ML083181193

Draft - Outlines (Folder 2)

ML083181193
Person / Time
Site:	Limerick
Issue date:	06/27/2008
From:	Caruso J G Operations Branch I
To:	Hunter J Exelon Generation Co
Hansell S
Shared Package
ML081060533	List: ML081840059 ML082890027 ML083181193 ML083181203 ML083181214 ML083181220 ML083190087 ML083190102 ML083190115 ML083190201 ML083190208 ML083190217 ML083220002 ML083520040 ML083650196 ML090260031
References
TAC U01745
Download: ML083181193 (29)

Text

RO Outline ES-401 BWR Examination Outline Form ES-401-1 Date of Exam: October 2008 dote: 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). 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 fl 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. Systemdevolutions within each group are identifed on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified: operationally important, site-specifc systems/evolutions that are not included on the outline should be added.

Refer to Section D.l .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 KIAs having ari 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) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.l .b of ES-401 for the applicable WAS 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 foi'Tier 2. Group 2 (Note #I 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 KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.

Limit SRO selechms to WAS that are linked to 10 CFR 55.43. 2. 3. 4. 5. 6. 7.' 8. 9. Page 1 of 21 RO Outline ES-401 2 Form ES-401-1 ES-401 295003 Partial or Complete Loss of AC II 16 295004 Partial or Total Loss of DC Pwr 295005 Main Turbine Generator Trip 1 3 295006 SCRAM / 1 295016 Control Room Abandonment 1 7 295018 Partial or Total Loss of CCW 1 8 295019 Partial or Total Loss of Inst. Air 18 295021 Loss of Shutdown Cooling 1 4 BWR E normal f mination Outline Form ES-401-1 volutions - Tier l/Group 1 (RO I SRO) c K/A Topic(s) IR K1.04 - Knowledge of the operational implications of Limiting cycle oscillation as it applies to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION 2.5 A2.04 - Ability to determine and/or interpret 35 system lineups as it applies to PARTIAL OR COMPLETE LOSS OF AC . A2.04 - Ability to determine and/or interpret System lineups as it applies to PARTIAL OR TOTAL LOSS OF DC PWR 3.2 K2.01 - Knowledge of the interrelations between MAIN TURBINE GENERATOR TRIP and Feedwater temperature.

Al.02 - Ability to operate and/or monitor Reactor water level control system as it applies to SCRAM A3.01 - Knowledge of the reasons for Reactor SCRAM as it applies to CONTROL ROOM ABANDONMENT K2.02 - Knowledge of the interrelations between PARTIAL OR TOTAL LOSS OF CCW and Plant operations.

A2.02 - Ability to determine and/or interpret Status of safety-related instrument air system loads as it applies to PARTIAL OR TOTAL 3.8 3.9 4.1 3.4 3.6 LOSS OF rwr. AIR K1.03 - Knowledge of the operational

3.9 implications

of Adequate core cooling as it applies to LOSS OF SHUTDOWN COOLING. K1.02 - Knowledge of the operational implications of Shutdown margin as it applies to REFUELING ACCIDENT.

G2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation, as it relates to HIGH DRYWELI, PRESSURE.

3.2 3.9 K3.08 - Knowledge ofthe reasons for 3.5 Reactoriturbine pressure regulating system operation as it applies to HIGH REACTOR PRESSURE.

3 4 5 7 8 - 9 10 11 12 pl Page 2 of 21 RO Outline 295027 High Containment Temperature I 295030 Low Suppression Pool Water Level 15 295031 Reactor Low Water Level I2 I I I I 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown I 1 I 295038 High Off-site Release Rate I9 600000 Plant Fire On Site I8 Y WIA X K2.03 - Knowledge of the lnterrelations between HIGH DRYWELL 'I EMPERATURE and Reactor water level indication.

A1.01 -Ability to operate and/or monitor ECCS systems (NPSH considerations) as it applies to LOW SUPPRESSION POOL WATER LEVEL A1.13 -Ability to operate and/or monitor the Reactor Water Level Control as it applies to REACTOR LOW WATER LEVEL K2.03 - Knowledge of the interrelations between SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM

DOWNSCALE OR LJNKNOWN and ARIIRPTIATWS.

A2.02 - Ability to determine andlor interpret Total number of curies released as it applies to HIGH OFF-SITE RELEASE RATE x G2.4.20 -Knowledge of the operational implications of EOP warnings, cautions, and notes, as it relates to PLANT FIRE ON SITE A1.05 - Ability to operate and/or monitor Engineered safety features as it applies to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES X X X x X 3.6 - 3.6 - 4.3 - 4.1 - 2.5 - 3.8 - 3.9 - 14 __ 15 - 16 _. 17 19 20 _. Page 3 of 21 RO Outline ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 */APE # / Name / Safety Function KIA Topic(s) 295007 High Reactor Pressure I3 IGH REACTOR PRESSURE and Reactor 29501 1 Hiah Containment Temo I 5 I 295012 High Drywell Temperature I5 295013 High Suppression Pool Temp. 295014 Inadvertent Reactivity Addition I1 295015 Incomplete SCRAM I 1 295017 High Off-site Release Rate I9 IIIII I lxl I I 295020 Inadvertent Cont.

Isolation I5 &7 295022 Loss of CRD Pumps I 1 lXl I I I 295032 High Secondary Containment Area Temperature I5 K2.01 - Knowledge of'the interrelations between HIGH SUPPRESSION POOL TEMPERATURE 23 and Suppression Pool Cooling. 3 6 X G2.4.9 - Knowledge of low power/shutdown

3.8 implications

in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies, as it relates to NCOMPLETE SCRAM. 24 I II K2.03 - Knowledge of the interrelations between INADVERTENT CONTAINMENT ISOLATION K1.02 - Knowledge of the opemtional implications of Radiation releases as it applies to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE.

Page 4 of 21 RO Outline ES-401 BWR Examination Outline Form ES-401-1 295034 Secondary Ventilation High Radiation I9 Page 5 of 21 RO Outline ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 205000 Shutdown Cooling 206000 HPCl 207000 Isolation NIA (Emergency)

Condenser 209001 LPCS X A1.08 - Ability to predict and/or monitor changes in parameters associated with operating the LOW PRESSURE CORE SPRAY SYSTEM controls including System lineup.

A3.04 - Ability to monitor automatic operations of the LOW PRESSURE CORE SPRAY SYSTEM 209001 LPCS X . , including System flow 209002 HPCS NIA 21 1000 SLC X K4.04 - Knowledge of STANDBY LIQUID CONTROL SYSTEM design feature(s) and/or interlocks which provide for Indication of fault in explosive valve firing circuits K3.05 Knowledge ofthe effect that a loss or malfunction of F.EACTOR PROTECTION SYSTEM will have on RPS logic ~ channels.

21 2000 RPS X ~ o predict and/or monitor changes ociated with operating the TECTION SYSTEM controls 212000 RPS 215003 IRM of the effect that a loss or NTERMEDIATE RANGE will have on Reactor manual Page 6 of 21 RO Outline ES-401 System #/Name 21 5004 Source Range Monitor 21 5005 APRM / LPRM 21 5005 APRM / LPRM 217000 RClC 217000 RClC 21 8000 ADS 223002 PClSlNuclear Steam Supply Shutoff 239002 SRVs 259002 Reactor Water Level Control 261 000 SGTS 262001 AC Electrical Distribution PI, EWR Examination Outline Form ES-401-1 AAG WA Topic(s) IR A4.06 - Abilirf to manually operate and/or tor in the control room Verification of A2.14 - Ability to (a) predict the impacts of Rupture Disk failure: Exhaust Diaphragm on the REACTOR CORE ISOLATION COOLING SYSTEM, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations K6.01 - Knowledge of the effect that a loss or malfunction of RHWLPCI system pressure will have on the AUTOMAI IC DEPRESSURILATION System A1.04 - Ability to prediLt and/or monitor changes in parameters arsociated with operating the PClS / NUCLEAR STEAM SUPPLY SHUTTOFF SYSTEM controls including Individual system relay status K2.01 - Knowledge of electncal power supplies to 2 8 SRV solenoids 3 9 2 6 K5.03 - Knowledge of the operational 31 implications of Water level measurement as it applies to REACTOR WATER LEVEL A3.01 - Ability to monitor automatic operations of 3 2 the STANDBY GAS TREATMENT SYSTEM CONTROL SYSTEM X K3.01 - Knowledge of the effect that a loss or malfunction of the AC ELECTRICAL 38 40 - 41 42 43 45 46 - 47 48 _c Page 7 of 21 RO Outline ES-401 System #I Name 262002 UPS (AC/DC) 263000 DC Electrical Distribution 263000 DC Electrical Distribution Ill 264000 EDGs 300000 Instrument Air X 400000 Component Cooling Water 300000 Instrument Air 7 400000 Component Cooling Water 'R Examination Outline Form ES-401-1 Tier ZIGroup 1 (RO / SRO) II AI GI WA Topic(s) K6.03 - Knowledge of the effect that a loss or malfunction of Static inverter will have on the UNITERRUPTABLE POWER SUPPLY System.

K1.02 - Knowledge of the physical connections andor cause-ei'fect relationships between DC ELECTRICAL DISTRIBUTION SYSTEM and Battery charger and battery. GZ.2.39 - Knowledge of less than or equal to one hour Technical Specification action statements for systems, as they relate to EDGs. K1.04 - Knowledge of the physical connections and/or cause-effect relationships between INSTRUMENT AIR SYSTEM and Cooling water to compressor.

GZ.1.20 - Ability to interpret and execute procedure steps, as it relates to COMPONENT COOLING WATER.

Grouo Point Total 52 53 Page 8 of 21 RO Outline ES-401 5 ES-401 BWR Examination Outline Fom ES-401-1 is - Tier Z/Group 2 (RO / SRO) ~ ~~ System #I Name A AAG WA TopiiXs) 2 34 ~ 201001 CRD Hydraulic 201002 RMCS 201003 Control Rod and Drive Mechanism I K1.O1 - Knowledge of the physical connections and/or cause-effect relationships between CONTROL ROD AND DRIVE hlECHANlSM SYSTEM and Control rod drive hydraulic system. NIA 20 1004 RSCS 201005 RClS N/A I 201006 RWM 202001 Recirculation K6.01 - Knowledge of the effect that a loss or malfunction of Jet Pumps will 202002 Recirculation Flow Control 3.1 - A4.03 - Ability to manually operate and/or monitor in the c'ontrol room:

Lights and alarms. 204000 RWCU 214000 RPlS 215001 Traversing In-core Probe K6.04 - Knowledge of the effect that a loss or malfunction of Primary containment isolation system will have on the TRAVERSING IN-CORE PROBE System K6.05 - Knowledge of the effect that a loss or malfunction an LPRM detector(s) will have on the ROD BLOCK MONITORING SYSTEM I 27 21 5002 RBM 21 6000 Nuclear Boiler Inst. 219000 RHR/LPCI:

ToruslPool Cooling Mode 223001 Primary CTMT and Aux. 2.8 - K5.03 - Knowledge of the operational implications of Down comer operation as it applies to PRIMARY CONTAINMENT SYSTEM AND .AUXILIARIES.

Page 9 of 21 RO Outline EM01 System #I Name 226001 RHRlLPCl CTMT Spray Mode 230000 RHRILPCI: ToruslPool Spray Mode 233000 Fuel Pool CoolinglCleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSlV Leakage Control 241 000 Reactormurbine Pressure Regulator 245000 Main Turbine Gen. I Aux. 256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation EWR Exi bZ(ROISR0)

WA Topic(s) G2.1.23 - Ability to perfonn specific system and integated plant procedures during all modes of plant operation, as it relates to RHWLPCI: CiONTAINMENT SPRAY. ~ G2.2.39 - Know ledge of less than or equal to one hour Technical Specification action statements for systems as they relate to FUEL HANDLING EQUIPMENT K1.02 - Knowledge of the physical connections and'or cause-effect relationships between MAIN AND REHEAT STEAM SYSTEM and SPDSIERISICRIDSIGDS A1.05 - Ability to predict andor monitor changes in parameters associated with operating the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEM controls including Reactor pressure.

A2.12 - Ability to (a) predict the impacts of Recombiner high temperature on the OFFGAS SYSTEM, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of lhose abnormal conditions or operations:

Page IO of 21 RO Outline 290003 Control Room Page 11 of21 SRO Outline ES-401 2 Form ES-401-1 1 ES-401 F/APT#l Name / Safety Function 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295005 Main Turbine Generator Trip

/ 3 I 295016 Control Room Abandonment

/ 7 1 295018 Partial or Total Loss of CCW I 295019 Partial or Total Loss of Inst. Air 295021 Loss of Shutdown Cooling I4 295025 High Reactor Pressure I3 295026 Suppression Pool High Water 295027 High Containment Temperature 295030 Low Suppression Pool Water Level I 5 BWI and Abnom ition Outline Form ES-401-1 WA Topic(s) A2.05 - Ability to determine andior interpret Reactor Power as it applies to MAIN TURBINE GENERATOR TRIP.

G2.2.22 - Knowledge of limiting conditions for operations and safety limits, as it relates to II G2.1.20 -Ability to interpret and execute procedure steps, as it relates to LOSS OF SHUTDOWN COOLING. A2.03 - Ability to determine andior interpret Suppression pool temperature as it applies to NIA Page 12 of 21 SRO Outline ES-401 EIAPE #I Name I Safety Function KE 1': 295037 SCRAM Condition Present and Reactor Power Above APRM 295038 High Off-site Release Rate

/ 9 BWR Examination Outline Form ES-401-1 VJA Topic(s) @ X CZ.4.6 - Knowledge of EOP mitigation strategies, as it relates to HIGH OFF-SITE RELEASE RATE. IIII Group Point Total J 2oi7 Page 13 of21 SRO Outline N/A ES-40 1 3 Form ES-401-1 Form ES-401-1 lates to LOW IlEACTOR WATER 295029 High Suppression Pool Water G2.1.20 - Ability to interpret and execute I 4.6 I 84 procedure steps, as it relates to INADVERTENT CONTAIMENT ISOLATION.

A2.03 - Ability to determine and/or interpret Cause of the high water level as it applies to SECONDARY CONTAINMENT HIGH Page I4 of 21 SRO Outline 500000 High CTMT Hydrogen Conc I Page 15 of21 SRO Outline ~~~~ - ~ ES-401 4 Form ES-401-1 I Plant IR Exam stems - 1 Outline Form ES401-1 ;roup 1 (RO I SRO) WA Topic(s) A2.08 - Ability to (a) predict the impacts of High suppression pool temperature on the HIGH PRESSURE COOLANT INJECTION SYSTEM; and (h) based on those predictions, use procedures to correct, conbol, or mitigate the consequences of those abnormal conditions or operations:

NIA i' I 207000 Isolation I (Emergency)

Condenser 209001 LPCS NIA x (32.4.11 - Knowledge of abnormal condition 42 87 procedures, as they relate to REACTOR PROTECTION SYSTEM. A2.07 - Ability to (a) predict the impacts of Recirculation flow channels flow mismatch on the APRM / LPRM SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations.

I 1 A2.02 - Ability to (a) predict the impacts 0fD.C. electrical distribution failures on the PCIS / NUCLEAR STEAM SUPPLY SHUTOFF SYSTEM; and (I)) based on those predictions, use procedures to COIT~C~, control, or mitigate the consequences of those abnormal conditions or operations.

3.2 89 Page 16 of21 SRO Outline Fom ES-401-1 ES-401 BWR Exarnlnatlon Outllne Tier ZIGroup 1 (RO / SRO) WA Topc(s) IR # 45 90 limitations in the facillty license, as it relates to Page 17 of21 SRO Outline ES-401 5 Form ES-401-) ES-401 BWR Examination Outline Form ES-401-1 and Drive Mechanism IIIIIIII Ill1 201 004 RSCS NIA 201005 RClS I NIA 239003 MSlV Leakaae 1 Control NIA Page I8 of2 1 SRO Outline Page 19of21 ROlSRO Generics ES-401 Generic Knowledge and Abilities Outline (Tier

3) Form ES-401-3 Facility:

Category 1. Conduct of Operations

2. Equipment Control 3. qadiation 2ontrol Limeri KIA # - 2.1.44 - 2.1.23 Date of Exam: Topic Knowledge of RO duties in the control room dunng fLel handling such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation Ability to perform specific system and integrated plant procedures during all modes of plant operation - SRO-On1 T -L SRO Only - 2.3.13 Knowledge of the design, procedural, and operational SRO Only I handling responsibilities, access to locked high-radiation Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel areas, aligning filters, etc.

Page 20 of 2 1 ROlSRO Generics 2.4.21 4. Emergency

Procedures

/ Plan 2.4.34 L Knowledge of the parameters and logic used to asses:; the status of safety functions, such as reactivity control, cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. Knowledge of RO responsibilities in emergency plan implementation.

Knowledge of RO tasks performed outside the main control room during an emergency and the resultant ooerational efftxts. core 1; 1 Page 21 of 21 ES-301 Administrative Topics Out I i ne Form ES-301-I Facility: Limerick Units 1 & 2 Examination Level:

RO x Ad m in is tra tive Topic (see Note) Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan Type Code* M, R D. S Date of Examination: 10/20/2008 Operating Test Number:

1 Describe activity to be performed - - 2.1.21 Prepare a Partial Procedure 2.1 .I9 Complete Jet Pump Surveillance 2.2.1 2 Perform Reactor Coolant Leakage Surveillance 2.3.1 I Gaseous Effluent Dose Rate Determination NOTE: All items (5 total) are required for SROs. f?O applicants require only 4 items unless they are retaking only the administrative topics, whlen all 5 are required.

• Type Codes

& Criteria: (C)ontrol room, (S)imulator, or Class( R)oom (D)irect from bank (I 3 for ROs; I 4 for SROs & RO retakes) (N)ew or (M)odified from bank (2 1) (P)revious 2 exam (I 1; randomly selected)

ES-301 Administrative Topics 0 ut I i ne Form ES-301-1 Facility: Limerick Units 1 & 2 Examination Level:

SRO X /I Date of Examination: 10/20/2008 Operating Test Number:

1 Describe activity to be performed - ~ ~ - ~ ~ ~ ~ ~~ ~ ~ ~

2.1.37 Authorize a Rx Maneuvering Shutdown Instruction (RMSI) Following a Rod Pattern Adjustment - 2.1.19 Complete Jet Pump Surveillance and Evaluate Operability 2.2.1 2 Review RHR Pump, Valve And Flow Test and Determine Required Actions

2.3.6 Review

and Approve a Liquid Rad Waste Discharge Permit 2.4.41 Make E- Plan Classification and Recommendation to issue KI Emergency ProceduredPlan NOTE: All items (5 total) are required for SROs. KO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

I 1

• Type Codes

& Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank. (I 3 for ROs; S 4 for SROs & RO retakes) (N)ew or (M)odified from bank (2 1) (P)revious 2 exams (I 1; randomly selected)

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 g. Component Cooling Water / Align RECW for Drywell Cooling

h. Control Room Ventilation

/ High Radiation Isolation Reset Facility: Limerick 1

& 2 Date of Examination: 10/20/2008 Exam Level:

RO SRO-I Cl SRO-u D Operating Test No.: I A, N, EN, S 8 D, EN, S 9 Control Room Systems@

(8 for RO); (7 for SRO-I);

(2 or 3 for SRO-U, including 1 ESF) I 1 i. Inventory Control I Alt Injection From Fire System j. Low Pressure Coolant Injection

/ Transfer RWST to CST k. D.C. Electrical Distribution

/ Supply Emer Power to RClC Isolation System / JPM Title w D, E, L, R 2 N, E, L, R 4 D, E, L, R 6 Safety Function Type Code*

• 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

/ Shutdown (N)ew or (M)odified from bank including 1(A) (R)CA (P)revious 2 exams (S)imulator

a. CRD Hydraulic System

/ Perform Reactor Startup

b. Low Pressure Core Spray I Manually Initiate Core Spray Criteria for RO I SRO-I / SRO-U 4-6 14-6 12-3 C~IC~IS~ 21 />I I21 21 I21 I21 52/52/21 C 3 I S 3 IS 2 (randomly selected) 2 1 I21 I21 - I - / rl (control room system) c. Main Steam / Open an MSlV d. High Pressure Coolant Injection

/ Manually Start HPCl e. RHR/LPCI:

CS System Mode

/ Initiate Containment Spray M, EN, S I( f. AC Elect Dist / Transfer Loads to the Unit Aux Transformer I D,S I 6 ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Type Code*

System / JPM Title Ir Safety Function Facility:

Limerick 1 & 2 Date of Examination:

10/20/2008 Exam Level: RO SRO-I w SRO-U E Operating Test No.: 1 I a. CRD Hydraulic System

/ Perform Reactor Startup 11 Control Room Systems@

(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) A, L, N, S 1 I l (A)lternate path (C)ontrol room , (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (RFA (S)imulator

b. Low Pressure Core Spray

/ Manually Initiate Core Spray I 2 11 c. Main Steam

/ Open an MSlV I N7S I 3 11 d. High Pressure Coolant Injection

/ Manually Start HPCl 4 11 e. RHWLPCI: CS System Mode

/ Initiate Containment Spray 5 g. Component Cooling Water

/ Align RECW for Drywell Cooling

h. Control Room Ventilation

/ High Radiation Isolation Reset I 11 In-Plant Systems@

(3 for RO); (3 for SRO-I); (3 or :Z for SRO-U) i. Inventory Control

/ AH Injection From Fire Systern j. Low Pressure Coolant Injection

/ Transfer RWST to CST 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 Criteria for RO I SRO-I I SRO-U ~~ 4-6 14-6 12-3 1911ai14 21 I21 I21 21 121 121 r21r21r1 I 3 I I 3 I I 2 (randomly selected) r1 121 12 1 - I - I rl (control room system)

ES-301 Control Roomlln-P System / JPM Title ant Systems Outline Form ES-301-2 Safety Function Type Code*

Facility:

Limerick 1 & 2 Exam Level: RO SRO-I c] SRO-U cfi1 a. CRD Hydraulic System I Perform Reactor Startup Date of Examination:

10/20/2008 Operating Test No.: 1 A,L N, s 1 11 Control Room Systems@

(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) b. Low Pressure Core Spray

/ Manually Initiate Core Spray A, L, M, p, 2 EN, S g. Component Cooling Water

/ Align RECW for Drywell Cooling A, N, EN, S 8 C. d. I. j. Low Pressure Coolant Injection

/ Transfer RWST to CST II f. N, E, L, R 4 11 Implant Systems@ (3 for RO); (3 for SRO-I); (3 or :? for SRO-U) ~ k. D.C. Electrical Distribution

/ Supply Emer Power to RCIC lsolatio 64 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 diflerent safety functions; in-plant systems and functions may overlap those tested in the control room. II

• Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odifted from bank including 1(A) (P)revious 2 exams (WCA (S)imulator 4-6 14-6 12-3 S~IS~IS~ 21 121 121 21 I21 /?I 2212212 1 s 3 I 5 3 I S 2 (randomly selected)

~11~1/21 - I - I 21 (control room system) I Form ES-D Appendix D Scenario Outline 5 Facility: Limerick 1

& 2 Scenario No.: 1 Op-Test No.: 1 Examiners: - Operators:

MCN078C MRR507A MPR020B MRDOl6F MRP029B MRP407C MSLl96B MSLl96C MRD024 Initial Conditions: 100°/~ power, EOL, Unit 2 in refueling, OPCON 5 Turnover: Standard turnover, number of components 00s for all scenarios, D12 Diesel Generator running unloaded at rated speed for run-in following cylinder liner replacement. Synchronize and load D12 Diesel Generator per RT-6-092-312-1, D12 Diesel Generator Run-In, beginning at Step 4.5.28. 1 Event Malf. No. No. 1 MHP450 M MEH104B OR Bkrs I Event Type* N-BOP R-RO MRC457B MRC458 RClC Turbine Trip RClC Flo\~ Controller Fails Low in Automatic with Subsequent C-BOP, TS-SRO C-RO, TS-SRO I-RO TSOSRO M Event Description Perform Loaded Run-In on D12 Diesel Generator 100 MWe Load Reduction For Minimum Generation Emergency HPCl Inadvertent Startup Condensate Pump C Trips, RRP A Fails to Runback APRM Channel 2 Fails to 96% 2 Control Rods Scram, ATWS, 1A SLC Pump Spurious Stop, B & C SLC Squib Valves Fail to Open, RDCS Failure - Inability to Drive Rods Main Turbine Trip, Transfer Failure of Unit Aux Buses 1 1 and 12 P (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRC Scenario #I - 2008 Limerick Operating Ted Page 1 of 21 Form ES-D Appendix D Scenario Outline

' Initial Conditions:

1 Unit 1 at 70% power. Unit 2 is at 100% power. Facility: Limerick 1

& 2 Scenario No.: 2 Op-Test No.: 1 I Turnover:

' ~ Standard turnover, number of components 00s for all scenarios.

Component xxx expected to be returned to service within the hour. Fuel handling is in progress in Unit 1 Spent Fuel Pool. Shift orders are to perform a rod pattern adjustment.

Examiners: - Operators: - - Event No. 1 2 3 4 5 6 __ Malf. No. Event Event Type* Description NIA R-RO Perform Rod Pattern Adjustment MRDol 6B TS-SRO C-Ro Control Rod XX-YY Drifts Out MRP0276 C-BOP MCU195B C-RO RPS Channel B Breaker Trip, RWCU Fails to Isolate TS-SRO RRP 1 B Lower Seal Failure, Followed By Upper Seal Failure, MRR433B C-RO MRR434B C-BOP RRP Suction Valve Fails As-Is OR F023B MRR441 M Steam Leak in Drywell MED261 MED263A M Loss of Offsite Power, D11 and D13 Lockouts MED263C ----I-- --r ~-~ MHP447A C-BOp I MHP449 I HPCl Aux Oil Pump Auto Start Failure and Turbine Trip Following Manual Start * (N)ormal, (R)eactivity, (I)nstrurnent, (C)omponent, (M)ajor NRC Scenario #2 - 2008 Limerick Operating Test Page 1 of 24

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

Limerick 1 & 2 Scenario No.: 3 Op-Test No.: 1 Examiners: - Operators: - - Initial Conditions:

Unit 1 at 50% power, EOL. Unit 2 is at ,loo% power Turnover: Standard turnover, number of components 00s for all scenarios.

Shift orders are to place the C RFP in service and then continue with rod withdrawal to raise power to 75%. Event Malf. No. No. 1 MRDOIGD 4 I MED282C MAD1 45E MV1231 D OR 112/E5 Event Event Type* I Description Start C Reactor Feed Pump N-BOP R-RO Raise Power to 75% C-Ro Stuck Control Rod XX-W TS-SRO Pump B Trip An SRV Fails Open, Manual Reactor Scram Requires ARI M I Instrument Line Break in Drywell M RHR Pump Suppression Pool Suction Line Rupture * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRC Scenario

1. 3 - 2008 Limerick Operating Test Page 1 of 29