ML102670495

Final Outlines (Folder 3)

ML102670495
Person / Time
Site:	Calvert Cliffs
Issue date:	07/13/2010
From:	Mark Draxton Constellation Energy Nuclear Group
To:	Peter Presby Operations Branch I
Hansell S
Shared Package
ML100560028	List: IR 05000317/2010301 ML102070208 ML102670378 ML102670380 ML102670391 ML102670392 ML102670396 ML102670401 ML102670495 ML102670496 ML102670508 ML102670524 ML111670753
References
TAC U01770
Download: ML102670495 (28)

Text

Calvert Cliffs 2010 Exam Operating Test - Change Summary, Draft to Final

1. Replaced Simulator JPM #4

2. Minor editorial changes

ES-401 PWR Examination Outline Form ES-401-2 IFacility: Calvert Cliffs Nuclear Power Plant Date ofExam: 08/02/2010 I RO Category KIA Points SRO Only Points Tier Group I

i K

K K.K *K K A

A A

A G

Total A2 G

Total 1

2 5

6 I

2 3

4 3 I 4

1. Emergency &

1 3

3 3

3 3

3 18 3

3 6

Abnormal Plant 2

1 2

1 N/A I

2 N/A 2

9 2

2 4

Evolutions Tier Totals 4

5 4

4 5

5 27 5

5 to 1

3 3

3 2

2 3

2 3

3 28 3

2 5

fJ-~

2. Plant Systems 2

1 1

0 1

I 1

1 1

1 10 2

1 3

Tier Totals 3

3 4

4 3

3 3

4 3

4 4

38 5

3 8

3. Generic Knowledge & Abilities I

2 3

4 1

2 3

4 to 7

Categories 3

2 2

3 2

2 2

1 I

Note:

1.

Ensure that at least two topics from every applicable KIA category are sampled within each tier ofthe RO and SRO-only outlines (i.e., except for one category in Tier 3 ofthe SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).

2.

The point total for each group and tier in the proposed outline must match that specified in the table.

The [mal point total for each group and tier may deviate by +/-I from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3.

Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.l.b of ES-40 I for guidance regarding the elimination of inappropriate KIA statements.

4.

Select topics from as many systems and evolutions a.s possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5.

Absent a plant-specific priority, only those KIAs having an importance rating (IR) of2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6.

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

7.*

The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 ofthe KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.I.b ofES-401 for the applicable KIAs.

8.

On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; iffuel handling equipment is sampled in other than Category A2 or G*

on the SRO-only exam, enter it on the left side ofColumn A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9.

For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

ES-401 PWR Examination Outline Form ES-401-2 Emergency & Abnormal Plant Evolutions - Tier 1 I Group 1 - REACTOR OPERATOR A

A

,Ki K K EIAPE #/Name/Safety Function G

KA Topic Imp Pts

. 1 2

3 1

2 Knowledge of the interrelations between 007 Reactor Trip - Stabilization -

X a reactor trip and the following:

2.6 1

Recovery /1 v;; EK2.02 - Breakers, relays and disconnects i

Ability to operate and I or monitor the 008 Pressurizer Vapor Space following as they apply to X

3.6 1

Accident 12 the Pressurizer Vapor Space Accident:

AAl.06 - Control ofPZR level Ability to determine or interpret the following as they apply to a 009 Small Break LOCA I 3 X

small break LOCA:

3.2 1

EA2.29 - CVCS pump indicating lights for determining pump status I

C--'

Knowledge of the interrelations between I

the and the following Large Break 011 Large Break LOCA I 3

• X' 2.6 1

LOCA:

EK2.02 - Pumps

~"

Knowledge of the operational implications of the following concepts as they apply to Reactor Coolant Pump

{,

Malfunctions (Loss of RC Flow):

015/017 RCP Malfunction I 4 X

2.9 1

AKl.04 - Basic steady state

! thermodynamic relationship between RCS loops and SIGs resulting from unbalanced RCS flow i

I T T I Ability to determine and interpret tbe 022 Loss of Reactor Coolant following as tbey apply to the Loss of X

3.2 1

Makeup/2 Reactor Coolant Makeup:

AA2.01-Whether charging line leak exists I

Ability to operate and I or monitor the following as they apply to the Loss of 025 Loss ofRHR System / 4 iX Residual Heat Removal System:

2.9 1

AA 1.08 - RHR cooler inlet and outlet i temperature indicators Ability to operate and I or monitor the following as they apply to the Loss of 026 Loss ofComponent Cooling Component Cooling Water:

X 3.1 1

Water 18 AA1.05 - The CCWS surge tank, including level control and level alarms, and radiation alarm I

r--'

i Knowledge of the interrelations between I

027 Pressurizer Pressure Control the Pressurizer Pressure Control X

2.6 1

System Malfunction / 3 Malfunctions and the following:

! AK2.03 - Controllers and positioners I

ES-401 PWR Examination Outline Form ES-401-2 Emergency & Abnormal Plant Evolutions - Tier 1 I Group 1 - REACTOR OPERATOR K

K K

A A EIAPE #iName/Safety Function

~,~

KA Topic Imp Pts 1

2 3

1

~.

Knowledge of the reasons for the I

following responses as the apply to the 029 ATWS/l 4.2 1

ATWS:

! X I i

EK3.01-Verifying a reactor trip; methods I

2.1.14 - Knowledge of criteria or 038 Steam Generator Tube Rupture conditions that require plant-wide X

3.1 1

/3 announcements, such as pump starts, reactor trips, mode changes, etc.

