ML030070533

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Final - Outlines (Change Summaries - Optional)
ML030070533
Person / Time
Site: Millstone Dominion icon.png
Issue date: 12/20/2002
From: Wilson M
Dominion Nuclear Connecticut
To: Conte R
NRC/RGN-I/DRS/OSB
Conte R
References
50-336/02-301 50-336/02-301
Download: ML030070533 (37)
v • d • e


Text

( Form ES-401-3 ES-401 PWR SRO Examination Outline Facility: Millstone Unit 2 10/2002 NRC EXAM Exam Level: SRO K/A Category Points Tier Group K11 K2 2 K3 K4 7 K5 K6 A I A 2 A3 A4 G PointTotal

1. 1 5 1 4 2 8 24 Emergency & 2 3 3 2 AA: 3 3 2 16 Abnormal 3 0 1 1 11 0 0 3 Plant Tier 8 5 7...... ' 6 11 ':> 6 43 Evolutions Totals ,*,'
2. 1 1 2 1 2 2 0 2 1 2 3 3 19 Plant 2 2 0 1 5 0 2 0 1 2 2 2 17 Systems 3 0 1 1 1 0 1 0 0 0 0 0 4 Tier 3 3 3 8 2 3 2 2 4 5 5 40 Totals
3. Generic Knowledge and Cat 1 Cat 2 Cat 3 Cat 4 Abilities 3 4 5 5 17 Note:

less than two).

1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., the "Tier Totals" in each K/A category shall not be
2. Actual point totals must match those specified in the table.
3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category/tier.

6.* The generic K/As in Tiers I 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.

totals for each system

7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the RO license level, and the point totals for each category in the table above.

and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier LOUT2K ES-401-3.doc

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ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points Seq. #

X AK1.21;Knowledge of the 2.9 1 7 000001 Continuous Rod Withdrawal/1 operational implications of the 3.2 following concepts as they apply to Continuous Rod Withdrawal:

Integral rod worth.

X AA2.04; Ability to determine and 3.4 1 10 000003 Dropped Control Rod / 1 interpret the following as they apply 3.6 to the Dropped Control Rod: Rod motion stops due to dropped rod 000005 Inoperable/Stuck Control Rod / 1 X 2.1.19: Ability to use plant 3.0 1 1

computer to obtain and evaluate 3.0 parametric information on system or component status.

000011 Large Break LOCA / 3 X EA1.04; Ability to operate and 4.4 1 15 monitor the following as they apply 4.4 to a Large Break LOCA: ESF

  • r l+ir~n cutctnrn in mr nii*nI X AK1.01; Knowledge of the 4.4 1 2 000015/17 RCP Malfunctions / 4 operational implications of the 4.6 following concepts as they apply to Reactor Coolant Pump Malfunctions (Loss of RC Flow):

Natural circulation in the nuclear reactor Dower Olant.

AA2.2; Ability to determine and 2.9 1 BW/E09; CE/Al 3; W/E09&E10 Natural Circ. /4 interpret the following as they apply 3.8 to the (Natural Circulation Operations): Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

LOUT2KES-401-3.doc

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ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points Seq. # E/APE # / Name / Safety Function X AK1.04; Knowledge of the 2.8 1 4 000024 Emergency Boration / 1 operational implications of the 3.6 following concepts as they apply to Emergency Boration: Low temperature limits for boron concentration.

X AK3.04; Knowledge of the reasons 3.5 1 5 000026 Loss of Component Cooling Water / 8 for the following responses as they 3.7 apply to the Loss of Component Cooling Water: Effect on the CCW flow header of a loss of CCW.

X EA2.07; Ability to determine or 4.2 1 24 000029 Anticipated Transient w/o Scram / 1 interpret the following as they apply 4.3 to a ATWS: Reactor trip breaker indicating lights.

X EK2.1; Knowledge of the 3.3 1 16 000040 (BW/E05; CE/E05; W/E12) Steam Line Rupture - Excessive Heat Transfer / 4 interrelations between the (Excess 3.6 Steam Demand) and the following:

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

X EK3.2; Knowledge of the reasons 3.3 1 17 000040 (BW/E05; CE/E05; W/E12) Steam Line Rupture - Excessive Heat Transfer / 4 for the following responses as they 3.8 apply to the (Excess Steam Demand): Normal, abnormal, and emergency operating procedures associated with (Excess Steam Demand).

LOUT2KES-401-3.doc

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ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 Seq. # E/APE # / Name / Safety Function Ki K2 K3 Al A2 G K/A Topic(s) Imp. Points X AK1.3; Knowledge of the 3.0 1 21 CE/Al1; W/E08 RCS Overcooling - PTS /4 operational implications of the 3.2 following concepts as they apply to the (RCS Overcooling):

Annunciators and conditions indicating signals, and remedial actions associated with the (RCS Overcooling).

000051 Loss of Condenser Vacuum /4 X AA2.02; Ability to determine and 3.9 1 8

interpret the following as they apply 4.1 to the Loss of Condenser Vacuum:

Conditions requiring reactor and/or turbine trip 9 000055 Station Blackout / 6 X EK3.02; Knowledge of the reasons 4.3 1 for the following responses as they 4.6 apply to the Station Blackout:

Actions contained in the EOP for loss of offsite and onsite power.

000057 Loss of Vital AC Elec. Inst. Bus /6 X 2.1.33; Ability to recognize 3.4 1 37 indications for system operating 4.0 parameters which are entry-level conditions for technical specifications.

X AA1.03; Ability to operate and/or 3.0* 1 30 000059 Accidental Liquid RadWaste Rel. / 9 monitor the following as they apply 2.9 to the Accidental Liquid Radwaste Release: Flow rate controller.

000062 Loss of Nuclear Service Water /4 X 2.4.11; Knowledge of abnormal 3.4 1 11 condition procedures. 3.6 000067 Plant fire on site / 9 X AK1.02; Knowledge of the 3.1 1 12 operational implications of the 3.9 following concepts as they apply to I___ __Plant Fire on Site: Fire fighting. I_ I LOUT2KES-401-3.doc

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ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 Seq. # E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 13 000068 (BW/A06) Control Room Evac. / 8 X AA2.07; Ability to determine and 4.1 1 interpret the following as they apply 4.3 to the Control Room Evacuation:

PZR level.

14 000069 (W/E14) Loss of CTMT Integrity / 5 X AA2.01; Ability to determine and 3.7 1 interpret the following as they apply 4.3 to the Loss of Containment Integrity: Loss of containment integrity.

