ML11145A093

2010 Byron Nuclear Station Initial License Examination Outline Submission ES-401-2 and ES-401-3 Forms

ML11145A093
Person / Time
Site:	Byron
Issue date:	09/30/2010
From:	Bielby M Operations Branch III
To:
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Download: ML11145A093 (10)

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ES-401 PWR Examination Outline FORM ES-401-2 Facility Name:Byron Date of Exam:09/27/2010 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4

• 1 3 3 3 3 3 3 18 3 3 6

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

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

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

Note: 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.

Note: 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 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.

Note: 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.

Note: 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: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

Note: 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.

Note: 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.

Note: 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, 22 of 34

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)

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

1 2 3 1 2 0

39 000007 Reactor Trip - Stabilization - Recovery / 1 Actions contained in EOP for reactor trip 4.0 1 1

0 40 000008 Pressurizer Vapor Space Accident / 3 Valves 2.7 1 1

000009 Small Break LOCA / 3 0 000011 Large Break LOCA / 3 0 1

41 000015 RCP Malfunctions / 4 RCP indicators and controls 2.8 0

1 000017 RCP Malfunctions (Loss of RC Flow) / 4 0

42 000022 Loss of Rx Coolant Makeup / 2 CVCS charging pump ammeters and running indicators 2.9 1 6

2 HPI pump control switch, indicators, ammeter running lights, and 43 000025 Loss of RHR System / 4 flow meter 2.6 1 0

0 44 000026 Loss of Component Cooling Water / 8 Effect on the CCW flow header of a loss of CCW 3.5 1 4

000027 Pressurizer Pressure Control System 0 45 Normal values for RCS pressure 3.8 1 Malfunction / 3 2 000029 ATWS / 1 0 04.

46 000038 Steam Gen. Tube Rupture / 3 Knowledge of EOP entry conditions and immediate action steps. 4.6 1 01 000040 Steam Line Rupture - Excessive Heat Transfer 0 47 Sensors and detectors 2.6

/4 2 1

WE12 Uncontrolled Depressurization of all Steam Generators / 4 0

48 000054 (CE/E06) Loss of Main Feedwater / 4 Reactor trip first-out panel indicator 3.4 1 7

0 49 000055 Station Blackout / 6 Natural circulation cooling 4.1 1 2

7 50 000056 Loss of Off-site Power / 6 Auxiliary feed pump (running) 4.1 1 7

0 Actions contained in EOP for loss of vital ac electrical instrument 51 000057 Loss of Vital AC Inst. Bus / 6 bus 4.1 1 1

000058 Loss of DC Power / 6 0

02. Ability to determine the expected plant configuration using design 52 000062 Loss of Nuclear Svc Water / 4 and configuration control documentation, such as drawings, line- 3.9 1 15 ups, tag-outs, etc.

02. Ability to obtain and interpret station electrical and mechanical 53 000065 Loss of Instrument Air / 8 drawings.

3.5 1 41 W/E04 LOCA Outside Containment / 3 0 0 Normal, abnormal and emergency operating procedures 54 W/E11 Loss of Emergency Coolant Recirc. / 4 associated with Loss of Emergency Coolant Recirculation 3.6 1 2

BW/E04; W/E05 Inadequate Heat Transfer - Loss of 0 Normal, abnormal and emergency operating procedures 55 associated with Loss of Secondary Heat Sink 3.9 1 Secondary Heat Sink / 4 2 000077 Generator Voltage and Electric 0 56 Turbine / generator controls 3.8 1 Grid Disturbances / 6 2 K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 ES-401, 23 of 34

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)

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

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 0

04. Knowledge of how abnormal operating procedures are used in 57 000003 Dropped Control Rod / 1 conjunction with EOPs.

3.8 1 08 000005 Inoperable/Stuck Control Rod / 1 0 58 000024 Emergency Boration / 1 01 When emergency boration is required 4.1 1 000028 Pressurizer Level Malfunction / 2 0 000032 Loss of Source Range NI / 7 0 000033 Loss of Intermediate Range NI / 7 0 59 000036 Fuel Handling Accident / 8 02 Occurrence of a fuel handling incident 3.4 1 000037 Steam Generator Tube Leak / 3 0 60 000051 Loss of Condenser Vacuum / 4 01 Loss of steam dump capability upon loss of condenser vacuum 2.8 1 000059 Accidental Liquid RadWaste Rel. / 9 0 000060 Accidental Gaseous Radwaste Rel. / 9 0 61 000061 ARM System Alarms / 7 01 Detectors at each ARM system location 2.5 1 62 000067 Plant Fire On-site / 8 09 Plant fire zone panel (including detector location) 3.0 1 000068 Control Room Evac. / 8 0 000069 Loss of CTMT Integrity / 5 1

