ML102920667

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Final Outlines (Folder 3)
ML102920667
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 09/29/2010
From: Caruso J
Operations Branch I
To: Goff C
Exelon Generation Co, Exelon Nuclear
Hansell S
Shared Package
ML100560247 List:
References
TAC U01767
Download: ML102920667 (31)
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Text

ES-401 Written Examination Outline Form ES-401-1

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Facility: LGS2010 SRO Date of Exam: 10/04110 RO KIA r: y Points SRn-~n}yPoints Tier Group K K K K K K A A A A G Tota} A2 G* Total i 1 2 3 4 5 6 1 2 3 4

  • I i
1. I 20 4 3 7 Emergency  ;

i 2 7 1 2 3

~~~i';;l Plant Tier Evolutions . .,.ssl 27 5 5 10 Totals I

1 26 3 2 5 2.

J Plant 2 12 1 1 1 3 i Systems Tier 38 5 3 8 Totals

3. Generic Knowledge & Abilities 1 2 3 4 1 2 3 4 I Categories 10 1 2 2 2 7

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 (Le., 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 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 +/- 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 that are not included on the outline should be added. Refer to section D.l.b of ES-401, for guidance regarding 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 KAs 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 I and 2 from the shaded systems and KIA categories.

7.* The generic (G) KiAs in Tiers 1 and 2 shall be selected from Section 2 of the KiA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.I.b of ES-40 I for the applicable KiA's

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IR) 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. Iffnel 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. 1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 ofthe KiA Catalog, and enter the KiA numbers, descriptions, IRs, and I point totals (#) on Form ES-401-3. Limit SRO selections to KJAs that are linked to IOCFR55.43

E8-401 2 Form E8-40 1-1 20108RO Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # I Name Safety Function KJA Topic{s) Imp. I Q# i EA2.04 - Ability to detennine and/or interpret the following as they apply to 295031 Reactor Low Water Level X 4.8 I REACTOR LOW WATER LEVEL:

Adequate core cooling EA2.02 - Ability to detennine and/or interpret the following as they apply to 295037 SCRAM Conditions Present SCRAM CONDITION PRESENT AND and Reactor Power Above APRM X 4.2 2 REACTOR POWER ABOVE APRM Downscale or Unknown I I DOWNSCALE OR UNKNOWN: Reactor water level

... AA2.IS Ability to detennine and interpret the following as they apply to PLANT 600000 Plant Fire On-site 18 X 3.5 3 FIRE ON SITE: Requirements for establishing a fire watch 2.237 Equipment Control: Ability to 295028 High Drywell Temperature I X detelmine operability and I or availability of 4.6 4 5

safety related equipment.

2.4.30 - Emergency Procedures I Plan; Knowledge of events related to system operation I status that must be reported to 295025 High Reactor Pressure I 3 X 4.1 5 intemal organizations or extemal agencies, such as the state, the NRC, or the transmission system operator.4.1 295023 Refueling Ace Cooling 2.4.11, Knowledge of abnonnal condition X 4.2 6 Mode 18 procedures.

EA2.04 Ability to detennine and/or 295038 High Off-site Release Rate I interpret the following as they apply to X 4.1 7 9 HIGH OFF-SITE RELEASE RATE:

Source of off-site release KIA Category Totals: 0 0 0 0 4 3 Group Point Total:

I 7

ES-401 3 Form ES-401-1 2010 SRO Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE # I Name Safety Function KIA Topic(s)

EA2.01 Ability to determine and/or interpret the following as they apply to 295035 Secondary Containment High Differential Pressure I 5 X SECONDARY CONTAINMENT HIGH 3.9 8 DlFFERENTIAL PRESSURE: Secondary eontainment pressure: Plant-Specific 295013 High Suppression Pool 2.1.25, Ability to interpret reference Temperature I 5 X materials, such as graphs, curves, tables, etc.

4.2 9 2.435 - Emergency Procedures I Plan:

295014 Inadvertent Reactivity Knowledge oflocal auxiliary operator tasks Addition 11 X during emergency and the resultant 4.0 10 operational effects.

KJA Category Totals: 0 0 0 0 1 2 Group Point Total:

I 3

ES-401 4 Form ES-401-1 2010 SRO Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A A System # I Name G Imp. Q#

1 2 3 4 5 6 1 2 3 4 A2.03 Ability to (a) predict the impacts of the following on the RECIRCULATION SYSTEM: and (b) based on those predictions, use 202001 Recirculation System X procedures to correct, control, or 3.7 II mitigate the consequences of those abnormal conditions or operations:

Single recirculation pump trip A2.02 - Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM)

SYSTEM; and (b) based on those 215004 Source Range Monitor X predictions, use procedures to correct, 3.7 12 control, or mitigate the consequences of those abnormal conditions or operations:

SRM inop condition 2.4.16, Knowledge of EOP implementation hierarchy and coordination with other support 217000 RCIC X procedures or guidelines such as, 4.4 13 operating proeedures, abnormal operating procedures, and severe a~cident management guidelines.

2.2.40, Ability to apply Technical 218000 ADS X 4.5 14 Specifications for a system.

A2.01 - Ability to (a) predict the impacts of the following on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM; and (b) based on those 2150031RM X predictions. use procedures to correct, 3.2 15 control, or mitigate the consequences of those abnormal conditions or operations:

Power supply degraded KIA Category Totals: 0 ~~ 0 0 0 0 3 0 0 2 Group Point Total:

I 5

ES-401 5 Form ES-401-1 2010 SRO Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A A System # f Name G Imp. Q#

1 2 3 4 5 6 1 2 3 4 A2.03 - Ability to (a) predict the impacts ofthe following on the REACTOR FEEDWATER SYSTEM; and (b) based on those predictions, use 25900 I Reactor Feedwater X 3.6 16 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of condensate pump(s) 2.1.20 - Ability to interpret and execute 204000 RWCU X 4.6 17 procedure steps.

234000 Fuel Handling I K4.01 Prevention of core alterations 4.1 18 Equipment X I during control rod movements I

I KIA Category Totals: 0 0 0 1 0 0 0 1 0 0 1 Group Point Total: 3 I I

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: 2010 SRO Date:

i RO SRO-Only Category KJA# Topic IR Q# IR Q#

1. Ability to direct personnel activities inside the 2.1.9 4.5 19 Conduct control room.

i of Operations "i, "!\

  • Subtotal 1 i Knowledge of the process for making changes 2.2.6 3.6 20
2. to procedures. I Equipment Knowledge of limiting conditions for  !

