Text

DC-2010-01-FINAL Outlines
	ML102300238
Person / Time
Site:	Diablo Canyon
Issue date:	08/18/2010
From:	Apger G; NRC Region 4
To:	;
References
	50-275/10-301, 50-323/10-301, DC-2010-01
	Download: ML102300238 (23)
	v • d • e

The FINAL Operating Test Outlines are contained in the Final Operating Test document.

ES-401 PWR Examination Outline Form ES-401-2 Facility: Diablo Canyon Reactor Operator Date of Exam: December 2009 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

Total

1. 1 3 2 3 4 4 2 18 6 Emergency &

Abnormal 2 1 2 2 N/A 1 1 N/A 2 9 4 Plant Evolutions Tier Totals 4 4 5 5 5 4 27 10 1 3 3 3 4 2 3 2 2 2 2 2 28 5 2.

Plant 2 1 1 0 1 1 1 1 1 1 1 1 10 3 Systems Tier Totals 4 4 3 5 3 4 3 3 3 3 3 38 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 3 3 2 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.

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery / 1 000008 Pressurizer Vapor Space x AK 1.02 Knowledge of the operational implications of 3.1 39 Accident / 3 the following concepts as they apply to a Pressurizer Vapor Space Accident: Change in leak rate with change in pressure 000009 Small Break LOCA / 3 x EK 2.03 Knowledge of the interrelations between the 3.0 40 small break LOCA and the following: S/Gs 000011 Large Break LOCA / 3 x EK 3.14 Knowledge of the reasons for the following 4.1 41 responses as they apply to the Large Break LOCA: RCP tripping requirement 000015/17 RCP Malfunctions / 4 x AA1.23 Ability to operate and/or monitor the following 3.1 42 as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): RCP vibrations 000022 Loss of Rx Coolant Makeup / 2 x AA2.01 Ability to determine and interpret the following 3.2 43 as they apply to the Loss of Reactor Coolant Makeup:

Whether charging line leak exists 000025 Loss of RHR System / 4 x 2.4.8 Emergency Procedures/Plan: Knowledge of how 3.8 44 abnormal operating procedures are used in conjunction with EOPs.

000026 Loss of Component Cooling x AA2..02 Ability to determine and interpret the following 2.9 45 Water / 8 as they apply to the Loss of Component Cooling Water:

The cause of possible CCW loss 000027 Pressurizer Pressure Control System Malfunction / 3 000029 ATWS / 1 x EA1.08 Ability to operate and monitor the following as 4.5 46 they apply to a ATWS: Reactor trip switch pushbutton 000038 Steam Gen. Tube Rupture / 3 x EK3.01 Knowledge of the reasons for the following 4.1 47 responses as they apply to the SGTR: Equalizing pressure on primary and secondary sides of ruptured S/G 000040 (BW/E05; CE/E05; W/E12) x AK2.02 Knowledge of the interrelations between the 2.6 48 Steam Line Rupture - Excessive Heat Steam Line Rupture and the following: Sensors and Transfer / 4 detectors 000054 (CE/E06) Loss of Main Feedwater / 4 000055 Station Blackout / 6 x EK1.01 Knowledge of the operational implications of the 3.3 49 following concepts as they apply to the Station Blackout:

Effect of battery discharge rates on capacity 000056 Loss of Off-site Power / 6 x AK1.04 Knowledge of the operational implications of 3.1 50 the following concepts as they apply to Loss of Offsite Power: Definition of saturation conditions, implication for the systems