Annunciators and conditions indicating signals, and remedial 63 W/E14 High Containment Pressure / 5 03 actions associated with the High Containment Pressure 3.3 000074 Inad. Core Cooling / 4 W/E06 Degraded Core Cooling / 4 0 W/E07 Saturated Core Cooling / 4 000076 High Reactor Coolant Activity / 9 0 Facility conditions and selection of appropriate procedures during 64 W/E01 Rediagnosis / 3 01 abnormal and emergency operations 3.2 1

W/E02 SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 0 W/E15 Containment Flooding / 5 0 W/E16 High Containment Radiation / 9 0 W/E03 LOCA Cooldown - Depress. / 4 0 Components, and functions of control and safety systems, 65 W/E09 Natural Circulation Operations / 4 01 including instrumentation, signals, interlocks, failure modes, and 3.2 automatic and manual features 1 W/E10 Natural Circulation with Steam Voide in Vessel with/without RVLIS. / 4 W/E08 RCS Overcooling - PTS / 4 0 K/A Category Totals: 1 2 2 1 2 1 Group Point Total: 9 ES-401, 24 of 34

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

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

1 2 3 4 5 6 1 2 3 4

04. Containment isolation valves affecting RCP operation; 2.8; 1,2 003 Reactor Coolant Pump 04 Ability to verify that the alarms are consistent with the plant 2 46 conditions. 4.2 1 Interlock between letdown isolation valve and flow control 3 004 Chemical and Volume Control valve 3.2 1 3

0 4 005 Residual Heat Removal Nil ductility transition temperature (brittle fracture) 2.6 1 1

0 5 006 Emergency Core Cooling BIT/borated water sources 3.4 1 1

0 6 007 Pressurizer Relief/Quench Tank Bubble formation in PZR 2.6 1 6

0 7 008 Component Cooling Water CCW pump, including emergency backup 3.0 1 2

0 8 010 Pressurizer Pressure Control RPS 4.0 1 2

0 0 2.9; 9,10 012 Reactor Protection Trip setpoint adjustment; Trip logic 2 1 6 3.7 013 Engineered Safety Features 0 0 3.4; 11,12 Main steam pressure; Operation of actuated equipment 2 Actuation 5 2 4.1 0 0 Loss of CCS pump; Containment readings of temperature, 2.8; 13,14 022 Containment Cooling pressure, and humidity system 2

6 5 3.8 025 Ice Condenser 0 0 04. ECCS; Knowledge of annunciator alarms, indications, or 4.2; 15,16 026 Containment Spray response procedures.

2 1 31 4.2 0

17 039 Main and Reheat Steam Condenser steam dump 3.1 1 6

0 18 059 Main Feedwater S/Gs 3.5 1 3

0 19 061 Auxiliary/Emergency Feedwater Feed line voiding and water hammer 2.7 1 5

0 01. Major system loads; Ability to interpret and execute 3.3; 20,21 062 AC Electrical Distribution procedure steps.

2 1 20 4.6 0 0 3.7; 22,23 063 DC Electrical Distribution ED/G; Battery voltage indicator 2 1 2 2.8 0

24 064 Emergency Diesel Generator Diesel fuel oil supply system 3.6 1 3

0 25 073 Process Radiation Monitoring Release termination when radiation exceeds setpoint 4.0 1 1

0 26 076 Service Water Emergency heat loads 3.7 1 2

0 27 078 Instrument Air Cross-over to other air systems 3.2 1 2

0 28 103 Containment Containment pressure, temperature, and humidity 3.7 1 1

0 K/A Category Totals: 3 2 3 3 2 2 3 2 3 2 3 Group Point Total: 28 ES-401, Page 25 of 34

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

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

1 2 3 4 5 6 1 2 3 4 0

29 001 Control Rod Drive 1 Reactor power 4.1 1 002 Reactor Coolant 0 0

30 011 Pressurizer Level Control 6 Indicated charging flow: seal flow plus actual charging flow 2.9 1 02.