2.2.22 4.7 23 Control operations and safety limits.

Subtotal \ 2 i'

Knowledge of radiation or contamination hazards that may arise during normal,

3. 2.3.14 3.8 21 abnormal, or emergency conditions or Radiation activities. i Control 2.3.11 Ability to control radiation releases. 4.3 24 Subtotal -, '""

2 Knowledge of emergency plan protective 2.4.44 4.4 22 action recommendations.

Knowledge of the parameters and logic used

4. to assess the status of safety functions, such Emergency as reactivity control, core cooling and heat Procedures I 2.4.21 4.6 25 removal, reactor coolant system integrity, Plan containment conditions, radioactivity release I i

control, etc.

/',' , .,.

Subtotal 2 Tier 3 Point Total I,> 10 ",'<"'!:.,' 7

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ES-401 Written Examination Outline Form ES-401-1

+Facility: LGS 2010 NRC RO Date of Exam: 10/04/10 RO KJ A Category Points SRO-Only Points Tier Group K K K K K K A A G Total A2 G* Total 1 2 3 I 2

  • L 3 4 3 3 20 7 Emergency

& 2 2 7 3 Plant Tier Evolutions 5 5 4 4 27 10 Totals i

3 2 3 2 3 2 2 3 2 2  ! 2 26 5 2.

Plant 2 2 12 3 Systems Tier 4 3 5 3 4 3 3 4 3 3 3 38 8 Totals

3. Generic Knowledge & Abilities 2 3 4 I I 2 3 4 10 7 Categories 3 3 2 2 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 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 final 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 that are not included on the outline should be added. Refer to section D.I.b ofES-401, for guidance regarding 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 KAs having an importance rating (lR) 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 I and 2 from the shaded systems and KIA categories.
7.
  • The generic (G) KI As in Tiers I 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.I.b of ES-401 for the applicable KIA's
8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IR) 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. lffuel 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. 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 oint totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to IOCFR55.43

ES-401 2 Form ES-401-1 2010 NRC RO Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # / Name Safety Function KiA Topic(s)

EKI.OI - Knowledge of the operational implications of the following concepts as 295037 SCRAM Conditions they apply to SCRAM CONDITION Present and Reactor Power Above X PRESENT AND REACTOR POWER 4.1 I APRM Downscale or Unknown I I ABOVE APRM DOWNSCALE OR UNKNOWN: Reactor pressure effects on reactor power

.. AKJ.02 - Knowledge of the operational 295001 Partial or Complete Loss of implications of the following concepts as Foreed Core Flow Circulation 1 I & X they apply to PARTIAL OR COMPLETE 3.3 2 4 LOSS OF FORCED CORE FLOW CIRCULATION: Powerlflow distribution AKJ.03 Knowledge of the operational 295006 SCRAM 1 I X implications of the following concepts as 3.7 3 they apply to SCRAM: Reactivity control

. AK2.01 - Knowledge of the interrelations 295016 Control Room between CONTROL ROOM X 4.4 4 Abandonment I 7 ABANDONMENT and the following:

Remote shutdown panel: Plant-Specific AK2.05 - Knowledge of the interrelations 295019 Partial or Total Loss of betwEien PARTIAL OR COMPLETE X 3.4 5 Inst. Air 18 LOSS OF INSTRUMENT AIR and the following: Main steam system EK2.118 - Knowledge of the interrelations 295024 High Drywell Pressure 1 5 X between HIGH DRYWELL PRESSURE 3.3 6 and the following: Ventilation EK3.01 - Knowledge of the reasons for the following responses as they apply to 295026 Suppression Pool High X SUPPRESSION POOL HIGH WATER 3.8 7 Water Temp. 15 TEMPERATURE: Emergency/normal depressurization AK3.05 - Knowledge of the reasons for the following responses as they apply to 295005 Main Turbine Generator X MAIN TURBINE GENERATOR TRIP: 2.5 8 Trip 13 Extraction steam/moisture separator isolations AK3.03 Knowledge of the reasons for the following responses as they apply to 295018 Partial or Total Loss of PARTIAL OR COMPLETE LOSS OF X 3.1 9 CCW/8 COMPONENT COOLING WATER:

Securing individual components (prevent equipment damage)

AA2.02 - Ability to operate and/or monitor the followi ng as they apply to 295023 Refueling Accidents X 3.4 10 REFUELING ACCIDENTS: Fuel Pool Level EA1.04 - Ability to operate and/or monitor 295038 High Off-site Release Rate the following as they apply to HIGH OFF X 2.8 II 19 SITE RELEASE RATE:

SPDSIERIS/CRIDS/GDS: Plant-Specific EA1.01 - Ability to operate and/or monitor 295028 High DryweJl Temperature the following as they apply to HIGH X 3.8 12 15 DRYINELL TEMPERATURE: Drywell spray: Mark-I&II AA2.04 - Ability to determine and/or 295021 Loss of Shutdown Cooling interpret the following as they apply to 14 X LOSS OF SHUTDOWN COOLING.

3.6 13 Reactor water temperature 295004 Partial or Total Loss of DC AA2.04 - Ability to determine and/or X 3.2 14 Pwr/6 interpret the following as they apply to

ES-401 2 Form ES-401-1 2010 NRC RO Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # I Name Safety Function KIA Topic(s)

PARTIAL OR COMPLETE LOSS OF D.C. POWER: System lineups EA2.06 - Ability to determine and/or interpret the following as they apply to 295025 High Reactor Pressure! 3 X HIGH REACTOR PRESSURE: Reactor 3.7 15 water level 2.1.23 - Conduct of Operations: Ability to 295030 Low Suppression Pool perform specific system and integrated Water Levell 5 X plant procedures during all modes of 4.3 16 plant operation.

2.2.4 - Equipment Control: (multi-unit license) Ability to explain the variations in 295003 Partial or Complete Loss of AC 16 X control board layouts, systems, 3.6 17 instrumentation and procedural actions between units at a facility.

2.4.8 - Emergency Procedures 1 Plan:

Knowledge of how abnormal operating 600000 Plant Fire On-site / 8 X 3.8 18 procedures are used in conjunction with EOP*s.