000057 Loss of Vital AC Inst. Bus / 6 x AK3.01 Knowledge of the reasons for the following 4.1 51 responses as they apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital ac electrical instrument bus 000058 Loss of DC Power / 6 000062 Loss of Nuclear Svc Water / 4 x AA1.02 Ability to operate and/or monitor the following 3.2 52 as they apply to the Loss of Nuclear Service Water (SWS): Loads on the SWS in the control room 000065 Loss of Instrument Air / 8 x AA2.06 Ability to determine and interpret the following 3.6 53 as they apply to the Loss of Instrument Air: When to trip reactor if instrument air pressure is decreasing W/E04 LOCA Outside Containment / 3 W/E11 Loss of Emergency Coolant x 2.1.30 Conduct of Operations: Ability to locate and 4.4 54 Recirc. / 4 operate components, including local controls BW/E04; W/E05 Inadequate Heat x EA2.1 Ability to determine and interpret the following as 3.4 55 Transfer - Loss of Secondary Heat Sink / 4 they apply to the (Loss of Secondary Heat Sink): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

000077 Generator Voltage and Electric x AA1.02 Ability to operate and/or monitor the following 3.8 56 Grid Disturbances / 6 as they apply to Generator Voltage and Electric Grid Disturbances: Turbine/generator controls K/A Category Totals: 3 2 3 4 4 2 Group Point Total: 18/6

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 x 2.1.20 Conduct of Operations: Ability to 4.6 57 interpret and execute procedure steps.

000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 x AA2.01 Ability to determine and interpret the 3.2 58 following as they apply to the Fuel Handling Incidents: ARM system indications 000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum / 4 x AA1.04 Ability to operate and/or monitor the 2.5 59 following as they apply to the Loss of Condenser Vacuum: Rod position 000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 000061 ARM System Alarms / 7 x AK3.02 Knowledge of the reasons for the 3.4 60 following responses as they apply to the Area Radiation Monitoring (ARM) System Alarms:

Guidance contained in alarm response for ARM system 000067 Plant Fire On-site / 8 000068 (BW/A06) Control Room Evac. / 8 x AK2.02 Knowledge of the interrelations between 3.7 61 the Control Room Evacuation and the following:

Reactor trip system 000069 (W/E14) Loss of CTMT Integrity / 5 000074 (W/E06&E07) Inad. Core Cooling / 4 000076 High Reactor Coolant Activity / 9 W/EO1 & E02 Rediagnosis & SI Termination / 3 x EK1.1 Knowledge of the operational 3.1 62 implications of the following concepts as they apply to the (Reactor Trip or Safety Injection/Rediagnosis): components, capacity, and function of emergency systems.

W/E13 Steam Generator Over-pressure / 4 x EK2.1 Knowledge of the interrelations between 3.0 63 the (Steam Generator Overpressure) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

W/E15 Containment Flooding / 5 x EK3.4 Knowledge of the reasons for the 2.9 64 following responses as they apply to the (Containment Flooding): 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.

W/E16 High Containment Radiation / 9 x 2.4.50 Ability to verify system alarm setpoints 4.2 65 and operate controls identified in the alarm response manual.

BW/A01 Plant Runback / 1 BW/A02&A03 Loss of NNI-X/Y / 7 BW/A04 Turbine Trip / 4 BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 BW/E03 Inadequate Subcooling Margin / 4 BW/E08; W/E03 LOCA Cooldown - Depress. / 4 BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 BW/E13&E14 EOP Rules and Enclosures CE/A11; W/E08 RCS Overcooling - PTS / 4 CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery K/A Category Point Totals: 1 2 2 1 1 2 Group Point Total: 9/4

