ML12325A281

Final Outlines (Folder 3)

ML12325A281
Person / Time
Site:	Limerick
Issue date:	11/15/2012
From:	Caruso J Operations Branch I
To:	Wasong A Exelon Generation Co
Jackson D
Shared Package
ML120230224	List: IR 05000352/2012301 ML120270009 ML12276A134 ML12279A055 ML12325A281 ML12325A303 ML12325A327 ML12325A335 ML12325A347 ML12332A082 ML12339A154 ML12339A158 ML12339A166 ML12339A170 ML12339A183
References
TAC U01858
Download: ML12325A281 (28)

Text

II ES-401 BWR Examination Outline Form ES-401-1 Date of Exam:

RO KIA Category Points SRO-Only Points Tier Group K

K K

K K

K A A A A G A2 G*

Total 2

3 4 5 6 1

2 3 4

Total

1.

1 4

4 2

20 7

Emergency &

Abnormal Plant N/A 1

1 N/A 1

7 3

Evolutions 5

5 3

27 10 1

2 3

2 3

3 1

2 26 5

2.

2 0

I I

1 I

2 1

I 2

12 3

Systems Plant Tier Totals 2

2 2

6 4

5 3

2 4

38 8

3. Generic Knowledge and Abilities 1

2 3

4 10 1

2 3

4 7

Categories 3

2 2

3 Note:

1.

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

2.

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

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

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.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.

4.

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

5.

Absent a plant-specific priority, only those KlAs having an importance rating OR) of 2.5 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 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KlAs.

S.

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; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam. enter it on the left side of Column A2 for Tier 2. Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO*only exams.

9.

For Tier 3, select topics from Section 2 of the KIA catalog. and enter the KIA numbers, descriptions. IRs,

"'"" I-'"",t totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

ES-401 2

Form ES-401-1 I

ES-401 BWR Examination Outline Form ES-401-1 Emergenc~ and Abnormal Plant Evolutions - Tier 1/Group 1 (RO I SRO)

E/APE # I Name I Safety Function K

K K A A G

KIA Topic(s)

IR 1

2 3

1 2

295001 Partial or Complete Loss of Forced X

AK3.06: Knowledge ofthe reasons for the following 2.9 I

Core Flow Circulation 11 &4 responses as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:

3.0 Core flow indication 295003 Partial or Complete Loss of AC I 6 X

AA2.02: Ability to detennine and/or interpret the 4.2 2

following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: Reactor power I pressure I and 4.3 level 295004 Partial or Total Loss of DC Pwr 16 X

AKI.05: Knowledge of the operational implications of 3.3 3

the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Loss ofbreaker 3.4 protection 295005 Main Turbine Generator Trip I 3 X G2.1.32: Ability to explain and apply system limits and 3.8 4

precautions as they relate to MAIN TURBINE GENERATOR TRIP.

4.0 295006 SCRAM I 1 X

AK2.04: Knowledge ofthe interrelations between 3.6 5

SCRAM and the following: Turbine trip logic 3.7 AAI.06: Ability to operate and/or monitor the following 295016 Control Room Abandonment! 7 X

4.0 6

as they apply to CONTROL ROOM ABANDONMENT:

Reactor water level 4.1 295018 Partial or Total Loss of CCW I 8 X

AA2.01: Ability to detennine and lor interpret the 3.3 7

following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:

3.4 Component temperatures 295019 Partial or Total Loss of Inst. Air I 8 X

AA 1.0 I: Ability to operate and/or monitor the backup air 3.5 8

supply as it applies to P ARTlAL OR COMPLETE LOSS OF INSTRUMENT AIR 3.3 295021 Loss of Shutdown Cooling I 4 X

AKI.OI: Knowledge ofthe operational implications of 3.6 9

the following concepts as they apply to LOSS OF SHUTDOWN COOLING: Decay heat 3.8 AK1.03: Knowledge ofthe operational implications of 295023 Refueling Acc I 8 X

3.7 10 the following concepts as they apply to REFUELING ACCIDENTS: Inadvertent criticality 4.0 295024 High Drywell Pressure I 5 X G2.4.21 : Knowledge ofthe parameters and logic used to 4.0 II assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant 4.6 system integrity, contaimnent conditions, radioactivity release control, etc, as they apply to High Drywell Pressure 295025 High Reactor Pressure I 3 X

EA2.0 I: Ability to detennine and/or interpret Reactor 4.3 12 Pressure as it applies to HIGH REACTOR PRESSURE 4.3 295026 Suppression Pool High Water X

EKI.O I: Knowledge of the operational implications of 3.0

\\3 Temp./5 the following concepts as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Pump NPSH 3.4

,~,,'. ~r.,~df:~,",:\\>&Hi;'s, ~,,j15~i:ils~~,.,.,

~.::~:: 1&':',,&&.H'" *'&pi.;&0*Y,;&

.,'p>>; '" 'f".lE~'l~~~:~&

'&&,'Y'I'PiE"

• 29502 I'v ur&1 s.'

~"""";,,, '..

Hi.. lEX'....,.,,';..

