Text

2016 Byron Nuclear Station Initial License Examination Form ES-401-2 and ES-401-3 Rev 0
	ML16116A255
Person / Time
Site:	Byron
Issue date:	03/23/2016
From:	Bielby M; Operations Branch III
To:	; Exelon Generation Co
References
	Download: ML16116A255 (10)
	v • d • e

ES-401 PWR Examination Outline FORM ES-401-2

!Facility Name:Byron 2016 Initial License Date of Exam:3/14/2016 I

RO KIA 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. Emergency 1 3 3 3 3 3 3 18 3 3 6 Abnormal 2 1 2 2 N/A 1 1 N/A 2 9 2 2 4 Plant Evolutions 5 5 Tier Totals 4 5 5 4 4 5 27 10 1 2 2 3 3 2 3 2 2 3 3 3 28 3 2 5 2.

Plant Systems 2 1 1 1 1 1 1 1 1 1 0 1 10 0 I 2 1 3 Tier Totals 3 3 4 4 3 4 3 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 2 1 2 I I I I I I Note : 1. Ensure that at least two topics from every applicable KJA category are sampled within each lier 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 KJA category sl1all 11ol be less than two) .

2. The point toti:ll for each group and tier in the proposed oullfne must match that speclfled in the table.

The final point total for each group and lier 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 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 berore selecting a second topic for any system or evolution.

5. Absent a plant*spectfic 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 porllons. respectlveiy.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7! The generic (G) KIAs In Tiers 1 and 2 shall be selected from Section 2 of the KJA 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 KIA numbers, a brief description of each topic, the topics' importance ratings (I Rs) 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 II on the left side of Column A2 ror 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 Sectlon 2 of lhe KJA cata log, and enter the KJA numbers, descriptions, IRs ,

and point tota ls(#) on Form ES-40i-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

ES-401, 21 of 33

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 #I Name I Safety Function G KIA Topic(s) IR #

1 2 3 1 2 0

39 000007 Reactor Trip - Stabilization - Recovery I 1 Actions conlained in EOP for reactor trip 4.0 1 1

0 Thermodynamics and flow characteristics of open or leaking 40 000008 Pressurizer Vapor Space Accident I 3 32 1 1 valves 000009 Small Break LOCA I 3 0 0

41 000011 Large Break LOCA I 3 Pumps 2.6 1 2

000015 RCP Malfunctions 14 1 42 RCP ammeter and lrip alarm 2.7 1 000017 RCP Malfunctions (Loss of RC Flow) 14 0 0

43 000022 Loss of Rx Coolant Makeup 12 Charging pump problems 3.2 1 2

2 HPI pump control swilch, indicators, ammeter running lights, and 44 000025 Loss of RHR System I 4 2.6 1 0 flow meter

- 0 45 !100026 Loss of Component Cooling Water I 8 Localion of a leak in the CCWS 2.9 1 1

!000027 Pressurizer Pressure Control System 0 46 Definition of saturation temperature 3.1 1 Malfunction I 3 1 0

47 P00029 ATWS / 1 Breakers, relays, and disconnects 2.9 1 6

3 48 P00038 Steam Gen . Tube Rupture I 3 Drawing SIG into the RCS, using the "feed and bleed" method 3.6 1 9

000040 Steam Line Rupture - Excessive Heat Transfer 4

0 WE12 Uncontrolled Depressurization of all Steam Generators I 4 000054 (CE/E06) Loss of Main Feedwater I 4 0

!000055 Station Blackout I 6 0

04. Knowl edge of the operalional implications of EOP warnings, 49 000056 Loss of Off-site Power I 6 38 1 20 cautions, and notes.

000057 Loss of Vital AC Inst. Bus/ 6 0 50 000058 Loss of DC Power 16

o Actions contained in EOP for loss of de power 4.0 1 2

0 The automatic actions (alignmenls) within the nuclear service 51 000062 Loss of Nuclear Svc Water I 4 water resulting from the actuation of the ES FAS 3.6 1 2

Knowledge of low power/shutdown 1mpflca ions 1n accident (e g ,

04.

52 000065 Loss of Instrument Air I 8 loss of coolant accident or loss of residual heat removal) 3.8 1 09 mlllnofinn s*~ *~le* .

