ML102920661

Draft - Outlines (Facility Letter Dated 7/20/10) (Folder 2)

ML102920661
Person / Time
Site:	Limerick
Issue date:	07/20/2010
From:	Goff C Exelon Generation Co, Exelon Nuclear
To:	Caruso J, Dapas M Region 1 Administrator
Hansell S
Shared Package
ML100560247	List: IR 05000352/2010302 ML101650598 ML102720677 ML102870021 ML102920654 ML102920658 ML102920661 ML102920664 ML102920667 ML102920669 ML102920673 ML102920676 ML103080887
References
TAC U01767
Download: ML102920661 (32)

Text

Limerick Generating Station www.exeloncorp.com 3146 Sanatoga Road Nuclear Pottstown, PA 19464 10CFR 55.40 July 20, 2010 Mr. Marc Dapas, Acting Regional Administrator U. S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353

Subject:

Initial License Operator Program Exam Outlines

Reference:

NRC letter dated 6/14/10 SRO & RO Initial Exams-LGS

Dear Sir:

As requested in the referenced letter, the following NUREG-1021 required documents have been provided to Mr. J. Caruso regarding the Initial Operator Licensing Exams to be administered beginning on October 4, 2010 at Limerick Generating Station.

ES-201-2 Exam Outline Quality Checklist ES-201-3 Examination Security Agreement ES-301-1 Administrative Topics Outlines ES-301-2 Control Roomlln-plant Systems Outlines ES-301-5 Transient and Event Checklists ES-401-1 BWR Exam Outline ES-401-3 Generic Knowledge and Abilities Outline ES-401-4 Record of Rejected KlAs ES-D-1 Scenario Outlines If you have any questions or need additional information, please contact Mr. Corey Goff at (610) 718-4040.

Sincerely, ~

~~~

Manager- Operator Training -LGS Exelon Generation Corp. LLC

Enclosures:

Documents stated above to Mr. J. Caruso only cc: J. Caruso, USNRC, Region I (w/encl)

S. Hansell, USNRC Region I (wlo encl)

E. DiPaolo, USNRC Senior Resident Inspector, LGS (wlo encl)

Document Control Desk, USNRC, Washington, DC (wlo encl)

bcc: W. Maguire - GML5-1 (w/o encl)

E. Callan -GML 5-1 (w/o encl)

P. Gardner - GML 5-1 (w/o encl)

R. Dickinson - LLC3-1 (w/o encl)

C. Goff - LLC-3-1 (w/o encl)

E. Pierce - LLC-3-1 (w/o encl)

J. Hunter III - SSB 2-4 (w/o encl)

A. Columbus - SSB 4-2 (w/o encl)

PA DERBRP Inspector, LGS 5MB2-4 (w/o encl)

27 July 2010 Review Comments for T -75 Day Limerick Exam Outline Submittal The exam outline was hand delivered to the Regional office on Tuesday, 7/20 and comments were provided per telecom on 7/27/10. The outline was developed using a BWR Owners Group Random Generator software. The audit exam is being developed independently by a different staff person in a separate area with no communications in so far as the written exam. The NRC operating tests were developed with no overlap with the topics planned for the audit exam.

Scenarios The scenario outlines are all new. Requested that narratives be provided next week which include the proposed Critical Tasks for each scenarios.

Admin JPMs RO topic Shift Turnover Checklist will be designed for classroom administration - change "S" to "R" on outline.

RO topic to Activate Site Evacuation is planned for HI Rad situation with announcement suggested to include activation of emergency organization also SRO topic Shift Turnover Checklist A.1.1 will be designed for classroom administration change "S" to "R" on outline. This will include TS implications SRO topic Pre Control Rod Withdrawal Checks will also include TS implications.

Simulator JPMs Three proposed alt path JPMs involve securing equip due to hi vibs (b) or hi temp (c & e) and in addition only one new and one modified JPM which is at the minimum the rest from the bank suggested replacing RCIC JPM with a new alt path JPMs.

In addition, for the 5 JPMs designated for SROUs 2 of the 5 were from the last 2008 NRC exam.

Suggested replacing a or g.

Written SRO Outline The following KIA question topics did not appear to be SRO level topics: 1, 2, 3, 6, 8, 9, 10, 13, 14,17,94,95,98,96.

Written RO Outline Cautioned not to write questions involving simply asking what the power supplies are to a component directly ex. air compressors.