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump x K1.04 Knowledge of the physical 2.6 1 connections and/or cause-effect relationships between the RCPS (Reactor Coolant Pump System) and the following systems: CVCS 004 Chemical and Volume x K2.03 Knowledge of bus power supplies to 3.3 2 Control the following: Charging pumps 005 Residual Heat Removal x K3.01 Knowledge of the effect that a loss or 3.9 3 malfunction of the RHRS will have on the following: RCS 006 Emergency Core Cooling x K4.13 Knowledge of ECCS design feature(s) 3.8 4 and/or interlock(s) which provide for the following: Reset of containment isolation 007 Pressurizer Relief/Quench x K4.01 Knowledge of PRTS design feature(s) 2.6 5 Tank and/or interlock(s) which provide for the following: Quench Tank Cooling 008 Component Cooling Water x A1.01 Ability to predict and/or monitor 2.8 6 changes in parameters (to prevent exceeding design limits) associated with operating the CCWS controls including: CCW flow rate 010 Pressurizer Pressure Control x x K6.03 Knowledge of the effect of a loss or 3.2 7 malfunction of the following will have on the PZR PCS: PZR sprays and heaters K5.01 Knowledge of the operational 3.5 8 implications of the following concepts as they apply to the PZR PCS: Determination of condition of fluid in PZR, using steam tables 012 Reactor Protection x A2.06 Ability to (a) predict the impacts of 4.4 9 the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of RPS signal to trip the reactor 013 Engineered Safety Features x x K3.01 Knowledge of the effect that a loss or 4.4 10 Actuation malfunction of the ESFAS will have on the following: Fuel A3.01 Ability to monitor automatic 3.7 11 operation of the ESFAS including: Input channels and logic 022 Containment Cooling x A4.05 Ability to manually operate and/or 3.8 12 monitor in the control room: Containment readings of temperature, pressure, and humidity system 025 Ice Condenser

026 Containment Spray x x K4.06 Knowledge of CSS design features 2.8 13 and/or interlock(s) which provide for the following: Iodine scavenging via the CSS 2.2.37 Ability to determine operability 3.6 14 and/or availability of safety related equipment 039 Main and Reheat Steam x x 2.1.28 Knowledge of the purpose and 4.1 15 function of major system components and controls.

K1.01 Knowledge of the physical 3.1 16 connections and/or cause-effect relationships between the MRSS and the following systems: S/G 059 Main Feedwater x A4.11 ability to manually operate and 3.1 17 monitor in the control room: Recovery from automatic feedwater isolation 061 Auxiliary/Emergency x x K6.02 Knowledge of the effect of a loss or 2.6 18 Feedwater malfunction of the following will have on the AFW components: Pumps A3.01 Ability to monitor automatic 4.1 19 operation of the AFW including: AFW startup and flow.

062 AC Electrical Distribution x A2.09 Ability to (a) predict the impacts of 2.7 20 the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Consequences of exceeding current limitations 063 DC Electrical Distribution x A1.01 Ability to predict and/or monitor 2.5 21 changes in parameters associated with operating the DC electrical system controls including: Battery capacity as it is affected by discharge rate.

064 Emergency Diesel Generator x K6.07 Knowledge of the effect of a loss or 2.7 22 malfunction of the following will have on the ED/G system: Air receivers 073 Process Radiation x K5.01 Knowledge of the operational 2.5 23 Monitoring implications as they apply to concepts as they apply to the PRM system: Radiation theory, including sources, types, units, and effects 076 Service Water x x K4.06 Knowledge of SWS design feature(s) 2.8 24 and/or interlock(s) which provide for the following: Service water train separation K2.01 Knowledge of bus power supplies to 2.7 25 the following: Service water 078 Instrument Air x x K2.02 Knowledge of bus power supplies to 3.3 26 the following: Emergency air compressor K3.01 Knowledge of the effect that a loss or malfunction of the IAS will have on the 3.1 27 following: Containment air system

103 Containment x K1.08 Knowledge of the physical 3.6 28 connections and/or cause-effect relationships between the containment system and the following systems: SIS, including action of safety injection reset K/A Category Point Totals: 3 3 3 4 2 3 2 2 2 2 2 Group Point Total: 28/5

