ML16116A255

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

Q#

E/APE #I Name I Safety Function K

K K

A A

G KIA Topic(s)

IR 1

2 3

1 2

39 000007 Reactor Trip - Stabilization - Recovery I 1 0

1 Actions conlained in EOP for reactor trip 4.0 1

40 000008 Pressurizer Vapor Space Accident I 3 0

Thermodynamics and flow characteristics of open or leaking 32 1

1 valves 000009 Small Break LOCA I 3 0

41 000011 Large Break LOCA I 3 0

2.6 1

2 Pumps 42 000015 RCP Malfunctions 14 1

RCP ammeter and lrip alarm 2.7 1

000017 RCP Malfunctions (Loss of RC Flow) 14 0

43 000022 Loss of Rx Coolant Makeup 12 0

Charging pump problems 3.2 1

2 44 000025 Loss of RHR System I 4 2

HPI pump control swilch, indicators, ammeter running lights, and 2.6 1

0 flow meter 45 !100026 Loss of Component Cooling Water I 8 0

Localion of a leak in the CCWS 2.9 1

1 46 !000027 Pressurizer Pressure Control System 0

3.1 1

Malfunction I 3 1

Definition of saturation temperature 47 P00029 ATWS / 1 0

6 Breakers, relays, and disconnects 2.9 1

48 P00038 Steam Gen. Tube Rupture I 3 3

9 Drawing SIG into the RCS, using the "feed and bleed" method 3.6 1

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

49 000056 Loss of Off-site Power I 6

04. Knowledge of the operalional implications of EOP warnings, 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 51 000062 Loss of Nuclear Svc Water I 4 0

The automatic actions (alignmenls) within the nuclear service 3.6 1

2 water resulting from the actuation of the ES FAS

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

52 000065 Loss of Instrument Air I 8 09 loss of coolant accident or loss of residual heat removal) 3.8 1

mlllnofinn s*~ *~le*.

53 W/E04 LOCA Outside Containment I 3 0

Adherence to appropriate procedures and operation within lhe 3.6 1

2 limitalions in the racihly's license and amendments 0

Components. and functions of conlrol and safety syslems, 54 W/E11 Loss of Emergency Coolant Recirc. 14 1

Including inslrumentatlon, signals, interlocks, railure modes, and 3.6 1

.................,Ir-. :ind mninlJ.,1 rea h1ra~

55 BW/E04; W/E05 Inadequate Heat Transfer - Loss of

02. Ability to determine operability and/or availability of safety relaled 36 1

Secondary Heat Sink I 4 37 equipment.

56 000077 Generator Voltage and Electric 0

Over*excitation 3.3 1

Grid Disturbances 16 2

KIA Category Totals:

3 3

3 3 Group Point Total:

18 ES-401, 22 of 33

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

Q#

E/APE #I Name I Safety Function K

K K

A A

G KIA Topic(s)

IR 1

2 3

1 2

000001 Continuous Rod Withdrawal/ 1 0

000003 Dropped Control Rod / 1 0

57 [000005 Inoperable/Stuck Control Rod/ 1

02. Knowledge of less than or equal to one hour Technical 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

59 000037 Steam Generator Tube Leak I 3 03 Thal the expected indication on main steam lines from the S/Gs 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

61 000060 Accidental Gaseous Radwaste Rel. 19 01 ARM system, including the normal radiation-level indications and 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

63 W/E14 High Containment Pressure I 5 02 Normal, abnormal and emergency operating procedures 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 65 W/E13 Steam Generator Over-pressure/ 4

04.