39 000069 (W/E14) Loss of CTMT Integrity / 5 X AA2.02; Ability to determine and 3.9 1 interpret the following as they apply 4.4 to the Loss of Containment Integrity: Verification of automatic and manual means of restoring integrity.

42 000074 (W/E06&E07) Inad. Core Cooling I 4 X EK3.07; Knowledge of the reasons 4.0 for the following responses as they 4.4 apply to the Inadequate Core Cooling: Starting up emergency feedwater and RCPs.

43 000074 (W/E06&E07) Inad. Core Cooling I 4 X EA2.02; Ability to determine or 4.6 1 interpret the following as they apply 4.9 to a Inadequate Core Cooling:

Availability of main or auxiliary feedwater.

[NtJoe 1] BWIE03 inadequiate Stubcooi~n~g Margin /4 ~~.A '

44 000076 High Reactor Coolant Activity / 9 X 2.1.32 Ability to explain and apply 3.4 1 all system limits and precautions. 3.8

[Note1] BW/A02&AO3 L.oss of NNI-XtY /7 . ... Ii,.

N/A K/A Category Totals: 5 1 4 2 8 4 Group Point Total: 24 LOUT2KES-401-3.doc

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ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points Seq. #

X EK2.2; Knowledge of the 3.5 1 18 000007 9BW/E02&El0; CE/E02) Reactor Trip -

Stabilization - Recovery / 1 interrelations between the (Reactor 4.0 Trip Recovery) and the following:

Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

[tNote11 ~BWJAO1 P ant Runback /'>I ~,

]BW/A04 Turbine TripI/ 4.

[Nt ~ .

X AA2.15; Ability to determine and 3.9 1 19 000008 Pressurizer Vapor Space Accident /3 interpret the following as they apply 4.2 to the Pressurizer Vapor Space Accident: ESF control board, valve controls, and indicators.

20 000009 Small Break LOCA / 3 X EA2.06; Ability to determine and 3.8 1 interpret the following as they apply 4.3 to a small break LOCA: Whether PZR water inventory loss is imminant X 2.4.46; Ability to verify that the 3.5 1 22 000022 Loss of Reactor Coolant Makeup / 2 alarms are consistent with plant 3.6 conditions.

AK1.01; Knowledge of the 3.9 1 23 000025 Loss of RHR System / 4 4.3 operational implications of the following concepts as they apply to Loss of Residual Heat Removal System: Loss of RHRS during all modes of operation.

LOUT2KES-401-3.doc

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ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 Seq. # E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 000027 Pressurizer Pressure Control System X AK1.02; Knowledge of the 2.8 1 6

Malfunction / 3 operational implications of the 3.1 following concepts as they apply to Pressurizer Pressure Control Malfunctions: Expansion of liquids as temperature increases.

45 000032 Loss of Source Range NI /7 X AK2.01; Knowledge of the 2.7* 1 interrelations between the Loss of 3.1 Source Range Nuclear Instrumentation and the following:

Power supplies, including proper switch positions.

25 000033 Loss of Intermediate Range NI /7 X AA1.01; Ability to operate and / or 2.9 1 monitor the following as they apply 3.1 to the Loss of Intermediate Range Nuclear Instrumentation: Power available indicators in cabinets or equipment drawers 26 000037 Steam Generator Tube Leak 3 X AK3.10; Knowledge of the reasons 3.3* 1 for the following responses as they 3.7*

apply to the Steam Generator Tube Leak: Automatic actions associated with high radioactivity in S/G sample lines.

27 000038 Steam Generator Tube Rupture /3 X EK1.03; Knowledge of the 3.9 1 operational implications of the 4.2 following concepts as they apply to the SGTR: Natural circulation.

28 000054 (CE/E06) Loss of Main Feedwater /4 X EA1I.1; Ability to operate and / or 4.0 1 monitor the following as they apply 3.9 to the (Loss of Feedwater):

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

LoU I 2K_"b-4U1 -3.aoc

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ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 Seq. # E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 29 000058 Loss of DC Power / 6 X AA1.03; Ability to operate and / or 3.1 1 monitor the following as they apply 3.3 to the Loss of DC Power: Vital and battery bus components.

31 000060 Accidental Gaseous Radwaste Rel. /9 X AA2.01; Ability to determine and 3.1 1 interpret the following as they apply 3.7 to the Accidental Gaseous Radwaste: A radiation-level alarm, as to whether the cause was due to a gradual (in time) signal increase or due to a sudden increase (a "spike"), including the use of strip chart recorders, meter and alarm observations.

32 000061 ARM System Alarms / 7 X AK3.02; Knowledge of the reasons 3.4 1 for the following responses as they 3.6 apply to the Area Radiation Monitoring (ARM) System Alarms:

Guidance contained in alarm response for ARM system.

[No 1] VV/E16 High Containment Radiationi 9 35 000065 Loss of Instrument Air / 8 X 2.4.48; Ability to interpret control 3.5 1 room indications to verify the status 3.8 and operation of system, and understand how operator actions and directives affect plant and system conditions.

33 CE/E09 Functional Recovery X EK2.1; Knowledge of the 3.6 1 interrelations between the 3.9 (Functional Recovery) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

N/A K/A Category Point Totals: 3 3 23 3 I2 7Group Point Total: 16 LOUT2KES-401-3.doc

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ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 Seq. # E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 34 000028 Pressurizer Level Malfunction / 2 X AA1.02; Ability to operate and / or 3.4 1 monitor the following as they apply 3.4 to the Pressurizer Level Control Malfunctions: CVCS N/A 000036 (BW/A08) Fuel Handling Accident /8 ~ Random Deselection ~

48 000056 Loss of Offsite Power / 6 X AK3.02; Knowledge of the reasons 4.4 1 for the following responses as they 4.7 apply to the Loss of Offsite Power:

[,Note1] B.W/AO5 Emergenc islAcuto

[Noteio1a / in EOP o 36 CE/A16 Excess RCS Leakage / 2 X AK2. 1; Knowledge of the 3.2 1 interrelations between the (Excess 3.5 RCS Leakage) and the following:

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features

[Note11i VVI13 Steam Generator Over-pressure 4..

ote11 r /El5 Contain m~ent Flooding / 5 .>

.0 -

N/A JK/A Category Point Totals: 0 1 1 1 0 0 GopPoint Total:3 LOUT2KES-401-3.doc

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ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 1 Seq. # System#/Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/ATopic(s) Imp. Points 38 001 Control Rod Drive X 2.2.34; Knowledge of the process for 2.8 1 determining the internal and external 3.2*

effects on core reactivity.