295028 High Drywell Temperature 15 295030 Low Suppression Pool Wtr Lvl/5 295031 Reactor Low Water Level 12 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown 11 295038 High Off-site Release Rate I 9 600000 Plant Fire On Site I 8 700000 Generator Voltage and Electric Grid Disturbances 1 6 X

AK2.04: Knowledge ofthe interrelations between HIGH DRYWELL TEMPERATURE and the following:

3.6 14 Drywell ventilation 3.6 X

EA2.02: Ability to detennine and/or interpret the 3.9 15 following as they apply to LOW SUPPRESSION POOL WATER LEVEL: Suppression pool temperature 3.9 X

EK2.IO: Knowledge of the interrelations between 4.0 16 REACTOR LOW WATER LEVEL and Redundant Reactivity Control 4.0 X

EK3.07: Knowledge of the reasons for the following 4.2 17 responses as tlley apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM 4.3 DOWNSCALE OR UNKNOWN: Various alternate methods ofcontrol rod insertion X

EAI.O I: Ability to operate and/or monitor the following as they apply to HIGH OFF-SITE RELEASE RATE:

3.9 18 Stack -gas monitoring system 4.2 X

AK3.04: Knowledge ofthe reasons for the following 2.8 19 responses as they apply to PLANT FIRE ON SITE:

Actions contained in the ahnonnal procedure for plant 3.4 fire on site X

AA1.03: Ability to operate and/or monitor voltage 3.8 20 regulator controls as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES 3.7 2

Group Point Total:

20 17

ES-401 3

Form ES-401-1

"'v*

BWR Examination Outline Form ES-401-1 tV Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO I SRO)

EIAPE # I Name I Safety Function K

1 K

2 K

3 A

1 A

2 G

KIA Topic(s) 295002 Loss of Main Condenser Vac I 3 X

AKI.03: Knowledge of the operational implications of the following concepts as they apply to LOSS OF MAIN CONDENSER VACUUM: Loss of heat sink 295007 High Reactor Pressure I 3 295008 High Reactor Water Levell 2 X G2.2.44: Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions, as they apply to High Reactor Water Level 295009 Low Reactor Water Level I 2 295010 High Drywell Pressure 15 X

AK2.05: Knowledge of the interrelations between HIGH DRYWELL PRESSURE and the following: Drywell cooling and ventilation 295011 High Containment Temp I 5 295012 High Drywell Temperature 15 295013 Hiqh Suppression Pool Temp./5 295014 Inadvertent Reactivity Addition 11 X

AK3.01: Knowledge of the reasons for the following responses as they apply to INADVERTENT REACTIVITY ADDITION: Reactor SCRAM 295015 Incomplete SCRAM 11 295017 High Off-site Release Rate I 9 295020 Inadvertent Cont. Isolation I 5 & 7 X

AA 1.02: Ability to operate and/or monitor the following as they apply to IN ADVERTENT CONTAINMENT ISOLATION: Drywell ventilation/cooling system 295022 Loss of CRD Pumps 11 295029 High Suppression Pool Wtr LviI 5 X

EK2.01: Knowledge ofthe interrelations between HIGH SUPPRESSION POOL WATER LEVEL and the following:

RHRlLPCI 295032 High Secondary Containment Area Temperature 15 295033 High Secondary Containment Area Radiation Levels I 9 295034 Secondary Containment Ventilation Hiqh Radiation I 9 295035 Secondary Containment High Differential Pressure I 5 295036 Secondary Containment High X

EA2.02: Ability to determine and/or interpret the following SumplArea Water Levell 5 as they apply to SECONDARY CONTAINMENT HIGH SUMPI AREA WATER LEVEL: Water level in the affected area 500000 High CTMT Hydrogen Conc. I 5 IR 3.6 21 3.8 4.2 22 4.4 3.7 23 3.8 4.1 24 4.1 3.2 25 3.2 3.0 26 3.3 3.1 27 3.1

t;j KIA Category Point Totals:

I 2

1 I

1 1

Group Point Total:

ES-401 4

Form ES-401-1 F~-4n1 BWR Examination Outline Plant Systems - Tie>r 2/Group 1 (RO I SRO)

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

IR JjK K 1

2 3

4 203000 RHRlLPCI: Injection X

A 1.03: Ability to predict and/or monitor changes 3.8 28 Mode in parameters associated with operating the RHRlLPCI: INJECTION MODE controls

3.7 including

System flow 205000 Shutdown Cooling X

K4.03: Knowledge of SHUTDOWN COOLING 3.8 29 SYSTEM (RHR SHUTDOWN COOLING MODE) design feature(s) and/or interlocks which 3.8 provide for low reactor water level 206000 HPCI X

X 1<2.0 I: Knowledge of thc electrical power supplies 3.2 30/31 to the following: System valves 3.3 A2.0i: Ability to (a) predict the impacts ofthe following on the HIGH PRESSURE COOLANT INJECTION SYSTEM; and (b) based on those 4.0 predictions, use procedures to correct, control, or mitigate the consequences ofthose abnormal 4.0 conditions or operations: Turbine trips 207000 Isolation (Emergency)

Condenser 209001 LPCS X

K4.08: Knowledge of LOW PRESSURE CORE 3.8 32 SPRAY SYSTEM design feature(s) and/or interlocks which provide fbr the following:

Automatic system initiation 209002 HPCS th 211000 SLC X

K5.06: Knowledge ofthe operational implications 3.0 33 ofthe following concepts as they apply to STANDBY LIQUID CONTROL SYSTEM: Tank 3.2 level measurement 212000 RPS X

X K5.02: Knowledge ofthe operational implications 3.3 34/35 of specific logic arrangements as they apply to REACTOR PROTECTION SYSTEM 3.4 A4.l4: Ability to manually operate andlor monitor in the control room: Reset system following 3.8 system actuati on 3.8 2150031RM X

K6.04: Knowledge of the effect that a loss or 3.0 36 malfunction ofthe following will have on the INTERMEDIATE RANGE MONITOR (lRM)

3.0 SYSTEM

Detectors 215004 Source Range Monitor AAl.05: Ability to predict and/or monitor changes 3.6 37 in parameters associated with operating the SOURCE RANGE MONITOR (SRM) SYSTEM 3.8 controls including: SCRAM, rod block, and period alarm trip setpoints

215005 APRM I LPRM K4.01: Knowledge ofAVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM design feature(s) andior interlocks which provide for the following: Rod withdrawal blocks 3.7 3.7 38 217000 RCIC X

X K6.0 I: Knowledge ofthe effect that a loss or malfunction ofclectrical power will have on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) 3.4 3.5 39/40 A2.03: Ability to (a) predict the impacts of valve closures on the REACTOR CORE ISOLATION 3.4 COOLING SYSTEM (RClC); and (b) based on those predictions, use procedures to con'ect, control, or mitigate the consequences ofthose abnormal conditions or operations 3.3 218000 ADS X

X K4.04: Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM design feature(s) and/or interlocks which provide lor the following: Insures adequate air supply to ADS valves: Plant-Specific 3.5 3.6 41142 A3.09: Ability to monitor automatic operations of the AUTOMATIC DEPRESSURIZATION SYSTEM including: Reactor vessel water level 4.2 4.3 223002 PCIS/Nuclear Steam Supply Shutoff X

A2.09: Ability to (a) predict the impacts ofthe following on the PRIMARY CONTAINMENT ISOLATION SYSTEMINUCLEAR STEAM 3.6 3.9 43 SUPPLY SHUT -OFF; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnonnal conditions or operations: System initiation 239002 SRVs X

A3.08: Ability to monitor automatic operations of the RELIEF/SAFETY VALVES including:

alanns 3.6 3.6 44 259002 Reactor Water Level Control X G2.1.28: Reactor Water Level Control:

Knowledge ofthe purpose and function ofmajor system com~nents and controls 4.1 4.1 45 261000 SGTS X

K6.05: Knowledge ofthe effect that a loss or malfunction ofthe following will have on the STANDBY GAS TREATMENT SYSTEM:

3.1 3.2 46 Reactorjlfotection system: Plant-Specific 262001 AC Electrical Distribution X

KI.O I: Knowledge ofthe physical connections andior cause effect relationships between AC.

ELECTRICAL DISTRIBUTION and the 3.8 4.3 47 following: Emer~ncy~enerators 262002 UPS (AC/DC)

X K4.0 I: Knowledge of UNrNTERRUPT ABLE POWER SlJPPL Y (AC.lD.C.) design feature(s) and/or interlocks which provide for the following:

Transfer from preferred power to alternate power supplies 3.1 3.4 48 263000 DC Electrical Distribution X:

K3.03: Knowledge ofthe effect that a loss or malfunction ofthe D.C. ELECTRICAL DISTRIBUTION will have on systems with D.C.

components 3.4 3.8 49

264000 EDGs X

X K I,04: Knowledge ofthe physical cOImections and/or cause-effect relationships between EMERGENCY GENERATORS (D1ESEUJET) and the following: Emergency generator cooling water system G2, 1.30: Ability to locate and operate components, including local controls, as they apply to Emergency Generators (Diesel/Jet),

~

4.4 4,0 300000 Instrument Air X

K5,0 I: Knowledge ofthe operational implications of the following concepts as they apply to the INSTRUMENT AIR SYSTEM: Aireompressors 2.5 2.5 52 400000 Component Cooling Water X

A3.0 I: Ability to monitor automatic operations of the CCWS including: Sctpoints on instrument signal levels for nonnal operations, warnings, and trips that are applicable to the CCWS 3.0 3.0 53 2

I I

5 3

3 2

3 3

I 2

Group Point Total:

26/5 II

ES-401 5

Form ES-401-1 BWR Examination Outline Plant SYstems - TiE,r 2/Group 2 RO I SRO)

Form ES-40 1-1 System # I Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 1\\

A 3

A 4

KIA Topic(s)

IR 201001 CRD Hydraulic X

K2.0 I: Knowledge of electrical power supplies to: Pumps 2.9 3.1 54 201002 RMCS 201003 Control Rod and Drive Mechanism 201004 RSCS 201006 RWM X

K4.01: Knowledge ofROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC) design feature(s) and/or interlocks which provide for the following:

Insert bloeks/errors 3.4 3.5 55 202001 Recirculation X

K3.07: Knowledge ofthe effect that a loss or malfunction ofthe RECIRCULATION SYSTEM will have on vessel bottom head drain temperature 2.9 2.9 56 202002 Recirculation Flow Control X

K4.02: Knowledge of RECIRCULAnON FLOW CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following: Recirculation pump speed control 3.0 3.0 57 204000 RWCU 214000 RPIS 215001 Traversing In-core PrObe 215002 RBM 216000 Nuclear Boiler Inst X

Al.02: Ability to predict and/or monitor changes in parameters assoeiated with operating the NUCLEAR BOILER INSTRUMENTATION controls including:

Removing or returning a sensor (transmitter) to service 2.9 3.1 58 219000 RHRlLPCI: Tonus/Pool Cooling Mode X

K6.0 I: Knowledge ofthe effect that a loss or malfunction ofthe following will have on the RHRlLPCI: TORUS/SUPPRESSION POOL COOLING MODE: A.C. electrical Dower 3.2 3.3 59 223001 Primary CTMT and Aux.

226001 RHRlLPCI: CTMT Spray Mode X

A3.04: Ability to monitor automatic operations ofthe RHRlLPCI:

CONTAINMENT SPRAY SYSTEM MODE including: lights and alanns 3.1 3.1 60 230000 RHRlLPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment

239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 ReactorfTurbine Pressure Regulator X

K5.04: Knowledge ofthe operational Implications ofthe following concepts as they apply to REACTORrrURBINE PRESSURE REGULATING SYSTEM:

PAM pressure VS. reactor Jlfessure 3.3 3.3 61 245000 Main Turbine Gen. I Aux.

X G.2.1.27: Knowledge ofsystem purpose and/or function as it applies to Main Turbine Generator and Auxiliary ~tems 3.9 4.0 62 256000 Reactor Condensate 259001 Reactor Feedwater X

A2.03: Ability to (a) predict the impacts of the following on the REACTOR FEEDW A TER SYSTEM; and (b) based on those predictions, use procedures to con"CCt, control, or mitigate the consequences of those ahnonnal conditions or operations:

Loss ofcondensateyump(s) 3.6 3.6 63 268000 Radwaste 271000 Offgas X

A4.09: Ability to manually operate and/or monitor in the control room: Offgas system controls/components 3.3 3.2 64 272000 Radiation Monitoring 286000 Fire Protection X

K6.0 I: Knowledge ofthe effect that a loss or malfunction of the following will have on the FIRE PROTECTION SYSTEM: A.C.

electrical distribution: Plant-fu>ecific 3.1 3.1 65 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals KIA Category Point Totals:

0 I

I 1

1 1

I 2

1 I

1 l~

Category KIA #

2.1.29

1.

Conduct 2.1.1 of Operations 2.1.25 Subtotal 2.2.39 2.2.1

2.

Equipment Control Subtotal 2.3.11 2.3.12

3.

Radiation Control Subtotal 2.4.8

4.

2.4.4 Emergency Procedures I Plan 2.4.34 Subtotal Tier 3 Point Total Topic RO Knowledge ofhow to conduct system lineups, such as valves, breakers, switches, etc.

IR 4.114.0 66 Knowledge of conduct of operations requirements.

Ability to interpret reference materials, such as graphs, curves, tables, etc.

3.8/4.2 3.9/4.2 67 68 Knowledge of less than or equal to one hour Technical Specification action statements for s~stems.

3.9/4.5 3

69 Ability to perfonn pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

4.5/4.4 70 2

Ability to control radiation releases 3.8/4.3 71 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

3.2/3.7 72 2

Knowledge of how abnonnal operating procedures are used in conjunction with EOPs.

Ability to recognize abnonnal indications for system operating parameters which are entry-level conditions for emergency and abnonnal operating procedures.

3.8/4.5 4.5/4.7 73 74 Knowledge of RO tasks perfonned outside the main control room during an emeql,ency and the resultant operational effects.

4.2/4.1 75 3

10

Ib Date of Exam:

RO KJA Category Points SRO-Only Points Tier Group K

K K K K K A A A A

G A2 G*

Total 1

2 3

4 5

6 1

2 3 4

Total

1.

1 20 4

3 7

Emergency &

Abnormal Plant 2

N/A N/A 7

2 I

1 Evolutions I

Tier Totals 27 4

IV II II 1

26 2

3 5

2.

2 12 0

1 2

3 Plant Systems Tier Totals

~R 3

5 8

3. Generic Knowledge and Abilities 1

2 3

4 10 1

2 3

4 7

Categories

. 2 2

1 2

Note:

1.

Ensure that at least two topics from every applicable KJA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KJA 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 final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

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.1.b of ES-401 for guidance regarding the elimination of inappropriate KJA statements.

4.

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

5.

Absent a plant-specific priority, only those KJp..s having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions. respectively.

6.

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

7.*

The generic (G) KJAs in Tiers 1 and 2 shall be selected from Section 2 of the KJA Catalog, but the topiCS must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KJAs.

8.

On the following pages, enter the KJA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9.