0 Adherence to appropriate procedures and operation within lhe 53 W/E04 LOCA Outs ide Containment I 3 limitalions in the racihly's license and amendments 3.6 1 2

Components. and functions of conlrol and safety syslems, 0

54 W/E11 Loss of Emergency Coolant Recirc. 14 Including inslrumentatlon, signals, interlocks, railure modes, and 3.6 1 1 ................. ,Ir-. :ind mninlJ.,1 rea h1ra~

BW/E04; W/E05 Inadequate Heat Transfer - Loss of 02. Ability to determine operability and/or availability of safety relaled 55 36 1 Secondary Heat Sink I 4 37 equipment.

000077 Generator Voltage and Electric 0 56 Over*excitation 3.3 1 Grid Disturbances 16 2 KIA Category Totals: 3 3 3 3 3 3 Group Point Total : 18 ES-401, 22 of 33

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)

Q# K K K A A E/APE #I Name I Safety Function G KIA Topic(s) IR 1 2 3 1 2 000001 Continuous Rod Withdrawal/ 1 0 000003 Dropped Control Rod / 1 0

02. Knowledge of less than or equal to one hour Technical 57 [000005 Inoperable/Stuck Control Rod/ 1 3.9 1 39 Specification aclion statements for systems 58 000024 Emergency Boration / 1 01 When emergency boration is required 4.1 1 000028 Pressurizer Level Malfunction I 2 0 000032 Loss of Source Range NI I 7 0 000033 Loss of Intermediate Range NI I 7 0 000036 Fuel Handling Accident I 8 0 Thal the expected indication on main steam lines from the S/Gs 59 000037 Steam Generator Tube Leak I 3 03 3.4 1 should show increasing radiation levels 60 000051 Loss of Condenser Vacuum/ 4 01 Loss or steam dump capability upon loss of condenser vacuum 2.8 1 000059 Accidental Liquid RadWaste Rel. I 9 0 ARM system, including the normal radiation-level indications and 61 000060 Accidental Gaseous Radwaste Rel. 19 01 2.6 1 the operability status 000061 ARM System Alarms/ 7 0 000067 Plant Fire On-site I 8 0 62 000068 Control Room Evac I 8 11 Emergency borate valve controls and indicators 3.9 1 000069 Loss of CTMT Integrity I 5 1

Normal, abnormal and emergency operating procedures 63 W/E14 High Containment Pressure I 5 02 3 .2 associated with High Conlainmenl Pressure 64 000074 lnad. Core Cooling 14 06 Turbine bypass and atmospheric dump valves 3.5 W/E06 Degraded Core Cooling I 4 1 WIE07 Saturated Core Cooling I 4 000076 High Reactor Coolant Activity I 9 0 W/E01 Rediagnosis I 3 0

W/E02 SI Termination/ 3 04.

65 W/E13 Steam Generator Over-pressure/ 4 Knowledge of EOP mitigation strategies 3.7 1 06 W/E15 Containment Flooding/ 5 0 W/E16 High Containment Radiation I 9 0

\iy/603 LOCA Cooldown - Depress. I 4 0 W/E09 Natural Circulation Operations I 4 0

W/E10 Natural Circulation with Steam Voide in Vessel wl(h/wlthput RVUS. / 4 IW/E06 RCS Overcooling - PTS I 4 0 KIA Category Totals: 1 2 2 1 1 2 Group Point Total: 9 ES-401, 23 of 33

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 21Group 1 (RO)

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

1 2 3 4 5 6 1 2 3 4 0 0 2. 5; 1,2 003 Reactor Coolant Pump CCW pumps; RPS 2 2 4 3.9 0 Thermal shock: high component stress due lo rapid 3 004 Chemical and Volume Control temperature change 3.7 1 9

0 4 005 Residual Heat Removal Heat exchanger bypass flow control 3.4 1 2

0 5 006 Emergency Core Cooling HPllLPI cooling waler 3.0 1 5

04.