40 003 Reactor Coolant X A4.04; Ability to manually operate 3.1 1 Pump and/or monitor in the control room: 3.0 RCP seal differential pressure instrumentation.

41 004 Chemical and X K5. 11; Knowledge of the operational 3.6 1 Volume Control implications of the following concepts 3.9 as they apply to the CVCS: Thermal stress, brittle fracture, pressurized thermal shock.

60 004 Chemical and X K1.24; Knowledge of the physical 3.4 1 Volume Control connections and/or cause-effect 3.9 relationships between the CVCS and the following systems: RHRS 50 013 Engineered Safety X K3.03; Knowledge of the effect that a 4.3 1 Features Actuation loss or malfunction of the ESFAS will 4.7 have on the following: Containment 51 013 Engineered Safety X A4.03; Ability to manually operate 4.5 1 Features Actuation and/or monitor in the control room: 4.7 ESFAS initiation.

65 014 Rod Position X A4.04; Ability to manually operate 2.7 1 Indication and/or monitor in the control room: 2.7 Re-zeroing of rod position prior to startup.

46 015 Nuclear X A3.01; Ability to monitor automatic 3.8 1 Instrumentation operation of the NIS, including: 3.8 Console and cabinet indications 47 017 In-core X A1.01; Ability to predict and/or monitor 3.7 1 Temperature Monitor changes in parameters (to prevent 3.9 exceeding design limits) associated with operating the ITM system controls including: Core exit temperature. I LOUT2K_ES-401-3.doc

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ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 1 Seq. # System#/Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/ATopic(s) Imp. Points 54 022 Containment X K2.01; Knowledge of bus power 3.0* 1 Cooling supplies to the following: Containment 3.1 cooling fans.

56 022 Containment X A1.04; Ability to predict and/or monitor 3.2 1 Cooling changes in parameters (to prevent 3.3 exceeding design limits) associated with operating the CCS system controls including: Cooling water flow

[Note 1] 025 Ice Condenser __

57 026 Containment X K4.02; Knowledge of CSS design 3.1 1 Spray feature(s) and/or interlock(s) which 3.6 provide for the following: Neutralize boric acid to reduce corrosion and remove inorganic fission product iodine from steam (NAOH) in containment spray.

49 056 Condensate X A2.04; Ability to (a) predict the 2.6 1 impacts of the following malfunctions 2.8*

or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of condensate pumps.

52 059 Main Feedwater X 2.4.50; Ability to verify system alarm 3.3 1 setpoints and operate controls 3.3 identified in the alarm response manual.

53 061 X K2.01; Knowledge of bus power 3.2* 1 Auxiliary/Emergency supplies to the following: AFW system 3.3 Feedwater MOVs.

74 063 DC Electrical X A3.01; Ability to monitor automatic 2.7 1 Distribution operation of the DC electrical system, 3.1 including: Meters, annunciators, dials recorders, and indicating lights.

LOUT2K_ES-401-3.doc

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ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 1 Seq.# System#/Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/ATopic(s) Imp. Points 55 068 Liquid Radwaste X K4.01; Knowledge of design feature(s) 3.4 1 and/or interlock(s) which provide for 4.1 the following: Safety and environmental precautions for handling hot, acidic, and radioactive liquids.

58 071 Waste Gas X 2.1.8; Ability to coordinate personnel 3.8 1 Disposal activities outside the control room. 3.6 59 072 Area Radiation X K5.01; Knowledge of the operational 2.7 1 Monitoring implications of the following concepts 3.0 as they apply to the ARM system:

Radiation theory, including sources, types, units, and effects.

N/A K/A Category Point 112 1 2[2 0 2 1 2]3]31 Group Point Total: 19 Totals: _I LOUT2K_ES-401-3.doc

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ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 2 Seq. # System#/Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/ATopic(s) Imp. Points N/A 002 Reactor Coolant - RANDOM DESELECTED 006 Emergency Core X K4.17; Knowledge of ECCS design 3.8 1 61 Cooling feature(s) and/or interlock(s) which 4.1 provide for the following: Safety injection valve interlocks.

N/A 010 Pressurizer RANDOM DESELECTED ~

Pressure Control 63 011 Pressurizer Level X K3.03; Knowledge of the effect that a 3.2 1 Control loss or malfunction of the PZR LCS will 3.7 have on the following: PZR PCS.

64 012 Reactor Protection X K1.01; Knowledge of the physical 3.4 1 connections and/or cause effect 3.7 relationships between the RPS and the following systems: 120V vital/instrument power system.

016 Non-nuclear X A2.01; Ability to (a) predict the impacts 3.0* 1 66 Instrumentation of the following malfunctions or 3.1

  • operations on the NNIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure.

11 LOUT2K_ES-401-3.doc

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ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 2 Seq. # System#/Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/ATopic(s) Imp. Points N/A 034 Fuel Handling - RANDOM DESELECTED ~

Equipment 70 035 Steam Generator X A4.08; Ability to manually operate 4.1 and/or monitor in the control room: 4.4 Recognition that increasing radiation levels in secondary systems may mean leaking and possibly ruptured S/G tubes.

71 039 Main and Reheat X K4.05; Knowledge of MRSS design 3.7 1 Steam feature(s) and/or interlock(s) which 3.7 provide for the following: Automatic isolation of steam line 72 055 Condenser Air X K1.06; Knowledge of the physical 2.6 1 Removal connections and/or cause-effect 2.6 relationships between the CARS and the following systems: PRM system 73 062 AC Electrical X 2.1.32; Ability to explain and apply all 3.4 1 Distribution system limits and precautions. 3.8 75 064 Emergency Diesel X K6.07; Knowledge of the effect of a 2.7 1 Generator loss or malfunction of the following will 2.9 have on the ED/G system: Air receivers 76 073 Process Radiation X K4.01; Knowledge of PRM system 4.0 1 Monitoring design feature(s) and interlock(s) 4.3 which provide for the following:

Release termination when radiation exceeds setpoint.

77 075 Circulating Water X K4.01; Knowledge of circulating water 2.5 1 system design feature(s) and 2.8 interlock(s) which provide for the following: Heat sink 78 079 Station Air X 2.1.32; Ability to explain and apply all 3.4 1 system limits and precautions. 3.8 LOUT2K_ES-401-3.doc

( ( I ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 2 Seq. # System#/Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/ATopic(s) Imp. Points 79 086 Fire Protection X A3.01; Ability to monitor automatic 2.9 1 operation of the Fire Protection 3.3 System, including: Starting mechanisms of fire water pumps.