ES-401 Written Examination Outline Form ES-401-1 Facility: 201ONRCRO Date of Exam:

RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4 *

<.' .,~:ii  ::'i~(

.1

l. 1 3 4 3 4 3 3 20 7 Emergency it.

& 2 2 1 1 1 1 7 3 Plant Tier Evolutions 5 5 4 4 4 27 10 Totals . . Ixi. . *. 5 1<

1 3 2 3 2 3 2 2 3 2 2 2 26 5 2.

Plant 2 1 1 2 1 1 1 1 1 I 1 1 12 3 Systems Tier 4 3 5 3 4 3 3 4 3 3 3 38 8 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge & Abilities 10 7 Categories 3 3 2 2 Note: l. 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 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 +/-l 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) 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.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. 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. 1 does not apply). Use duplicate pages for RO and SRO-only exams.

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

EKLOI - 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 39 APRM Downscale or Unknown I I ABOVE APRM DOWNSCALE OR UNKNOWN: Reactor pressure effects on reactor power AKI.02 - Knowledge of the operational 295001 Partial or Complete Loss of implications of the following concepts as Forced Core Flow Circulation I I & X they apply to PARTIAL OR COMPLETE 3.3 40 4 LOSS OF FORCED CORE FLOW ClRCULATION : Powerlflow distribution 295006 SCRAM I I I i~~I~~~~~n~Owledge of the operational s of the following concepts as 3.7 41 they apply to SCRAM: Reactivity control AK2.0I - Knowledge of the interrelations 295016 Control Room between CONTROL ROOM X 4.4 42 Abandonment I 7 ABANDONMENT and the following:

Remote shutdown panel: Plant-Specific AK2.05 - Knowledge of the interrelations 295019 Partial or Total Loss of between PARTIAL OR COMPLETE X 3.4 43 Ins!. Air 18 LOSS OF INSTRUMENT AIR and the following: Main steam system EK2.18 - Knowledge of the interrelations 295024 High Drywell Pressure I 5 X I between HIGH DRYWELL PRESSURE and the following: Ventilation 3.3 44 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 45 Water Temp. IS 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.S 46 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 CCW/8 X 3.1 47 COMPONENT COOLING WATER.

Securing individual components (prevent equipment damage)

AA1.01 Ability to operate and/or monitor 295023 Refueling Ace Cooling the following as they apply to Model 8 X 3.3 48 REFUELING ACCIDENTS: Secondary containment ventilation EA1.04 Ability to operate and/or monitor 295038 High Off-site Release Rate the following as they apply to HIGH OFF 19 X 2.8 49 SITE RELEASE RATE:

SPDS/ERIS/CRIDS/GDS: Plant-Specific EA1.01 Ability to operate and/or monitor 295028 High Drywell Temperature the following as they apply to HIGH X 3.8 50 15 DRYWELL 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 3.6 51 LOSS OF SHUTDOWN COOLING:

Reactor water temperature

~Partial or Total Loss of DC X AA2.04 - Ability to determine and/or 3.2 52 r 16 interpret the following as they apply to

ES-401 2 Form ES-401-1 2010 !\IRC RO Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1

/ 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 I 3 X 3.7 53 HIGH REACTOR PRESSURE: Reactor 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 54 plant operation.

2.2.4 Equipment Control: (multi-unit license} Ability to explain the variations in 295003 Partial or Complete Loss of AC/6 X control board layouts, systems, 3,6 55 instrumentation and procedural actions between units at a facility.

2.4,8 Emergency Procedures / Plan:

Knowledge of how abnormal operating 600000 Plant Fire On-site I 8 X 3,8 56 procedures are used in conjunction with EOP's.

AA 1.01 - Ability to operate and/or monitor the following as they apply to 700000 Generator Voltage and X GENERATOR VOLTAGE AND 3.6 57 Electric Grid Disturbances ELECTRIC GRID DISTURBANCES: Grid frequency and Voltage.