06 Knowledge of EOP mitigation strategies 3.7 1

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 W/E10 Natural Circulation with Steam Voide in 0

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

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

Q# System #I Name K K K K K K A A A A G

KIA Topic(s)

IR 1

2 3

4 5

6 1 2 3

4 1,2 003 Reactor Coolant Pump 0

0 CCW pumps; RPS 2.5; 2

2 4

3.9 3

004 Chemical and Volume Control 0

Thermal shock: high component stress due lo rapid 3.7 1

9 temperature change 4

005 Residual Heat Removal 0

Heat exchanger bypass flow control 3.4 1

2 5

006 Emergency Core Cooling 0

HPllLPI cooling waler 3.0 1

5 6

007 Pressurizer Relief/Quench Tank

04. Knowledge of abnormal condilion procedures 4.0 1

11 7

008 Component Cooling Water 0

Loads cooled by CCWS 3.4 1

1 8

010 Pressurizer Pressure Control 0

2 PZR pressure 3.6 1

9 012 Reactor Protection 0

RPS channels, components, and interconnections 3.3 1

1 10, 11 013 Engineered Safety Features 0

0 Sensors and detectors: RCS pressure and temperature 2.7; 4 2

!Actuation 1

1 12 022 Containment Cooling 0

4 Chilled waler 2.9 1

025 Ice Condenser

~~*-

13, 1~ 026 Containment Spray 0

01. Chemical additive lank level and concentration; Ability to 3.1; 2

5 20 interpret and execute procedure steps 4.6

-15 039 Main and Reheat Steam 0

MFWpumps 2.5 1

4 16 059 Main Feedwater 0

Tripping of MFW pump lurbine 3.0 1

7 17,H 061 Auxiliary/Emergency Feedwater 0

0 Emergency water source; pump failure or improper 3.6; 2

7 4

operation 3.4 19 062 AC Electrical Distribution 1

0 Uninterruptable ac power sources 3.1 1

20.063 DC Electrical Distribution 0

Trips 2.6 1

4 22.2: 064 Emergency Diesel Generator 0

0 Fuel oil storage tanks; Automatic start of compressor and 3.2; 2

8 1

EDIG 4.1 0

04. Radialion intensity changes with source distance; 2.5; 24,2~ 073 Process Radiation Monitoring 2

31 Knowledge of annunciator alarms, indications, or response 4.2 2

orocedures, 26, 2 076 Service Water 0

0 Service water train separation: SWS pumps 2.8:

2 6

1 2.9 27 078 Instrument Air 0

Pressure gauges 3.1 1

1 28 103 Containment 0

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

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

Q# System #I Name K

K K

K A

A A

A G

KIA Topic(s)

IR 1

2 3

4 5

6 1

2 3

4 29 001 Control Rod Drive 0

2 One-line diagram of power supply to trip breakers 3.6 1

30 002 Reactor Coolant 0

3 Containmenl 4.2 1

011 Pressurizer Level Control 0

31 014 Rod Position Indication 0

2 Control rod position indication on control room panels 3.2 1

015 Nuclear Instrumentation 0

32 016 Non-nuclear Instrumentation 0

1 Separation of control and protection circuits 2.7 1

33

!017 In-core Temperature Monitor 0

Indications of normal, natural. and interrupted circulation of 3.6 1

1 RCS 34 Kl27 Containment Iodine Removal 0

1 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

35 i035 Steam Generator 0

3 Automatic blowdown and sample line isolation and resel 2.6 1

36 041 Steam DumpfTurbine Bypass Control 0

5 RCS 3.5 1

045 Main Turbine Generator 0

055 Condenser Air Removal 0

056 Condensate 0

37 068 Liquid Radwaste 1

0 Radiation monitors 2.5 1

071 Waste Gas Disposal 0

072 Area Radiation Monitoring 0

075 Circulating Water 0

38 079 Station Air

04. Ability to verify system alarm setpoints and operate controls 4.2 1

50 Identified in the alarm response manual 086 Fire Protection 0

KIA Category Totals:

1 1

1 0

1 Group Point Total:

10 ES-401, Page 25 of 33

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

Q#

E/APE #I Name I Safety Function K

K K

A A

G KIA Topic(s)

IR 1

2 3

1 2

f000007 Reactor Trip - Stabilization - Recovery/ 1 0

84 000008 Pressurizer Vapor Space Accident I 3 0

PORV isolation (block valve switches and indicalors) 3.9 1

5 000009 Small Break LOCA I 3 0

85 000011 Large Break LOCA I 3 0

2 Consequences lo RHR of not reselting safely injection 3.7 1

000015 RCP Malfunctions I 4 0

000017 RCP Malfunctions (Loss of RC Flow) I 4 86 000022 Loss of Rx Coolant Makeup I 2

02.