62 103 Containment X A3.01; Ability to monitor automatic 3.9 1 operation of the Containment System, 4.2 including: Containment isolation.

N/A K/A Category Point 210 11 5 02 2 Group Point Total: 17 Totals:

[Note 1] Grayed out rows are not applicable to Millstone Unit Two (CE designed plant)

LOUT2K_ES-401-3.doc

( C ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 3 Seq. # System#/Name K1 K2 K3 K4 K5 K6 All A2 A3 A4 G K/ATopic(s) Imp. Points 80 005 Residual Heat X K2.03; Knowledge of bus power 2.7* 1 Removal supplies to the following: RCS 2.8*

pressure boundary motor-operated valves.

81 007 Pressurizer X K4.01; Knowledge of PRTS design 2.6 1 Relief/Quench Tank feature(s) and interlock(s) which 2.9 provide for the following: Quench tank cooling.

N/A 008 Component -RANDOM DESELECTED Cooling Water 85 041 Steam X K6.03; Knowledge of the effect of a 2.7 1 Dump/Turbine Bypass loss or malfunction on the following will 2.9 Control have on the SDS: Controller and I_ I_ III positioners, including ICS, S/G, CRDS._

N/A 045 Main Turbine -RANDOM DESELECTED Generator N/A 076 Service Water -RANDOM DESELECTED 67 078 Instrument Air X K3.02; Knowledge of the effect that a 3.4 1 loss or malfunction of the IAS will have 3.6 on the following: Systems having I pneumatic valves and controls.

[ J10[ 0 N/A K/A Category Point 0T1t1l1 0 1 0 Group Point Total:

____ ____ Totals:jj _ _ _ _ _ ] _ _ _ _ _I _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

4 Plant-Specific Priorities Seq. System / Topic Recommended Replacement Reason Points for LPlant-Specific Priority Total: (limit 10)

LOUT2K_ES-401-3.doc

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ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 Facility: Millstone Unit 2 Date of Exam: 10/25/02 Exam Level: SRO Category Seq. K/A # Topic Imp. Points 89 2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, and 2.8/3.1 1 tables which contain performance data.

Conduct of 88 2.1.14 Knowledge of system status criteria which require the notification of plant personnel. 2.5/3.3 1 Operations 82 2.1.31 Ability to locate control room switches, controls and indications and to determine that they are 4.2/3.9 1 correctly reflecting the desired plant lineup.

Total 3 84 2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown 4.0/3.5 1 and designated power levels.

Equipment 86 2.2.21 Knowledge of pre- and post-maintenance operability requirements. 2.3/3.5 1 Control 91 2.2.12 Knowledge of surveillance procedures. 3.0/3.4 1 90 2.2.27 Knowledge of the refueling process. 2.6/3.5 1 Total 4 92 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements. 2.6/3.0 1 Radiation 93 2.3.2 Knowledge of facility ALARA program. 2.5/2.9 1 Control 94 2.3.9 Knowledge of the process for performing a containment purge. 2.5/3.4 1 95 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against 2.9/3.3 1 personnel exposure.

96 2.3.11 Ability to control radiation releases. 2.7/3.2 1 Total 5 Emergency 97 2.4.12 Knowledge of general operating crew responsibilities during emergency operations. 3.4/3.9 1 Procedures 98 2.4.17 "Knowledge of EOP terms and definitions, 3.1/3.8 1 and Plan 99 2.4.25 Knowledge of fire protection procedures. 2.9/3.4 1 87 2.4.46 Ability to verify that the alarms are consistent with the plant conditions. 3.5/3.6 1 100 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the 3.4/3.7 1 appropriate control room reference material.

Total 5 Tier 3 Target Point Total (R-/SRO) 17 LOUT2KES-401-3.doc

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ES-401 PWR RO Examination Outline Form ES-401-4 Facility: Millstone Unit 2 2002 NRC EXAM Exam Level: RO K/A Category Points Tier Group K1 K2 K3 K4 K5 K6 2 A3 A4 G PointTotal I IIII_ _ I

1. 1 5 0 3 0 4 4 16 Emergency & 2 2 2 2 5 5 1 17 Abnormal 3 0 1 0 1 0 1 3 Plant Tier 7 3 5 6 9 6 36 Evolutions Totals 1 6.36
2. 1 1 2 2 2 3 0 2 2 3 2 4 23 Plant 2 2 2 1 5 0 1 1 1 2 3 2 20 Systems 3 0 1 2 1 0 2 1 0 0 0 1 8 Tier Totl 3 5 5 8 3 3 4 3 TotalsIIII 5 5 7 51 1 1
3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 2 2 5 4 13 Note:
1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., the "Tier Totals" in each K/A category shall not be less than two).
2. Actual point totals must match those specified in the table.
3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category/tier.
6.
  • The generic 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.
7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the RO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 Seq. # E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 1 000005 Inoperable/Stuck Control Rod / 1 X 2.1.19; Ability to use plant 3.0/ 1 computer to obtain and evaluate 3.0 parametric information on system or component status 2 000015/17 RCP Malfunctions / 4 X AK1.01; Knowledge of the 4.4/ 1 operational implications of the 4.6 following concepts as they apply to Reactor Coolant Pump Malfunctions(Loss of RC Flow):

Natural circulation in a nuclear reactor power plant.

3 BW/E09; CE/Al 3; W/E09&E1 0 Natural Circ. / 4 X AA2.2; Ability to determine and 2.9/ 1 interpret the following as they apply 3.8 to the (Natural Circulation Operations) Adherence to appropriate procedures and operation within the limitations in the facilities license and amendments.

4 000024 Emergency Boration / 1 X AK1.04; Knowledge of the 2.8/ 1 operational implications of the 3.6 following concepts as they apply to Emergency Boration: Low temperature limits for Boron concentration.

5 000026 Loss of Component Cooling Water / 8 X AK3.04; Knowledge of the reasons 3.5/ 1 for the following responses as they 3.7 apply to the Loss of Component Cooling Water: Effect on the CCW flow header of a loss of CCW.

6 000027 Pressurizer Pressure Control System X AK1.02; Knowledge of the 2.8/ 1 Malfunction / 3 operational implications of the 3.1 following concepts as they apply to Pressurizer Pressure Control Malfunctions and the following:

Expansion of liquids as temperature increases.