EK2.02 Knowledge of the interrelations 295031 Reactor Low Water Levell between REACTOR LOW WATER X 3.8 58 2 LEVEL and the following: Reactor pressure KI A Category Totals: 3 4 3 4 3 3 Group Point Total:

I 20

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

EKI.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 59 19 CONTAINMENT AREA RADIATION LEVELS: Personnel protection EK2.04 Knowledge of the interrelations 295035 Secondary Containment between SECONDARY CONTAINMENT High Differential Pressure I 5 X 3.3 60 HIGH DIFFERENTIAL PRESSURE and the following: Blow-out panels: Plant-Specific AK3,02 Knowledge of the reasons for the 295022 Loss of CRD Pumps I I X following responses as they apply to LOSS 2,9 61 OF CRD PUMPS: CRDM high temperature EAL03 Ability to operate and/or monitor 295036 Secondary Containment the following as they apply to SECONDARY X 2,8 62 High Sumpl Area Water Levell 5 CONTAINMENT HIGH SUMPIAREA WATER LEVEL: Radwaste EA2,03 Ability to determine and/or 295029 High Suppression Pool interpret the following as they apply to HIGH Water Levell 5 X 3.4 63 SUPPRESSION POOL WATER LEVEL:

Dryweillcontainment water level 2,1.7- Conduct of Operations: Ability to evaluate plant performance and make 295014 Inadvertent Reactivity Addition! 1 X operational judgments based on operating 4.4 64 characteristics. reactor behavior, and instrument interpretation.

AKI,02 Knowledge of the operational implications of the following concepts as 295012 High Drywel\ Temperature 15 X they apply to HIGH DRYWELL 3.1 65 TEMPERATURE' 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 System # / Name G Imp. Q#

KI.I2 Knowledge of the physical connections and/or cause- effect 223002 PCIS/Nuclear Steam relationships between PRIMARY Supply Shutoff X CONTAINMENT ISOLATlON 31 1 SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF and the Standby gas treatment system K1.05* Knowledge of the physical connections and/or cause- effect relationships between 264000 EDGs X EMERGENCY GENERATORS 3. 2 (DIESEUJET) and the following:

Emergency generator fuel oil supply system 203000 RHRlLPCI: Injection K2.02 Knowledge of electrical Mode X power supplies to the following:

Valves K2.01 Knowledge of electrical 300000 Instrument Air X power supplies to the following:

Instru K3.01 Knowledge of the effect that a loss or malfunction of the 205000 Shutdown Cooling SHUTDOWN COOLING SYSTEM X 3.3 5 (RHR SHUTDOWN COOLING MODE) will have on following:

Reactor pressure K3.08 - Knowledge of the effect that a loss or malfunction of the AVERAGE POWER RANGE 215005 APRM / LPRM X MONITOR/LOCAL POWER 30 6 RANGE MONITOR SYSTEM will have on following: core thennal calculations K4.02 Knowledge of SOURCE RANGE MONITOR (SRM) 215004 Source Range Monitor X SYSTEM design feature(s) and/or 3.4 7 interlocks which provide for the followinq: Reactor SCRAM siQnals K4.05 - Knowledge of A.C.

ELECTRICAL DISTRIBUTION 26200 1 AC Electrical design feature(s) and/or interlocks X 3.4 8 Distribution which provide for the following:

Paralleling of A.C. sources (synchroscope)

K5.02 - Knowledge of the operational implications of the 217000 RCIC following concepts as they apply to X 3.1 9 REACTOR CORE ISOLATION COOLING SYSTEM (RCIC): Flow indication K5.07 - Knowledge of the operational implications of the 211000 SLC X following concepts as they apply to 2.7 10 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 206000 HPCI following will have on the HIGH X 3.6 II 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 12 ELECTRICAL DISTRIBUTION:

A.C. electrical distribution A 1.06 - Ability to predict and/or monitor changes in parameters associated with operating the 215003 IRM X INTERMEDIATE RANGE 3.3 13 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 14 SYSTEM controls including:

Secondary containment differential pressure A2.02 - Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES; and 239002 SRVs (b) based on those predictions, use X 3.1 IS 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 16 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 17 Individual system relay status:

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

400000 Component Cooling Setpoints on instrument signal Water X 3.0 18 levels for normal operations,warnings, and trips that are applicable to the CCWS A4.03 - Ability to manually operate 218000 ADS X and/or monitor in the control room: 4.2 19 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 Control X All individual component 3.8 20 controllers when transferring from manual to automatic modes 2.2.22 - Equipment Control:

262002 UPS (ACIDC) X Knowledge of limiting conditions 4.0 21 for operations and safety limits.

2.1.28 - Knowledge of conduct of operations requirements:

262002 UPS (AC/DC) X Knowledge of the purpose and 4.1 22 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 26200 I AC Electrical Distribution X those predictions, use procedures 3.9 23 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 24

<> 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 261oo0SGTS X 2.8 25 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 215005 APRM I LPRM X 2.9 26 MONITOR/LOCAL POWER RANGE MONITOR SYSTEM:

LPRM detector location and core symmetry KIA Category Totals: 3 2 3 2 3 2 2 13 2 2 2 Group Point Total: 26 I

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

1 3 4 KI.02 - Knowledge of the physical connections and/or cause- effect 215002 RBM X relationships between ROD BLOCK 3.2 27 MONITOR SYSTEM and the following: LPRM: BWR-3,4,5 K2.02 - Knowledge of electrical 201001 CRD Hydraulic X power supplies to the following: 36 28 Scram valve solenoids K3.02 Knowledge of the effect that a loss or malfunction of the FIRE 286000 Fire Protection X 3.2 29 PROTECTION SYSTEM will have on following: Personnel protection K4.02 - Knowledge of PLANT VENTILATION SYSTEMS design 288000 Plant Ventilation X feature(s) and/or interlocks which 3.7 30 provide for the following:

Secondary containment isolation K5.05 - Knowledge of the operational Implications of the 241000 ReactorlTurbine following concepts as they apply X to REACTOR/TURBINE 2.8 31 Pressure Regulator PRESSURE REGULATING SYSTEM: Turbine inlet pressure vs. turbine load K6.11 - Knowledge of the effect that a loss or malfunction of the 22600 1 RHRlLPCI: CTMT following will have on the Spray Mode X 2.8 32 RHRlLPCI: CONTAINMENT SPRAY SYSTEM MODE:

Component cooling water systems A 1.01 - Ability to predict and/or monitor changes in parameters 201003 Control Rod and Drive associated with operating the Mechanism X 3.7 33 CONTROL ROD AND DRIVE MECHANISM controls including:

Reactor power A2.07 - Ability to predict the impacts of the following on the RADIATION MONITORING SYSTEM; and {b} based on those 272000 Radiation Monitoring predictions, use procedures to X 2.8 34 correct, control, or mitigate the consequences of those abnormal conditions or operations:

Hydrogen injection operation:

Plant-Specific A3.01 Ability to monitor automatic operations of the 230000 RHRlLPCI: Torus/Pool RHRlLPCI:

Spray Mode X 3.4 3S TORUS/SUPPRESSION POOL SPRAY MODE including: Valve operation A4.01 - Ability to manually operate 290003 Control Room HVAC X and/or monitor in the control room: 3.2 36 Initiate/reset system 2.2.37 Equipment Control: Ability 233000 Fuel Pool to determine operability and! or Cooling/Cleanup X 3.6 37 availability of safety related equipment.

ES-401 5 Form ES-40 1-1 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 K3.01 - Knowledge of the effect that a loss or malfunction of the 271000 Off-gas X 3.5 38 OFFGAS SYSTEM will have on following: Condenser vacuum KIA Category Totals: 1 1

-=

1 1 1 1 1 1 1 1 Group Point Total:

I 12

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-40 1-3 Facility: 2010 NRC RO Date:

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

Ability to interpret and execute procedure 2.1.20 4.6 66 steps.

1. Ability to perform specific system and Conduct 2.1.23 integrated plant procedures during all modes 4.3 67 of Operations of plant operation.

Knowledge of administrative requirements for temporary management directives, such as 2.1.15 2.7 74 standing orders, night orders, Operations memos, etc.

• Subtotal . / .....*.. 3 Ii/i .*****.*.

Ability to determine the expected plant

2. configuration using design and configuration 2.2.15 3.9 68 Equipment control documentation, such as drawings, Control line-ups, tag-outs, etc.

Knowledge of the process for conducting 2.2.7 2.9 69 special or infrequent tests.

Ability to apply technical specifications for a 2.2.40 3.4 75 s;tstem.

3.

Radiation Control Subtotal .~;I~!I~ili~~ 3 Knowledge of Radialogical Safety Principles pertaining to licensed operator duties, such as 2.3.12 containment entry requirements, fuel handling 3.2 70 responsibilities, access to locked high-radiation areas, aligning filters, etc.

Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3.5 2.9 71 portable survey instruments, personell monitoring eguiement, etc.