22 Knowledge of limiting conditions for operations and safely limits 4.7 1

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 A TWS I 1 0

87 000038 Steam Gen. Tube Rupture I 3 0

6 Shutdown margins and required boron concentralions 4.4 1

000040 Steam Line Rupture - Excessive Heat Transfer 14 0

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

41 classifications

02. Ability 10 interpret control room indications to verify the sra1us and 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 Grid Disturbances I 6 0

KIA Category Totals:

0 0

3 3

Group Point Total:

6 ES-401, 22 of 33

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

Q#

E/APE #I Name I Safety Function K

K K

A A

G KIA Topic(s)

IR 1

2 3

1 2

000001 Continuous Rod Withdrawal / 1 0

90 000003 Dropped Control Rod / 1 01. Ability lo perform specific system and integrated plant procedures 4.4 1

23 during all modes of plant QParalicn, 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

93 r.'lllE02 SI Termination I 3

04. AbniW to diagnose and recognize trends in an accurate and timely 4.2 47 manner utilizing the epp(opnate control room reference material, 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 W/E10 Natural Circulation with Steam Voide in 0

Vessel with/without RVLIS. I 4 VV/EOB RCS Overcooling - PTS I 4 0

KIA Category Totals:

0 0

2 2 Group Point Total:

4 ES-401, 23 of 33

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

Q# System # I Name K K K K K K A A A A G

KIA Topic(s)

IR 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 77 006 Emergency Core Cooling 0

8 Effect of electric power loss on valve position 3.3 1

007 Pressurizer Relief/Quench Tank 0

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

78 059.Main Feedwater

04. Knowledge of how abnormal operating procedures are used 4.5 1

08 in conjunction wilh EOPs_

061 Auxiliary/Emergency Feedwater 0

062 AC Electrical Distribution 0

063 DC Electrical Distribution 0

064 Emergency Diesel Generator 0

073 Process Radiation Monitoring 0

79 076 Service Water 0

Loss of SWS 3.7 1

1 078 Instrument Air 0

04. Knowledge of the parameters and logic used lo assess the 80 103 Containment 21 stalus of safely functions, such as reactivity control, core 4.6 1

coolina and heal removal reactor coolant svstem intenritv.

0 KIA Category Totals:

0 0

0 3

0 0

2 Group Point Total:

5 ES-401, Page 24 of 33

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

Q# System # I Name K

K K

K A

A A

A G

KIA Topic(s)

IR 1

2 3

4 5

6 1

2 3

4 001 Control Rod Drive 0

002 Reactor Coolant 0

81 011 Pressurizer Level Control 0

Loss of PZR level 3.9 1

3 014 Rod Position Indication 0

0 Effects on axial flux density of control rod alignment and 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

83 034 Fuel Handling Equipment

02. Knowledge of the bases in Technical Specifications for limiting 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 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 I

Category KIA#

Topic RO

SRO-Only Q#

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

4.1 1

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

reflect lhe desired plant lineup.

-68 2.1. 43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant 4.1 1

1.

system temperature, secondary plant, fuel deplelion, etc.

Conduct of Operations 2.1.

-94 2.1. 07 Abilily to evaluate plant performance and make operalional judgments based on operaling 4.7 1

characteristics, reactor behavior, and instrument interpretation.

-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

designaled power levels.

70 2.2, 12 Knowledge of surveillance procedures.

3.7 1

71

2.

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

Equipment 2.2.

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

4.3 1

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

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

Instruments, personnel monitoring equipmenl, etc,

3.

2.3.