N/A 000040 (BW/E05; CE/E05; W/E12) Steam Line RANDOMLY DESELECTED Rupture - Excessive Heat Transfer / 4 LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

1 r 1 r 7 CE/Al1l; W/E08 RCS Overcooling - PTS / 4 x AK1.3; Knowledge of the 3.0/ 1 operational implications of the 3.2 following concepts as they apply to the (RCS Overcooling)

Annunciators and conditions indication signals, and remedial actions associated with the (RCS overcooling).

8 000051 Loss of Condenser Vacuum /4 X AA2.02; Ability to determine and 3.9/

interpret the following as they apply 4.1 to the Loss of Condenser Vacuum:

Conditions requiring reactor and/or turbine trip 9 000055 Station Blackout / 6 X EK3.02; Knowledge of the reasons 4.3/

for the following responses as the 4.6 apply to the Station Blackout:

Actions contained in EOP for loss of offsite and onsite power.

10 000057 Loss of Vital AC Elec. Inst. Bus /6 X 2.4.10; Knowledge of annunciator 3.0/

response procedures. 3.1 11 000062 Loss of Nuclear Service Water /4 X 2.4.11: Knowledge of abnormal 3.4/

condition procedures. 3.6 12 000067 Plant fire on site / 9 X AK1.02; Knowledge of the 3.1/

operational implications of the 3.9 following concepts as they apply to Plant Fire on Site: Fire fighting 13 000068 (BW/A06) Control Room Evac. / 8 X AA2.07; Ability to determine and 4.1/

interpret the following as they apply 4.3 to the Control Room Evacuation:

PZR Level.

14 000069 (W/E14) Loss of CTMT Integrity / 5 X AA2.01; Ability to determine and 3.7/

interpret the following as they apply 4.3 to the Loss of Containment Integrity.

15 000074 (W/E06&E07) Inad. Core Cooling / 4 X EK3.07; Knowledge of the reasons 4.0/

for the following responses as the 4.4 apply to the Inadequate Core Cooling: Starting up emergency feedwater and RCPs.

LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

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S[Note 1 .BV/E03 inadequate Subcooling Margin /4 _____ ______ _____ ,..... _ _ _ _ _ _ ... .. _.

16 000076 High Reactor Coolant Activity / 9 X 2.1.32; Ability to explain and apply 3.4/

all system limits and precautions. 3.8

[Note 1 BW/A02&AO3 W Loss of NNI-X/Y ___

K/A Category Totals: 5 0 3 1 [ 4 [ 4 [Group Point Total: -6

[Note 1] Grayed out rows are not applicable to Millstone Unit Two (CE designed plant)

LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

/¢ ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 Seq. # E/APE # / Name / Safety Function KI K2 K3 Al A2 G K/A Topic(s) Imp. Points N/A 000001 Continuous Rod Withdrawal / 1 RANDOMALY DESELECTED 17 000003 Dropped Control Rod / 1 X AA2.04; Ability to determine and interpret the following 3.4/ 1 as they apply to the Dropped Control Rod: Rod motion 3.6 stops due to dropped rod.

18 000007 9BW/E02&E10; CE/E02) Reactor Trip - X EK2.2; Knowledge of the interrelations between the 3.5/ 1 Stabilization - Recovery / 1 (Reactor Trip Recovery) and the following: Facilities 4.0 heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and the relations between the proper operation of these systems to the operation of the facility.

[Note 1] BWIAO1 Plant Runback / 1--------------------- - ____________________

[Note 1] BW/A04 Turbine Trip / 4 ____________________

19 000008 Pressurizer Vapor Space Accident / 3 X AA2.15; Ability to determine and interpret the following 3.9/ 1 as they apply to the Pressurizer Vapor Space Accident 4.2 and the following: ESF Control Board, valve controls, and indicators.

20 000009 Small Break LOCA / 3 X EA2.06; Ability to determine or interpret the following 4.0/ 1 as they apply to the small break LOCA: Whether PZR 4.1 water inventory loss is imminent.

21 000011 Large Break LOCA / 3 x EA1.04; Ability to operate and monitor the following as 4.4/ 1 they apply to a Large Break LOCA: ESF Actuation 4.4 system in manual.

22 000022 Loss of Reactor Coolant Makeup / 2 X 2.4.46; Ability to verify that the alarms are consistent 3.5/ 1 with the plant conditions. 3.6 I~

23 000025 Loss of RHR System / 4 AK1.01; Knowledge of the operational implications of 3.9/ 1 the following concepts as they apply to Loss of Residual 4.3 Heat Removal System: Loss of RHRS during all modes 11 of operation.

LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 Seq. # E/APE # / Name / Safety Function KI K2 K3 Al A2 G K/A Topic(s) Imp. Points 24 000029 Anticipated Transient w/o Scram / 1 X EA2.07; Ability to determine and interpret the following 4.2/ 1 as they apply to a ATWS: Reactor Trip Breaker 4.3 indicating lights.

N/A 000032 Loss of Source Range NI / 7 RANDONALLY DESELECTED 25 000033 Loss of Intermediate Range NI / 7 X AA1.01; Ability to operate and / or monitor the 3.2./ 1 following as they apply to the Loss of Intermediate 3.6 Range Nuclear Instrumentation: Power-available indicators in cabinets or equipment drawers.

26 000037 Steam Generator Tube Leak / 3 X AK3.1 0; Knowledge of the reasons for the following 3.3*/ 1 responses as they apply to the Steam Generator Tube 3.7*

Leak: Automatic actions associated with high radioactivity in S/G sample lines.

27 000038 Steam Generator Tube Rupture / 3 X EK1.03; Knowledge of the operational implications of 3.9/ 1 the following concepts as they apply to the SGTR: 4.2 Natural Circulation 28 000054 (CE/E06) Loss of Main Feedwater / 4 X EA1.1; Ability to operate and/or monitor the following 4.0/ 1 as they apply to the (Loss of Feedwater) Components, 3.9 and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

[Note 1] BWIEO4; W/E05 Inadequate Heat Transfer - Loss of Secondary heat Sink 14 29 000058 Loss of DC Power / 6 X AA1.03; Ability to operate and / or monitor the 3.1/ 1 following as they apply to the Loss of DC Power: Vital 3.3 and battery bus components 30 000059 Accidental Liquid RadWaste Rel. / 9 X AA1.03; Ability to operate and / or monitor the 3.0/ 1 following as they apply to the Accidental Liquid 2.9 RadWaste Release: Flow Rate Controller 31 000060 Accidental Gaseous Radwaste Rel. / 9 X AA2.01; Ability to determine and interpret the following 3.1/ 1 as they apply to the Accidental Gaseous RadWaste: A 3.7 radiation-level alarm, as to whether the cause was due to a gradual (in time) signal increase or due to a sudden increase (a "spike"), including the use of strip chart recorders, meter and alarm observations.