AA1.01 Ability to operate and/or monitor the following as they apply to 700000 Generator Voltage and Electric Grid Disturbances X GENERATOR VOLTAGE AND 3.6 19 ELECTRIC GRID DISTURBANCES: Grid frequoncy and voltage.

EK2.02 - Knowledge of the interrelations 295031 Reactor Low Water Level / between REACTOR LOW WATER X 3.8 20 2 LEVEL and the following: Reactor pressure KIA Category Totals: 3 4 3 3 4 3 Group Point Total:

I 20

ES-401 3 Form ES-401-1 2010 NRC RO Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE # I Name Safety Function KIA Topic(s)

EK 1.02 - Knowledge of the operational 295033 High Secondary implications of the following concepts as Containment Area Radiation Levels X they apply to HIGH SECONDARY 3.9 21 19 CONTAINMENT AREA RADIATION LEVELS: Personnel protection EK2.04 - Knowledge ofthe interrelations 295035 Secondary Containment between SECONDARY CONTAINMENT X 3.3 22 High Differential Pressure I 5 HIGH DIFFERENTIAL PRESSURE and the following: Blow-out panels: Plant-Specific AKJ.OI. Knowledge ofthe reasons for the 295009 Low Reactor Water Levell X following responses as they apply to 3.2 23 2

Recirculation pump run back: Plant-Specific EAl.03 - Ability to operate and/or monitor 295036 Secondary Containment the following as they apply to SECONDARY X 2.8 24 High SumplArea Water Level 15 CONTATNMENT HIGH SUMPI AREA WATER LEVEL: Radwaste EA2.03 Ability to determine and/or 295029 High Suppression Pool interpret the following as they apply to HIGH X 3.4 25 Water Level! 5 SUPPRESSION POOL WATER LEVEL:

Drywdl/containment water level 2.1.7- Conduct of Operations: Ability to evaluate plant performance and make 295014 Inadvertent Reactivity X operational judgments based on operating 4.4 26 Addition! I characteristics, reactor behavior, and

. instrument interpretation .

AKl.02 Knowledge of the operational implications of the following concepts as 295012 High Drywell Temperature X they apply to HIGH DRYWELL 3.1 27

!5 TEMPERATlJRE : Reactor power level control KIA Category Totals: 2 1 1 1 1 1 Group Point Total:

I 7

ES-401 4 Form ES-401-1 2010 NRC RO Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A A System # I Name G Imp. Q#

1 2 3 4 5 6 1 2 3 4 KLOI Knowledge of the physical connections and/or cause- effect relationships between PRIMARY 223002 PelS/Nuclear Steam X CONTAINMENT ISOLATION 3.8 28 Supply Shutoff SYSTEMINUCLEAR STEAM SUPPLY SHUT*OFF and the following: Main Steam System K1.05* Knowledge of the physical connections and/or cause- effect relationships between 264000 EDGs X EMERGENCY GENERATORS 3.2 29 (DIESEUJET) and the following:

Emergency generator fuel oil supply system K2.02 - Knowledge of electrical 203000 RHRlLPCI: Injection X power supplies to the following: 2.5 30 Mode Valves K2.01 - Knowledge of electrical 300000 Instrument Air X power supplies to the following: 2.8 31 Instrument air compressor K3.01 Knowledge of the effect that a loss or malfunction of the SHUTDOWN COOLING SYSTEM 205000 Shutdown Cooling X 3.3 32 (RHR SHUTDOWN COOLING MODE) will have on following:

Reactor pressure K3.01 - Knowledge of the effect that a loss or malfunction of the AVERAGE POWER RANGE 215005 APRM / LPRM X 4.0 33 MONITOR/LOCAL POWER RANGE MONITOR SYSTEM will have on followin~: RPS K4.02 - Knowledge of SOURCE RANGE MONITOR (SRM) 2 J 5004 Source Range Monitor X SYSTEM design feature(s) and/or 3.4 34 nterlocks which provide for the

'following: Reactor SCRAM signals K4.05 - Knowledge of A.C.

ELECTRICAL DISTRIBUTION 26200 I AC Electrical design feature(s) and/or interlocks X 3.4 35 Distribution which provide for the following:

Paralleling of A.C. sources (synchroscope) 1<5.02 - Knowledge of the operational implications of the following concepts as they apply to 217000 RCIC X 3.1 36 REACTOR CORE ISOLATION COOLING SYSTEM (RCIC): Flow indication f<5.07 . Knowledge of the operational implications of the 211000 SLC X following concepts as they apply to 2.7 37 STANDBY LIQUID CONTROL SYSTEM: Tank heater operation

ES-401 4 Form ES-401-1 2010 NRC RO Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A A System # / Name G Imp. Q#

1 2 3 4 5 6 1 2 3 4 K6.11 - Knowledge of the effect that a loss or malfunction of the following will have on the HIGH 206000 [-fPCI X 3,6 38 PRESSURE COOLANT INJECTION SYSTEM: Nuclear boiler instrumentation: BWR-2,3,4 K6.01 - Knowledge of the effect that a loss or malfunction of the 263000 DC Electrical Distribution X following will have on the D.C. 3.2 39 ELECTRICAL DISTRIBUTION:

A.C. electrical distribution A 1.06 - Ability to predict and/or monitor changes in parameters associated with operating the 2150031RM X INTERMEDIATE RANGE 3.3 40 MONITOR (IRM) SYSTEM controls including: Lights and alarms A 1.04 - Ability to predict and/or monitor changes in parameters associated with operating the 261000 SGTS X STANDBY GAS TREATMENT 3.0 41 SYSTEM controls including:

Secondary containment differential pressure A2.02 - Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES; and (b) based on those predictions, use 239002 SRVs X 3.1 42 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Leaky SRV A2.04 Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based on those 209001 LPCS X predictions, use procedures to 2.9 43 correct, control, or mitigate the consequences of those abnormal conditions or operations: D.C.