6 007 Pressurizer Relief/Quench Tank Knowledge of abnormal condilion procedures 4.0 1 11 0

7 008 Component Cooling Water Loads cooled by CCWS 3.4 1 1

0 8 010 Pressurizer Pressure Control PZR pressure 3.6 1 2

0 9 012 Reactor Protection RPS channels, components, and interconnections 3.3 1 1

013 Engineered Safety Features 0 0 10, 11 Sensors and detectors: RCS pressure and temperature 2.7; 4 2

!Actuation 1 1 0

12 022 Containment Cooling Chilled waler 2.9 1 4

~~*-

- 025 Ice Condenser 0 01. 3.1; Chemical additive lank level and concentration; Ability to 13, 1~ 026 Containment Spray interpret and execute procedure steps 2

5 20 4.6 0

15 039 Main and Reheat Steam MFWpumps 2.5 1 4

0 16 059 Main Feedwater Tripping of MFW pump lurbine 3.0 1 7

0 0 Emergency water source; pump failure or improper 3.6; 17,H 061 Auxiliary/Emergency Feedwater 2 7 4 operation 3.4 1

19 062 AC Electrical Distribution Uninterruptable ac power sources 3.1 1 0

0 20 .063 DC Electrical Distribution Trips 2.6 1 4

0 0 Fuel oil storage tanks; Automatic start of compressor and 3.2; 22.2: 064 Emergency Diesel Generator EDIG 2

8 1 4.1 Radialion intensity changes with source distance; 0 04. 2.5; 24,2~ 073 Process Radiation Monitoring Knowledge of annunciator alarms, indications, or response 2 2 31 orocedures, 4.2 0 0 2.8:

26, 2 076 Service Water Service water train separation: SWS pumps 2 6 1 2.9 0

27 078 Instrument Air Pressure gauges 3.1 1 1

0 28 103 Containment Containment Isolation 3.9 1 1

0 KIA Category Totals: 2 2 3 3 2 3 2 2 3 3 3 Group Point Total: 28 ES-401, Page 24 of 33

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 #I Name G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 0

29 001 Control Rod Drive One-line diagram of power supply to trip breakers 3.6 1 2

0 30 002 Reactor Coolant Containmenl 4.2 1 3

011 Pressurizer Level Control 0 0

31 014 Rod Position Indication Control rod position indica tion on con trol room panels 3.2 1 2

015 Nuclear Instrumentation 0 0

32 016 Non-nuclear Instrume ntation Separation of control and protection circuits 2.7 1 1

0 Indications of normal, natural. and interrupted circulation of 33 !017 In-core Temperature Monitor 3.6 1

-34 Kl27 Containment Iodine Removal 0

1 1 RCS High temperature in the filler system 3.0 1 Kl28 Hydrogen Recombiner and Purge 0

Control 029 Containment Purge 0 fo33 Spent Fuel Pool Cooling 0 034 Fuel Handling Equipment 0 0

35 i035 Steam Generator Automatic blowdown and sample line isolation and resel 2.6 1 3

0 36 041 Steam DumpfTurbine Bypass Control RCS 3.5 1 5

045 Main Turbine Generator 0 055 Condenser Air Removal 0 056 Condensate 0 1

37 068 Liquid Radwaste Radiation monitors 2.5 1 0

071 Waste Gas Disposal 0 072 Area Radiation Monitoring 0 075 Circulating Water 0

04. Ability to verify system alarm setpoints and operate controls 38 079 Station Air 4.2 1 50 Identified in the alarm re sponse manual 086 Fire Protection 0 KIA Category Totals: 1 1 1 1 1 1 1 1 1 0 1 Group Point Total: 10 ES-401 , Page 25 of 33

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 #I Name I Safety Function G KIA Topic(s) IR #

1 2 3 1 2 f000007 Reactor Trip - Stabilization - Recovery/ 1 0 0

84 000008 Pressurizer Vapor Space Accident I 3 PORV isolation (block valve switches and indicalors) 3.9 1

....__ 5 000009 Small Break LOCA I 3 0 0

85 000011 Large Break LOCA I 3 Consequences lo RHR of not reselting safely injection 3.7 1 2

000015 RCP Malfunctions I 4 0

000017 RCP Malfunctions (Loss of RC Flow) I 4 02.

86 000022 Loss of Rx Coolant Makeup I 2 Knowledge of limiting conditions for operations and safely limits 4.7 1 22 000025 Loss of RHR System I 4 0 000026 Loss of Component Cooling Water I 8 0 000027 Pressurizer Pressure Control System 0