LOIT2K2 ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier l/Group 2 Seq. # E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 32 000061 ARM System Alarms / 7 X AK3.02; Knowledge of the reasons for the following 3.4/ 1 responses as they apply to the Area Radiation Monitor 3.6 (ARM) System Alarms: Guidance contained in alarm response for ARM System.

[Note 1] WV/E16 High Containment Radiation 19 ____________________

33 CE/E09 Functional Recovery X EK2.1; Knowledge of the interrelations between the 3.6/ 1 (Functional Recovery) and the following: Components, 3.9 and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

N/A K/A Category Totals: I 2 1 2 15 5 1 Group Point Total: j 17 LOIT2K<2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 Seq. # E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 34 000028 Pressurizer Level Malfunction / 2 X AA1.02; Ability to operate and / or monitor the 3.4/ 1 following as they apply to the Pressurizer Level Control 3.4 Malfunctions: CVCS N/A 000036 (BW/A08) Fuel Handling Accident / 8 RANDOMALY DESELECTED N/A 000056 Loss of Off-site Power / 6 RANDOMALY DESELECTED 35 000065 Loss of Instrument Air / 8 X 2.4.48; Ability to interpret control room indications to 3.5/ 1 verify the status and operation of system, and understand 3.8 how operator actions and directives affect plant and system conditions.

[Note 1] 8W/El 3&E1 4 EOP Rules and Enclosures

&[Note 1] l3W/A05 Emergency Diesel' Actuation 16 > 1A

[Note 11 BWIA07 Flooiding / 8 21 36 CE/A16 Excess RCS Leakage / 2 X AK2.1; Knowledge of the interrelations between the 3.2/

(Excess RCS Leakage) and the following: Components, 3.5 and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

[Note 1. W/El 3 Steam Generato r Over-pressur 4

[Not 1] IEI5Continment Flooding /15 N/A_ K/A Category Point Totals: 0. i 011jGroup Point Total:3_

[Note 1] Grayed out rows are not applicable to Millstone Unit Two (0E designed plant)

LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

( ( f ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 Seq. # System # / Name K1 K2 K3 K4 K5 K6 A 1 A2 A 3 A4 G K/A Topic(s) Imp. Points 37 001 Control Rod Drive X K4.10; Knowledge of CRDS design 3.6/ 1 feature(s) and/or interlock(s) which 3.8 provide for the following: Trip signals that would prevent reset of reactor trip signals.

38 001 Control Rod Drive X 2.2.34; Knowledge of the process for 3.8/ 1 determining the internal and external 4.1 effects on core reactivity.

39 003 Reactor Coolant Pump X A2.03; Ability to (a) predict the 2.7/ 1 impacts of the following malfunctions 3.1 or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Problems associated with RCP motors, including faulty motors and current, and winding and bearing temperature problems.

40 003 Reactor Coolant Pump X A4.04; Ability to manually operate 3.1/ 1 and/or monitor in the control room: 3.0 RCP seal differential pressure instrumentation.

41 004 Chemical and Volume X K5.1 1; Knowledge of the operational 2.6/ 1 Control implications of the following concepts 3.1 as they apply to the CVCS: Thermal stress, brittle fracture, PTS.

42 004 Chemical and Volume X A4.02; Ability to manually operate 3.2/ 1 Control and/or monitor in the control room: 3.9 Calculation of ECP and related boration/dilution/reactivity relationships.

43 013 Engineered Safety X K3.02; Knowledge of the effect that a 4.3/ 1 Features Actuation loss or have onmalfunction of the ESFAS will the following: RCS 4.5 44 013 Engineered Safety X A3.01; Ability to monitor automatic 3.7*/ 1 Features Actuation operation of the ESFAS including: 3.9 Input channels and logic LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 Seq. # System #/Name K1 K2 K3 K4 K5 K6 All A2 A3 A4 G K/ATopic(s) Imp. Points 45 015 Nuclear Instrumentation X K3.01; Knowledge of the effect that a 3.9/ 1 loss or malfunction of NIS will have 4.3 on the following: RPS 46 015 Nuclear Instrumentation X A3.01; Ability to monitor automatic 3.8/ 1 operation of the NIS including: 3.8 Console and Cabinet Indications.

47 017 In-core Temperature X A1.01; Ability to predict and/or 3.7/ 1 Monitor monitor changes in parameters (to 3.9 prevent exceeding design limits) associated with operating the ITM System controls including: Core Exit Temperature.

48 022 Containment Cooling X K2.01; Knowledge of bus power 3.0*/ 1 supplies to the following: 3.1 Containment cooling fans.

49 056 Condensate X A2.04; Ability to (a) predict the 2.6/ 1 impacts of the following malfunctions 2.8*

or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Loss of Condensate Pumps.

50 056 Condensate X 2.1.32; Ability to explain and apply all 3.4/ 1 system limits and precautions. 3.8 51 059 Main Feedwater X K1.05; Knowledge of the physical 3.1*/ 1 connections and/or cause-effect 3.2 relationships between the MFW and the following systems: RCS 52 059 Main Feedwater X 2.4.50; Ability to verify alarm 3.3/ 1 setpoints and operate controls 3.3 identified in the alarm response manual.

53 061 Auxiliary/Emergency X K2.01; Knowledge of bus power 3.2*/ 1 Feedwater supplies to the following: AFW 3.3 system MOVs LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 Seq.# System #/Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/ATopic(s) Imp. Points 54 061 Auxiliary/Emergency X A 1.04; Ability to predict and/or 3.9/ 1 Feedwater monitor changes in parameters (to 3.9 prevent exceeding design limits) associated with operating the AFW System controls including: AFW source tank level.

55 068 Liquid Radwaste X K4.01; Knowledge of design 3.4/ 1 feature(s) and/or interlock(s) which 4.1 provide for the following: Safety and safety precautions for handling hot, acidic, and radioactive liquids.

56 068 Liquid Radwaste X A3.02; Ability to monitor automatic 3.6/ 1 operation of the Liquid Radwaste 3.6 System, including: Automatic isolation.

57 071 Waste Gas Disposal X K5.04; Knowledge of the operational 2.5/ 1 implications of the following concepts 3.1 as they apply to the Waste Gas Disposal System: Relationship of hydrogen/oxygen concentrations to flammability.

