ML12339A166

Draft - Outlines (Folder 2)

ML12339A166
Person / Time
Site:	Limerick
Issue date:	11/15/2012
From:	Caruso J G Operations Branch I
To:	Wasong A J Exelon Generation Co
Jackson D E
Shared Package
ML120230224	List: IR 05000352/2012301 ML120270009 ML12276A134 ML12279A055 ML12325A281 ML12325A303 ML12325A327 ML12325A335 ML12325A347 ML12332A082 ML12339A154 ML12339A158 ML12339A166 ML12339A170 ML12339A183
References
ES-401-1, TAC U01858
Download: ML12339A166 (25)

Text

II BWR Examination Outline Form ES401*1 Date of Exam: RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total 1. 1 4 3 3 4 4 2 20 7 Emergency

& ' Abnormal Plant 2 1 I 2 N/A 1 1 N/A 1 7 3 Evolutions Tier Totals 5 4 5 5 5 3 10 1 2 I 5 3 3 2 3 3 I 2 26 5 2. Plant 2 0 I 1 I I 2 I 1 1 1 2 12 3 Systems Tier Totals 2 2 2 6 4 5 3 4 4 2 4 8 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 Note: 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). The point total for each group and tier in the proposed outline must match that specified in the table. The final pOint total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 pOints and the SRO-only exam must total 25 pOints. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. RefElr to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements. 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. Absent a plant-specific priority, only those KlAs having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories. 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 01 system. Refer to Section D.1.b of ES-401 for the applicable KlAs. On the following pages, enter the KIA numbers, a brief description of each topic, the topiCS' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category.

Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2. Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams. For Tier 3, select topics from Section 2 of the KJA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.

Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

2 Form ES-401-1 BWR Examination Outline EIAPE # I Name I Safety G KIA Topic(s) IR #295001 Partial or Complete Loss of Forced X AK3.06: Knowledge of the reasons forthe following 2.9 I Core Flow Circulation / 1 & 4 responses as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:

3.0 Core flow ..295003 Partial or Complete Loss of AC I 6 AA2.02: Ability to detennine and/or interpret the 4.2 2 following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: Reactor power / pressure I and 4.3 level -295004 Partial or Total loss of DC Pwr 1 6 AK 1.05: Knowledge of the operational implications of the following concepts as they apply to P ARTIA L COMPLETE LOSS OF D.C. POWER: Loss of3.4 -295005 Main Turbine Generator Trip 1 3 G2.1.32: Ability to explain and apply system limits and precautions as they relate to MAIN GENERATOR 4.0 295006 SCRAM 11 AK2.04: Knowledge of the interrelations between 3.6 5 SCRAM and the following:

Turbine trip logic 3.7 AAI.06: Ability to operate and/or monitor the following 295016 Control Room Abandonment I 7 X 4.0 6 as they apply to CONTROL ROOM ABAN DONMENT : Reactor water level 4.1 295018 Partial or Total Loss of CCW / 8 AA2.0 I: Ability to detennine and lor interpret the 3.3 7 following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: 3.4 ,.., 295019 Partial or Total Loss of Inst. Air 18 AA 1.0 I: Ability to operate and/or monitor the backup air 3.5 8 supply as it applies to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR 3.3 295021 Loss of Shutdown Cooling 14 AKI.Ol: Knowledge of the operational implications of 3.6 9 the following concepts as they apply to LOSS OF SHlJI Vl !WN COOLING: Decay heat 3.8 AK1.03: Knowledge ohhe "1 implications of 295023 Refueling Acc I 8 the following concepts as apply to REFUELING 3.7 10 ACCIDENTS:

Inadvertent criticality

4.0 295024

High Drywell Pressure I 5 G2.4.21: Knowledge of the parameters and logic used to 4.0 11 assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant 4.6 system integrity, containment conditions, radioactivity release control, etc, as they apply to High Drywe\l Pressure 295025 High Reactor Pressure I 3 EA2.0 I: Ability to detennine and/or interpret Reactor 4.3 12 Pressure as it applies to HIGH REACTOR PRESSURE 4.3 EK].OI, Knowlol,o ,nh, "Pcm<i,n,]

imph"ti',"'f 3.0 13 Temp. / 5 the following concepts as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:

Pump NPSH 3.4 "<;,

/4D 295028 High Drywell Temperature I 5 X AK2.04: Knowledge of the interrelations between HIGH DRYWELL TEMPERATURE and the following:

Drywell ventilation 3.6 3.6 14 295030 Low Suppression Pool Wtr LviI 5 X EA2.02: Ability to detennine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL: Suppression pool temperature 3.9 3.9 15 295031 Reactor Low Water Level 12 EK2.IO: Knowledge of the interrelations between REACTOR LOW WATER LEVEL and Redundant Reactivity Control 4.0 4.0 16 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown 11 295038 High Off-site Release Rate I 9 X X EK3.07: Knowledge of the reasons for the following responses as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNK.,"<OWN:

Various alternate methods of control rod insertion EA1.OI: Ability to operate and/or monitor the tollowing as they apply to HIGH OFF-SITE RELEASE RATE: Stack -gas monitoring system 4.2 4.3 3.9 4.2 17 18 600000 Plant Fire On Site I 8 X AK3.04: Knowledge of the reasons for the following responses as they apply to PLANT FIRE ON SITE: Actions contained in the abnonnal procedure for plant fire on site 2.8 3.4 19 700000 Generator Voltage and Electric Grid Disturbances I 6 I X AAI.03: Ability to operate and/or monitor voltage regulator controls as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES 3.8 3.7 20 KIA Category Totals: I 4 3 3 4 4 2 t Total:

3 Form ES-401-1 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions

-Tier 1/Group 2 (RO I SRO) E/APE # I Name I Safety K K K A A G KIA 1 2 3 1 295002 Loss of Main Condenser Vac I 3 AKI.03: Knowledge of the operational implications of following concepts as they apply to LOSS OF CONDENSER VACUUM: Loss of heat 295007 High Reactor Pressure I 295008 High Reactor Water Levell 2 G2.2.44: Ability to interpret control room indications verify the status and operation of a system, and how operator actions and directives affect plant and conditions, as they apply to High Reactor Water 295009 Low Reactor Water Levell 295010 High Drywell Pressure I 5 AK2.05: Knowledge of the interrelations between DRYWELL PRESSURE and the following: cooling and 295011 High Containment Temp I 295012 High Drywell Temperature 295013 High Suppression Pool Temp./5 295014 Inadvertent Reactivity Addition 11 AK3.01: Knowledge ofthe reasons for the responses as they apply to INADVERTENT ADDITION:

Reactor 295015 Incomplete SCRAM 295017 High Off-site Release Rate 295020 Inadvertent Cont. Isolation I 5 & 7 AAI.02: Ability to operate and/or monitor the following they apply to INADVERTENT ISOLATION:

Drywell ventilation/cooling 295022 Loss of CRD Pumps 295029 High Suppression Pool Wtr LviI 5 EK3.02: Knowledge of the reasons for the responses as they apply to HIGH SUPPRESSION WATER LEVEL: Lowering suppression pool water 295032 High Secondary Area Temperature 295033 High Secondary Area Radiation Levels I 295034 Secondary Ventilation High Radiation I 295035 Secondary Containment Differential Pressure I 295036 Secondary Containment High EA2.02: Ability to detennine and/or interpret the following Sump/Area Water Levell as they apply to SECONDARY CONTAINMENT HIGH SUMPI AREA WATER LEVEL: Water level in the affected area 500000 High CTMT Hydrogen Conc. I IR # 3.6 3.8 4.2 4.4 3.7 3.8 4.1 4.1 3.2 3.2 3.6 4.0 3.1 3.1 I I I: 7/3 4 Form ES-401-1 ES-401 BWR Examination Outline Plant Systems -Tier 21Group 1 (RO I System # I K K K K K K A A A A G KIA Topic(s) IR # 1 2 3 4 5 6 1 2 3 4 203000 RHR/LPCI:

Injection X AI.03: Ability to predict andlor monitor changes 3.8 Mode in parameters associated with operating RHRlLPCI:

INJECTION MODE 3.7 i including:

System flow 205000 Shutdown Cooling K4.03: Knowledge of SHUTDOWN COOLING 3.8 SYSTEM (RHR SHUTDOWN MODE) design feature(s) and/or interlocks 3.8 ! provide for low reactor water level 206000 HPCI X K2.01: Knowledge OftllC electrical power supplies 3.2 30/31 to the following:

System valves 33 A2.0 I: Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM; and (b) based on those 4.0 predictions, use procedures to correct, control, or mitigate the consequences of those abnonnal 4.0 conditions or operations:

Turbine trips i .. .. ....< 201000Iso!ation(Emergency)

...