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

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO I SRO)

E/APE # I Name 1Safety Function K K K A A

G KIA Topic(s)

IR 1

2 3

1 2

295001 Partial or Complete Loss of Forced Core Flow Circulation 11 & 4 295003 Partial or Complete Loss of AC 16 295004 Partial or Total Loss of DC Pwr I 6 X

AA2.03: Ability to detennine and/or interpret the 2.9 76 following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Battery voltage 295005 Main Turbine Generator Trip 13 295006 SCRAM 11 X

AA2.03: Ability to detennine and/or interpret the 4.2 77 following as they apply to SCRAM: Reaetor water level 295016 Control Room Abandonment 1 7 295018 Partial or Total Loss of CCW 18 295019 Partial or Total Loss of Inst. Air 18 X

AA2.02: Ability to detennine and/or interpret the 3.7 78 following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: Status of safety-related instrument air system loads.

295021 Loss of Shutdown Cooling I 4 295023 Refueling Acc I 8 295024 High Drywell Pressure I 5 X

02.4.18: Knowledge of speeific bases for EOPs as they 4.0 80 apply to High Drywell Pressure.

295025 High Reactor Pressure I 3 295026 Suppression Pool High Water Temp./5 295027 High Containment Temperature 15 295028 High Drywell Temperature 15 295030 Low Suppression Pool Wtr Lvl/5 295031 Reactor Low Water Level 12 X

EA2.04: Ability to detennine and/or interpret the 4.8 81 following as they apply to REACTOR LOW WATER LEVEL: Adequate Core Cooling 295037 SCRAM Condition Present X

02.4.6: Knowledge of EOP mitigation strategies as they 4.7 82 and Reactor Power Above APRM apply to SCRAM Condition Present and Reactor Power Downscale or Unknown 11 Above APRM Downscale or Unknown.

295038 High Off-site Release Rate 1 9 X

02.4.31: Knowledge ofannunciator alanns, indications, 4.1 79

-I or response proeedures. (High Off-site Release Rate) 600000 Plant Fire On Site 1 8

'6?0000 Generator Voltage and Electric Grid isturbances I 6 orvTotals:

4 20/7 II

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

E/APE # I Name I Safety Function K K KIA Topic(s)

IR 1

2 3

1 Kfa 295002 Loss of Main Condenser Vac I 3 295007 High Reactor Pressure I 3 295008 High Reactor Water Levell 2 295009 Low Reactor Water Levell 2 295011 High Containment Temp 15 295012 High Drywell Temperature 15 295013 High Suppression Pool Temp. 15 X

A2.01: Ability to detennine and/or interpret the following 4.0 as they apply to HIGH SUPPRESSION POOL TEMPERATURE: Suppression Pool Temperature.

295014 Inadvertent Reactivity Addition 11 295015 Incomplete SCRAM I 1 X G.2.4.41: Knowledge ofthe emergency action level 3.6 84 thresholds and classifications.

295017 High Off-site Release Rate I 9 AA2.01: Ability to detennine and/or interpret the 4.2 85 following as they apply to HIGH OFF-SITE RELEASE RATE: Off-site release rate: Plant-Specific.

295020 Inadvertent Cont. Isolation 15 & 7

~

295022 Loss of CRD Pumps 11 295029 High Suppression Pool Wtr LviI 5 295032 High Secondary Containment Area TemQerature I 5 295033 High Secondary Containment Area Radiation Levels I 9 295034 Secondary Containment Ventilation High Radiation 19 295035 Secondary Containment High Differential Pressure I 5 295036 Secondary Containment High SumplArea Water Level 15 500000 High CTMT Hydrogen Conc. I 5 R

KIA Category Point Totals:

2 I

Group Point Total:

i ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 21Group 1 (RO ISRO)

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

IR 1

2 3

4 5

6 1

2

~

4 203000 RHRlLPCI: Injection Mode U

205000 Shutdown Cooling X

A2.03: Ability to (a) predict the impacts of A.c.

3.2 89 failures on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnonnal conditions or operations.

206000 HPCI 207000 Isolation (Emergency)

Condenser 209001 LPCS 209002 HPCS 211000 SLC X G2.4.47: Ability to diagnose and recognize trends 4.2 86 in an accurate and timely manner utilizing the appropriate control room reference material.

212000 RPS 2150031RM 215004 Source Range Monitor X G2.2.40: Ability to apply Technical Specifications 4.7 87 for a system as they apply to the Source Range Monitor (SRM) System.

215005 APRM I LPRM 217000 RCIC 218000 ADS X 2.4.6: Knowledge of EOP mitiuation strategies.

4.7 88 223002 PCIS/Nuclear Steam Supply Shutoff 239002 SRVs 259002 Reactor Water Level Control 261000 SGTS 262001 AC Electrical X

A2.04: Ability to (a) predict the impacts of types 4.2 90 Distribution ofloads that, if deenergized, would degrade or hinder plant operation on the A.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of the abnonnal conditions or operations 262002 UPS (AC/DC) 263000 DC Electrical Distribution 264000 EDGs 300000 Instrument Air DIIIJ

400000 Component Cooling Water KIA Category Point Totals:

2 3

Group Point Total:

26/5

Form ES-401-1 System # / Name 201001 CRD H draulic 201002 RMCS 201003 Control Rod and Drive Mechanism 201004 RSCS 201005 RCIS 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 215001 Traversin In-core Probe 215002 RBM 216000 Nuclear Boiler Inst 219000 RHRlLPCI: Torus/Pool Cooling Mode 223001 Prima CTMT and Aux.