failures A3.02 Ability to monitor automatic operations of the REACTOR 212000 RPS X PROTECTION SYSTEM including: 3.2 44 Individual system relay status:

Plant-Specific A3.01 - Ability to monitor automatic operations of the CCWS including:

400000 Component Cooling Setpoints on instrument signal X 3.0 45 Water levels for normal operations,warnings, and trips that are applicable to the CCWS M.03 Ability to manually operate 218000 ADS X and/or monitor in the control room: 4.2 46 ADS logic reset

ES-401 4 Form ES-401-1 2010 NRC RO Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A A System # / Name G Imp. Q#

1 2 3 4 5 6 1 2 3 4 A4.03 - Ability to manually operate and/or monitor in the control room:

259002 Reactor Water Level X All individual component 3.8 47 Control

[!

controllers when transferring from manual to automatic modes 2.2.22 Equipment Control:

262002 UPS (ACIDC) X Knowledge of limiting conditions 4.0 48 for operations and safety limits.

2.1.28 - Knowledge of conduct of operations requirements:

262002 UPS (ACIDC) X Knowledge of the purpose and 4.1 49 function of major system components and controls ..

A2.03 - Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL DISTRIBUTION; and (b) based on 262001 AC Electrical Distribution X those predictions, use procedures 3.9 50 to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of off-site power K3.02 - Knowledge of the effect that a loss or malfunction of the STANDBY LIQUID CONTROL 211000 SLC X 3.0 51 SYSTEM will have on following:

Core spray line break detection system: Plant-Specific K1.08 - Knowledge of the physical connections and/or cause- effect relationships between STANDBY 261000 SGTS X 2.8 52 GAS TREATMENT SYSTEM and the following: Process radiation monitoring system K5.04 - Knowledge of the operational implications of the following concepts as they apply to AVERAGE POWER RANGE 2 J 5005 APRM I LPRM X 2.9 53 MONITOR/LOCAL POWER RANGE MONITOR SYSTEM:

LPRM detector location and core symmetry KJ A Category Totals: 3 2 3 2 3 2 2 3 2 2 2 Group Point Total:

I 26

ES-401 5 Form ES-401-1 2010 NRC RO Written Examination Outline Plant Systems Tier 2 Group 2 K K K K K K A A A A System # I Name G Imp. Q#

1 2 3 4 5 6 1 2 3 4 KI.02 Knowledge ofthe physical connections and/or cause- effect 215002 RBM X relationships between ROD BLOCK 3.2 54 MONITOR SYSTEM and the following:

LPRM: BWR-3,4,5 K2.02 - Knowledge of electrical power 201001 CRD Hydraulic X supplies to the following: Scram valve 3.6 55 solenoids K3.02 - Knowledge of the effect that a loss or malfunction of the FIRE 286000 Fire Protection X PROTECTION SYSTEM will have on 3.2 56 followin~: Personndprotection K4.02 - Knowledge of PLANT VENTILATION SYSTEMS design 288000 Plant Ventilation X feature(s) and/or interlocks which 3.7 57 provide for the following: Secondary containment isolation A 1.07 Ability to predict and/or monitor changes in parameters 241000 ReactorlTurbine X associated with operating the Pressure Regulator REACTORITURBINE PRESSURE 3.8 58 REGULATING SYSTEM controls IncludiQ9: Bypass valve position K6.11 Knowledge of the effect that a loss or malfunction of the following 226001 RHR/LPCI: CTMT will have on the RHRlLPCI:

Spray Mode X 2.8 59 CONTAINMENT SPRAY SYSTEM MODE: Component cooling water systems K5.01 Knowledge of the operational implications of the following concepts 201003 Control Rod and Drive X as they apply to CONTROL ROD 2.6 60 Mechanism AND DRIVE MECHANISM: HydrauliCS JI.2.07 Ability to predict the impacts of the following on the RADIATION MONITORING SYSTEM; and (b) t,ased on those predictions. use 272000 Radiation Monitoring X procedures to correct, control, or 2.8 61 mitigate the consequences of those 8,bnormal conditions or operations:

Hydrogen injection operation: Plant-Specific A3.01 - Ability to monitor automatic operations of the RHRlLPCI:

230000 RHRJLPCl: Torus/Pool X TORUS/SUPPRESSION POOL 3.4 62 Spray Mode SPRAY MODE including: Valve operation A4.01 - Ability to manually operate 290003 Control Room BVAC X and/or monitor in the control room: 3.2 63 Initiate/reset system 2.4.4. Ability to recognize abnormal indications for system operating 233000 Fuel Pool Cooling/Cleanup X parameters that are entry-level 4.5 64 conditions for emergency and abnormal operating procedures.

K3.01

  • Knowledge of the effect that a loss or malfunction of the OFFGAS 271000 Off-gas X 3.5 65 SYSTEM will have on following:

Condenser vacuum K! A Category Totals: 1 1 2 1 1 1 1 1 1 1 1 Group Point Total:

I 12

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: 2010 NRC RO Date:

KIA # Topic RO SRO-Only I IR Q# IR Q#

Ability to interpret and execute procedure 2.1.20 4.6 66 steps.

Ability to perform specific system and i 2.1.23 integrated plant procedures during all modes 4.3 67 I of plant operation.

Knowledge of operator responsibilities during 2.1.2 4.1 68 I all modes of plant operation.

Subtotal r" "", 3 i Ability to determine the expected plant configuration using design and configuration 2.2.15 3.9 69 control documentation, such as drawings, I line-ups, tag-outs, etc. I I Knowledge of the process for conducting 2.2.7 2.9 70 i special or infrequent tests.

Ability to apply technical specifications for a I 2.2.40 3.4 71 system.

',' ,Y' Category Subtotal ';

3 Knowledge of Radialogical Safety Principles

. pertaining to licensed operator duties, such as 2.3.12 containment entry requirements, fuel handling 3.2 72 responsibilities, access to locked high-radiation areas, aligning filters, etc.

Ability to use radiation monitoring systems, I such as fixed radiation monitors and alarms, 2.3.5 2.9 73 portable survey instruments, personell monitoring equipment, etc. I I Subtotal .' 2 I;;' .,1;,.

Ability to perform without reference to procedures those actions that require 2.4.49 4.6 74 I immediate operation of system components I and controls.

I Ability to recognize abnormal indications for system operating parameters which are entry-2.4.4 4.5 75 I level conditions for emergency and abnormal operating procedures. I

~

Subtotal ~t;;;;.*, 2 ....~ **.*L.,

Tier 3 Point Total 10 k"hi 7 f > *..