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive x K2.02 Knowledge of bus power supplies to the 3.6 29 following: One-line diagram of power supply to trip breakers 002 Reactor Coolant x 2.4.31 Knowledge of annunciator alarms, 4.2 30 indications, or response procedures 011 Pressurizer Level Control 014 Rod Position Indication 015 Nuclear Instrumentation x A4.02 Ability to manually operate and/or 3.9 31 monitor in the control room: NIS indicators 016 Non-nuclear Instrumentation x A3.01 Ability to monitor automatic operation of 2.9 32 the NNIS, including: Automatic selection of NNIS inputs to control systems 017 In-core Temperature Monitor x A2.02 Ability to (a) predict the impacts of the 3.6 33 following malfunctions or operations on the ITM system; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: Core damage 027 Containment Iodine Removal 028 Hydrogen Recombiner x A1.01 Ability to predict and/or monitor changes 3.4 34 and Purge Control in parameter (to prevent exceeding design limits) associated with operating the HRPS controls including: Hydrogen concentration 29 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator 041 Steam Dump/Turbine x K6.03 Knowledge of the effect of a loss or 2.7 35 Bypass Control malfunction on the following will have on the SDS: Controller and positioners, including ICS, S/G, CRDS 045 Main Turbine Generator x K5.18 Knowledge of the operational 2.7 36 implications of the following concepts as they apply to the MT/B System: Purpose of low-power reactor trips (limited to 25% power) 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring x K4.02 Knowledge of ARM system design 3.2 37 feature(s) and/or interlock(s) which provide for the following: Fuel Building isolation

075 Circulating Water x K1.08 Knowledge of the physical connections 3.2 38 and/or cause-effect relationships between the circulating water system and the following systems: Emergency/essential SWS 079 Station Air 086 Fire Protection K/A Category Point Totals: 1 1 0 1 1 1 1 1 1 1 1 Group Point Total: 10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date of Exam:

Category K/A # Topic RO SRO-Only IR # IR #

2.1. 2.1.31 Ability to locate control room switches, controls, and 4.6 66 indications, and to determine that they correctly reflect the

1. desired plant lineup.

Conduct 2.1. 2.1.1 Knowledge of conduct of operations requirements. 3.8 67 of Operations 2.1.

2.1.

Subtotal 2 2.2. 2.2.6 Knowledge of the process for making changes to 3.0 68 procedures.

2. 2.2. 2.2.13 Knowledge of tagging and clearance procedures. 4.1 69 Equipment 2.2. 2.2.20 Knowledge of the process for managing troubleshooting 2.6 70 Control activities.

2.2.

Subtotal 3 2.3. 2.3.4 Knowledge of radiation exposure limits under normal or 3.2 71 emergency conditions.

3. 2.3. 2.3.11 Ability to control radiation releases. 3.8 72 Radiation 2.3. 2.3.7 Ability to comply with radiation work permit 3.5 73 Control requirements during normal or abnormal conditions.

2.3.

Subtotal 3 2.4. 2.4.3 Ability to identify post accident instrumentation. 3.7 74 2.4. 2.4.19 Knowledge of EOP layout, symbols, and icons. 3.4 75 4.

Emergency 2.4.

Procedures /

Plan 2.4.

2.4.

Subtotal 2 Tier 3 Point Total 10

ES-401 Record of Rejected K/As Form ES-401-4 RO exam Tier / Randomly Reason for Rejection Group Selected K/A Tier 2.1.39 Suppressed per Diablo Canyon as not applicable 1/Group 2 T2/G2 028 A1.02 Not a good tie in for Diablo Canyon. Would make better JPM.

Randomly selected A1.01 as a replacement.

T2/G2 072 K4.03 Similar question already sampled on this exam. Replaced with K4.02 T2/G2 075 K3.07 No connection at DC between ESFAS and Circulation Water System. Replaced with K1.08 T2/G1 006 K5.01 Could not write discriminating question due to lack of system complexity.

T2/G1 061 A3.04 No Automatic isolations.

ES-401 PWR Examination Outline Form ES-401-2 SRO exam Facility: Diablo Canyon Senior Reactor Operator Date of Exam: December 2009 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

Total

1. 1 18 3 3 6 Emergency &

Abnormal 2 N/A N/A 9 2 2 4 Plant Evolutions Tier Totals 27 5 5 10 1 28 2 3 5 2.

Plant 2 10 2 1 3 Systems Tier Totals 38 4 4 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 1 2 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).