226001 RHRlLPCI: CTMT Spray Mode 230000 RHRlLPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 ReactorlT urbine Pressure R

ulator 245000 Main Turbine Gen. / Aux.

256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 286000 Fire Protection KIA Topic(s) x G2.1.7: Ability to evaluate plant 4.7 perfonnance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation (RHRlLPCI:

CTMT S ra Mode) x G2.4.ll: Knowledge ofabnonnal condition 4.2 92 procedures as they relate to Main Turbine Generator and Auxili

'S stems x

A2.07: Ability to (a) predict the impacts of 3.8 93 thc following on the REACTOR FEEDWA TER SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnonnal conditions or operations:

Reactor water level control system malfunctions 91

288000 Plant Ventilation 290001 Seconda GTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals KIA Gate 0 Point Totals:

SRO OUTLINE Category KIA #

Topic SRO IR 2.1.35 Knowledge ofthe fuel-handling responsibilities of SROs.

3.9 94

1.

2.1.32 Ability to explain and apply system limits and precautions.

4.0 95 Conduct of Operations Subtotal 2

2.2.17 Knowledge ofthe process for managing maintenance activities during 3.8 96 power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.

2.

Equipment 2.2.S Knowledge ofthe process for making changes in the facility as described in the safety analysis report.

3.2 97 Control Subtotal 2

2.3.14 Knowledge of radiation or contamination hazards that may arise during 3.8 98 normal, abnonual or emergency conditions or activities.

3.

Radiation Subtotal 1

Control 2.4.16 Knowledge of EOP implementation hierarehy and coordination with 4.4 99 other support procedures or guidelines sueh as, operating procedures,

4.

Emergency Procedures /

2.4.30 abnonual operating procedures, and severe accident management guidelines.

Knowledge ofthe emergency plan.

4.0 100 Plan Subtotal 2

Tier 3 Point Total 7

ES-401 Record of Rejected KI As Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA T1/G2 295029 EK3.02

• After the 0 was written and determined to be acceptable by the Chief Examiner (CE), the decision was made, with CE (026) concurrence, to retain system being tested but revise KIA topic to better reflect 0 content while meeting sample plan requirement.

Changed KIA topic to EK2.01 T2/G1 212000 A4.04

• After the 0 was written and determined to be acceptable by the Chief Examiner (CE), the decision was made, with CE (035) concurrence, to retain system being tested but revise KIA topic to better reflect 0 content while meeting sample plan requirement.

Changed KIA topic to EA4.14 T2/G1 218000 K3.02

• After the 0 was written and determined to be acceptable by the Chief Examiner (CE), the decision was made, with CE (041) concurrence, to retain system being tested but revise KIA topiC to better reflect 0 content while meeting sample plan requirement.

Changed KIA topic to EK4.04 T2/G2 219000 K2.02

• After the 0 was written and determined to be acceptable by the Chief Examiner (CE), the decision was made, with CE (059) concurrence, to retain system being tested but revise KIA topic to better reflect 0 content while meeting sample plan requirement.

Changed KIA topiC to EK6.01 Generic G 2.3.7 Changed to G 2.3.12 due to CE determined the original 0 to be GET level and randomly selected new KIA.

(072)

T1/G2 295017 AA2.05

• After the 0 was written and determined to be acceptable by the Chief Examiner (CE), the decision was made, with CE (085) concurrence, to retain system being tested but revise KIA topic to better reflect 0 content while meeting sample plan requirement.

Changed KIA topic to AA2.01

• The original 0 concept was retained.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Limerick Examination Level:

RO Administrative Topic (see Note)

Conduct of Operations A-l.l Conduct of Operations A-1.2 Equipment Control A-2 Radiation Control A-3 Emergency Procedures/Plan A-4 Date of Examination: 10/9/12-10/12/12 Operating Test Number: 1 Type Describe activity to be performed Code*

R,N Evaluate Overtime Work Request R,N Review Drywell Floor Drain Sump/Equipment Drain Tank Logs and Determine Compliance with TS 3.4.3.2 R,N Determine Blocking Required per OP-MA-109-101 "Clearance and Tagging" N/A N/A R,N Emergency Plan Communications 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)irnulator, or Class(R)oorn (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 (s 1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 I

Facility: Limerick Examination Level:

SRO Administrative Topic (see Note)

Conduct of Operations A-l.1 Conduct of Operations A-1.2 Equipment Control A-2 Radiation Control A-3 Emergency Procedures/Plan A-4 Type Code*

R,N R,N R,N R,N R,N Date of Examination: 10/9/12-10/12/12 Operating Test Number: 1 Describe activity to be performed Evaluation of Overtime Hours to Determine Availability Review Drywell Floor Drain Sump/Equipment Drain Tank Logs and Determine Compliance with TS 3.4.3.2 Review and Verify Blocking Required per OP-MA-109 101 <<Clearance and Tagging" Review and Approve Inventory Release from Equipment Drain Sample Tank to Cooling Tower Blowdown Line Classify an SAE with Escalation to a GE and Make Protective Action Recommendations 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)odifieci from bank (~ 1)