Radiation 2.3.

Control 2.3. 06 98 2.3. 14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency 3.8 1

conditions or activities.

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, 2.4.

Emergency Procedures I 2.4.

Plan 99 2.4. 38 Abilily to take actions called for in the facility emergency plan, including supporting or acting as 4.4 1

emergency coordinator if required.

-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

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 A

A A

A G

1 2

3 4

5 6

1 2

3 4

Total A2 G*

Total

1. Emergency 1

3 3

18 3

3 6

Abnormal 2

1 2

2 N/A 1

1 N/A 2

9 2

2 4

Plant Evolutions Tier Totals 4

5 5

4 4

5 27 5

5 10 1

2 2

3 3

2 3

2 2

3 3

3 28 3

2 5

2.

2 1

1 1

Plant Systems 1

1 0

1 10 0 I 2

1 3

Tier Totals 3

3 4

4 3

3 4

38 5

3 8

1 2

3 4

I 1

I 2

I 3

I 4

I I

3. Generic Knowledge and Abilities 10 7

Categories 3

3 2

2 2

2 1

2 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 catalog, and enter the KJA numbers, descriptions, IRs, and point totals(#) on Form ES-40i-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

ES-401, 21 of 33

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

Q#

E/APE #I Name I Safety Function K

K K

A A

G KIA Topic(s)

IR 1

2 3

1 2

39 000007 Reactor Trip - Stabilization - Recovery I 1 0

1 Actions conlained in EOP for reactor trip 4.0 1

40 000008 Pressurizer Vapor Space Accident I 3 0

Thermodynamics and flow characteristics of open or leaking 32 1

1 valves 000009 Small Break LOCA I 3 0

41 000011 Large Break LOCA I 3 0

2.6 1

2 Pumps 42 000015 RCP Malfunctions 14 1

RCP ammeter and lrip alarm 2.7 1

000017 RCP Malfunctions (Loss of RC Flow) 14 0

43 000022 Loss of Rx Coolant Makeup 12 0

Charging pump problems 3.2 1

2 44 000025 Loss of RHR System I 4 2

HPI pump control swilch, indicators, ammeter running lights, and 2.6 1

0 flow meter 45 !100026 Loss of Component Cooling Water I 8 0

Localion of a leak in the CCWS 2.9 1

1 46 !000027 Pressurizer Pressure Control System 0

3.1 1

Malfunction I 3 1

Definition of saturation temperature 47 P00029 ATWS / 1 0

6 Breakers, relays, and disconnects 2.9 1

48 P00038 Steam Gen. Tube Rupture I 3 3

9 Drawing SIG into the RCS, using the "feed and bleed" method 3.6 1

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

49 000056 Loss of Off-site Power I 6

04. Knowledge of the operalional implications of EOP warnings, 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 51 000062 Loss of Nuclear Svc Water I 4 0

The automatic actions (alignmenls) within the nuclear service 3.6 1

2 water resulting from the actuation of the ES FAS

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

52 000065 Loss of Instrument Air I 8 09 loss of coolant accident or loss of residual heat removal) 3.8 1

mlllnofinn s*~ *~le*.

53 W/E04 LOCA Outside Containment I 3 0

Adherence to appropriate procedures and operation within lhe 3.6 1

2 limitalions in the racihly's license and amendments 0

Components. and functions of conlrol and safety syslems, 54 W/E11 Loss of Emergency Coolant Recirc. 14 1

Including inslrumentatlon, signals, interlocks, railure modes, and 3.6 1

.................,Ir-. :ind mninlJ.,1 rea h1ra~

55 BW/E04; W/E05 Inadequate Heat Transfer - Loss of

02. Ability to determine operability and/or availability of safety relaled 36 1

Secondary Heat Sink I 4 37 equipment.