31 014 Rod Position Indication Ability to apply Technical Specifications for a system. 3.4 1 40 015 Nuclear Instrumentation 0 0

32 016 Non-nuclear Instrumentation 1 Reading of NNIS channel values outside control room 2.8 1 017 In-core Temperature Monitor 0 0

33 027 Containment Iodine Removal 2 Remote operation and handling of iodine filters 2.8 1 028 Hydrogen Recombiner and Purge 0

Control 029 Containment Purge 0 0

34 033 Spent Fuel Pool Cooling 2 Loss of SFPCS 2.7 1 034 Fuel Handling Equipment 0 0

35 035 Steam Generator 2 S/G pressure 3.5 1 041 Steam Dump/Turbine Bypass Control 0 045 Main Turbine Generator 0 055 Condenser Air Removal 0 056 Condensate 0 1

36 068 Liquid Radwaste 0 Radiation monitors 2.5 1 0

37 071 Waste Gas Disposal 6 ARM and PRM systems 3.1 1 072 Area Radiation Monitoring 0 0

38 075 Circulating Water 3 Emergency/essential SWS pumps 2.6 1 079 Station Air 0 086 Fire Protection 0 K/A Category Totals: 1 1 0 1 1 1 1 1 1 1 1 Group Point Total: 10 ES-401, Page 26 of 34

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 (SRO)

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

1 2 3 1 2 000007 Reactor Trip - Stabilization - Recovery / 1 0 000008 Pressurizer Vapor Space Accident / 3 0 2

84 000009 Small Break LOCA / 3 Reactor trip setpoints 4.1 1 5

0 85 000011 Large Break LOCA / 3 Consequences to RHR of not resetting safety injection 3.7 1 2

000015 RCP Malfunctions / 4 0

000017 RCP Malfunctions (Loss of RC Flow) / 4 000022 Loss of Rx Coolant Makeup / 2 0 000025 Loss of RHR System / 4 0 000026 Loss of Component Cooling Water / 8 0 000027 Pressurizer Pressure Control System 0

Malfunction / 3

04. Knowledge of the parameters and logic used to assess the status 86 000029 ATWS / 1 of safety functions, such as reactivity control, core cooling and 4.6 1 21 heat removal, reactor coolant system integrity, containment 000038 Steam Gen. Tube Rupture / 3 0 000040 Steam Line Rupture - Excessive Heat Transfer

/4 1

WE12 Uncontrolled Depressurization of all Steam 04. Knowledge of the emergency action level thresholds and 87 classifications.

4.6 Generators / 4 41 000054 (CE/E06) Loss of Main Feedwater / 4 0 000055 Station Blackout / 6 0 000056 Loss of Off-site Power / 6 0 000057 Loss of Vital AC Inst. Bus / 6 0 04.

88 000058 Loss of DC Power / 6 Knowledge of operator response to loss of all annunciators. 4.0 1 32 000062 Loss of Nuclear Svc Water / 4 0 000065 Loss of Instrument Air / 8 0 W/E04 LOCA Outside Containment / 3 0 W/E11 Loss of Emergency Coolant Recirc. / 4 0 BW/E04; W/E05 Inadequate Heat Transfer - Loss of 0 Adherence to appropriate procedures and operation within the 89 limitations in the facility's license and amendments 4.3 1 Secondary Heat Sink / 4 2 000077 Generator Voltage and Electric 0

Grid Disturbances / 6 K/A Category Totals: 0 0 0 0 3 3 Group Point Total: 6 ES-401, 23 of 34

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 (SRO)

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

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 0 000003 Dropped Control Rod / 1 0 Stuck or inoperable rod from in-core and ex-core NIS, in-core or 90 000005 Inoperable/Stuck Control Rod / 1 01 loop temperature measurements 4.1 1 000024 Emergency Boration / 1 0 91 000028 Pressurizer Level Malfunction / 2 05 Flow control valve isolation valve indicator 2.7 1 000032 Loss of Source Range NI / 7 0 000033 Loss of Intermediate Range NI / 7 0 000036 Fuel Handling Accident / 8 0 000037 Steam Generator Tube Leak / 3 0 000051 Loss of Condenser Vacuum / 4 0 000059 Accidental Liquid RadWaste Rel. / 9 0 000060 Accidental Gaseous Radwaste Rel. / 9 0 000061 ARM System Alarms / 7 0 000067 Plant Fire On-site / 8 0 000068 Control Room Evac. / 8 0 000069 Loss of CTMT Integrity / 5 0

W/E14 High Containment Pressure / 5 000074 Inad. Core Cooling / 4 W/E06 Degraded Core Cooling / 4 0 W/E07 Saturated Core Cooling / 4 000076 High Reactor Coolant Activity / 9 0 W/E01 Rediagnosis / 3 0

W/E02 SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 0 W/E15 Containment Flooding / 5 0 W/E16 High Containment Radiation / 9 0

01. Ability to interpret reference materials, such as graphs, curves, 92 W/E03 LOCA Cooldown - Depress. / 4 tables, etc.

4.2 1 25 W/E09 Natural Circulation Operations / 4 0

W/E10 Natural Circulation with Steam Voide in Vessel with/without RVLIS. / 4

01. Ability to evaluate plant performance and make operational 93 W/E08 RCS Overcooling - PTS / 4 judgments based on operating characteristics, reactor behavior, 4.7 1 07 and instrument interpretation.