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Limerick Date of Examination:

10/9/12 Exam Level: RO

• SRO-I D SRO-U D Operating Test No.:

1 I,.,.

'"'oom Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

Safety Function 1

• b. HPCI Manual Start 1 206000 A,EN,N, S

a. Start Reactor Recirculation Pump 1202001 A,N,S 2

• • c. Perform Turbine Bypass Valve Testing lAW ST-6-001-761-11 D,S 3

241000

d. SDC Restoration 1 223002 A,L,N,S 4

• • e. Synchronize and Load D12 Diesel Generator to 1000 KW 1 A,E,N 6

264000

f. Scram Channel Ai and A2 Functional Test 1212000 A,M,S 7

g. Restore RECW, DWCW, and Instrument Gas 1400000 D,S 8

• h. Standby Gas Treatment Manual Startup with Charcoal Enclosure A,M,S 9

Hi Temp / 261000 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Maximize CRD Flow After Shutdown During Emergency Conditions L,N,R 1

(T-240) Unit 2/295031 f Equipment for Manual Operation of LPCI/203000 A,N,R 2

k. Venting Primary Containment Using the 24" Suppression Pool E,N 5

Purge Supply 1295010223001 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 1SRO-U (A)ltemate path 4-6 1 4-6 1 2-3 (C)ontrol room (D)irect from bank

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

~1/~1/~1 (EN)gineered safety feature I

~1 (control room system)

(L)ow-Power I Shutdown

~1/~1/;;::1 (N)ew or {M)odified from bank including 1 (A)

~21"2:.2/~1

{P}revious 2 exams

s: 3 1:s: 3 I:s: 2 (randomly selected)

(R)CA

~1/"2:.1/;;::1 (S}imulator

• JPM B & H are paired to run simultaneously.

• • JPM C & E are paired with a stagger start. JPM E will be folilowed by JPM C.

ES-301 Control Roornlln-Plant Systems Outline Form ES-301-2 Facility:

Limerick Date of Examination:

10/9/12 Exam Level: RO D SRO-I

• SRO-U D Operating Test No.:

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

System /,IPM Title Type Code*

Safety Function

a. Start Reactor Recirculation Pump / 20200'1 A,N,S 1

• b. HPCI Manual Start / 206000 A, EN,N, S 2

• • c. Perform Turbine Bypass Valve Testing lAW ST-6-001-76'1-1 /

D, S 3

241000

d. SDC Restoration / 223002 A,L,N,S 4

• • e. Synchronize and Load D12 Diesel Generator to 1000 KW I A,E,N 6

264000

f. Scram Channel A1 and A2 Functional Test / 212000 A,M,S 7

• h. Standby Gas Treatment Manual Startup with Charcoal Enclosure A,M,S 9

Hi Temp / 261000 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Maximize CRD Flow After Shutdown During Emergency Conditions E,L,N,R 1

(T-240) Unit 2/295031

j. Alignment of Equipment for Manual Operation of LPCI /203000 A,N,R 2

k. Venting Primary Containment Using the 24" Suppression Pool E,N 5

Purge Supply / 295010 223001 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)lternate path 4-6/4-6/2-3 (C)ontrol room (D)irect from bank

$9/$8/$4 (E)mergency or abnormal in-plant 2':1/2':1/::::1 (EN)gineered safety feature

- / - / ::::1 (control room system)

(L)ow-Power / Shutdown 2':1/2':1/::::1 (N)ew or (M)odified from bank including 1 (A) 2':2/2':2/::::1 (P)revious 2 exams

$ 3 / $ 3 / $ 2 (randomly selected)

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

• JPM B & H are paired to run simultaneously.

• • JPM C & E are paired with a stagger start. JPM E will be followed by JPM C.

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility:

Limerick Date of Examination:

10/9/12 Exam Level: RO D SRO-I D SRO-U

• Operating Test No.:

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

System I JPM Title Type Code*

Safety Function

• b. HPCI Manual Start I 206000 A,EN,N,S 2

d. SDC Restoration 1223002 A,L,N,S 4

• • e. Synchronize and Load D12 Diesel Generator to 1000 KW 1 A,E,N 6

264000 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Maximize CRD Flow After Shutdown During Emergency Conditions E,L,N,R 1

(T-240) Unit 2/295031

k. Venting Primary Containment Using the 24" Suppression Pool E,N 5

Purge Supply /295010223001 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 sHrve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO 1SRO-l I SRO-U (A)lternate path 4-6 1 4-6 1 2-3 (C)ontrol room (D)irect from bank

~9/$8/$4 (E)mergency or abnormal in-plant 2:1/.::::1/.::::1 (EN)gineered safety feature

- I - I.::::1 (control room system)

(L)ow-Power I Shutdown

>

1/.::::1/;:>:1 (N)ew or (M)odified from bank including 1(A) 2:2/.::::2/2:1 (P)revious 2 exams

$ 3 {$ 31 $ 2 (randomly selected)

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

• JPM B & H are paired to run simultaneously.