I 209001 LPCS K4.08: Knowledge of LOW PRESSURE CORE 3.8 SPRAY SYSTEM design feature(s) 4.0 interlocks which provide for the following:

Automatic systcm initiation

...: ..: I ..: 209002 HPCS **** 211000 SLC K5.06: Knowledge of the operational implications 3.0 of the following concepts as they apply STANDBY LIQUID CONTROL SYSTEM: 3.2 level measurement 212000 RPS X K4.04: Ability to manually operate andlor monitor 3.9 34135 in the control room: Bypass SCRAM instrument volume high level SCRAM signal 3.9 K5.02: Knowledge of the operational implications of specific logic arrangements as they apply to 3.3 REACTOR PROTECTION SYSTEM 3.4 2150031RM K6.04: Knowledge of the effect that a loss or 3.0 malfunction of the following will have on INTERMEDIATE RANGE MONITOR 3.0 SYSTEM: Detectors 215004 Source Range Monitor AA 1.05: Ability to predict and/or monitor changes 3.6 in parameters associated with operating SOURCE RANGE MONITOR (SRM) 3.8 i controls including:

SCRAM, rod block, and period ! I I I alann trip setpoints 215005 APRM / LPRM X K4,01: Knowledge of AVERAGE POWER RANGE MONITOR/WCAL POWER RANGE MONITOR SYSTEM design feature(s) andlor interlocks whieh provide for the following:

Rod withdrawal blocks 3.7 3,7 38 217000 RCIC X X K6,0l: Knowledge of the effect that a loss or malfunetion of electrical power will have on the REACTOR CORE ISOLATION COOLING 3,4 3,5 39/40 SYSTEM (RCIC) A2,03: Ability to (a) predict the impacts of valve closures on the REACTOR CORE ISOLATION

3.4 COOLING

SYSTEM (RClC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnonnal conditions or operations 33 218000 ADS X X KJ,02: Knowledge of the effect that a loss or malfunction of the AUTOMATIC DEPRESSURIZATION SYSTEM will have on 4,5 4,6 41142 the following:

Ability to rapidly depressurize the reactor A3,09: Ability to monitor automatic operations of the AUTOMATIC DEPRESSURIZATION SYSTEM including:

Reactor vessel water level 4.2 43 223002 PCIS/Nuclear Steam Supply Shutoff X A2.09: Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEMINUCLEAR STEAM 3,6 3,9 43 SUPPLY SHUT-OFF; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequenees of those abnonnal conditions or operations:

System initiation 239002 SRVs X A3 ,08: Ability to monitor automatic operations of the RELIEFISAFETY VALVES including:

Lights and alanns 3,6 3,6 44 259002 Reactor Water Level Control X G2, 1.28: Reactor Water Level Control: Knowledge of the purpose and function of major system components and controls 4.1 4.1 45 261000 SGTS X K6.05: Knowledge of the effect that a loss or malfunction of the following will have on the STANDBY GAS TREATMENT SYSTEM: 3.1 3.2 46 Reactor protection system: Plant-Specific 262001 AC Electrical Distribution X KLOl: Knowledge of the physical connections andlor cause effect relationships between AC, ELECTRICAL DISTRIBUTION and the 3,8 43 47 followi ency generators 262002 UPS (AC/DC) 263000 DC Electrical Distribution X X K4,Ol: Knowledge ofUNINTERRUPT ABLE POWER SUPPLY (AC.lD,c')

design feature{s) andlor interlocks which provide for the following:

Transfer from preferred power to alternate power supplies K3.03: Knowledge of the effect that a loss or malfunction of the D.c' ELECTRICAL DISTRIBUTION will have on systems with D,C, components 3.1 48 3,4 3Ar. 3,8 264000 EDGs X Kl.04: Knowledge of the physical conneetions 3.2 50/51 andlor cause-effeet relationships between EMERGENCY GENERATORS (D1ESEUJET) 3.3 and the following:

Emergency generator eooling water system 4.4 G2.1.30: Ability to locate and operate components, including local controls, as they 4.0 apply to Emergency Generators (Diesel/Jet).