Malfunction I 3 000029 ATWS I 1 0 0

87 000038 Steam Gen. Tube Rupture I 3 Shutdown margins and required boron concentralions 4.4 1 6

000040 Steam Line Rupture - Excessive Heat Transfer 14 0

WE12 Uncontrolled Depressurization of all Steam Generators I 4 04 , Knowledge of the emergency action level thresholds and 88 000054 (CE/E06) Loss of Main Feedwater I 4 4.6 1 41 classifications

- Ability 10 interpret control room indications to verify the sra1us and 02.

89 000055 Station Blackout/ 6 operation of a system. and understand how operalor actions and 4.4 1 44 rlj{Pr.ll"'""" afffir.I nlant ann .,.,.,+.cm r.onditions

~J00056 Loss of Off-site Power/ 6 0 000057 Loss of Vital AC Inst. Bus I 6 0 000058 Loss of DC Power I 6 0 000062 Loss of Nuclear Svc Water I 4 0 000065 Loss of Instrument Air I 8 0 W/E04 LOCA Outside Containment I 3 0 W/E11 Loss of Emergency Coolant Recirc. / 4 0 BW/E04; W/E05 Inadequate Heat Transfer - Loss of 0

Secondary Heat Sink I 4 000077 Generator Voltage and Electric 0

Grid Disturbances I 6 KIA Category Totals: 0 0 0 0 3 3 Group Point Total: 6 ES-401, 22 of 33

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)

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

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 0 90 01 . Ability lo perform specific system and integrated plant procedures 000003 Dropped Control Rod / 1 during all modes of plant QParalicn, 4.4 1 23 000005 Inoperable/Stuck Control Rod / 1 0 000024 Emergency Boration / 1 0 000028 Pressurizer Level Malfunction I 2 0 000032 Loss of Source Range NI I 7 0 000033 Loss of Intermediate Range NI/ 7 0 91 !000036 Fuel Handling Accident I 8 02 Occurrence of a fuel handling incident 4.1 1

!000037 Steam Generator Tube Leak I 3 0

!000051 Loss of Condenser Vacuum I 4 0

~00059 Accidental Liquid RadWaste Rel. I 9 0

~00060 Accidental Gaseous Radwaste Rel. I 9 0 000061 ARM System Alarms I 7 0 000067 Plant Fire On-site I 8 0 000068 Control Room Evac. I 8 0 000069 Loss of CTMT Integrity I 5 0

WIE14 High Containment Pressure I 5 000074 lnad . Core Cooling/ 4 W/E06 Degraded Core Cooling I 4 0 l\NIE07 Saturated Core Cooling I 4 92 000076 High Reactor Coolant Activity I 9 02 Corrective actions required for high fission product activity in RCS 3.4 1 l\NIE01 Rediagnosis I 3

>--- 1

04. AbniW to diagnose and recognize trends in an accurate and timely 93 r.'lllE02 SI Termination I 3 manner utilizing the epp(opnate control room reference material ,

4.2

,.._ 47 W/E13 Steam Generator Over-pressure/ 4 0 W/E15 Containment Flooding 15 0 W/E16 High Containment Radiation/ 9 0 W/E03 LOCA Cooldown - Depress. I 4 0 W/E09 Natural Circulation Operations I 4 0

W/E10 Natural Circulation with Steam Voide in Vessel with/without RVLIS. I 4 VV/EOB RCS Overcooling - PTS I 4 0 KIA Category Totals: 0 0 0 0 2 2 Group Point Total: 4 ES-401, 23 of 33

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 KIA Topic(s) IR #

Q# System # I Name G 1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump 0 004 Chemical and Volume Control 0

- 76 005 Residual Heat Removal 0 Failure modes for pressure, flow, pump motor amps, motor 2.9 1 1 temperalure, and lank level instrumentation 0 3.3 1 77 006 Emergency Core Cooling Effect of electric power loss on valve position 8

