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2008-06 - Draft Written Exam Outline
	ML082830496
Person / Time
Site:	Diablo Canyon
Issue date:	06/27/2008
From:	Ryan Lantz; Operations Branch IV
To:	Keenan J; Pacific Gas & Electric Co
References
	50-275/08-301, 50-323/08-301, ES-401, ES-401-2 50-275/08-301, 50-323/08-301
	Download: ML082830496 (17)
	v • d • e

ES-401 PWR Examination Outline Form ES-401-2 Facility: DCPP Printed: 03/05/2008 Date Of Exam: 06/13/2008 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 2 2 0 9 0 0 0

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

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

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

02/04/2008 12:53:13 pm 1

PWR RO Examination Outline Printed: 02/04/2008 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 - Recovery X EK3.01 - Actions contained in EOP for 4.0 1

/1 reactor trip 000008 Pressurizer Vapor Space Accident / 3 X AK1.01 - Thermodynamics and flow 3.2 1 characteristics of open or leaking valves 000009 Small Break LOCA / 3 X EK2.03 - S/Gs 3.0 1 000011 Large Break LOCA / 3 X EA2.13 - Difference between overcooling 3.7* 1 and LOCA indications 000015/000017 RCP Malfunctions / 4 X AK2.10 - RCP indicators and controls 2.8* 1 000022 Loss of Rx Coolant Makeup / 2 X 2.4.31 - Knowledge of annunciator 4.2 1 alarms, indications, or response procedures.

000025 Loss of RHR System / 4 X AA1.11 - Reactor building sump level 2.9 1 indicators 000026 Loss of Component Cooling Water / 8 X AA2.04 - The normal values and upper 2.5 1 limits for the temperatures of the components cooled by CCW 000027 Pressurizer Pressure Control System X AA2.04 - Tech-Spec limits for RCS 3.7 1 Malfunction / 3 pressure 000038 Steam Gen. Tube Rupture / 3 X EK3.04 - Automatic actions provided by 3.9 1 each PRM 000054 Loss of Main Feedwater / 4 X AK3.01 - Reactor and/or turbine trip, 4.1 1 manual and automatic 000055 Station Blackout / 6 X EA1.06 - Restoration of power with one 4.1 1 ED/G 000058 Loss of DC Power / 6 X 2.2.37 - Ability to determine operability 3.6 1 and/or availability of safety related equipment.

000065 Loss of Instrument Air / 8 X 2.1.23 - Ability to perform specific system 4.3 1 and integrated plant procedures during all modes of plant operation.

W/E04 LOCA Outside Containment / 3 X EA1.3 - Desired operating results during 3.8 1 abnormal and emergency situations W/E05 Inadequate Heat Transfer - Loss of X EK2.1 - Components, and functions of 3.7 1 Secondary Heat Sink / 4 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features W/E11 Loss of Emergency Coolant Recirc. / 4 X EK1.2 - Normal, abnormal and 3.6 1 emergency operating procedures associated with Loss of Emergency Coolant Recirculation 02/04/2008 12:52:37 pm 1

PWR RO Examination Outline Printed:

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 Heat X EK1.3 - Annunciators and conditions 3.4 1 Transfer / 4 indicating signals, and remedial actions associated with the Uncontrolled Depressurization of all Steam Generators K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 02/04/2008 2

PWR RO Examination Outline Printed: 02/04/2008 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 000003 Dropped Control Rod / 1 X AK2.05 - Control rod drive power 2.5 1 supplies and logic circuits 000024 Emergency Boration / 1 X AK2.03 - Controllers and positioners 2.6 1 000028 Pressurizer Level Malfunction / 2 X AA1.05 - Initiation of excess letdown per 2.8 1 the CVCS 000036 Fuel Handling Accident / 8 X AA2.01 - ARM system indications 3.2 1 000051 Loss of Condenser Vacuum / 4 X AA2.02 - Conditions requiring reactor 3.9 1 and/or turbine trip 000061 ARM System Alarms / 7 X AA1.01 - Automatic actuation 3.6 1 W/E02 SI Termination / 3 X EK1.1 - Components, capacity, and 3.2 1 function of emergency systems W/E09 Natural Circ. / 4 X EK1.3 - Annunciators and conditions 3.3 1 indicating signals, and remedial actions associated with the Natural Circulation Operations W/E16 High Containment Radiation / 9 X EK3.2 - Normal, abnormal and 2.9 1 emergency operating procedures associated with High Containment Radiation K/A Category Totals: 2 2 1 2 2 0 Group Point Total: 9 02/04/2008 12:52:37 pm 1

PWR RO Examination Outline Printed: 02/04/2008 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 2.1.27 - Knowledge of system 3.9 1 purpose and/or function.