300000 Instrument Air KS.O I: Knowledge of the operational implications 2.5 52 of the following concepts as they apply to the INSTRUMENT AIR SYSTEM: Air compressors

2.5 400000

Component Cooling X A3.0 I: Ability to monitor automatic operations of 3.0 53 Water the CCWS including:

Setpoints on instrument signal levels for nonnal operations, wamings, and 3.0 trips that are applicable to the CCWS ,+/-It KIA Category Point Totals: 2 I I 3 I 2 Point 26/5 ES-401 5 Form ES-401-1 System # I Name Hydraulic 201003 Control Rod and 201004 RSCS 201006RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU Probe 216000 Nuclear Boiler Inst. 219000 RHRllPCI:

Torus/Pool Cooling Mode 223001 Primary CTMT and Aux. 226001 RHRlLPCI:

CTMT Spray Mode 230000 RHRlLPCI:

Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam BWR Examination Plant SYstems -TIer 21Group 2 (RO I K K K A A A A G KIA Topic{s)4 5 6 1 2 3 4 X K2.01: Knowledge of electrical power supplies to: Pumps X K4.0 I: Knowledge of ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC) design feature(s) and/or interlocks which provide for the following:

Insert blocks/errors K3.07: Knowledge of the effect that a loss or malfunction of the RECIRCULATION SYSTEM will have on vessel bottom head drain temperature X K4.02: Knowledge of RECIRCULATION FLOW CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following:

Recirculation pump speed control X AI.02: Ability to predict and/or monitor changes in parameters associated with operating the NUCLEAR BOILER INSTR UM ENTATION controls including:

Removing or returning a sensor (transmitter) to service X K2.02: Knowledge of electrical power supplies to the following:

Pumps X A3.04: Ability to monitor automatic operations of the RHRlLPCI:

CONTAINMENT SPRAY SYSTEM MODE including:

lights and alanns Form ES IR # 2.9 54 3.1 I 3.4 55 3.5 2.9 56 2.9 3.0 57 3.0 2.9 58 3.1 3.1 3.3 3.1 60 3.1 MSIV Leakage Control 241000 Reactorrrurbine Pressure Regulator X KS.04: Knowledge of the operational Implications of the following concepts as they apply to REACTOR/TURBINE PRESSURE REGULATING SYSTEM: PAM pressure vs. reactor pressure 3.3 3.3 61 245000 Main Turbine Gen. I Aux. X G.2.1.27:

Knowledge of system purpose and/or function as it applies to Main Turbine Generator and Auxiliarv Svstems 3.9 4.0 62 256000 Reactor Condensate 259001 Reactor Feedwater X A2.03: Ability to (a) predict the impacts of the following on the REACTOR FEEDWATER SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnonnal conditions or operations:

Loss of condensate pump( s) 3.6 3.6 63 268000 Radwaste 2710000ffgas X A4.09: Ability to manually operate and/or monitor in the control room: Offgas system controls/components 3.3 3.2 64 272000 Radiation Monitoring 286000 Fire Protection X K6.0 I: Knowledge ofthe effect that a Joss or malfunction ofthe following will have on the FIRE PROTECTION SYSTEM: A.c. electrical distribution:

Plant-Specific 3.1 3.1 65 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals I I KIA Category Point Totals: 0 2 1 I 1 1 oint Total: 12/3 Category KJA# 2.1.29 1. Conduct 2.1.1 of Operations 2.1.25 Subtotal 2.2.39 2.2.1 2. Equipment Control Subtotal 2.3.11 2.3.7 3. Radiation Control Subtotal 2.4.8 4. 2.4.4 Emergency Procedures I Plan 2.4.34 Subtotal Tier 3 Point Total Topic RO Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc. IR 4.1/4.0 # 66 Knowledge of conduct of operations requirements, Ability to interpret reference materials, such as graphs, curves, tables, etc. 3.8/4.2 3.9/4.2 67 68 Knowledge ofless than or equal to one hour Technical Specification action statements for systems. 3.9/4.5 3 69 Ability to perform pre-startup procedures for the facility, including operating those eontrols associated with plant equipment tbat could affect reactivity.

4.5/4.4 70 2 Ability to control radiation releases 3.8/4.3 71 Ability to comply with radiation work permit requirements during nonnal or abnormal conditions.

3.5/3.6 72 2 Knowledge of how abnonnal operating procedures are used in coniunction with EOPs. Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnonnal operating procedures.

3.8/4.5 4.5/4.7 73 74 Knowledge of RO tasks perfonncd outside the main control room during an emergency and the resultant operational effects. 4.2/4.1 75 3 10 II Date of Exam: RO KIA Category Points SRO-Only Points Tier Group A A A G A2 G* TotalK K 1 r=r3 4 6 1 2 3 4

• Total 1. 1 20 7 Emergency

& Abnormal Plant 2 N/A N/A 7 2 1 3 Evolutions Tier Totals 27 6 4 10 1 I 26 2 3 5 2. Plant 2 12 0 1 2 3 Systems Tier Totals 38 3 5 8 Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 Categories 2 2 1 2 Note: Ensure that at least two topics from every applicable KJA category are sampled within each tier of the RO and SRO-only outlines (Le .. except for one category in Tier 3 of the SRO-only outline. the "Tier Totals" in each KJA category shall not be less than two). The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KJA statements. 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. Absent a plant-specific priority, only those KJAs having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively. Select SRO topics for Tiers 1 and 2 from the shaded systems and KJA categories. The generic (G) KJAs in Tiers 1 and 2 shall be selected from Section 2 of the KJA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KJAs. On the following pages, enter the KJA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category.

Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam. enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KJA numbers, descriptions.

IRs, and point totals (#) on Form ES-401-3.

Limit SRO selections to KJAs that are linked to 10 CFR 55.43. 7

_. BWR Examination Outline Form ES-401-1 ISRO) KIA Topic(s) IR # 1 2 I or Complete Loss of ulation I 1 & lor Complete Loss of AC 295004 Partial or Total Loss of DC Pwr I 6 AA2.03: Ability to detennine andior interpret the 76 following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: BatterY voltage 295005 Main Turbine Generator Trip / 3 295006 SCRAM 11 AA2.03: Ability to detennine andior interpret the 4.2 77 following as they apply to SCRAM: Reactor water level 01 Room Abandonment I 7 or Total Loss of CCW / 8 295019 Partial or Total Loss of Inst. Air 18 X AA2.02: Ability to detennine andior interpret the 3.7 78 following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: Status of safety-related instrument air system load,. 295021 Loss of Shutdown Cooling 14 295023 Refueling Ace / 8 295024 High Drywell Pressure / 5 X G2.4.IS: Knowledge of specific bases for EOPs as they apply to High Dn'well Pressure.

295025 High Reactor Pressure / 3 295026 Suppression Pool High Water H Temp. /5 295027 High Containment Temperature / 5 295028 High Drywell Temperature 15 295030 Low Suppression Pool Wtr Lvl/5 295031 Reactor Low Water Level / 2 EA2.04: Ability to detennine andior interpret the 4.8 81 following as they apply to REACTOR LOW WATER LEVEL: Adequate Core Cooling 295037 SCRAM Condition Present X G2.4.6: Knowledge of EOP mitigation strategies as they 4.7 82 and Reactor Power Above APRM apply to SCRAM Condition Present and Reactor Power Downscale or Unknown / 1 Above APRM Downscale or Unknown. 295038 High Off-site Release Rate / 9 G2.4.3I: Knowledge of annunciator alanns, indications, 4.1 79 or response procedures. (High Off-site Release Rate) i 600000 Plant Fire On Site / 8 700000 Generator Voltage and Electric Grid Disturbances / 6 -20/7 II 295012 I::';)-'"tu BWR Examination EmerQency and Abnormal Plant Evolutions

-Tier 1/Group 2 (RO I E/APE # I Name I Safety Function 295002 Loss of Main Condenser Vac I 295007 High Reactor Pressure I 295008 HiQh Reactor Water Levell 295009 Low Reactor Water Level I 295011 High Containment Temp 295013 High Suppression Pool Temp./5 295014 Inadvertent Reactivity Addition 295015 Incomplete SCRAM 295017 High Off-site Release Rate 1295020 Inadvertent Cont. Isolation 1 5 &295022 Loss of CRD Pumps 295029 High Suppression Pool Wtr 295032 High Secondary Area Temperature 1 295033 High Secondary Area Radiation Levels I 295034 Secondary Ventilation High Radiation I 295035 Secondary Containment Differential Pressure 1295036 Secondary Containment It:: K K K A A G KIA Topic{s) 1 2 3 1 A2.0 I: Ability to determine and/or intetpret the following 4.0 as they apply to HIGH SUPPRESSION TEMPERATURE:

Suppression Pool G.2A AI: Knowledge of the emergency action level 3.6 thresholds and AA2.0S: Ability to determine and/or interpret the 4.2 following as they apply to HIGH OFF-SITE RATE: Metenrological R= Group Point Total: 7/3 ES-401 BWR Examination Outline Plant Systems -Tier 2/Group 1 (RO I SRO) System # I Name K K K K A A G KIA IR #KMA 1 2 3 4 5 2 " 4 203000 RHRlLPCI:

Injection Mode 205000 Shutdown Cooling A2.03: Ability to (a) predict the impacts of A.C. 3.2 89 failures on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING i MODE); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations.

206000 I I ... 20.7000 Isolation (Emergency)

Condenser . ...

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

212000 RPS 2150031RM

= t-i* 215004 Source Range Monitor G2.2.40: Ability to apply Technical Specifications 4.7 87 for a system as they apply to the Source Range Monitor (SRM) System. 215005 APRM I LPRM 217000 RCIC 218000 ADS 2.4.6: Knowledge of EOP mitigation strategies.

4.7 G== 223002 PCIS/Nuclear Steam Supply Shutoff 239002 SRVs 259002 Reactor Water Level Control 261000 SGTS 262001 AC Electrical A2.04: Ability to (a) predict the impacts of types 4.2 90 of loads that, if deenergized, would degrade or hinder plant operation on the A.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of the abnormal conditions or operations 262002 UPS (AC/DC) 263000 DC Electrical Distribution 264000 EDGs 300000 Instrument Air 400000 Component Cooling Water Cate

S-401 BWR Examination Outline Plant Systems -Tier 2/Group 2 (RO / SRO) Form ES-40 1-1 System # I Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G KIA Topic(s) IR # 201001 CRD Hydraulic 201002 RMCS 201003 Control Rod and Drive Mechanism 201004 RSCS 201005 RCIS 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 215001 Traversing In-<

ore Probe 215002 RBM 216000 Nuclear Boiler Inst. 219000 RHRlLPCI:

Torus/Pool Cooling Mode 223001 Primary CTMT and Aux. 226001 RHRlLPCI:

CTMT Spray Mode X 02.1.7: Ability to evaluate plant perfonnance and make operational judgments based on operating charaeteristics, reactor behavior, and instrument interpretation (RHRlLPCI:

CTMT Mode} 4.7 91 230000 RHRlLPCI:

Torus/Pool Spray Mode I 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 ReactoriTurbine Pressure ReQulator 245000 Main Turbine Gen. I Aux. X 02.4.11: Knowledge of abnonnal condition procedures as they relate to Main Turbine Oenerator and Auxiliary Systems 4.2 92 256000 Reactor Condensate 259001 Reactor Feedwater X A2.07: Ability to (a) predict the impacts of the following on the REACTOR FEEDWATER SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnonnal conditions or operations:

Reactor water level control system malfunctions 3.8 93 268000 Radwaste 2710000ffgas 272000 Radiation Monitoring 286000 Fire Protection I

12/3 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessellnterna!s KJA Category POint Totals: I 2 Group Point Total:

SRO Category KIA # SRO IR # Knowledge of the fuel-handling responsibilities of SROs.3.9 94 Ability to explain and apply system limits and precautions.

4.095 Conduct of Operations 2 Knowledge of the process for managing maintenance activities during 3.8 96 power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.

2. 2.2.5 Knowledge of the process for making changcs in the facility as 3.2 97 Equipment described in the safety analysis repot1.. Control Subtotal 2 2.3.14 Knowledge of radiation or contamination hazards that may arise during 3.8 98 normal, abnormal or emergency conditions or activities.

3. Radiation Subtotal 1 Control 2.4.16 Knowledge ofEOP implementation h.ierarchy and coordination with 4.4 99 other support procedures or guidelines such as, operating procedures, abnonnal operating procedures, and severe accident management

4. guidelines.

Emergency Knowledge of the emergency plan. Procedures I i 4.0 100 Plan Subtotal 2 Tier 3 Point 7 Administrative Topics Outline Form ES-301-1 Facility:

Limerick Date of Examination:

10/8/12-10/12/12 Examination Level: RO Operating Test Number: 1 Administrative Topic Type Describe activity to be (see Note) R,N Conduct of Evaluate Overtime Work Request A-l.1 Review of Drywell Floor Drain/Equipment Drain Tank R,N Conduct of Operations Surveillance Logs A-1.2 Equipment Blocking of equipment A-2 N/A Radiation N/A A-3 R,N Emergency EAL Callout A-4 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)odifiecl from bank (:0: 1) (P)revious 2 exams (:S: 1; randomly selected)

Administrative Topics Outline Form ES*301*1 Facility:

Limerick Examination Level: SRO*I Date of Examination:

10/8/12-10/12/12 Operating Test Number: 1 Administrative Topic (see Note) Type Code* Describe activity to be performed R,N Conduct of Evaluation of Overtime Hours to Determine Availability A-l.1 of Drywell Floor Drain/Equipment Drain Tank R,N Conduct of Operations Surveillance Logs A-1.2 R,N Equipment Blocking of equipment A-2 Review inventory release from Equipment Drain Sample R,N Radiation Control Tanks to Cooling Tower Blowdown Line. A-3 R,N Emergency EALCall A-4 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 & (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 Room/In-Plant Systems Outline Form ES-301-2 Facility:

Limerick Date of Examination:

10/9/12 *Exam Level: RO. SRO-I D SRO-U D Operating Test No.: 1 Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System I JPM Title a. Recirculation Pump System/Start Up 1A Recirc Pump ! b. Manually Start HPCI c. Main Turbine Bypass Valve Exercising

d. SOC Operations

e. EOG Operations

f. Scram Channel A1 and A2 Functional Test g. Restore RECW, DWCW, and Instrument Gas h. Standby Gas Treatment Manual Startup with Charcoal Enclosure Hi Temp In_Dbnt Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Maximize CRD Flow After Shutdown During Emergency Conditions (T-240) Unit 2 j. Alignment of Equipment for Manual Operation of LPCI k. Venting Primary Containment Using the 6" ILRT Line from Type Code* Safety Function A,N,S 1 A,EN,N, S 2 D, S 3 A, L, N, S 4 A,E,N 6 A,M,S 7 D, S 8 A,M,S 9 E,L,N,R 1 A,N,R 2 E,N 5 @ 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 (A)lternate path (C}ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power 1 Shutdown (N)ew or (M)odified from bank including i(A) (P)revious 2 exams (R)CA (S)imulator Criteria for RO 1 SRO-II SRO-U 1 (control room system) :::; 31:::; 31:::; 2 (randomly selected)

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

Limerick Scenario No.. 1 Op-Test No.: __ Examiners:

Operators:

Initial Conditions:

Unit 1 at 90% power to recover HCU maintenance rods, 011 EOG out of service for overhaul, day 2 of 30 day LCO Turnover:

Recover the HCU maintenance rods and return Unit 1 10100% power Event Malf. No. Event Event No. Description 1 R-ATC Raise power by control rod withdrawal 2 MPR011B I-ATC, 1 B RBM Fails Inop TS-SRO 3 MMC077B C-BOP Hotwell level controller failure 4 MR0016A, MR0016B C-ATC TS-SRO Control rod drifts out -5 ME00150 C-BOP, Closure failure of 1 01-0i21T emporary loss of C-ATC 0124-G-0 Load CenterlTemporary loss of ability to drive control rods 6 MSLOOiA, C-ATC, SLC spurious injection with RWCU isolation MCU195A TS-SRO failure 7 MRP029C. M-ALL Electric A TWS/RRCS failure/SLC header rupture MRP407C, MSL559 C-ATC C-BOP 8 MMT002, C-ATC T-221 failure, main turbine trip, bypass valve MCR412A,MEH10B CRD pump I,;p' 9 MSW492A-0 Pump Trip in Suppression Pool Cooling * (N)onnal, (R)eactivity, (I)nstrument, (C)omponent, (M)aior Page 1 of 33 NRC Scenario #1 Limerick Generating Station Operating Test Appendix 0 Scenario Outline Form ES-O-1 Facility:

Limerick Scenario No.: 2 Op-Test No.: Examiners:

Operators: -....Initial Conditions:

100% power following a rod pattern adjustment, MOL, D11 Diesel out of service to repair a Jacket Water System leak (48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> into a 30 day LCO -3.8.1, AC Sources Operating);

repairs expected to be completed within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Turnover:

Maintain power with Recirc to compensate for Xenon Event Malf. No. No. 1 MPR017A 2 MFH564B 3 MEH105C MRD016D 4 XXXXXXX MED282B 5 6 MED261 7 MDG420C 8 MRR440A MDG418D 9 MRC466 * (N)ormal, (R)eactivity, Event Type* I-ATC TS-SRO C-BOP R-ATC C-ATC TS-SRO (I)nstrument,

'A' Recirc Flow Unit fails downscale FWH 12B Level Sensing Line Fails High (Reduce Power:::;

85%) EHC Pressure Regulator

'A' Fails (Oscillates)

'1A' Recirc Pump Motor Bearing Temperatures Exceed 200 of Requiring Pump Trip / Results in Single Loop Operation in Restricted Region of Power/Flow Map / Stuck Control Rod 30-31 During Insertion lAW Reactor Maneuvering Shutdown Instructions (RMSI) Loss of 125/250 VDC Safeguard Bus 1 BD105 Grid Instability Resulting in Loss of Offsite Power D13 Diesel Auto Start Failure (Recoverable)

Small Break LOCA (0.5% to 1% ramp over minutes) with D14 Diesel Trip on Bus RCIC Trip on Overspeed (Recoverable after RPV Level reaches -129") (C)omponent. (M)ajor Page 1 of 49 NRC Scenario #2 -Limerick Generating Station Operating Test Appendix Scenario Outline Form ES-O-1 Facility:

Limerick Scenario No.: 4 Op-Test No.: Examiners:

Operators: ..... Initial Conditions:

100% power, ST-6-092-314-1, "D14 Diesel Generator Slow Start Operability Test Run," in progress Turnover:

D14 DIG has been running atfuilioad for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. ST-6-092-314-1 is completed up to and including step 4.12.3. The crew is directed to shutdown D14 DIG starting at step 4.12.4 Event Malf. No. Event Event No. Type* Descri ption 1 N/A Shutdown D14 DIG lAW ST-6-092-314-1 2 MVI232F I-ATC Rx Level Transmitter L T 1 N080C Fails Low MRP029A TS-SRO with No RPS Actuation SiQnal 3 VIC105A6 R-ATC '1A' Recirc Pump Motor High Vibration (Power TS-SRO Reduced to < 93% to Clear Annunciator 111 D2) MCU194 4 C-80P RWCU Leak with Auto Isolation Failure (Manual TS-SRO Isolation Successful) 5 MEG095 Main Generator Voltage Regulator Failure with Volts/Hertz Exceeding Alarm Setpoint 6 XXXXXX C-ATC '1A' Recirc Pump ASD Controller Fails Upscale TS-SRO *7 MMS069 C-BOP Steam Seal Evaporator Steam Outlet Valve Fails R-ATC Closed TS-SRO 8 OBE Earthquake with Loss of Safeguard Bus C-80P D134 (Loss of 1 A Instrument Air Compressor I TS-SRO 'Loss of Secondary Containment) 9 Main Steam Line High High Radiation (Fuel i M-ALL MMS061A Failure) / MSL Break in Outboard MSIV Room MMS062A (Rooms 407 and 518) with Failure of the lA' Main MMS136 Steam Line to Isolate 10 MRE001A SGTS Exhaust Fan OA(8}V163 Trip with Failure MRE001B to Start of the ST8Y SGTS Exhaust Fan MRE317 OB(A)V163 (Recoverable)

I Leak Propagation RRE013 * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 57 NRC Scenario #4 -Limerick Generating Station Operating Test