56 000077 Generator Voltage and Electric 0

Over*excitation 3.3 1

Grid Disturbances 16 2

KIA Category Totals:

3 3

3 3 Group Point Total:

18 ES-401, 22 of 33

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

Q#

E/APE #I Name I Safety Function K

K K

A A

G KIA Topic(s)

IR 1

2 3

1 2

000001 Continuous Rod Withdrawal/ 1 0

000003 Dropped Control Rod / 1 0

57 [000005 Inoperable/Stuck Control Rod/ 1

02. Knowledge of less than or equal to one hour Technical 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

59 000037 Steam Generator Tube Leak I 3 03 Thal the expected indication on main steam lines from the S/Gs 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

61 000060 Accidental Gaseous Radwaste Rel. 19 01 ARM system, including the normal radiation-level indications and 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

63 W/E14 High Containment Pressure I 5 02 Normal, abnormal and emergency operating procedures 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 65 W/E13 Steam Generator Over-pressure/ 4

04.

06 Knowledge of EOP mitigation strategies 3.7 1

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 W/E10 Natural Circulation with Steam Voide in 0

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

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

Q# System #I Name K K K K K K A A A A G

KIA Topic(s)

IR 1

2 3

4 5

6 1 2 3

4 1,2 003 Reactor Coolant Pump 0

0 CCW pumps; RPS 2.5; 2

2 4

3.9 3

004 Chemical and Volume Control 0

Thermal shock: high component stress due lo rapid 3.7 1

9 temperature change 4

005 Residual Heat Removal 0

Heat exchanger bypass flow control 3.4 1

2 5

006 Emergency Core Cooling 0

HPllLPI cooling waler 3.0 1

5 6

007 Pressurizer Relief/Quench Tank

04. Knowledge of abnormal condilion procedures 4.0 1

11 7

008 Component Cooling Water 0

Loads cooled by CCWS 3.4 1

1 8

010 Pressurizer Pressure Control 0

2 PZR pressure 3.6 1

9 012 Reactor Protection 0

RPS channels, components, and interconnections 3.3 1

1 10, 11 013 Engineered Safety Features 0

0 Sensors and detectors: RCS pressure and temperature 2.7; 4 2

!Actuation 1

1 12 022 Containment Cooling 0

4 Chilled waler 2.9 1

025 Ice Condenser

~~*-

13, 1~ 026 Containment Spray 0

01. Chemical additive lank level and concentration; Ability to 3.1; 2

5 20 interpret and execute procedure steps 4.6

-15 039 Main and Reheat Steam 0

MFWpumps 2.5 1

4 16 059 Main Feedwater 0

Tripping of MFW pump lurbine 3.0 1

7 17,H 061 Auxiliary/Emergency Feedwater 0

0 Emergency water source; pump failure or improper 3.6; 2

7 4

operation 3.4 19 062 AC Electrical Distribution 1

0 Uninterruptable ac power sources 3.1 1

20.063 DC Electrical Distribution 0

Trips 2.6 1

4 22.2: 064 Emergency Diesel Generator 0

0 Fuel oil storage tanks; Automatic start of compressor and 3.2; 2

8 1

EDIG 4.1 0

04. Radialion intensity changes with source distance; 2.5; 24,2~ 073 Process Radiation Monitoring 2

31 Knowledge of annunciator alarms, indications, or response 4.2 2

orocedures, 26, 2 076 Service Water 0

0 Service water train separation: SWS pumps 2.8:

2 6

1 2.9 27 078 Instrument Air 0

Pressure gauges 3.1 1

1 28 103 Containment 0

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

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

Q# System #I Name K

K K

K A

A A

A G

KIA Topic(s)