58 071 Waste Gas Disposal X 2.1.8; Ability to coordinate personnel 3.8/ 1 activities outside the control room. 3.6 59 072 Area Radiation X K5.01; Knowledge of the operational 2.7/ 1 Monitoring implications of the following concepts 3.0 as they apply to the ARM system:

Radiation theory, including sources, types, units, and effects N/A JK/A Category Point Totals: 1112!2!2 3[10]2]2! 3 2[14 Group Point Total:] 23

[Note 11 G3rayed out rows. ar not appi~cable to Millstone Unit Two (CE designed plant)

LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 2 Seq. # System #/Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G K/ATopic(s) Imp. Pts 60 002 Reactor Coolant X A 1.07; Ability to predict and/or monitor changes in 3.3/ 1 parameters (to prevent exceeding design limits) 3.5 associated with operating the RCS controls including: Reactor differential temperature.

61 006 Emergency Core X K4.17; Knowledge of ECCS design feature(s) 3.8/ 1 Cooling and/or interlock(s) which provide for the following: 4.1 Safety injection valve interlocks.

62 010 Pressurizer X K2.01; Knowledge of bus power supplies to the 3.6/

Pressure Control following: PZR Heaters 3.9 63 011 Pressurizer Level X K3.03; Knowledge of the effect that a loss or 3.2/ 1 Control malfunction of the PZR LCS will have on the 3.7 following: PZR PCS 64 012 Reactor Protection X K1.01; Knowledge of the physical connections 3.4/ 1 and/or cause effect relationships between the RPS 3.7 and the following systems: 120V vital/instrument power system.

65 014 Rod Position X A4.04; Ability to manually operate and/or monitor 2.7/ 1 Indication in the control room: Rezeroing of rod position prior 2.7 to startup.

66 016 Non-nuclear X A2.01; Ability to (a) predict the impacts of the 3.0* 1 Instrumentation following malfunctions or operations on the NNIS 3.1*

Channels; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Detector failure.

67 026 Containment Spray X K2.01 ; Knowledge of bus power supplies to the 3.4*/ 1 following: Containment spray pumps 3.6 68 029 Containment Purge X A4.04; Ability to manually operate and/or monitor 3.5/ 1 in the control room: Containment evacuation 3.6 signal.

69 033 Spent Fuel Pool X K4.03; Knowledge of design feature(s) and/or 2.6/ 1 Cooling interlock(s) which provide for the following: Anti- 2.9 Siphon devices.

70 035 Steam Generator X A4.08; Ability to manually operate and/or monitor 4.1/ 1 in the control room: Recognition that increasing 4.4 radiation levels in secondary systems may mean leaking and possible ruptured S/G tubes.

LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 2 Seq. # System #/Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/ATopic(s) Imp. Pts 71 039 Main and Reheat X K4.05; Knowledge of MRSS design feature(s) 3.7/ 1 Steam and/or interlock(s) which provide for the following: 3.7 Automatic isolation of steam line.

72 055 Condenser Air X K I.06; Knowledge of the physical connections 2.6/ 1 Removal and/or cause-effect relationships between the CARS 2.6 and the following systems: PRM System.

73 062 AC Electrical X 2.1.32; Ability to explain and apply all system 3.4/ 1 Distribution limits and precautions. 3.8 74 063 DC Electrical X A3.01; Ability to monitor automatic operation of the 2.7/ 1 Distribution DC Electrical System, including: Meters, 3.1 annunciators, dials, recorders, and indicating lights.

75 064 Emergency Diesel X K6.07; Knowledge of the effect of a loss or 2.7/ 1 Generator malfunction on the following will have on the ED/G 2.9 System: Air Receivers 76 073 Process Radiation X K4.0 1; Knowledge of PRM design feature(s) and/or 4.0/ 1 Monitoring interlock(s) which provide for the following: 4.3 Release termination when radiation exceeds setpoint 77 075 Circulating Water X K4.01; Knowledge of Circulating Water design 2.5/ 1 feature(s) and/or interlock(s) which provide for the 2.8 following: Heat Sink 78 079 Station Air X 2.1.32; Ability to explain and apply all system 3.4/ 1 limits and precautions. 3.8 79 086 Fire Protection X A3.0Fire the 1; Ability to monitor automatic operation of 2.9! 1 Protection System including: Starting mechanisms of the 3.3 fire water pumps.

N/A K/A Category Point 2[2[ 1 510 1[ 1[225 Group Point Total: 20 Totals:

LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 3 Seq. # System #/Name K1 K2 K3 K4 K5 K6 All A2 A3 A4 G K/ATopic(s) Imp. Pts 80 005 Residual Heat X K2.03; Knowledge of bus power supplies to the 2.7*/ 1 Removal following: RCS pressure boundary motor-operated 2.8*

valves.

81 007 Pressurizer X K4.01; Knowledge of PRTS design feature(s) and/or 2.6/ 1 Relief/Quench Tank interlock(s) which provide for the following: 2.9 Quench Tank Cooling 82 008 Component Cooling X K3.03; Knowledge of the effect that a loss or 4.1/ 1 Water malfunction of the CCWS will have on the 4.2 following: RCPs

[Note 1] 027 Containment Iodine Removal___________________

83 028 Hydrogen X K6.01; Knowledge of the effect of a loss or 2.6/ 1 Recombiner and Purge malfunction on the following will have on the 3.1 Control HRPS: Hydrogen Recombiners.

84 034 Fuel Handling X 2.2.28; Knowledge of new and spent fuel movement 2.6/ 1 Equipment procedures. 3.5 85 041 Steam X K6.03; Knowledge of the effect of a loss or 2.7/ 1 Dump/Turbine Bypass malfunction on the following will have on the SDS: 2.9 Control Controller and positioners, including ICS, S/G, CRDS 86 045 Main Turbine X K3.0 1; Knowledge of the effect that a loss or 2.9/ 1 Generator malfunction of the MT/G will have on the 3.2 following: Remainder of the plant.

87 076 Service Water X A 1.02; Ability to predict and/or monitor changes in 2.6*/ 1 parameters (to prevent exceeding design limits) 2.6*

associated with operating the SWS controls including: Reactor and turbine building closed cooling water temperatures.