ES-401 Record of Rejected K1As Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KiA RO 295014 Inadvertent 2.2.42- Equipment Control: Ability to recognize system parameters Reactivity Addition, that are entry-level conditions for Technical Specifications.

1/2 2.2.42 Reason for Rejection: There are no entry-level conditions for Technical Specifications for Inadvertent Reactivity Addition.

Randomly reselected another item within 295014 G: 2.1.7- Conduct of Operations: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

RO 300000 Instrument K2.02 - Knowledge of electrical power supplies to the following:

Air, K2.02 Emergency air compressor 2/1 Reason for Rejection: Equipment not applicable to LGS Randomly reselected another item within 300000 K2: K2.01 Knowledge of electrical power supplies to the following: Instrument air compressor RO 263000 DC K6.02 - Knowledge of the effect that a loss or malfunction of the Electrical following will have on tile D.C. ELECTRICAL DISTRIBUTION:

2/1 Distribution, K6.02 Battery ventilation Reason for Rejection: Loss of battery ventilation does not result in plant conditions that can be used to develop a discriminating question for a control room operator.

Randomly reselected another item within 263000 K6: K6.01 Knowledge of the effect that a loss or malfunction of the following will have on the D.C. EI:"'ECTRICAL DISTRIBUTION :A.C. electrical distribution RO 262002 UPS 2.4.21 - Emergency Procedures 1 Plan: Knowledge of the (AC/DC), 2.4.21 parameters and logic used to assess the status of safety functions, 2/1 such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

Reason for Rejection: There are no UPS related functions that impact parameters and logic used to assess the status of safety functions.

Randomly reselected another item within 262002 G: 2.1.28 Knowledge of conduct of operations requirements: Knowledge of the purpose and function of major system components and controls.

RO 272000 Radiation A2.14 - Ability to predict the impacts of the following on the Monitoring, A2.14 RADIATION MONITORING SYSTEM; and (b) based on those 2/2 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of, or inadequate, shielding Reason for Rejection: there are no operations related AOPIEOP procedures for loss of, or inadequate, shielding for a radiation monitoring.

Randomly reselected another item within 272000 A2: A2.07 - Ability to predict the impacts of the following on the RADIATION MONITORING SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Hydrogen injection operation: Plant-Specific SRO 300000 Instrument A2.01 - Ability to (a) pn9dict the impacts of the following on the Air, A2.01 INSTRUMENT AIR SYSTEM and (b) based on those predictions, 2/1 use procedures to correct, control, or mitigate the consequences of those abnormal operation: Air dryer and filter malfunctions Reason for Rejection: For air dryer and filter malfunctions, control room personnel take no action to correct, control, or mitigate the consequences other than to dispatch appropriate personnel. All other actions are performed locally.

Randomly reselected another item: 300000 A2 only contains 1 item.

For this reason randomly selected a different system A2 item:

202001 Recirculation System, A2.03 Ability to (a) predict the impacts of the following on the RECIRCULATION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Single recirculation pump trip RO 295016 Control AK2.03 - Knowledge of the interrelations between CONTROL Room ROOM ABANDONMENT and the following: Control room HVAC 1/1 Abandonment Reason for Rejection: There are no directions provided for an RO to take regarding Control Room Abandonment due to Control Room HVAC. Additionally, there are no directions provided for an RO to take with regards to MeR HVAC during Control Room Abandonment.

Randomly reselected another item within 295016 AK2 item: AK2.01 Remote shutdown panel: Plant-Specific RO 262001 AC A2.08 - Ability to (a) prE!dict the impacts of the following on the A.C.

Electrical ELECTRICAL DISTRIBUTION; and (b) based on those predictions, 2/1 Distribution use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Opening a disconnect under load Reason for Rejection: All disconnects at Limerick require operator action to operate, therefore there are no situations in which a disconnect would be opened under load that would not involve operator error. Furthermore, there are no procedural actions for an RO to take to correct, control, or mitigate the consequences of a disconnect intentionally opened under load.

Randomly reselected another item within 262001 A2 Item: A2.03 Loss of off-site power

RO 295022 Loss of AK3. Knowledge of the reasons for the following responses as they CRD Pumps apply to LOSS OF CRD PUMPS: AK3.02 CRDM high temperature 1/2 Reason for Rejection: There are no Emergency or Abnormal procedures that are exercised as a result of CRDM high temperature.

Randomly reselected another Tier 1/Group 2 system, AK3 item:

295009 Low Reactor Water Level /2, AK3.01. Knowledge of the reasons for the following responses as they apply to Recirculation pump run back: Plant-S~ecific RO 295023 Refueling AA1.01 - Ability to operate and/or monitor the following as they Accident apply to REFUELING ACCIDENTS: Secondary containment 1/1 ventilation Reason for Rejection: Review of Sample plan determined there was an oversampling of KlAs related to Secondary Containment ventilation and response to system isolations.

Randomly reselected another 295023 item: AA2.02, Fuel Pool Level RO 223002 Primary K1.12 - Knowledge of the physical connections and/or cause effect Containment relationships between PRIMARY CONTAINMENT ISOLATION 2/1 Isolation SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF and the System/Nuclear following: Standby gas treatment system Steam Supply Shut-Reason for Rejection: Review of Sample plan determined there was Off an oversampling of KlAs related to Secondary Containment ventilation and response to system isolations. Additionally Tier 2 Group 1 sample already includes two system 261000 (SGTS) Items Randomly reselected another 223002 K1 item: K1.01, Main steam System RO 215005 APRM / K3.08 - Knowledge of the effect that a loss or malfunction of the LPRM AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE 2/1 MONITOR SYSTEM will have on following: core thermal calculations Reason for Rejection: APRM / LPRMS are not utilized to determine Core Thermal Power Calculations. Core Thermal Power is independently determined by a thermodynamic heat balance and is infected by LPRM failures Randomly reselected another 215005 K3 Item: K3.01, RPS SRO 295023 Refueling 2.4.34 - Emergency Procedures / Plan: Knowledge of RO tasks Acc Cooling Mode / performed outside the main control room during an emergency and 1/1 8 the resultant operational effects.