IR 1

2 3

4 5

6 1

2 3

4 29 001 Control Rod Drive 0

2 One-line diagram of power supply to trip breakers 3.6 1

30 002 Reactor Coolant 0

3 Containmenl 4.2 1

011 Pressurizer Level Control 0

31 014 Rod Position Indication 0

2 Control rod position indication on control room panels 3.2 1

015 Nuclear Instrumentation 0

32 016 Non-nuclear Instrumentation 0

1 Separation of control and protection circuits 2.7 1

33

!017 In-core Temperature Monitor 0

Indications of normal, natural. and interrupted circulation of 3.6 1

1 RCS 34 Kl27 Containment Iodine Removal 0

1 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

35 i035 Steam Generator 0

3 Automatic blowdown and sample line isolation and resel 2.6 1

36 041 Steam DumpfTurbine Bypass Control 0

5 RCS 3.5 1

045 Main Turbine Generator 0

055 Condenser Air Removal 0

056 Condensate 0

37 068 Liquid Radwaste 1

0 Radiation monitors 2.5 1

071 Waste Gas Disposal 0

072 Area Radiation Monitoring 0

075 Circulating Water 0

38 079 Station Air

04. Ability to verify system alarm setpoints and operate controls 4.2 1

50 Identified in the alarm response manual 086 Fire Protection 0

KIA Category Totals:

1 1

1 0

1 Group Point Total:

10 ES-401, Page 25 of 33

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

Q#

E/APE #I Name I Safety Function K

K K

A A

G KIA Topic(s)

IR 1

2 3

1 2

f000007 Reactor Trip - Stabilization - Recovery/ 1 0

84 000008 Pressurizer Vapor Space Accident I 3 0

PORV isolation (block valve switches and indicalors) 3.9 1

5 000009 Small Break LOCA I 3 0

85 000011 Large Break LOCA I 3 0

2 Consequences lo RHR of not reselting safely injection 3.7 1

000015 RCP Malfunctions I 4 0

000017 RCP Malfunctions (Loss of RC Flow) I 4 86 000022 Loss of Rx Coolant Makeup I 2

02.

22 Knowledge of limiting conditions for operations and safely limits 4.7 1

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 A TWS I 1 0

87 000038 Steam Gen. Tube Rupture I 3 0

6 Shutdown margins and required boron concentralions 4.4 1

000040 Steam Line Rupture - Excessive Heat Transfer 14 0

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

41 classifications

02. Ability 10 interpret control room indications to verify the sra1us and 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 Grid Disturbances I 6 0

KIA Category Totals:

0 0

3 3

Group Point Total:

6 ES-401, 22 of 33

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

Q#

E/APE #I Name I Safety Function K

K K

A A

G KIA Topic(s)

IR 1

2 3

1 2

000001 Continuous Rod Withdrawal / 1 0

90 000003 Dropped Control Rod / 1 01. Ability lo perform specific system and integrated plant procedures 4.4 1

23 during all modes of plant QParalicn, 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

93 r.'lllE02 SI Termination I 3

04. AbniW to diagnose and recognize trends in an accurate and timely 4.2 47 manner utilizing the epp(opnate control room reference material, 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 W/E10 Natural Circulation with Steam Voide in 0

Vessel with/without RVLIS. I 4 VV/EOB RCS Overcooling - PTS I 4 0

KIA Category Totals:

0 0

2 2 Group Point Total:

4 ES-401, 23 of 33

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

Q# System # I Name K K K K K K A A A A G

KIA Topic(s)

IR 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 77 006 Emergency Core Cooling 0

8 Effect of electric power loss on valve position 3.3 1

007 Pressurizer Relief/Quench Tank 0

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

78 059.Main Feedwater

04. Knowledge of how abnormal operating procedures are used 4.5 1

08 in conjunction wilh EOPs_

061 Auxiliary/Emergency Feedwater 0

062 AC Electrical Distribution 0

063 DC Electrical Distribution 0

064 Emergency Diesel Generator 0

073 Process Radiation Monitoring 0

79 076 Service Water 0

Loss of SWS 3.7 1

1 078 Instrument Air 0

04. Knowledge of the parameters and logic used lo assess the 80 103 Containment 21 stalus of safely functions, such as reactivity control, core 4.6 1

coolina and heal removal reactor coolant svstem intenritv.

0 KIA Category Totals:

0 0

0 3

0 0

2 Group Point Total:

5 ES-401, Page 24 of 33