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Subtotal " 2 "",'

Ability to perform without reference to

4. procedures those actions that require 2.4.49 4.6 72 Emergency immediate operation of system components Procedures I and controls.

Plan Ability to recognize abnormal indications for system operating parameters which are entry-2.4.4 4.5 73 level conditions for emergency and abnormal operating procedures.

i'

~

SUbtotal I"'" ,','

Tier 3 Point Total 7 I'.**.'.**.***,'.'*"".**.,**,..*

ES-401 Written Examination Outline Form ES-401-1 Facility: 201OSRO Date of Exam: 10/04/10 Points Tier Group K K G Total A2 G* Total 1 2 *

1. 20 4 3 7 Emergency

& 2 7 1 2 3 Plant Tier Evolutions 27 5 5 10 Totals 26 3 2 5 2.

Plant 2 12 1 3 Systems Tier 38 5 3 8 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge & Abilities 10 7 Categories 2 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 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 +/-l from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1.b of ES-401, for guidance regarding 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) 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 (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. Lb 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. 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. 1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the KIA Catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to IOCFR55.43

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

AA2,01 - Ability to determine andlor interpret the following as they apply to 295004 Partial or Total Loss of DC X PARTIAL OR COMPLETE LOSS OF D.C. 3,6 I Pwr/6 POWER: Cause of partial or complete loss of D,c' power EA2.06 - Ability to determine andlor interpret the following as they apply to 295037 SCRAM Conditions Present SCRAM CONDITION PRESENT AND and Reactor Power Above APRM X 4.1 2 REACTOR POWER ABOVE APRM Downscale or Unknown I I DOWNSCALE OR UNKNOWN: Reactor pressure AA2.IS Ability to determine and interpret the following as they apply to PLANT 600000 Plant Fire On-site I 8 X FIRE ON SITE: Requirements for 3.5 3 establishing a fire watch 2.2.37 - Equipment Control: Ability to 295028 High Drywell Temperature I 5

X determine operability and I or availability of 4,6 4 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 internal organizations or external agencies.

5 such as the state, the NRC, or the transmission system operator.4, I 2.4.34 - Emergency Procedures I Plan:

295023 Refueling Acc Cooling Knowledge of RO tasks performed outside X 4.1 6 Mode/8 the main control room during an emergency and the resultant operational effects, EA2.02 Ability to determine andlor 295038 High Off-site Release Rate I interpret the following as they apply to X 3.3 7 9 HIGH OFF-SITE RELEASE RATE: Total number of curies released 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)

EA2.0 I - Ability to determine andlor interpret the following as they apply to 295035 Secondary Containment High Differential Pressure I 5 X SECONDARY CONTAINMENT HIGH 3.9 8 DIFFERENTIAL PRESSURE: Secondary containment pressure: Plant-Specific 2.4.46 Emergency Procedures / Plan:

295013 High Suppression Pool Temperature / 5 X Ability to verify that the alarms are 42 9 consistent with the plant conditions.

2.4.35 - Emergency Procedures I Plan:

295014 Inadvertent Reactivity Knowledge of local auxiliary operator tasks Addition II X 4.0 10 during emergency and the resultant operational effects.

KfA Category Totals: 0 0 0 0 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 # / 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 3.7 II procedures to correct. control. or 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 3.7 12 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

SRM inop condition 2.4.49 - Emergency Procedures / Plan:

Ability to perform without reference to 217000 RCIC X procedures those actions that require 4.4 13 i~eration of syste~

comp,~--~*nfrols. -

2.2.39 - Equipment Control: Knowledge of less than one hour technical 218000 ADS X 4.5 14 specification action statements for systems.

A2.01 - Ability to (a) predict the impacts of the following on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM; and (b) based on those 215003 IRM X 3.2 15 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Power supply degraded KI A Category Totals: 0 0 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 # 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 REACfOR FEEDWATER SYSTEM; and (b) based on those predictions, use 259001 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) 2.4.2 - Emergency Procedures / Plan:

Knowledge of system set points, 204000 RWCU X 4.6 17 interlocks and automatic actions assoeiated with EOP entry conditions.

234000 Fuel Handling Equipment K/A Category Totals: 0 0 0 X

1 0 0 0 1 0 0 1 K4.01 Prevention of core alterations during control rod movements Group Point Total:

4.1 I t1

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

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

Knowledge of facility requirements for 2.1.13 3.2 94 controlling vitalI controlled access.