007 Pressurizer Relief/Quench Tank 0 008 Component Cooling Water 0 010 Pressurizer Pressure Control 0

- 012 Reactor Protection 013 Engineered Safety Features 0

- Actuation 022 Containment Cooling 0

0

- 025 Ice Condenser 0 026 Containment Spray 039. Main and Reheat Steam 0

0

04. Knowledge of how abnormal operating procedures are used 4.5 1 78 059.Main Feedwater in conjunction wilh EOPs _

08 061 Auxiliary/Emergency Feedwater 0 062 AC Electrical Distribution 0

- 063 DC Electrical Distribution 0

- 064 Emergency Diesel Generator 073 Process Radiation Monitoring 0

0

- 79 076 Service Water 0

Loss of SWS 3.7 1 1

078 Instrument Air 0 Knowledge of the parameters and logic used lo assess the 04.

80 103 Containment stalus of safely functions, such as reactivity control, core 4.6 1 21 coolina and heal removal reactor coolant svstem intenritv.

0 KIA Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 ES-401, Page 24 of 33

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 # I Name G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4

- 001 Control Rod Drive 002 Reactor Coolant 0

0 0

81 011 Pressurizer Level Control Loss of PZR level 3.9 1 3

014 Rod Position Indication 0 Effects on axial flux density of control rod alignment and 0

82 015 Nuclear Instrumentation 4

sequencing, xenon production and decay, and boron vs control 3.8 1

'°" reactivitv '"*nn**

016 Non-nuclear Instrumentation 0 017 In-core Temperature Monitor 0 027 Containment Iodine Removal 0 028 Hydrogen Recombiner and Purge 0

Control 029 Containment Purge 0 033 Spent Fuel Pool Cooling 0

02. Knowledge of the bases in Technical Specifications for limiting 83 034 Fuel Handling Equipment 4.2 1 25 conditions for operations and safely limits.

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 07S Station Air 0 086 Fire Protection 0 KIA Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total : 3 ES-401, Page 25 of 33

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3

!Facility Name:Byron 2016 Initial License Date of Exam:3/14/2016 RO :SRO-On ly I

- Q# Category KIA# Topic IR # IR #

66 2.1. 28 Knowledge of the purpose and function of major system components and controls. 4.1 1

- Ability to locale control room switches, controls, and indications, and to determine thal they correctly 67 2.1. 31 4.6 1

- 68 1. 2.1. 43 reflect lhe desired plant lineup.

Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel deplelion, etc. 4.1 1 Conduct of

- Operations 2.1 .

Abilily to evaluate plant performance and make operalional judgments based on operaling 94 2.1. 07 characteristics, reactor behavior, and instrument interpretation.

4.7 1 95 2.1. 40 Knowledge of refueling adminislrative requirements . 3.9 1 Subtotal 3 2

- 69 2.2. 02 Ability lo manipulate the console conlrols as required to operate the facility between shuldown and 4.6 1

- 70 2.2, 12 designaled power levels.

3.7 1 Knowledge of surveillance procedures.

71 2.2. 42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications 3.9 1

- 2.

Equipment 2.2.

- 96 Control or the process for controlling equipmenl configuration or status. 4.3 1 2.2. 14 Knowledge

- 97 2.2. 40 Abilily lo apply Technical Specifications for a system. 4.7 1

- Subtotal 3 2 72 2.3. 04 Knowledge of radialion exposure limils under normal or emergency conditions. 3.2 1

- Ability to use radiation monitoring systems, such as fixed radiation monilors and alarms, portable survey 73 2.3. 05 Instruments, personnel monitoring equipmenl, etc, 2.9 1 2.3.

- 3.

Radiation 2.3.

- Control 2.3. 06

- Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency 98 2.3. 14 conditions or activities . 3.8 1 Subtotal 2 1

- 74 2.4. 18 Knowledge of lhe specific bases for EOPs. 3.3 1

- 75 2.4. 39 Knowledge of RO responsibililieS in emergency plan implemenlalion . 3.9 1

- 4, Emergency 2.4.

- Procedures I Plan 2.4.

Abilily to take actions called for in the facility emergency plan, including supporting or acting as 99 2.4. 38 emergency coordinator if required .

4.4 1 100 2.4. 40 Knowledge of SRO responsibilities in emergency plan implementation. 4.5 1 Subtotal ' 2 2 Tier 3 Point Total 10 7 ES-401, Page 26 of 33