K/A Category Totals: 0 0 0 0 2 2 Group Point Total: 4 ES-401, 24 of 34

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

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

1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump 0

03. Ability to use radiation monitoring systems, such as fixed 76 004 Chemical and Volume Control radiation monitors and alarms, portable survey 2.9 1 05 instruments, personnel monitoring equipment, etc.

005 Residual Heat Removal 0 006 Emergency Core Cooling 0

04. Knowledge of the bases for prioritizing emergency 77 007 Pressurizer Relief/Quench Tank procedure implementation during emergency operations.

4.4 1 23 008 Component Cooling Water 0 010 Pressurizer Pressure Control 0 012 Reactor Protection 0 013 Engineered Safety Features 0

Actuation 022 Containment Cooling 0 025 Ice Condenser 0 026 Containment Spray 0 039 Main and Reheat Steam 0 059 Main Feedwater 0 0

78 061 Auxiliary/Emergency Feedwater Automatic control malfunction 3.4 1 5

062 AC Electrical Distribution 0 063 DC Electrical Distribution 0 064 Emergency Diesel Generator 0 0

79 073 Process Radiation Monitoring Erratic or failed power supply 2.9 1 1

0 80 076 Service Water Loss of SWS 3.7 1 1

078 Instrument Air 0 103 Containment 0 0

K/A Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 ES-401, Page 25 of 34

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

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

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive 0 0

81 002 Reactor Coolant 2 Loss of coolant pressure 4.4 1 011 Pressurizer Level Control 0 014 Rod Position Indication 0 015 Nuclear Instrumentation 0 016 Non-nuclear Instrumentation 0 017 In-core Temperature Monitor 0 027 Containment Iodine Removal 0 028 Hydrogen Recombiner and Purge 0

Control

01. Knowledge of procedures and limitations involved in core 82 029 Containment Purge 4.1 1 36 alterations.

033 Spent Fuel Pool Cooling 0 0

83 034 Fuel Handling Equipment 2 Water level in the refueling canal 3.7 1 035 Steam Generator 0 041 Steam Dump/Turbine Bypass Control 0 045 Main Turbine Generator 0 055 Condenser Air Removal 0 056 Condensate 0 068 Liquid Radwaste 0 071 Waste Gas Disposal 0 072 Area Radiation Monitoring 0 075 Circulating Water 0 079 Station Air 0 086 Fire Protection 0 K/A Category Totals: 0 0 0 0 0 0 1 1 0 0 1 Group Point Total: 3 ES-401, Page 26 of 34

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility Name:Byron Date of Exam:09/27/2010 RO SRO-Only Category K/A # Topic Q# IR # IR #

Knowledge of administrative requirements for temporary management directives, such as standing 66 2.1. 15 orders, night orders, operations memos, etc. 2.7 1 Knowledge of RO duties in the control room during fuel handling such as responding to alarms from the 67 2.1. 44 fuel handling area, communication with the fuel storage facility, systems operated from the control room 3.9 1 in support of fueling operations, and supporting instrumentation.

68 1. 2.1. 02 Knowledge of operator responsibilities during all modes of plant operation. 4.1 1 Conduct of 94 Operations 2.1. 40 Knowledge of refueling administrative requirements. 3.9 1 95 2.1. 42 Knowledge of new and spent fuel movement procedures. 3.4 1 2.1.

Subtotal 3 2 69 2.2. 13 Knowledge of tagging and clearance procedures. 4.1 1 70 2.2. 42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications. 3.9 1 Ability to interpret control room indications to verify the status and operation of a system, and 71 2.2. 44 understand how operator actions and directives affect plant and system conditions. 4.2 1 2.

Equipment 2.2.

Control 96 2.2. 05 Knowledge of the process for making design or operating changes to the facility. 3.2 1 2.2.

Subtotal 3 1 2.3.

Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment 72 2.3. 12 entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, 3.2 1 etc.

Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or 73 2.3. 14 emergency conditions or activities. 3.4 1 3.

Radiation 2.3.

Control 97 2.3. 11 Ability to control radiation releases. 4.3 1 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable 98 2.3. 15 survey instruments, personnel monitoring equipment, etc. 3.1 1 Subtotal 2 2 Knowledge of EOP implementation hierarchy and coordination with other support procedures or 74 2.4. 16 guidelines such as, operating procedures, abnormal operating procedures, and severe accident 3.5 1 management guidelines.

75 2.4. 39 Knowledge of RO responsibilities in emergency plan implementation. 3.9 1

4. 2.4.

Emergency 99 Procedures / 2.4. 22 Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations. 4.4 1 Plan 100 2.4. 50 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 4.0 1 2.4.

Subtotal 2 2 Tier 3 Point Total 10 7