1.

Conduct of Operations Subtotal I",

>J li'",%"t 1 Knowledge of the process for conducting 2.2.7 3.6 95 special or infrequent tests.

Knowledge of limiting conditions for 2.2.22 4.7 98 operations and safety limits.

2.

Equipment Control Subtotal 'd~j~J:/0i ~ 2 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3.15 3.1 96 portable survey instruments, personnel monitoring equipment, etc.

2.3.11 Ability to control radiation releases. 4.3 99 3.

Radiation Control Subtotal .i 2

4. Knowledge of emergency plan protective 2.4.44 4.4 97 Emergency action recommendations.

Procedures! Knowledge of the parameters and logic used Plan to assess the status of safety functions, such as reactivity control, core cooling and heat 2.4.21 4.6 100 removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Subtotal <G~:! }'. 2 Tier 3 Point Total 10 !iii 7

?

ES-401 Record of Rejected KIAs 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 the 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. ELECTRICAL 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) predict 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 MCR 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) predict the impacts of the following on the A.C.

Electrical ELECTRICAL DISTRIBUTION; and (b) based on those predictions, 211 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

ES-301 Administrative Topics Outline Form ES-301-1 Facility: LGS Date of Examination: 10104/10 Examination Level: RO [8J SRO D Operating Test Number: ILT09-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations G.2.1.3 Shift Turnover Checklist N';

~

Conduct of Operations Equipment Control N,R G .2.2.12 Review ST 04 7-370-1, Pre Control Rod Withdrawal Check Radiation Control D,R,P G.2.3.11 Gaseous Effluent Release Rate Determination (2008 RO A3)

Emergency M,S G.2.4.12 Activate Site Evacuation Alarm Procedures/Plan )/t' KJ/4d~

f1 J tL /lNPcx. JtJCf tltl£..l1/r 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 (S 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 Facility: LGS Date of Examination: 10/04/10 Examination Level: RO DSRO l8] Operating Test Number: ILT09-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations G.2.1.3 Shift Turnover CheckJ:bsL N'lf- t~7>~

Conduct of Operations N,R G.2.1.8 Coordinate Personnel Activates Outside the Control Room Equipment Control N,R G.2.2.12 Review ST-6-047-370-1, Pre Control Rod Withdrawal Check

-r;~~

Radiation Control D,R,P G.2.3.6 Review and Approve a Liquid Rad Waste Discharge Permit, (2008 SRO A3)

Emergency D,R G.2.4.21 Make an E-plan Classification, Procedures/Plan (0131 )

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 (~ 1; randomly selected)

ES-301 Control Roomnn-Plant Systems Outline Form ES-301-2 Facilitv: LGS Date of Examination: 10/04/10 Exam Level: RO ~ SRO-I D SRO-U D Operating Test No.: lLT09-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. CRD Hydraulic System / Perform Reactor, Startup, Alternate A,D,L,S,P 1 Path (2008 ..'PM A)

b. Manually place a RFP in Service, Alternate Path N,A,S 2

c. RCIC slow start, High Bearing oil temp (0002) A,D,S 4

d. Primary Containment N2 Makeup (0523) D,S 5

e. Transfer D13 from 101 to 201 (0519) A,D,S 6

1. Control Rod Exercise Test (0107) D,S 7

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 of Shutdown Cooling (Fire E, M, L, R, 4 Safe Shutdown) (0267)

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 4-6/4-6/2-3 (C)ontrol room (D)irecl frorn bank ~9/~8/~4 (E)rnergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature - I - / ~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 ~ 3/ 5 3/5 2 (randomly selected)

(R)CA ~1/~1/~1 IS)imulator

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facilitv: LGS Date of Examination: 10/04/10 Exam Level: RO [J SRO-I 18l 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 1 Perform Reactor, Startup, Alternate A,D,L,S,P 1 Path (2008 ..IPM A)

b. Manually place a RFP in Service, Alternate Path N,A,S 2

c. RCIC slow start, High Bearing oil temp (0002) A,D,S 4

d. Primary Containment N2 Makeup (0523) D,S 5 i

e. TransferD13from 101 to 201 (0519) A,D,S 6

f. Comp Cooling Water 1 Align RECW for DW Cooling (2008 JPM G) A, D. EN, S, 8 P