7/27/10 review of sample plan by chief examiner identified this KIA as not appropriate for development of an SRO level question Randomly reselected another 295023 generic item: 2.4.11, Knowledge of abnormal condition procedures

SRO 295013 High 2.4.46 - Emergency Procedures 1 Plan: Ability to verify that the Suppression Pool alarms are consistent with the plant conditions 1/2 Temperature /5 7/27/10 review of sample plan by chief examiner identified this KIA as not appropriate for development of an SRO level question Randomly reselected another 295013 generic item: 2.1.25, Ability to interpret reference materials, such as graphs, curves, tables, etc.

SRO 217000 RCIC 2.4.49 - Emergency Procedures 1 Plan: Ability to perform without reference to procedures those actions that require immediate 2/1 operation of system components and controls.

7/27/10 review of sample plan by chief examiner identified this KIA as not appropriate for development of an SRO level question Randomly reselected another 217000 generic item: 2.4.16, Knowledge of EOP implementation hierarchy and coordination with other support procedurE~s or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.

SRO 218000 ADS 2.2.39 - Equipment Control: Knowledge of less than one hour technical specification action statements for systems.

2/1 7/27/10 review of sample plan by chief examiner identified this KIA as not appropriate for development of an SRO level question Randomly reselected another 218000 generic item: 2.2.40, Ability to apply Technical Specifications for a system.

SRO 204000 RWCU 2.4.2 - Emergency Procedures 1 Plan: Knowledge of system set pOints, interlocks and automatic actions associated with EOP entry 2/2 conditions.

7/27/10 review of sample plan by chief examiner identified this KIA as not appropriate for dE~velopment of an SRO level question Randomly reselected another 204000 generic item: 2.1.41, Ability to obtain and interpret station electrical and mechanical drawings.

SRO 2.1.13, Knowledge of facility requirements for contrOlling vitali controlled access.

Tier 3 7/27/10 review of sample plan by chief examiner identified this KIA as not appropriate for development of an SRO level question Randomly res elected another generic item: 2.1.9, Ability to direct personnel activities inside the control room.

SRO 2.2.7, Knowledge of the process for conducting special or infrequent tests.

Tier 3 7/27/10 review of sample plan by chief examiner identified this KIA as not appropriate for dE!Velopment of an SRO level question Randomly reselected another generic item: 2.2.6, Knowledge of the process for making changes to procedures.

SRO 2.3.15, Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, Tier 3 personnel monitoring equipment, etc.

7/27/10 review of sample plan by chief examiner identified this KIA as not appropriate for development of an SRO level question Randomly reselected another generic item: 2.3.14, Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

RO 233000 Fuel Pool 2.2.37 - Equipment Control: Ability to determine operability and lor Cooling/Cleanup availability of safety related equipment.

Reason for Rejection: Fuel Pool Cleanup has a limited interface with safety related equipment. A discriminating question for the system could not be written Randomly reselected another 233000 Generic Item: 2.4.4, Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

RO 241000 K5.05 - Knowledge of the operational Implications of the following Reactor/T urbine concepts as they apply to REACTORITURBINE PRESSURE Pressure Regulator REGULATING SYSTEM: Turbine inlet pressure vs. turbine load Reason for Rejection: Based on Review during NRC Prep Week, a discriminating question for the system could not be written for this specific knowledge Replaced with another 241000 Item: A1.07, Ability to predict and/or monitor changes in parameters associated with operating the REACTOR/TURBINE PRESSURE REGULATING SYSTEM controls including: Bypass valve position RO 201003 Control Rod A1.01 - Ability to predict and/or monitor changes in parameters and Drive associated with operating the CONTROL ROD AND DRIVE Mechanism MECHANISM controls including: Reactor power Reason for Rejection: Based on Review during NRC Prep Week, a discriminating question for the system could not be written for this specific knowledge Replaced with another 201003 item: K5.01, Knowledge of the operational implications of the following concepts as they apply to CONTROL ROD AND DRIVE MECHANISM: Hydraulics RO 2.1.15, Knowledge of administrative requirements for temporary management directives, such as standing orders, night orders, Operations memos, etc.

Reason for Rejection: Based on Review during NRC Prep Week, This was determined to be more applicable to an SRO, a discriminating RO question for this KA could not be written Randomly reselected another Conduct of Operations Item: 2.1.2, Knowledge of operator responsibilities during all modes of plant operation.

SRO 295004 Partial or AA2.01 - Ability to determine and/or interpret the following as they Total Loss of DC apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER:

Pwr Cause of partial or complete loss of D.C. power Reason for Rejection: Based on Review during NRC Prep Week, This was determined to be more applicable to an RO, a discriminating SRO question for this KA could not be written Randomly reselected another Tier 1 Group 1 Item: 295031 Reactor Low Water Level, EA.04, Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL:

Adequate core cooling SRO 295037 SCRAM EA2.06 - Ability to determine and/or interpret the following as they Conditions Present apply to SCRAM CONDITION PRESENT AND REACTOR POWER and Reactor Power ABOVE APRM DOWNSCALE OR UNKNOWN: Reactor pressure Above APRM Reason for Rejection: Based on Review during NRC Prep Week, Downscale or This was determined to be more applicable to EA2.02 Unknown Replaced with 295037, EA2.02, Reactor Water Level SRO 295038 High Off- EA2.02 - Ability to determine and/or interpret the following as they site Release Rate apply to HIGH OFF-SITE RELEASE RATE: Total number of curies released Reason for Rejection: Based on Review during NRC Prep Week, This was determined that a discriminating question related to Operations responsibilities could not be developed.

Randomly reselected another 295038, EA2 item, EA2.04, Source of off-site release SRO 204000 RWCU 2.2.41, Ability to obtain and interpret station electrical and mechanical drawings.