N/A 078 Instrument Air RANDOMAIY DESELECTED N/A 103 Containment RANDOMALY DESELECTED N/A K/A Category Point 0 11 2 1]012 11 0 0[0[1 Group Point Total:

Totals: I

[Note 1] Grayed out rows are not applicable to Millstone Unit Two (CE designed plant)

LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 3 Plant-Specific Priorities System / Topic Recommended Replacement for Reason Points Plant-Specific Priority Total: (limit 10)

LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 Facility: Millstone Unit 2 Date of Exam: 10/21/02 Exam Level: RO Category K/A # Topic Imp. Points Conduct of 2.1.14 Knowledge of system status criteria which require the notification of plant personnel. 2.5/3.3 1 Operations 2.1.25 Ability to obtain and interpret station reference materials such as graphs, momographs, and tables which contain 2.8/3.1 1 performance data.

Total 2 Equipment 2.2.27 Knowledge of the refueling process. 2.6/3.5 1 Control 2.2.12 Knowledge of surveillance procedures. 3.0/3.4 1 Total 2 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control. 2.6/3.0 1 Radiation 2.3.2 Knowledge of facility ALARA program. 2.5/2.9 1 Control 2.3.9 Knowledge of the process for performing a Containment Purge. 2.5/3.4 1 2.3.10 Ability to perform procedure to reduce excessive levels of radiation and guard against personnel exposure. 2.9/3.3 1 2.3.11 Ability to control radiation releases. 2.7/3.2 1 Total 5 Emergency 2.4.12 Knowledge of general operating crew responsibilities during emergency operations. 3.4/3.9 1 Procedures 2.4.17 Knowledge of EOP terms and definitions. 3.1/3.8 1 and Plan 2.4.25 Knowledge of fire protection procedures. 2.9/3.4 1 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control 3.4/3.7 1 room reference material.

Total 4 Tier 3 Target Point Total (RO/SRG) 13 LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

Record of Reiected K/As Tier/Group Randomly Selected K/A Reason for Rejection RO 1/1 AK1.03 Operation with <4 RCPs not allowed at MP2.

1/2 AA2.05 In-core TC map not used by operators in determining dropped CEA location.

1/2 AK3.08 RCPs not secured for SG tube leak at MP2.

1/2 AK3.09 Unrelated to K/A for MP2, maximum load change not required for SGTL.

1/3 AAI.05 Excess letdown is a manually initiated evolution at MP2, not a malfunction.

2/1 K5.40 Pressurizer flooded over and isolated from QT when drawing bubble at MP2.

2/1 K3.06 No effect on RRS at MP2 Gen/Cat 1 2.1.25 Approved deviation from "2 part" K/A. Question #89 (RO & SRO) addresses higher order portion of the 2 part K/A-"Interpret station reference material"; lower order portion-"Obtain" only requires removal from ordered file cabinet.

2/2 A4.04 Randomly selected new K/A (K1.03) due to inability to meet initial K/A SRO 1/1 EA2.01 "Inadequate Core Cooling" not an EOP at MP2, i.e.: determination of subcooling margin not procedurally significant.

2/1 Al.02 Question on this K/A won't discriminate between competent and not competent operator 2/1 K2.01 Power supplies to CS pumps, too basic 2/1 K3.02 Containment systems over-sampled; replaced with random selection (CVCS) 2/2 A1.01 Question on this K/A won't discriminate between competent and not competent operator Gen/Cat 2 2.2.2 K/A replaced; facility selected 10% replacement questions allowed under NUREG 1021 ES-401 D. 1.d. (Facility specific learning objectives MB-00062, MB-01416, MB-0144 1)

Ouestion Revision and Resolution RO Exam:

  1. 1 Corrected error in justification initially showing wrong selection as correct. */
  1. 5 Accepted as is after discussion of credibility of distractors. /
  1. 7 Removed "cue" from question stem and revised 2 distractors.
  1. 16 K/A required "explain and apply". Question initially required examinee to apply. Revised stem and expanded selections to require "explain" as well.
  1. 31 Revised answer selections to remove cueing words relating to stem.
  1. 32 Question replaced due to low level of difficulty. J
  1. 53 Corrected identification of correct answer selection in justification, C vice A. /
  1. 61 Revised question to address an electrical interlock vice procedural practice for accurate K/A match.
  1. 62 Revised stem to reflect focus of the question on "knowledge of power supplies" to better reflect K/A match.
  1. 63 Revised question stem to include a malfunction as required for K/A match.
  1. 68 Reselected K/A and replaced question due to inability to match initial K/A. /
  1. 69 Corrected typo in justification.

I

  1. 70 Replaced A & B distractors due to low credibility.
  1. 72 Same concept, but revised stem to be more operationally oriented.
  1. 76 Replaced one distractor and modified a second to improve credibility. /
  1. 78 Developed new question.
  1. 79 Accepted as is after discussion why one of the distractors was not also 7 correct.

/

  1. 83 Revised one distractor to prevent the correct selection from being a stand out.
  1. 88 Revised stem from "changing charging" to "when charging flow is raised" to accurately reflect condition of concern and to avoid potential mis-reading due to the similarity of changing and charging.
  1. 89 Accepted as an approved deviation under recent guidance from NRC HQ regarding 2 part K/As. The "obtain" portion of the K/A is low level and better tested in the operating portion of the test. The question addresses th higher order portion of the K/A, "interpret station reference material". This question is listed on Form 401-10 as an accepted deviation.
  1. 90 Replaced question. Initial question addressed trivial knowledge.
  1. 92 Question accepted as is after discussion of credibility of two of the-,

distractors.

  1. 93 Question replaced due to low level of difficulty. "'
  1. 99 Question replaced for better K/A match. /

SRO Only Exam:

  1. 10 Question revised to address both parts of the two part K/A.
  1. 15 Discussion of increasing vs. rising. Rising accepted due to MP2 procedural guidance to avoid use of increase and decrease in favor of rise and lower due to potential for communication error.
  1. 17 Removed procedural reference from stem. J
  1. 37 Revised from selecting applicable Tech Specs to selecting correct actions required by Tech Specs.
  1. 39 Revised one distractor to prevent the correct answer from being a stand-out. /
  1. 44 Accepted as is due to Tech Spec bases not provided. /
  1. 48 Accepted as is, necessary to specify which IA compressor is running due to K/A requirement for "knowledge of reasons" based on power supplies.
  1. 51 Removed procedural reference from stem and revised one distractor. #/
  1. 57 Replaced question due to low LOD.
  1. 62 Revised from selecting applicable Tech Specs to selecting correct actions required by Tech Specs.
  1. 84 K/A mismatch. Retained question and linked to appropriate K/A based on past instances of misunderstanding of Tech Spec at MP2.
  1. 86 One distractor revised.
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