g. Manually Isolate the RE Enclosure (0022) D,S 9 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 D,R 6 i Service (0203)

I

j. Alignment of Equipment or Operation of Shutdown Cooling (Fire E, M, L, R, 4 Safe Shutdown) (0267)

K Scram and MSIV closure from the AER (0261 ) A, D, L, R 7

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; alf 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 1 SRO-U (A)lternate path 4-6 1 4-6 1 2-3 (C)ontrol room (D)irect from bank s;9/s;8/S;4 (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 1Shutdown 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 1 s; 3 / s; 2 (randomly selected)

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facilitv: LGS Date of Examination: 10104/10 Exam Level: RO D SRO-I D SRO-U I8l 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 1 Perform Reactor, Startup, Alternate A,D, L,S, P 1 Path (2008 JPM A)

b. Manually place a RFP in Service, Alternate Path N,A,S 2

c. 4

d. 5

e. 6

f. 7

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

h 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 of Shutdown Cooling (Fire E, M, L, R 4 Safe Shutdown) (0267)

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-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 ~1/~1/~1 (EN)gineered safety feature - / - / ~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 ~ 3/ ~ 3/ ~ 2 (randomly selected)

(R)CA ~1/~1/~1 (S)imulator

Appendix D Required Operator Actions Form ES-D-2 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 Pull 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 both F/Ds

• "1 B" DW Chiller in service

• All ECCS are operable

• 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 Planned Evolutions:

• Swap EHC pumps from 1A to 1B per S31.6.C, Swapping operating EHC Pumps

• 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.

Appendix D Required Operator Actions Form ES-D-2 Event No.

... u;nl e*

Event Description 1 N/A N-BOP EHC pumps 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 Loss of Div III DC TS,C-SRO 5 MCC074C C-SRO Loss of Condenser Vacuum 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' ment, (C)omponent (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: 4 Op-Test No .. 1 Examiners: '1-'""QlUI Initial Conditions:

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

Turnover:

Inoperable/Out of Service Equipment and ETR

• Outboard MSIV HV-41-1 F028A inadvertently closed due to an instrument air leak

• Repairs complete on HV-41-1 F028A instrument air leak Planned Evolutions:

• Open the MSIV HV-41-1 F028A per S41.3.B

• Raise power to 100% power per GP-5 Attachment 1. The RE is not in the control room.

Event ... Event Type* Event No. Description 1 N-SRO N/A Open Outboard MSIV HV-41-1 F028A N-BOP 2 R-RO N/A Raise Power to 100%

N-SRO 3 C-RO MRR504B C-BOP Reactor Recirc Pump 1B Shaft Shear TS,C-SRO 4 MCW484A C-BOP TECW pump A Trip, B TECW fails to auto start MCW486B C-SRO 5 VIM123A01 C-BOP RWCU A pump vibration, and Low Flow TS,C-SRO 6 MRP445 M HPCI Steam leak MHP446a MHP446B 7 I-RO RPS Failure 8 MFW244B C-RO "A" RFP Steam Supply Valve Fails 9 MAD141 D C-BOP E SRV fails closed C-SRO NRC Scenario #4 - 2010 Limerick Operating Test Page 1 of 21

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

Initial Conditions:

Reactor Power is 58%, Unit 2 100% power 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.o for oil sampling.

• Completion of oil sampling is expected to take 15 minutes .

• HPCI will be shutdown when sampling is complete Event Malf. No. Event Event No. Type* Description 1 N/A N-BOP Start HPCI using Manual Quick Start Method N-SRO  !

2 MHP448B C-BOP HPCI Flow controller failure TS, C-SRO 3 MFH564A C-SRO 2A Feedwater Heater Isolation R-RO 4 MVI231A C-BOP Div 1 LOCA Signal. D11 fails to start MDG420A TS, C-SRO C-RO 5 MCU575 M Unisolable Steam leak will occur in RWCU Regen Heat Exchanger Room.

MCU195A MCU195B MCU195C 6 MRR440A M LOCA via "1 A" Recirc 7 MRH172C C-BOP "C" RHR pump and "B" Core Spay pump fail to auto start.

MCS183B 8 MRH171 B C-BOP Failure of B RHR pump and "Aft RHR drywell Spray valves MRH528C C-SRO C-RO

• (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRC Scenario # - 2010 Limerick Operating Test Page 1 of 17