003 Reactor Coolant Pump X K5.03 - Effects of RCP 3.1 1 shutdown on T-ave.,

including the reason for the unreliability of T-ave. in the shutdown loop 004 Chemical and Volume Control X K6.04 - Pumps 2.8 1 005 Residual Heat Removal X K4.05 - Relation between 2.5 1 RHR flowpath and refueling cavity 005 Residual Heat Removal X A4.01 - Controls and 3.6* 1 indication for RHR pumps 006 Emergency Core Cooling X K5.06 - Relationship between 3.5 1 ECCS flow and RCS pressure 006 Emergency Core Cooling X K4.16 - Interlocks between 3.2 1 RHR valves and RCS 007 Pressurizer Relief/Quench Tank X A1.02 - Maintaining quench 2.7 1 tank pressure 008 Component Cooling Water X K3.01 - Loads cooled by 3.4 1 CCWS 010 Pressurizer Pressure Control X K2.01 - PZR heaters 3.0 1 012 Reactor Protection X K1.08 - MFW 2.9* 1 013 Engineered Safety Features X K2.01 - ESFAS/safeguards 3.6* 1 Actuation equipment control 013 Engineered Safety Features X K5.02 - Safety system logic 2.9 1 Actuation and reliability 022 Containment Cooling X K4.04 - Cooling of control 2.8 1 rod drive motors 022 Containment Cooling X A1.02 - Containment pressure 3.6 1 026 Containment Spray X K1.01 - ECCS 4.2 1 039 Main and Reheat Steam X K1.05 - T/G 2.5* 1 059 Main Feedwater X A4.12 - Initiation of 3.4 1 automatic feedwater isolation 061 Auxiliary/Emergency Feedwater X K3.02 - S/G 4.2 1 061 Auxiliary/Emergency Feedwater X A2.04 - pump failure or 3.4 1 improper operation 062 AC Electrical Distribution X A3.04 - Operation of inverter 2.7 1 (e.g., precharging synchronizing light, static transfer) 063 DC Electrical Distribution X A2.01 - Grounds 2.5 1 02/04/2008 12:52:53 pm 1

PWR RO Examination Outline Printed: 02/04/2008 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 064 Emergency Diesel Generator X A2.05 - Loading the ED/G 3.1 1 064 Emergency Diesel Generator X K6.07 - Air receivers 2.7 1 073 Process Radiation Monitoring X A1.01 - Radiation levels 3.2 1 076 Service Water X K3.07 - ESF loads 3.7 1 078 Instrument Air X A4.01 - Pressure gauges 3.1 1 103 Containment X A3.01 - Containment 3.9 1 isolation K/A Category Totals: 3 2 3 3 3 2 3 3 2 3 1 Group Point Total: 28 02/04/2008 12:52:53 pm 2

PWR RO Examination Outline Printed: 02/04/2008 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 002 Reactor Coolant X K3.03 - Containment 4.2 1 011 Pressurizer Level Control X 2.4.4 - Ability to recognize 4.5 1 abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

014 Rod Position Indication X K1.01 - CRDS 3.2* 1 017 In-core Temperature Monitor X K5.01 - Temperature at which 3.1 1 cladding and fuel melt 027 Containment Iodine Removal X K2.01 - Fans 3.1* 1 028 Hydrogen Recombiner and X K6.01 - Hydrogen 2.6 1 Purge Control recombiners 033 Spent Fuel Pool Cooling X K4.01 - Maintenance of spent 2.9 1 fuel level 035 Steam Generator X A1.01 - S/G wide and narrow 3.6 1 range level during startup, shutdown, and normal operations 045 Main Turbine Generator X A3.04 - T/G trip 3.4 1 079 Station Air X A2.01 - Cross-connection 2.9 1 with IAS K/A Category Totals: 1 1 1 1 1 1 1 1 1 0 1 Group Point Total: 10 02/04/2008 1 12:52:45m

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 02/04/2008 Facility: DCPP Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.2 Knowledge of operator responsibilities during all 4.1 1 modes of plant operation.

2.1.37 Knowledge of procedures, guidelines, or limitations 4.3 1 associated with reactivity management.

Category Total: 2 Equipment Control 2.2.12 Knowledge of surveillance procedures. 3.7 1 2.2.14 Knowledge of the process for controlling equipment 3.9 1 configuration or status.

2.2.43 Knowledge of the process used to track inoperable 3.2 1 alarms.

Category Total: 3 Radiation Control 2.3.4 Knowledge of radiation exposure limits under 3.2 1 normal or emergency conditions.

2.3.13 Knowledge of radiological safety procedures 3.4 1 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.

Category Total: 2 Emergency Procedures/Plan 2.4.14 Knowledge of general guidelines for EOP usage. 3.8 1 2.4.25 Knowledge of fire protection procedures. 3.3 1 2.4.37 Knowledge of the lines of authority during 3.0 1 implementation of the emergency plan.

Category Total: 3 Generic Total: 10 12:53:00 pm 02/04/2008 12:53:07 pm 1