Knowledge of the operational I

040 Steam Line Rupture -

implications of the following concepts as X.

3.2 I

Excessive Heat Transfer / 4 they apply to Steam Line Rupture:

AKl.04 - Nil ductility temperature Knowledge of the reasons for the following responses as they apply to the 054 (CEIE06) Loss of Main (Loss of Feedwater)

X 3.2 1

F eedwater I 4 EK3.2 - Normal, abnormal and emergency operating procedures associated with (Loss I

of Feedwater).

i Ability to determine or interpret the following as they apply to a Station Blackout:

055 Station Blackout / 6 X

3.7 1

EA2.04 - Instruments and controls

! operable with only dc battery power

• available I

2.1.25 - Ability to interpret reference I

056 Loss ofOffsite Power / 6

• • X materials, such as graphs, curves, tables, 3.9 1

etc.

I Knowledge of the reasons for the I

following responses as they apply to the 057 Loss ofVital AC Inst. Bus 16 X*

4.1 1

Loss of Vital AC Instrument Bus:

AK3.01-Actions contained in EOP for loss of vital ac electrical instrument bus I

Knowledge of the operational implications of the following concepts as 058 Loss ofDC Power 16

! X they apply to Loss of DC Power:

2.8 1

AKLOI - Battery charger equipment and instrumentation I

1 2.4.45 - Ability to prioritize and interpret i

065 Loss of Instrument Air / 8 X the significance of each annunciator or 4.1 1

alarm.

I KIA Category Totals:

3 3

3 3

3 f I Group Point Total:

18

ES-401 PWR Examination Outline Form ES-401-2 Emergency & Abnormal Plant Evolutions Tier 1 / Group 2 - REACTOR OPERATOR I

K K

K A

A E/APE #/Name/Safety Function G

KA Topic Imp I Pts 1

2 3

1

2.. I.

Knowledge of the reasons for the I

I following responses as they apply to I

024 Emergency Boration 1 I X

Emergency Boration:

4.1 I

AK3.01 - When emergency boration is required 028 Pressurizer (PZR) Level 2.4.6 - Knowledge ofEOP Mitigation X

3.7 1

Control Malfunction 12 Strategies Knowledge of the interrelations between the Loss of Source Range Nuclear 032 Loss of Source Range Nuclear X

Instrumentation and the following:

2.7 1

Instrumentation 17 AK2.01 - Power supplies, including proper switch positions I

I Ability to operate and 1or monitor tbe following as they apply to the Fuel 036 Fuel Handling Incidents / 8 X

i Handling Incidents:

3.3 1

AAl.Ol - Reactor building containment purge ventilation system 2.2.40 - Ability to apply Technical 037 Steam Generator Tube Leak! 3 X

3.4 1

Specifications for a system Ability to determine and interpret the following as they apply to the Loss of 051 Loss ofCondenser Vacuum / 4 X

Condenser Vacuum:

3.9 1

AA2.02 - Conditions requiring reactor and/or turbine trip H

i I

Knowledge of the operational I

implications of the following concepts as 061 Area Radiation Monitoring they apply to Area Radiation 2.5 1

!X (ARM) System Alarms 17 i Monitoring (ARM) System Alarms:

! AKl.Ol - Detector limitations Ability to determine and interpret the following as they apply to the (Functional Recovery):

CElE09 - Functional Recovery X

3.2 1

EA2.1 - Facility conditions and selection of appropriate procedures during abnormal I and emergency operations.

i I

Knowledge of the interrelations between the (Excess RCS Leakage) and the following:

CE/A16 Excess RCS Leakage 12 X

AK2.1 - Components, and functions of 3.2 1

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

KIA Category Totals:

1 2

1 1

2 2 ! Group Point Total:

9

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 - REACTOR OPERATOR K

K K

K K

K A

A A

A System/Evolution #/Name G

KA Topic Imp Pts 1

2 3

4 5

6 1

2 3

4 I '

I, 2.1.30 - Ability to locate and 003 Reactor Coolant Pump X

operate components, including 4.4 I

System local controls.

Knowledge of the physical connections and/or cause-effect relationships between the 003 Reactor Coolant Pump

• X 3.3 1

RCPS and the following System systems:

I Kl.03 - RCP seal system i

I I

Knowledge of the effect that a loss or malfunction of the CVCS will have on the 004 Chemical and Volume X

3.4 1

following:

Control System

• K3.06 - RCS temperature and

• pressure Ability to manually operate and/or monitor in the control 004 Chemical and Volume X

3.6 1

room:

Control System A4.10 - Boric acid pumps Knowledge of the operational implications of the following concepts as they apply the 005 Residual Heat Removal X

3.2 1

RHRS:

System (RHRS)

K5.09 - Dilution and boration considerations I

I Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those predictions, use 006 Emergency Core Cooling X

3.9 1

procedures to correct, control, System or mitigate the consequences of those malfunctions or operations:

A2.02 - Loss of flow path It Knowledge of the operational implications of the following 007 Pressurizer Relief concepts as the apply to PRTS:

X 3.1 1

Tank/Quench Tank System K5.02 - Method offorming a steam bubble in the PZR I

I

ES-401 PWR Examination Outline Form ES-40 1-2 Plant Systems Tier 21 Group 1 - REACTOR OPERATOR K

K K

K K

K A

A A

A SystemlEvolution #lName G

KA Topic Imp Pts 1

2 3

4 5

6 1

2 3

4 Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use Ie procedures to correct, control, 008 Component Cooling or mitigate the consequences of X

3.3 1

Water System those malfunctions or operations:

A2.05 - Effect of loss of instrument and control air on the position ofthe CCW valves that I

are air operated I

Knowledge of bus power I

supplies to the following:

010 Pressurizer Pressure X

2.5 I

Control System K2.02 - Controller for PZR spray valve I

2.2.2 - Ability to manipulate the e

console controls as required to 010 Pressurizer Pressure X

operate the facility between 4.6 1

Control System shutdown and designated power levels.

• Knowledge of the effed that a loss or malfunction of the RPS 012 Reactor Protection X

3.2 I

will have on the following:

System K3.02 - T/G I

t.

Ability to monitor automatic operation of the RPS, 012 Reactor Protection X

3.8 1

including:

System A3.01-Individual channel Knowledge of the effect of a loss or malfunction on the following 013 Engineered Safety X

2.7 1

will have on the ESFAS:

Features Actuation System K6.0 I - Sensors and detectors Ability to monitor automatic 1

operation of the CCS, 022 Containment Cooling including:

X 4.1 1

System (CCS) i A3.0 1 - Initiation of safeguards mode of operation I

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 I Group 1 - REACTOR OPERATOR K

K K

K K

K A

A A

A SystemlEvolution #lName G

KA Topic Imp Pts 1

2 3

4 5

6 1

2 3

4 Knowledge of ess design I

I I

feature(s) andlor interlock(s) which provide for the 026 Containment Spray X

following:

3.8 I

System (CSS)

K4.07 - Adequate level in containment sump for suction (interlock) i Knowledge of the operational implications of the following 039 Main and Reheat Steam concepts as they apply to the Xi 2.7 1

(MRSS)System MRSS:

K5.05 - Bases for RCS cooldown limits Knowledge of MRSS design feature(s) andlor interlock(s) which provide for the following:

039 Main and Reheat Steam X

K4.02 - Utilization of Tave.

3.1 1

(MRSS)System program control when steam dumping through atmospheric relief/dump valves, including T ave. limits Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits) associated with 059 Main Feedwater System X

operating the MFW controls 2.7 1

(MFW) including:

Al.03 - Power level restrictions for operation of MFW pumps and valves.

Knowledge of the effect that a 061 Auxiliary / Emergency loss or malfunction of the AFW I

X 4.2 I

Feedwater System (AFW) will have on the following:

K3.02-S/G

~..

Knowledge of bus power 062 A.C. Electrical X

supplies to the following:

3.3 I

Distribution K2.0l - Major system loads i

1.

Ability to manually operate I

andlor monitor in the control 062 A.C. Electrical

• X room:

3.3 I

Distribution A4.01 - All breakers (including available switchyard)

I I

I I

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 - REACTOR OPERATOR SystemlEvolution #lName K

1 KIillIillJ A 2

1 A

1 A

3 A

4 G

KA Topic Imp Pts 063 D.C. Electrical Distribution i

X Ability to (a) predict the impacts of the following malfunctions or operations on the DC electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences ofthose malfunctions or operations:

A2.0 1 - Grounds 2.5

]

064 Emergency Diesel Generators X

Ability to manually operate and/or monitor in the control room:

A4.06 - Manual start, loading, and stopping ofthe ED/G 3.9 1

064 Emergency Diesel Generators X

Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system:

2.7 1

K6.07 - Air receivers 073 Process Radiation Monitoring System X

2.4.18 - Knowledge ofthe specific bases for EOPs.

3.3 1

076 Service Water System (SWS)

X Knowledge of SWS design feature(s) and/or interlock(s) which provide for the following:

K4.02 - Automatic start features associated with SWS pump controls 2.9 1

078 Instrument Air System (lAS)

X Knowledge of the physical connections and/or cause-effect relationships between the lAS and the following systems:

K].04 - Coo ling water to compressor 2.6 I

103 Containment System X

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the containment system controls including:

3.7 I

Al.OI

• Containment pressure, temperature, and humidity KIA Category Totals:

2 2

3 3

3 2 12 3

2 3

3 Group Point Total:

28

ES-401 PWR Examination Outline Form ES-40l-2 Plant Systems - Tier 2 / Group 2 - REACTOR OPERATOR K

K A

SystemlEvolution #lName G

KA Topic Imp Pts 1

2 6

1 lITh K 1itil Knowledge of RCS design feature(s) and/or interlock(s) which provide for the Following:

002 Reactor Coolant System X

3.1 1

K4.07 - Contraction and expansion during heatup and cooldown Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) based on those predictions, use 011 Pressurizer Level Control X

3.0 1

procedures to correct, control, System or mitigate the consequences of those malfunctions or operations:

A2.07 - Isolation of letdown Knowledge of the effect of a loss or malfunction of the 015 Nuclear Instrumentation X

2.9 1

following will have on the NIS:

K6.0 1 - Sensors and detectors K2 Knowledge of bus power 027 Containment Iodine X

supplies to the following:

3.1 1

Removal System K2.01 - Fans Knowledge of the effect that a loss or malfunction of the Spent Fuel Pool Cooling 033 Spent Fuel Pool Cooling X

2.6 1

System will have on the System following:

K3.01 - Area ventilation systems A4 - Ability to manually operate and/or monitor in the control 034 Fuel Handling Equipment X

3.5 1

room:

System (FHES)

A4.02 - Neutron levels Ability to monitor automatic operation of the S/G including:

035 Steam Generator System X

4.0 1

A3.01 - S/G water level control I

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 2 - REACTOR OPERATOR K

K K

K K

K A

A A

A SystemlEvolution #lName G

KA Topic Imp Pts 1

2 3

4 5

6 1

l 3

4 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with 045 Main Turbine Generator operating the MT/G system X

3.3 1

System controls including:

A 1.06 - Expected response of secondary plant parameters following T/G trip Knowledge of the pbysical connections and/or cause effect relationsbips between the SAS 079 Station Air System X

3.0 1

and tbe following systems:

Kl.Ol - lAS 2.4.31-Knowledge of 086 Fire Protection System X annunciator alarms, indications, 4.2 1

or response procedures.

KIA Category Totals:

1 1

0 I

1 l

1 1 I 1 Group Point Total:

10 Ell

1 ES-401 PWR Examination Outline Form ES-401-2 Emergency & Abnormal Plant Evolutions - Tier 1 / Group 1 - SENIOR REACTOR OPERATOR E/APE #/Name/Safety K

K K

A A

G KA Topic Imp Pts Function 1

2 3

1 2

2.2.44 - Ability to interpret control room indications to verifY the status and oII Large Break LOCA 1 3 X

operation of a system, and understand how 4.4 operator actions and directives affect plant and system conditions.

054 Loss ofMain Feedwater 2.2.38 - Knowledge of conditions and X

4.5 1

14 limitations in the facility license.

2.4.40 - Knowledge of SRO 055 Station Blackout 1 6 X

responsibilities in emergency plan 4.5 1

implementation.

Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water:

062 Loss of Nuclear Service X

2.9 1

Water 14 AA2.04 - The normal values and upper limits for the temperatures ofthe components cooled by SWS Ability to determine and interpret tbe following as tbey apply to the (Reactor Trip Recovery)

CE/E02 Reactor Trip X

3.7 1

Recovery 11 EA2.1 - Facility conditions and selection ofappropriate procedures during abnormal and emergency operations.

Ability to determine and interpret the following as they apply to the (Excess Steam Demand):

CElE05 Excess Steam X

4.0 1

Demand 14 EA2.1 - Facility conditions and selection ofappropriate procedures during abnormal and emergency operations.

IKIA Category Totals:

0 0

0 0

3 3

Group Point Total:

I 6

1 ES-40I PWR Examination Outline Form ES-40l-2 Emergency & Abnormal Plant Evolutions - Tier 11 Group 2 - SENIOR REACTOR OPERATOR E/APE #iName/Safety Function 003 Dropped Control Rod 1 069 Loss of Containment Integrity 1 5 CE/A13 Natural Circulation Operations 14 CElE09 Functional Recovery KIA Category Totals:

K 1

K 2

K 3

A 1

A 2

G KA Topic Imp Pts IX 2.4.11 - Knowledge of abnormal condition procedures.

2.2.39 - Knowledge ofless than or equal to X

one hour Technical Specification action statements for systems.

Ability to determine and interpret the following as they apply to the (Natural X

Circulation Operations):

3.7 I

AA2.1 - Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

Ability to determine and interpret the following as they apply to the (Functional Recovery):

X EA2.2 - Adherence to appropriate 4.0 I

procedures and operation within the limitations in the facility's license and amendments.

0 0

0 0

2 2

Group Point Total:

4

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1-SENIOR REACTOR OPERATOR SystemlEvolution #lName 005 Residual Heat Removal System 006 Emergency Core Cooling 039 Main and Reheat Steam System 061 Auxiliary / Emergency Feedwater System 062 AC Electrical Distribution IKIA Category Totals:

K K K

K K

K A

A A

A G

KA Topic Imp Pts 1 2 3 4

5 6

1 2 3 4 2.1.23 - Ability to perform specific system and integrated X

4.4 1

plant procedures during all modes of plant operation..

2.2.22 - Knowledge oflimiting X conditions for operations and 4.7 I

safety limits.

Ability to (a) predict the impacts ofthe following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to X

3.2 I

correct, control, or mitigate the consequences of those malfunctions or operations:

A2.01 - Flow paths of steam during a LOCA Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use X

3.5 I

procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.07 - Air or MOV failure Ability to (a) predict the impacts of the following malfunctions or operations on the lAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the X

3.9 I

consequences of those malfunctions or operations:

A2.01 - Types ofloads that, ifde energized, would degrade or hinder plant operation 5

1010101010101013101012 1Group Point Total:

I

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/ Group 2 SENIOR REACTOR OPERATOR SystemlEvolution #lName K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

KA Topic Imp Pts 014 Rod Position Indication System I

X 2.4.30 - Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

4.1 1

041 Steam Dump System and Turbine Bypass Control I

X Ability to (a) predict the impacts of the following malfunctions or operations on the SDS; and (b) based on those predictions or mitigate the consequences of those malfunctions or operations:

3.1 1

A2.03 - Loss ofIAS 035 Steam Generator System (S/GS)

X A2 - Ability to (a) predict the impacts of the following malfunctions or operations on the SG; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

4.6 1

I A2.06 Small Break LOCA KIA Category Totals:

0 0

0 0

0 0

0

2. 0 0

1 Group Point Total:

3

ES-401 PWR Examination Outline Form ES-401-3 Tier 3 Generic Knowledge & Abilities Outline - RO & SRO Facility: Calvert Cliffs Nuclear Power Plant Date ofExam: 08/02/2010 I RO SRO Category KIA #

Topic IR IR 2.1.20 Ability to interpret and execute procedure steps.

4.6 1

2.1.21 Ability to verify the controlled procedure copy.

3.5 1

Conduct Ability to interpret reference materials, such as graphs, curves, 2.1.25 3.9 1

tables, etc.

of Operations 2.1.32 Ability to explain and apply system limits and precautions.

4.0 1

2.1.42 Knowledge of new and spent fuel movement procedures.

3.4 1

Subtotal 3

2 2.2.l3 Knowledge oftagging and clearance procedures.

4.1 1

Ability to determine operability and/or availability of safety related 2.2.37 3.6 1

equipment.

Knowledge ofthe process for making design or operating changes to 2.2.5 3.2 1

Equipment Control the facility.

Ability to analyze the effect of maintenance activities, such as 2.2.36 degraded power sources, on the status of limiting conditions for operations.

4~

1

~

Subtotal I

2 2

2.3.11 Ability to control radiation releases.

3.8 1

Knowledge ofradiation exposure limits under normal or emergency 2.3.4 3.2 1

conditions.

Ability to use radiation monitoring systems, such as fixed radiation Radiation Control 2.3.5 monitors and alarms, portable survey instruments, personnel 2.9 1

monitoring equipment, etc.

Knowledge of radiation or contamination hazards that may ari I

2.3.14 I

3.8 1

during normal, abnormal, or emergency conditions or activiti Subtotal 2

2 Ability to recognize abnormal indications for system operating 2.4.4 parameters that are entry-level conditions for emergency and 4.5 1

abnormal operating procedures.

2.4.11 Knowledge ofabnormal condition procedures.

4.0 1

Emergency ProcedureslPlan 2.4.14 Knowledge of general guidelines for EOP usage.

3.8 1

Knowledge of facility protection requirements, including fire 2.4.26 3.6 1

brigade and portable fire fighting equipment usage.

Subtotal 3

1 ITier 3 Total 10 I I 7 1

1'1 I

ES-401 Record of Rejected K/As Form ES-401-4

!I Tier I Group Randomly Selected KIA Reason for Rejection Not applicable at CCNPP. There is no link between ATWS and the RO - 111 System 029, EK3.03 operation ofBIT inlet or outlet valves. Replaced with randomly drawn (using numbered poker chips) 029 EK3.01 KIA mismatch for EIAPE. Radiation exposure limits with respect to System 056, Generic RO - 111 LOOP? Replaced with randomly drawn (using numbered poker 2.3.4 chips) Generic KIA 2.1.25 Could not generate a suitable question. First attempt was rejected by validators. Replaced with randomly drawn system # 011 and KIA RO - III System 077, EK2.07 EK2 (using numbered poker chips). Used KIA # EK2.02 (only KIA with RO importance rating of> 2.5)

CCNPP procedural direction is to trip the reactor ifplacing CEDS in RO - 1/2 System 001, AK3.01 offdoes not terminate the event. Replaced with randomly drawn system # 024 (using numbered poker chips). Used same KIA #.

CCNPP does not have an Intermediate Range NI System. Replaced RO-1I2 System 033, AA2.02 with randomly drawn system # 076 (using numbered poker chips).

Used same K/A#.

Could not generate a question after several hours effort. Replaced RO - 112 System 059, 2.2.40 with randomly drawn system # 037 (using numbered poker chips).

Used same KIA #.

Radiation release/detection oversampled throughout outline.

Replaced with randomly drawn CEIA 16, AK2.I. Other items sampled for this exam include:

061, AKl.Ol (RO) 073,2.4.18 (RO) 068, A4.04 (RO)

RO-112 System 060, AK2.0 1 2.3.11 (RO) 2.3.13 (RO) 071, A2.09 (SRO) 2.3.5 (SRO) 2.3.14 (SRO)

Could not generate a satisfactory question after several attempts.

System 076, KIA RO - I12 Replaced with (using numbered poker chips) randomly drawn system AA2.02 CE/09 and KIA EA2.1.

ES-401 I Tier I Group Randomly Selected KIA RO 211 System 0 I 0, 2.2.1 RO-2/1 System 064, A4.07 RO-211 System 073, K4.02 RO - 2/1 System 076, K4.03 RO-211 System 103, A4.06 RO-2/2 System 002, K4.07 RO-2/2 System 017, K6.01 RO-2/2 System 028, K2.01 RO -2/2 System 035, A3.02 RO-2/2 System 068, A4.04 RO -2/2 System 086, G 2.4.49 Record of Rejected KJAs Form ES-40 1-4 Reason for Rejection KIA not a good match for the system selected. Replaced with randomly drawn KIA 2.2.2 A JPM was previously selected that covered the exact same subject matter. Replac(~d with randomly drawn (using numbered poker chips)

KIA, A4.06 Not applicable at CCNPP. Replaced with randomly drawn system 039 (using numbered poker chips) using same KIA (K4.02). Selected new system because the remaining System 073, K4 essentially mirrors the Tier 2 I Group 2 System 068 KIA that was sampled.

Not applicable at CCNPP. There are no automatic opening features associated with the SWS isolation valves to CCW. Replaced with randomly drawn (using numbered poker chips) K4.02 Low operational validity. Replaced with randomly drawn System (using numbered poker chips) 0062, and KIA A4.01.

Could not generate a suitable question. First attempt was rejected by NRC as SRO level. Replaced with randomly drawn system KIA #

K4.10 (using numbered poker chips).

Could not generate a suitable question. First attempt was rejected by validators. Replaced with randomly drawn system # 015 (using numbered poker chips). Used original KIA #.

H2 Recombiners no longer SR @ CCNPP. Replaced with randomly drawn system # 027 (using numbered poker chips). Used original KlA#.

Selected new KIA. This KIA essentially mirrors the Tier 2 I Group 1 System 039 KIA that was sampled. Replaced with remaining System 35 KIA, A3.0I, having an importance rating of=:: 2.5.

Could not write a sufficiently discriminating question using this KIA Replaced with randomly drawn (using numbered poker chips) system 034 and KIA A4.02 KIA Not applicable at CCNPP. There are no from memory "immediate actions" associated with the Fire Protection System.

Replaced with randomly drawn (using numbered poker chips) KIA G 2.4.31

ES-401 Tier 1Group Randomly Selected KIA SRO-111 System 065, 2.4.40 SRO-1I2 System 068, 2.2.23 SRO -1/2 System 003, 2.2.23 SRO-1/2 CE/AI3, AA2.2 SRO -211 System 005, G2.1.39 SRO-211 System 076, G2.1.3.4 SRO-211 System 078, A2.0 I SRO -2/2 System 071, A2.09 RO - Generic KIA 2.1.9 RO - Generic KIA 2.3.13 RO - Generic KIA 2.4.23 Record of Rejec:ted KIAs Form ES-40 1-4 Reason for Rejection Discussed with Peter Presby. KIA mismatch for EI APE. Replaced with randomly drawn System (using numbered poker chips) 055, using original KJA.

Discussed with Peter Presby. KIA mismatch for EI APE. Replaced with randomly drawn System 003 (using numbered poker chips),

using original KJA.

Could not generate a suitable question. First attempt was rejected by NRC. Replaced with randomly drawn Generic KIA 2.4.11 (using numbered poker chips).

Could not generate a suitable question. First attempt was rejected by validators. Replaced with remaining AA2 KIA, AA2.1.

KIA not one of group specified for random sampling in ES-40 I.

Replaced with randomly drawn (using numbered poker chips) KIA G2.1.23.

Discussed with Peter Presby. KIA Not applicable at CCNPP. Open cooling water system has no chemistry limits. Replaced with randomly drawn (using numbered poker chips) System 006, and KIA G 2.2.22.

Sampled in last exam written for CCNPP. Malfunctions ofthis component are limited in scope. Randomly sampled new system (using numbered poker chips) 062, kept same KIA Could not generate a suitable question. First attempt was rejected by NRC. Replaced with randomly drawn system # 035 (using numbered poker chips) and KIA # A2.06.

2.1.9 is SRO responsibility. Replaced with randomly drawn (using numbered poker chips) G2.1.20.

Could not generate a suitable question. First attempt was rejected by NRC. Replaced with randomly drawn (using numbered poker chips)

KIA # 2.3.4.

2.4.23 is SRO responsibility. Replaced with randomly drawn (using numbered poker chips) G2.4.ll.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: 8/2/10 - 8/11/10 Exam Level: RO / SRO-U Administrative Topic (see Note)

Conduct ofOperations Conduct of Operations Equipment Control Radiation Control Emergency Procedures /

Plan Operating Test No.: 2010 Type Describe activity to be performed Code*

Ability to Implement Plant procedures for Condenser tube leak.

N,R (SRO-Admin-l) 2.1.34 - Knowledge of primary and secondary plant chemistry limits. (2.7, 3.5)

Verify an Estimated Critical Condition calculation.

(SRO-Admin-2)

M,R 2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9,4.2)

Monitor Azimuthal Power Tilt (Tq) using Excore NIs.

(SRO-Admin-3)

D,R 2.2.42 - Ability to recognize system parameters that are entry-level conditions for Technical Specifications. (3.9,4.6)

Approve a Liquid Waste Discharge Permit.

M,R (SRO-Admin-4) 2.3.6 - Ability to approve release permits. (2.0, 3.8)

Determine the appropriate emergency response actions per the ERPIP while maintaining an overview ofplant conditions.

D,R (SRO-Admin-5) 2.4.41 - Knowledge of the emergency action level thresholds and classifications.(2.9,4.6)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank 3 for ROs; ::; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank

1)

(P)revious 2 exams I; randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Calvert Cliffs Nuclear Power Plant Date ofExamination: 8/2/10 - 8/ll/10 Exam Level: RO I SRO-I 1SRO-U Operating Test No.: 2010

• Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System 1JPM Title Type Code*

Function

a.

002 - Use procedures to correct Loss ofForced Circulation D,S,L 4 (primary)

(Sim-2)

b.

004 - Respond to RCS leakage exceeding one Chg Pp, Modes 1 and 2 A,D,S 2

(Sim-3)

c.

006 Verify Recirculation Actuation Signal A, EN, M, S 3

(Sim-4)

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

d.

022 - Start 11 & 12 Containment Air Coolers D,E,P,R 5

(Plant-I)

e.

059 - Respond to a FRV or FRV Controller Malfunction D,E,P 4 (secondary)

(Plant-2)

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I 1SRO-U (A)ltemate path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank S:9/S:8/S:4 (E)mergency or abnormal in-plant 2::1/2::112::1 (EN)gineered safety feature I 2::1 (control room system)

(L)ow-Power 1Shutdown 2::1/2::1/2::1 (N)ew or (M)odified from bank including l(A) i 2::2/2::2/2::1 (P)revious 2 exams s: 3 IS: 3 1s: 2 (randomly selected)

(R)CA 2::1/2::1/2::1 (S)imulator II

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: 8/2/10 - 8/11110 Exam Level: RO / SRO-I Operating Test No.: 2010 Administrative Topic (see Note)

Conduct ofOperations Conduct of Operations Equipment Control Radiation Control Emergency Procedures / Plan Type Describe activity to be performed Code*

Ability to Implement Plant procedures for Condenser tube leak.

(SRO-Admin-l )

N,R 2.1.34 - Knowledge of primary and secondary plant chemistry limits. (2.7" 3.5)

Verify an Estimated Critical Condition calculation.

(SRO-Admin-2)

M,R 2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9,4.2)

Monitor Azimuthal Power Tilt (Tq) using Excore NIs.

(SRO-Admin-3)

D,R 2.2.42 - Ability to recognize system parameters that are entry-i level conditions for Technical Specifications. (3.9,4.6)

Approve a Liquid Waste Discharge Permit.

M,R (SRO-Admin-4) 2.3.6 - Ability to approve release permits. (2.0, 3.8)

Determine the appropriate emergency response actions per the ERPIP while maintaining an overview of plant conditions.

D,R (SRO-Admin-5) 2.4.41 - Knowledge ofthe emergency action level thresholds and classifications.(2.9,4.6)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank 3 for ROs; :S 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (2: 1)

(P)revious 2 exams (:S 1; randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: 8/211 0 8/11110 Exam Level: RO 1SRO-I / SRO-U Opt:rating Test No.: 2010 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a.

001 Respond to multiple misaligned CEAs A,N,S 1

(Sim-I)

b.

002 - Use procedures to correct Loss of Forced Circulation D,S,L 4 (primary)

(Sim-2)

c.

004 - Respond to RCS leakage exceeding one Chg Pp, Modes 1 and 2 A,D,S 2

(Sim-3)

d.

006 - Verify Recirculation Actuation Signal A,EN,M,S 3

(Sim-4)

e.

022 - Verify the Containment Environment Safety Function is satisfied D,S 5

(Sim-5)

f.

034 - Respond to a Containment Fuel Handling Incident N,S 8

(Sim-6)

g.

059 - Recover from Automatic Feedwater Isolation A,S,D 4 (secondary)

(Sim-7)

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

h.

022 - Start 11 & 12 Containment Air Coolers D,E,P,R 5

(Plant-I)

i.

059 - Respond to a FRV or FRV Controller Malfunction D,E,P 4 (secondary)

(Plant-2)

j.

062 - Align the OC DG to 11 4 KV Bus D,E 6

(Plant-3)

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO 1SRO-I / SRO-U (A)lternate path 4-6/4-6/2-3 (C)ontro\\ room (D)irect from bank 59/58/54 (E)mergency or abnormal in-plant

~1/2=1/2=1 (EN)gineered safety feature

- / - /

~l (control room system)

(L)ow-Power / Shutdown 2=1/2=1/2=1 (N)ew or (M)odified from bank including leA) 2=2/2=2/2= 1 (P)revious 2 exams 5 3 / :5 3 / 5 2 (randomly selected)

(R)CA

~1I2=1I~1 (S)imulator I

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: 8/2/10 8/11/10 Exam Level: RO I SRO-I Operating Test No.: 2010 Type Administrative Topic (see Note)

Describe activity to be performed Code*

Estimate Time to Boiling and Core Uncovery Conduct of Operations N,S (RO-Admin-l) 2.1.20 - Ability to interpret and execute procedure steps.

Monitor Azimuthal Power Tilt (Tq) using Excore Nls.

(RO-Admin-2)

Conduct ofOperations M,R 2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc.

(3.9,4.2)

Verify CCW System valve operability (RO-Admin-3)

Equipment Control N,R 2.2.21 Knowledge ofpre-and post-maintenance operability requirements.

(2.9,4.1 )

Radiation Control Recall the Emergency Response Organization IA W ERPIP 3.0.

(RO-Admin-4)

Emergency Procedures / Plan D,S 2.4.39 - Knowledge of RO responsibilities in emergency plan implementation. (3.9, 3.8)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank 3 for ROs; :s 4 for SROs & RO retakes)

(N)ew or (M)odified from bank

1)

(P)revious 2 exams 1; randomly selected)

1 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Calvert Cliffs Nuclear Power Plant Date ofExamination: 8/2/10 - 8111110 Exam Level: RO 1SRO-I I SRO-U Ope:rating Test No.: 2010 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System 1JPM Title Type Code'"

Function

a.

001 - Respond to multiple misaligned CEAs A,N,S (Sim-I)

b.

002 - Use procedures to correct Loss of Forced Circulation D,S,L 4 (primary)

(Sim-2)

I

c.

004 - Respond to RCS leakage exceeding one Chg Pp, Modes 1 and 2 A,D,S 2

(Sim-3)

d.

006 - Verify Recirculation Actuation Signal A,EN, 3

(Sim-4)

e.

022 - Verify the Containment Environment Safety Function is satisfied D,S 5

(Sim-5)

f.

034 - Respond to a Containment Fuel Handling Incident N,S 8

(Sim-6)

g.

059 - Recover from Automatic Feedwater Isolation A,S,D 4 (secondary)

(Sim-7)

h.

064 - Transfer 4KV Bus Loads from DG to Offsite Power Source D,S 6

(Sim-8)

In-Plant Systems@ (3 for RO); (3 for SRO-J); (3 or 2 for SRO-U)

i.

022 - Start 11 & 12 Containment Air Coolers D,E,P,R 5

(Plant-I)

j.