Reason for Rejection: Based on Review during NRC Prep Week, This was determined to be more applicable to an RO, a discriminating SRO question for this KA could not be written

\

Randomly reselected another Conduct of Operations item: 2.1.20, Ability to interpret and execute procedure steps.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: LGS Date of Examination: 10/04/10 Examination Level: RO 181 SRO D Operating Test Number: ILT09-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

L. Conduct of Operations N,R G.2.1.3 Shift Turnover Checklist M. Conduct N,R G.2.2.12 Evaluate Valve Stroke Data of Operations ST-6-10'7-20'0'-0' N. Equipment Control N,R G.2.2.12: Review ST-6-O'47-37O'-1, Pre Control Rod Withdrawal Check O. Radiation Control D,R,P G.2.3.11 Gaseous Effluent Release Rate Determination (20'0'8 RO A3)

Emergency Procedures/Plan 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 (S 1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: LGS Date of Examination: 10/04/10 Examination Level: RO DSRO I8l Operating Test Number: ILT09-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

P. Conduct of Operations N,R G.2.1.3 Shift Turnover Checklist Q. Conduct of Operations N,R G.2.1.S Maintain Minimum Shift Staffing and rJIoIi ,)/

Control Overtime tl tJZ R. Equipment Control N,R G.2.2.12 Heview ST-S-047-370-1, Pre Control f/IJ.J9(

Rod Withdrawal Check H "p.-o S. Radiation Control D,R,P G.2.3.S Review and Approve a Liquid Rad Waste Discharge Permit, (2008 SRO A3)

T. Emergency D,R G.2.4.21 Make an E-plan Classification, dlf£ of.J Procedures/Plan (0131 ) tJl/'?

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

  • Type Codes & Criteria: (C)ontrol room, {S)imulator, or Class{R)oom (D)irect from bank (:5 3 for ROs; :5 4 for SROs & RO retakes)

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

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

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facilitv: LGS Date of Examination: 10104110

. Exam Level: RO 181 SRo-ID SRO-U 0 Operating Test No.: ILT09-1 .

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

System 1 JPM Title Type Code* Safety Function

a. CRD Hydraulic System / Perform Reactor, Startup, Altornate A,D,L,S,P 1 Path (2008 JPM A)
b. Manually place a RFP in Service, Alternate Path N,A,S 2
c. Transfer HPCI From Pressure Control Mode to Level Control A,N,S 4 Mode, Alternate Path
d. T-228, Inerting/Purging Primary Containment N,S 5
e. Transfer 013 from 101 to 201 (0519) A,D,S 6
1. Control Rod Exercise Test N,S 7
g. Comp Cooling Water 1 Align RECW for OW Cooling (2008 JPM G) A, 0, EN, S, 8 P

Manually Isolate the RE Enclosure (0022) D,S 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Bypassing and Removing the *A RPS and UPS Static Inverter from D,R 6 Service (0203)
j. Alignment of Equipment or Operation for Shutdown Cooling (Fire E, N, L, R, 4 Safe Shutdown)
k. RO, SRO-I I SRO-U, Scram and MSIV closure from the AER A,D,E,L,R 7 (0261)

@ 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 I SRO-II SRO-U (A)lternate path 4-6/ 4-6/ 2-3 (C)ontrol room (D}irect from bank  :;;9/::;8/.s4 (E)mergency or abnormal in-plant C!:1/~1/C!:1 (EN)gineered safety feature - I - I C!:1 (control room system)

(L)ow-Power I Shutdown ~1/C!:1/C!:1 (N)ew or (M)odified from bank including 1(A) C!:2/~2/~1 (P)revious 2 exams  :;; 3/.s 31 s; 2 (randomly selected)

(R)CA C!:1/~1/::?:1 is)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facilitv: LGS Date of Examination: 10/04/10 Exam Level: RO 0 SRO-I 181 SRO-U 0 Operating Test No.: ILT09-1 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

a. CRD Hydraulic System I Perform Reactor, Startup, AltE!rnate A,D,L,S,P 1 Path (2008 J PM A)
b. Manually place a RFP in Service, Alternate Path N,A,S 2
c. Transfer HPCI From Pressure Control Mode to Level Control A,N,S 4 Mode, Alternate Path
d. T-228, Inerting/Purging Primary Containment N,S 5
e. Transfer 013 from 101 to 201 (0519) A,D,S 6 f
g. Camp Cooling Water I Align RECW for DW Cooling (2008 JPM G) A, D, EN, S, 8 P
h. Manually Isolate the RE Enclosure (0022) D,S 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Bypassing and Removing the *A RPS and UPS Static Inverter from D,R 6 Service (0203)
j. Alignment of Equipment or Operation for Shutdown Cooling (Fire E,N, L, R, 4 i Safe Shutdown)
k. RO, SRO-I , SRO-U, Scram and MSIV closure from the AER A,D,E,L,R 7 (0261 )

@ 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 I SRO-II SRO-U (A)lternate path 4-6 I 4-61 2-3 (C)ontrol room (D)irect from bank s9/s8/s4 (E)mergency or abnormal in-plant 2!1/2!1/2!1 (EN)gineered safety feature - I - I 2!1 (control room system)

(L)ow-Power I Shutdown 2!1/2!1/2!1 (N)ew or (M)odified from bank including 1(A) 2!2/2!2/2!1 (P)revious 2 exams :s; 3/ s 3/:S; 2 (randomly selected) t)CA  ?:1/2!1/2!1 S)imulator

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: LGS Date of Examination: 10/04/10 Exam Level: RO 0 SRo-ID SRO-U 181 Operating Test No.: ILT09-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 'for SRO-U, including 1 ESF)

System 1 JPM Title Type Code* Safety Function

a. CRO Hydraulic System 1 Perform Reactor, Startup, Alternate A,O,L,S,P 1 Path (2008 JPM A)
b. Manually place a RFP in Service, Alternate Path N,A,S 2 c.

d.

, e.

I f

g. Comp Cooling Water 1 Align RECW for OW Cooling (2008 JPM G) A, 0, EN, S, 8 P

h.

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

i. Bypassing and Removing the
  • A RPS and UPS Static Inverter from O,R 6 Service (0203)
j. Alignment of Equipment or Operation for Shutdown Cooling (Fire E, N, L, R, 4 Safe Shutdown) k.

@ 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-II SRO-U (A}lternate path 4-6 , 4-6 12-3 (C)ontrol room (D}irect from bank S9/S8/:54 (E}mergency or abnormal in-plant  ?:1/;::1/?:1 (EN)gineered safety feature 1 ?:1 (control room system)

(L)ow-Power / Shutdown  ?:1/?:1/?:1 (N)ew or (M)odified from bank including 1(A)  ?:2/;::2/?:1 (P)revious 2 exams S 31 S 31 S 2 (randomly selected)

(R)CA  ;::1/;::1/;::1 IS)imulator

Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: 2 Op-Test No.: 1 Examiners: _ _ _ _ _ _ _ _ _ _ _ __ Operators: _ _ _ _ _ _ _ _ _ _ _ __

Initial Conditions:

Reactor Power is 19%, Unit 2 100% power Turnover:

  • Unit 1 is in OPCON 1, Reactor Power is approximately 19%
  • GP-2, Normal Plant Startup is in progress and complete through step 3.4.25.