• • JPM C & E are paired with a stagger start. JPM E will be followed by JPM C.

Appendix D Scenario Outline Form ES-D-1 Facility: Limerick Scenario No.:

1 Op-Test No.:

Examiners:

Op.~rators:

... -~-.--

Initial Conditions: Unit 1 at 95% power to recover HCU maintenance rods, D11 EDG out of service for overhaul, day 2 of 30 day LCO Turnover: Recover the HCU maintenance rods and return Unit 1 to 100% power Event No.

Malt. No.

Event T~~e" I

Event Description 1

R-ATC Recover HCU maintenance rods 2

MPR011B I-ATC, TS-SRO 1 B RI3M Fails Inop 3

MMC077B C-BOP Hotwell level controller failure 4

MED015D, MGD422B, MED012 C-BOP, C-ATC Closure failure of 101-D12fTemporary loss of D124-G-D Load CenterfTemporary loss of ability to drive control rods 5

MSL001A, MCU195A C-ATC, TS-SRO SLC spurious injection with RWCU isolation failure

MRP029C, I

6 M-ALL Electric ATWS/RRCS failure/SLC header rupture MRP407C, MSL559 C-ATC, MEH110, MEH108 7

T-22"1 failure, main turbine trip, bypass valve C-BOP closure 8

MRSW600AlC C-BOP RHRSW Pump Trip in Suppression Pool Cooling (N)onnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 36 NRC Scenario #1 - Limerick Generating Station Operating Test

Appendix 0 Scenario Outline Form ES-D-1 Facility: Limerick Scenario No.:

2 Op-Test No.:

Examiners:

Operators:

Initial Conditions: 100% power following a rod pattern adjustment, MOL, D11 Diesel out of service to repair a Jacket Water System leak (48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> into a 30 day LCO - 3.8.1, AC Sources Operating); repairs expE~cted to be completed within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Turnover: Maintain 100% power t

Malt. No.

1 MFW005B 2

MHP450 3

MFH564B 4

MRR201A MRR209A1 MRR209A2 5

MED282B 6

MED261 7

8 MDG420C MRR440A MDG418D MRC466 (N)onnal, (R)eactivity, Event Type*

I-ATC TS-SRO C-BOP R-ATC C-ATC TS-SRO C-BOP TS-SRO M-AII C-BOP M-AII

( I)nstrument, Event Description LEFM Spool 'B' Enters Maintenance Mode HPCI Spurious Start FWH 12B Level Sensing Line Fails High (Reduce PowerS 85%)

'1A' Recirc ASD Loss of Cooling with a Failure of the '1A' ASD 13.2 KV Breaker to Trip I Results in Single Loop Operation in Restricted Region of Power/Flow Map Loss of 125/250 VDC Safeguard Bus 1BD105 Grid Instability Resulting in Loss of Offsite Power D13 Diesel Auto Start Failure (Recoverable)

Small Break LOCA (0.5% to 1 % ramp over 5 minutes) with D14 Diesel Trip on Bus Lockout 1 RCle Trip on Overspeed (Recoverable after RPV Level reaches -161")

(C)omponent, (M)ajor Page 1 of 50 NRC Scenario #2 - Limerick Generating Station Operating Test

Scenario Summary and Administration Instructions Appendix 0 Scenario Outline Form ES-D-1 Facility: Limerick Scenario No.:

4 Op-Test No.:

Examiners:

Operators:

Initial Conditions: 100% power Turnover: The PJM has issued a Maximum Emergency Generation Alert due to grid instabilities. Maintain reactor power at 100% and comply with TSO requests for grid support as necessary.

Malf. No.

1 MVI232F MRP029A 2

VIC105A6 3

MCU194 4

MEG095

! 5 6

ME0275C 7

MRT001B MMS061A MMS062A MMS136 8

MRE001A MRE001B MRE317 RRE013 (N)ormal, (R)eactivity, Event Type*

I-ATC TS-SRO R-ATC TS-SRO C-BOP C-BOP C-ATC C-BOP TS-SRO M-ALL C-ATC (l)nstrument, Event Description Rx Level Transmitter L T 1 N080C Fails Low with No RPS Actuation Signal

'1A' Recirc Pump Motor High Vibration (Power Reduced to ::;; 93% to Clear Annunciator 111 D2)

RWCU Leak with Auto Isolation Failure (Manual Isolation Successful)

Main Generator Auto AC Voltage Regulator Failure Resulting in Transfer to the Manual DC Voltage Regulator

'1A' Recirc Pump ASO Controller Incremental Speed Increase Loss of Safeguard Bus 0134 (Loss of Reactor Enclosure Supply, Exhaust, and REECE Fans)

Main Steam Line High High Radiation (Fuel Failure) I MSL Break in Outboard MSIV Room (Rooms 407 and 518) with Failure of the 'A' Main Steam Line to Isolate SGTS Exhaust Fans OAV163 and OBV163 Trip (Recoverable) I Leak Propagation

( C)oml'onent, (M)aior Page 1 of 53 NRC Scenario #4 - Limerick Generating Station Operating Test