059 - Respond to a FRV or FRV Controller Malfunction D,E,P 4 (secondary)

(Plant-2)

k.

062 - Align the OC DG to 11 4 KV Bus D,E 6

(Plant-3)

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

'" Type Codes Criteria for RO / SRO-I / SRO-U (A)ltemate path 4-6/4-6/2-3 (C)ontrol room (D)irect from bank

$9/::;8/::;4 (E)mergency or abnormal in-plant

~1/~1/~1 (EN)gineered safety feature 1 ~1 (control room system)

(L)ow-Power 1Shutdown

~1/~1/~1 (N)ew or (M)odified from bank including I(A)

~2/~2/~ I (P)revious 2 exams

31

:; 3 / ::; 2 (randomly selected)

(R)CA

~l/~l/~I (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility:

CCNPP Scenario No.:

1 Op-Test No.:

2010 Examiners:

Operators:

Initial Conditions:

U-1 is at 100% [lower MOC 10,885 MWD/MTU with long term stead~ state [2ower histor~. U-2 at 100% power BOC.

Turnover:

1 A DIG removed from service and tagged out for scheduled maintenance {return in 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s}, with OC DIG aligned to 11 4kv bus (disconnect 189-1106 shut}.

13 CBP is in PTL and is considered emergency use only due to high vibrations. Instructions for the shift are to maintain l20wer @ 100%.

Event Event Malf. No.

Event Type*

No.

Description RCS023 02 PZR Press Xmtr 100Y fails low RCS024 03 I (ATC)

PZR Press Xmtr lO2C fails low 1

RCS025 02 TS (SRO)

PZR Press Xmtr 103-1 fails low RCS026 02 PZR level XMTR 1 lOY fails hiJ2:h C (ALL) 2 RCS003 20 gpm RCS leak TS (SRO)

R(ATC!SRO) 3 Expeditious Downpower N (BOP) 4 HDV005 02 C (BOP/SRO) 12 Condensate Booster Pump Failure w/o auto start of standby 5

SWYD002 M (ALL)

Loss of offsite power 6

CEDSOI0 C (ATC) 2 Stuck CEA's 7

DG002 02 C (BOP)

IB DIG Auto Start Failure C (BOP/SRO) 8 4KVOOl 02 11 4kv bus electrical fault TS (SRO)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Critical Tasks: (bold)

Commence boration due to 2 stuck CEA's prior to losing 114KV bus on fault Restore 4kv vital bus power with OC DIG to 14 4KV bus (after Station Blackout)

19Appendjx D Scenario Oytline Form ES*O*1 Facility:

CCNPP Scenario No.:

2 Op-Test No.: 2010 Examiners:

Operators:

Initial Conditions:

U-1 is at 100% gower EOC, 15,500 MWD/MTU with long term steady state Qower histo[Y. U-2 at 100% Qower MOC Turnover:

11 HPSI PumQ is removed from service for scheduled rnaintenance (return in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />). 13 CCW gurnQ is 005 for work on 3ro gumQ disconnect. 13 CBP is for emergency use onli! due to high vibrations.

Instructions for the shift is to remain at 100% gower.

Event Event Malf. No.

Event Type*

No.

Description I

CNTMOOI 04 TS (SRO) 14 Containment Air Cooler failure C (BOP/SRO) 2 TG017 Turbine vibration on bearing 4 R(ATC)

C (ATC) l-CVC-SI4-MOV breaker failure & l-CVC-S08-MOV, l-CVC 3

Various 509-MOV fail to open.

TS (SRO) 4 TGOOI C (ALL)

Turbine trip RPSOO5, 5

RPS006 &

C (ATC)

RPS & Manual Trip Pushbutton failure DSS failure 6

CCW002 01 C (BOP) 11 Component Cooling Pump failure 7

RCS022 M (ALL)

Pressurizer Safety Valve fails to reseat (leak on top ofPZR) 8 ESFAOOI 02 I (BOP)

SIAS B failure (N)ormal, (R)eactivity, (I)nstrument, {C)omponent, (M)ajor Critical Tasks (bold):

Trip Reactor from electrical panels due to A TWS Trip all Rep's due to no cooling prior to exceeding temperature limits Manually actuate SIAS B prior to superheat

Appendix 0 Scenario Outline Form ES-O-1 Facility:

CCNPP Scenario No.:

4 Op-Test No.:

2010 Examiners:

Operators:

Initial Conditions:

U-1 is at 100% power MOC 10,885 MWD/MTU long term steady state, U-2 is at 100% power EOC.

Turnover:

13 4kv bus aligned to alternate feed while normal feed breaker 152-1311 is OOS for scheduled maintenance.

Event Event Malf, No.

Event Type*

No.

Description C (SROlBOP) 1 MS009 01 TBV 3940 fails open R(ATC) 2 480vOOI 04 C (SROlBOP) 12B 480V bus failure 3

CVCS003 01 C (ATC) 11 Charging Pump coupling failure I (BOP) 4 ESFA009 02 Spurious CIS B Actuation TS (SRO)

I CVCSOO9 I (ATC)

VCT level transmitter fails high 6

CCW003 C (All)

Component Cooling leak in the containment M (All) 7 MS002_02 12 S/G tube rupture TS (SRO)

(I

ity, (I}nstrument, (r t

(M)ajor Critical Tasks (bold):

Secure RCP's prior to exceeding temp limits.

Isolate S/G in EOP-6 Depressurize RCS to minimize leakage