  • Rod Move Sheet sequence step #22, Group 5 is complete, Step #23 is in progress, with rod 10-11 at 00 and going to position 12
  • GP-2, App. 3, Startup of the Main Turbine is in progress and complete through step 3.3.7
  • All MCR annunciators in alarm are understood and expected due to present plant condition.
  • "1 B" RFP is in AUTO through the 108B
  • Both recirc pumps are operating at 28% speed
  • "1 A" and "1 B" Condensate pumps are in service
  • "1 B" and "1 C" Circ water pumps are in service
  • RWCU is in service with "1 A" pump and botl, F/Ds
  • "1 B" OW Chiller in service
  • All available Deep Bed Demins are in service
  • 4 Condensate Filter Demins are in service Inoperable/Out of Service Equipment and ETR
  • 1A EHC pump needs to be removed from service before Startup continues Planned Evolutions:
  • Prior to continuing Control Rod Withdrawal, swap EHC pumps from 1A to 1B per S31.6.C, Swapping operating EHC Pumps prior to continuing control rod withdrawal.
  • Continue with GP-2, and GP-2, App. 3 activities in support of plant startup.
  • Regulatory Action Log has been reviewed and no equipment is known to be INOP which would affect continuing the startup.

Event Malf. No. Event Event No. Type* Description 1 N/A N-BOP Swap EHC pumps NRC Scenario #2 - 2010 Limerick Operating Test Page 1 of Error! Bookmark not defined.

Appendix D Scenario Outline Form ES-D-1 2 N/A N-SRO Pull control rods per GP-2 in support of plant startup_

R-RO 3 MPROO4B TS,I-SRO APRM Fails Inoperable I-RO 4 C-BOP MED282C TS,C Loss of Div III DC SRO 5 MRR442B C-SRO Recirc Pump 1B RPT Breaker Trip C-RO C-BOP 6 MRP029D M ATWS MRP407C MSL197 7 MRD024 C-RO Rod Drive Control System Failure 8 MEH108 C-BOP Turbine Bypass valves fail C-SRO C-RO

  • (N)ormal, (R)eactivity, 11)nstrument, (C)omponent, (M)ajor NRC Scenario #2 - 2010 Limerick Operating Test Pa!Je 2 of Error! Bookmark not defined.

Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: 4 Op-Test No.: 1 Examiners: Operators:

Initial Conditions:

Unit 1 at 75% power. Unit 2 is at 100% power.

Turnover:

OPRM Pre-Trip Alarms have been occurring sporadically and have been evaluated by Operations and Reactor Engineering. The alarms are expected for current plant conditions and planned power ascension may proce.~d.

Inoperable/Out of Service Equipment and ETR

  • Inboard MSIV HV-41-1F022A inadvertently closed due to an Electrical Fault
  • Repairs complete on HV 1 F022A
  • RCIC is Out of Service for repairs to the RCIC Trip Throttle Valve, HV-50-112
  • Repairs are expected to take 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Planned Evolutions:
  • Open the MSIV HV-41-1F022A per S41.3.B, Reopening a Single Isolated MSIV.
  • Raise Reactor Power to 100% power per GP-5 Appendix 2, Planned Rx Maneuvering Without Shutdown, Section 3.2, Rx Power Restoration.
  • The RE is in the control room.

Event Malf. No. Event Event No. Type* Description N-SRO 1 N/A Open Inboard MSIV HV-41-1 F022A N-BOP R-RO 2 N/A Raise Power to 100%

N-SRO C-RO 3 MRR504B C-BOP Reactor Recirc Pump 1B Shaft Shear TS,C-SRO MCW484A C-BOP 4 TECW pump A Trip, B TECW fails to auto start MCW486B C-SRO VIM123A01 C-BOP 5 RWCU A pump vibration, and Low Flow TS,C-SRO MRP445 M 6 HPCI Steam leak MHP446A J MHP446B NRC Scenario #4 - 2010 Limerick Operating Test Page 1 of 30

MRP029C I-RO 7 RPS Failure MFW244B C-RO 8 "A" RFP Steam Supply Valve Fails MAD141D C-BOP 9 E SRV fails to open C-SRO

  • (N)ormal, (R}eactivity, {I)nstrument, {C}omponent, (M)ajor NRC Scenario #4 - 2010 Limerick Operating Test Page 2 of 30

Appendix D Scenario Outline Form E8-D*1 Facility: Limerick 1 & 2 Scenario No.: 5 Op-Test No.: 1 Examiners: Operators:

Initial Conditions:

Unit 1 Reactor Power is 100%, Unit 2 Reactor Power is 100%.

Turnover:

Inoperable/Out of Service Equipment and ETR:

None Planned Evolutions:

  • Maintain 100% power
  • Place HPCI in Full Flow Test, using the Manual Quick Start Method per S55.1.D for oil sampling.
  • Completion of oil sampling is expected to take 15 minutes.
  • HPCI will be shutdown when sampling is complete
  • 1A RHR is in Suppression Pool cooling to support HPCI operation Event Malf. No. Event Event No. Type* Description N/A I\I-BOP 1 Start HPCI using Manual Quick Start Method N-SRO MHP448B C-BOP 2 HPCI Flow controller failure TS, C SRO MFH564A C-SRO 3 2A Feedwater Heater Isolation R-RO MRP029A I-SRO 4 Pressure Instrument Fails High & RPS Failure MVI234G TS- SRO MVI231A C-BOP 5 Div 1 LOCA Signal. D11 fails to start MDG420A TS,C SRO

. C-RO MCU575 M 6 Unisolable Steam leak will occur in RWCU Regen Heat MCU195A Exchanger Room.

MCU195B MCU195C MRR440A M 7 LOCA via "1 A" Recirc MMS067 MRH172C C-BOP 8 "C" RHR pump and "B" Core Spay pump fail to auto MCS183B start.

MRH171B C-BOP 9 Failure of B RHR pump and "A" RHR drywell Spray MRH528C C-SRO valves C-RO

  • (N)ormal, (R }eactivity, (I}nstrument, (C}omponent, (M)ajor NRC Scenario # 52010 Limerick Operating Test Page 1 of 34
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