.4 - Ability to recognize abnormal 4.5 1 indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

W/E02 SI Termination / 3 X EK3.4 - RO or SRO function within the 3.5 1 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 W/E03 LOCA Cooldown - Depress. / 4 X EA2.2 - Adherence to appropriate 3.5 1 procedures and operation within the limitations in the facility's license and amendments W/E06 Inad. Core Cooling / 4 X EK2.1 - Components, and functions of 3.6 1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features K/A Category Totals: 2 2 1 1 2 1 Group Point Total: 9 03/27/2012 8:37:00 am 1

PWR RO Examination Outline Printed: 03/27/2012 Facility: DCPP ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump X K5.05 - The dependency of 2.8 1 RCS flow rates upon the number of operating RCPs 003 Reactor Coolant Pump X K3.03 - Feedwater and 2.8 1 emergency feedwater 004 Chemical and Volume Control X K5.50 - Design basis 2.6 1 letdown system temperatures: resin integrity 005 Residual Heat Removal X K4.05 - Relation between 2.5 1 RHR flowpath and refueling cavity 006 Emergency Core Cooling X A1.19 - Subcooling 4.0 1 007 Pressurizer Relief /Quench X K4.01 - Quench tank 2.6 1 Tank cooling 008 Component Cooling Water X K1.04 - RCS, in order to 3.3 1 determine source(s) of RCS leakage into the CCWS 010 Pressurizer Pressure Control X K5.01 - Determination of 3.5 1 condition of fluid in PZR, using steam tables 012 Reactor Protection X K2.01 - RPS channels, 3.3 1 components, and interconnections 013 Engineered Safety Features X K6.01 - Sensors and 2.7* 1 Actuation detectors 013 Engineered Safety Features X 2.4.9 - Knowledge of low 3.8 1 Actuation power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

022 Containment Cooling X 2.4.34 - Knowledge of RO 4.2 1 tasks performed outside the main control room during an emergency and the resultant operational effects.

022 Containment Cooling X A2.04 - Loss of service 2.9* 1 water 026 Containment Spray X A4.05 - Containment spray 3.5 1 reset switches 039 Main and Reheat Steam X K4.02 - Utilization of T-ave. 3.1 1 program control when steam dumping through atmospheric relief /dump valves, including T-ave.

limits 059 Main Feedwater X A4.08 - Feed regulating 3.0* 1 valve controller 03/27/2012 8:37:09 am 1

PWR RO Examination Outline Printed: 03/27/2012 Facility: DCPP ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 059 Main Feedwater X A2.11 - Failure of feedwater 3.0* 1 control system 061 Auxiliary/Emergency X K2.01 - AFW system MOVs 3.2* 1 Feedwater 061 Auxiliary/Emergency X A3.01 - AFW startup and 4.2 1 Feedwater flows 062 AC Electrical Distribution X A2.12 - Restoration of 3.2 1 power to a system with a fault on it 063 DC Electrical Distribution X K1.03 - Battery charger and 2.9 1 battery 064 Emergency Diesel Generator X 2.1.30 - Ability to locate and 4.4 1 operate components, including local controls.

064 Emergency Diesel Generator X K6.08 - Fuel oil storage 3.2 1 tanks 073 Process Radiation Monitoring X K3.01 - Radioactive effluent 3.6 1 releases 076 Service Water X K3.07 - ESF loads 3.7 1 078 Instrument Air X K1.05 - MSIV air 3.4* 1 078 Instrument Air X A3.01 - Air pressure 3.1 1 103 Containment X A1.01 - Containment 3.7 1 pressure, temperature, and humidity K/A Category Totals: 3 2 3 3 3 2 2 3 2 2 3 Group Point Total: 28 03/27/2012 8:37:09 am 2

PWR RO Examination Outline Printed: 03/27/2012 Facility: DCPP ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 001 Control Rod Drive X A4.02 - Boration/dilution 4.1 1 002 Reactor Coolant X K1.05 - PRT 3.2 1 011 Pressurizer Level Control X K6.04 - Operation of PZR 3.1 1 level controllers 015 Nuclear Instrumentation X K2.01 - NIS channels, 3.3 1 components, and interconnections 016 Non-nuclear Instrumentation X A3.01 - Automatic selection 2.9* 1 of NNIS inputs to control systems 029 Containment Purge X A1.02 - Radiation levels 3.4 1 033 Spent Fuel Pool Cooling X K4.01 - Maintenance of 2.9 1 spent fuel level 045 Main Turbine Generator X 2.4.49 - Ability to perform 4.6 1 without reference to procedures those actions that require immediate operation of system components and controls.

071 Waste Gas Disposal X K3.05 - ARM and PRM 3.2 1 systems 075 Circulating Water X A2.01 - Loss of intake 3.0* 1 structure K/A Category Totals: 1 1 1 1 0 1 1 1 1 1 1 Group Point Total: 10 03/27/2012 8:37:17 am 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 03/27/2012 Facility: DCPP Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.26 Knowledge of industrial safety procedures (such 3.4 1 as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

2.1.40 Knowledge of refueling administrative 2.8 1 requirements.

2.1.45 Ability to identify and interpret diverse 4.3 1 indications to validate the response of another indication.

Category Total: 3 Equipment Control 2.2.6 Knowledge of the process for making changes to 3.0 1 procedures.

2.2.35 Ability to determine Technical Specification 3.6 1 Mode of Operation.

Category Total: 2 Radiation Control 2.3.7 Ability to comply with radiation work permit 3.5 1 requirements during normal or abnormal conditions.

2.3.14 Knowledge of radiation or contamination hazards 3.4 1 that may arise during normal, abnormal, or emergency conditions or activities.

Category Total: 2 Emergency Procedures/Plan 2.4.19 Knowledge of EOP layout, symbols, and icons. 3.4 1 2.4.28 Knowledge of procedures relating to a security 3.2 1 event (non-safeguards information).

2.4.46 Ability to verify that the alarms are consistent 4.2 1 with the plant conditions.

Category Total: 3 Generic Total: 10 03/27/2012 8:37:26 am 1

ES-401 PWR Examination Outline Form ES-401-2 Facility: DCPP Printed: 03/27/2012 Date Of Exam: 02/03/2012 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 0 0 0 0 0 0 0 3 3 6 Emergency 2 0 0 0 N/A 0 0 0 0 2 2 4

& N/A Abnormal Tier Plant Totals 0 0 0 0 0 0 0 5 5 10 Evolutions 1 0 0 0 0 0 0 0 0 0 0 0 0 3 2 5 2.

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

3. Generic Knowledge And 0 7 Abilities Categories 0 0 0 0 1 2 2 2 Note: