ML083181193

Draft - Outlines (Folder 2)

ML083181193
Person / Time
Site:	Limerick
Issue date:	06/27/2008
From:	Caruso J 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).

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 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.

3. Systemdevolutions within each group are identifedon the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified: operationally important, site-specifc systems/evolutionsthat 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.

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 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.

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

7.' 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

8. 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 A 2 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.

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 selechms to WAS that are linked to 10 CFR 55.43.

Page 1 of 21

RO Outline ES-401 2 Form ES-401-1 ES-401 BWR E mination Outline Form ES-401-1 normal f volutions - Tier l/Group 1 (RO I SRO) c K/A Topic(s) IR K1.04 - Knowledge of the operational implications 2.5 of Limiting cycle oscillation as it applies to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION 295003 Partial or Complete Loss of AC A2.04 - Ability to determine and/or interpret 35 16 II system lineups as it applies to PARTIAL OR COMPLETE LOSS OF AC .

295004 Partial or Total Loss of DC Pwr A2.04 - Ability to determine and/or interpret 3.2 System lineups as it applies to PARTIAL OR 3 TOTAL LOSS OF DC PWR 295005 Main Turbine Generator Trip 1 3 K2.01 - Knowledge of the interrelations between 3.8 MAIN TURBINE GENERATOR TRIP and 4 Feedwater temperature.

295006 SCRAM / 1 Al.02 - Ability to operate and/or monitor Reactor 3.9 water level control system as it applies to 5 SCRAM -

295016 Control Room Abandonment 1 A3.01 - Knowledge of the reasons for Reactor 4.1 7 SCRAM as it applies to CONTROL ROOM 6 ABANDONMENT -

295018 Partial or Total Loss of CCW 1 K2.02 - Knowledge of the interrelations between 3.4 8 PARTIAL OR TOTAL LOSS OF CCW and Plant 7 operations.

295019 Partial or Total Loss of Inst. Air A2.02 - Ability to determine and/or interpret 3.6 18 Status of safety-related instrument air system loads as it applies to PARTIAL OR TOTAL 8 LOSS OF r w r . A I R -

295021 Loss of Shutdown Cooling 1 4 K1.03 - Knowledge of the operational 3.9 implications of Adequate core cooling as it 9 applies to LOSS OF SHUTDOWN COOLING.

K1.02 - Knowledge of the operational 3.2 implications of Shutdown margin as it applies to 10 REFUELING ACCIDENT.

G2.1.23 - Ability to perform specific system and 3.9 integrated plant procedures during all modes of plant operation, as it relates to HIGH DRYWELI, 11 PRESSURE.

K3.08 - Knowledge ofthe reasons for 3.5 Reactoriturbine pressure regulating system operation as it applies to HIGH REACTOR 12 PRESSURE.

p l Page 2 of 21

RO Outline 295027 High Containment Temperature WIA X K2.03 - Knowledge of the lnterrelations between 3.6 HIGH DRYWELL 'IEMPERATURE and 14 Reactor water level indication. - __

295030 Low Suppression Pool Water Level 1 5 I X A1.01 -Ability to operate and/or monitor ECCS systems (NPSH considerations) as it applies to LOW SUPPRESSION POOL WATER LEVEL 3.6

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15 I

I 295031 Reactor Low Water Level I 2 I

I X A1.13 -Ability to operate and/or monitor the Reactor Water Level Control as it applies to REACTOR LOW WATER LEVEL 4.3

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16

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I 295037 SCRAM Condition Present X K2.03 - Knowledge of the interrelations between 4.1 and Reactor Power Above APRM SCRAM CONDITION PRESENT Downscale or Unknown I 1 AND REACTOR POWER ABOVE APRM 17 DOWNSCALE OR LJNKNOWN and ARIIRPTIATWS. - -

295038 High Off-site Release Rate I 9 x A2.02 - Ability to determine andlor interpret Total 2.5 number of curies released as it applies to HIGH 18 OFF-SITE RELEASE RATE - -

600000 Plant Fire On Site I 8 x G2.4.20 -Knowledge of the operational 3.8 implications of EOP warnings, cautions, and 19 notes, as it relates to PLANT FIRE ON SITE -

X A1.05 - Ability to operate and/or monitor 3.9 Engineered safety features as it applies to GENERATOR VOLTAGE AND ELECTRIC 20 GRID DISTURBANCES - _ .

Y 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 I 5 295013 High Suppression Pool Temp. K2.01 - Knowledge of'the interrelations between 36 HIGH SUPPRESSION POOL TEMPERATURE 23 and Suppression Pool Cooling.

295014 Inadvertent Reactivity Addition I1 295015 Incomplete SCRAM I 1 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) 24 mitigation strategies, as it relates to NCOMPLETE SCRAM.

295017 High Off-site Release Rate I 9 I I I I I I I I 295020 Inadvertent Cont. Isolation I 5

&7 295022 Loss of CRD Pumps I 1 I lxl I I K2.03 - Knowledge of the interrelations between INADVERTENT CONTAINMENT ISOLATION lXl I I I 295032 High Secondary Containment K1.02 - Knowledge of the opemtional Area Temperature I5 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 I 9 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.

209001 LPCS X A3.04 - Ability to monitor automatic operations of the LOW PRESSURE CORE SPRAY SYSTEM

. , 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 21 2000 RPS X K3.05 Knowledge ofthe effect that a loss or malfunction of F.EACTOR PROTECTION SYSTEM will have on RPS logic channels.

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212000 RPS o predict and/or monitor changes ociated with operating the TECTION SYSTEM controls 215003 IRM of the effect that a loss or NTERMEDIATE RANGE will have on Reactor manual Page 6 of 21

RO Outline ES-401 EWR Examination Outline Form ES-401-1 PI, System #/Name A A G W A Topic(s) IR 21 5004 Source Range 38 Monitor

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21 5005 APRM / LPRM A4.06 - Abilirf to manually operate and/or 39 tor in the control room Verification of

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21 5005 APRM / LPRM 40

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217000 RClC 41 217000 RClC A2.14 - Ability to (a) predict the impacts of 42 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 21 8000 ADS K6.01 - Knowledge of the effect that a loss or 39 43 malfunction of RHWLPCI system pressure will have on the AUTOMAI IC DEPRESSURILATION System -

223002 PClSlNuclear A1.04 - Ability to prediLt and/or monitor changes 26 44 Steam Supply Shutoff in parameters arsociated with operating the PClS /

NUCLEAR STEAM SUPPLY SHUTTOFF SYSTEM controls including Individual system relay status -

239002 SRVs K2.01 - Knowledge of electncal power supplies to 28 45 SRV solenoids 259002 Reactor Water -

K5.03 Knowledge of the operational 31 46 Level Control implications of Water level measurement as it applies to REACTOR WATER LEVEL CONTROL SYSTEM -

261 000 SGTS X A3.01 - Ability to monitor automatic operations of 32 47 the STANDBY GAS TREATMENT SYSTEM 262001 AC Electrical K3.01 - Knowledge of the effect that a loss or 48 Distribution malfunction of the AC ELECTRICAL

_c Page 7 of 21

RO Outline ES-401 'R Examination Outline Form ES-401-1 Tier ZIGroup 1 (RO / SRO)

I I System # I Name A I GI WA Topic(s) 262002 UPS (AC/DC) K6.03 - Knowledge of the effect that a loss or malfunction of Static inverter will have on the UNITERRUPTABLE POWER SUPPLY System.

263000 DC Electrical K1.02 - Knowledge of the physical connections Distribution andor cause-ei'fect relationships between DC ELECTRICAL DISTRIBUTION SYSTEM and Battery charger and battery.

264000 EDGs Ill GZ.2.39 - Knowledge of less than or equal to one hour Technical Specification action statements for systems, as they relate to EDGs.

7 300000 Instrument Air 400000 Component Cooling Water X 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.

52 53 Grouo Point Total Page 8 of 21

RO Outline ES-401 5 ES-401 BWR ExaminationOutline F o m ES-401-1 i s - Tier Z/Group 2 (RO / SRO)

~ ~~

System # I Name A A A G WA TopiiXs)

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2 3 4 201001 CRD Hydraulic 201002 RMCS 201003 Control Rod and Drive Mechanism 20 1004 RSCS 201005 RClS 201006 RWM 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 N/A I

202001 Recirculation K6.01 - Knowledge of the effect that a loss or malfunction of Jet Pumps will 202002 Recirculation Flow A4.03 - Ability to manually operate and/or 3.1 Control monitor in the c'ontrol room: Lights and alarms. -

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

219000 RHR/LPCI:

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

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Page 9 of 21

RO Outline EM01 EWR Exi bZ(ROISR0)

System # I Name WA Topic(s) 226001 RHRlLPCl CTMT G2.1.23 - Ability to perfonn specific Spray Mode system and integated plant procedures during all modes of plant operation, as it relates to RHWLPCI: CiONTAINMENT SPRAY.

230000 RHRILPCI:

ToruslPool Spray Mode 233000 Fuel Pool CoolinglCleanup ~

234000 Fuel Handling G2.2.39 - Know ledge of less than or equal Equipment to one hour Technical Specification action statements for systems as they relate to FUEL HANDLING EQUIPMENT 239001 Main and Reheat K1.02 - Knowledge of the physical Steam connections andor cause-effect relationships between MAIN AND REHEAT STEAM SYSTEM and SPDSIERISICRIDSIGDS 239003 MSlV Leakage Control 241 000 Reactormurbine Pressure Regulator 245000 Main Turbine Gen. A1.05 - Ability to predict andor monitor I Aux. changes in parameters associated with operating the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEM controls including Reactor pressure.

256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas 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:

272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation Page I O of 21

RO Outline 290003 Control Room Page 1 1 of21

SRO Outline ES-401 2 Form ES-401-1 1 ES-401 BWI ition Outline Form ES-401-1 and Abnom F / A P T # l Name / Safety Function WA Topic(s) 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 I 295005 Main Turbine Generator Trip / 3 A2.05 - Ability to determine andior interpret Reactor Power as it applies to MAIN TURBINE GENERATOR TRIP.

295016 Control Room Abandonment / G2.2.22 - Knowledge of limiting conditions for 7 operations and safety limits, as i t relates to 1 295018 Partial or Total Loss of CCW I I I 295019 Partial or Total Loss of Inst. Air 295021 Loss of Shutdown Cooling I 4 G2.1.20 -Ability to interpret and execute procedure steps, as it relates to LOSS OF SHUTDOWN COOLING.

295025 High Reactor Pressure I 3 A2.03 - Ability to determine andior interpret Suppression pool temperature as i t applies to 295026 Suppression Pool High Water 295027 High Containment Temperature NIA 295030 Low Suppression Pool Water Level I 5 Page 12 of 21

SRO Outline ES-401 BWR Examination Outline Form ES-401-1

@

EIAPE #I Name I Safety Function K E VJA Topic(s) 1 ' :

295037 SCRAM Condition Present and Reactor Power Above APRM 295038 High Off-site Release Rate / 9 X CZ.4.6 - Knowledge of EOP mitigation strategies, as it relates to HIGH OFF-SITE RELEASE RATE.

I I I I Group Point Total J 2oi7 Page 13 of21

SRO Outline ES-401 3 Form ES-401-1 Form ES-401-1 lates to LOW IlEACTOR WATER N/A G2.1.20 - Ability to interpret and execute I 4.6 I 84 procedure steps, as it relates to INADVERTENT CONTAIMENT ISOLATION.

295029 High Suppression Pool Water 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

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ES-401 4 Form ES-401-1 I 207000 Isolation (Emergency) Condenser 209001 LPCS I

Plant I IR Exam stems - 1 Outline

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'

Form ES401-1 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. 3.2 89 electrical distribution failures on the PCIS /

NUCLEAR STEAM SUPPLY SHUTOFF SYSTEM; and (I)) based on those predictions, use procedures to C O I T ~control, C ~ , or mitigate the consequences of those abnormal conditions or operations.

Page 16 of21

SRO Outline ES-401 BWR Exarnlnatlon Outllne F o m ES-401-1 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 I I I I I I I I I l l 1 201 004 RSCS NIA 201005 RClS I NIA 239003 MSlV Leakaae 1 NIA Control 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

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Limeri KIA #

Date of Exam:

Topic SRO-On1 1.

Conduct of Operations 2.1.44

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2.1.23 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 T

-L procedures during all modes of plant operation -

SRO Only 2.

Equipment Control Knowledge of the design, procedural, and operational 3.

qadiation 2ontrol

- SRO Only I

2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Page 20 of 2 1

ROlSRO Generics 4.

Emergency Procedures /

Plan 2.4.21 L

2.4.34 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 OutIine Form ES-301-I Facility: Limerick Units 1 & 2 Date of Examination: 10/20/2008 Examination Level: RO x Operating Test Number: 1 Ad ministrative Topic Type Describe activity to be performed (see Note) Code*

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Conduct of Operations 2.1.21 Prepare a Partial Procedure Conduct of Operations M, R 2.1 . I 9 Complete Jet Pump Surveillance 2.2.12 Perform Reactor Coolant Leakage Equipment Control Surveillance Radiation Control D. S 2.3.1 I Gaseous Effluent Dose Rate Determination Emergency Procedures/Plan 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 e x a m (I 1; randomly selected)

ES-301 Administrative Topics 0utIine Form ES-301-1

/I Facility: Limerick Units 1 & 2 Examination Level: SRO X 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

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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 Emergency ProceduredPlan Recommendation to issue KI 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 Facility: Limerick 1 & 2 Date of Examination: 10/20/2008 Exam Level: RO SRO-I Cl SRO-u D Operating Test No.: I Control Room Systems@(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) w I 1 Safety System / JPM Title Type Code*

Function

a. CRD Hydraulic System / Perform Reactor Startup

b. Low Pressure Core Spray I Manually Initiate Core Spray

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

g. Component Cooling Water / Align RECW for Drywell Cooling A, N, EN, S 8

h. Control Room Ventilation / High Radiation Isolation Reset D, EN, S 9

i. Inventory Control I Alt Injection From Fire System D, E, L, R 2

j. Low Pressure Coolant Injection / Transfer RWST to CST N, E, L, R 4

k. D.C. Electrical Distribution / Supply Emer Power to RClC Isolation D, E, L, R 6

• Type Codes Criteria for RO I SRO-I / SRO-U (A)lternatepath 4-6 14-6 12-3 (C)ontrol room (D)irect from bank C ~ I C ~ I S ~

(E)mergency or abnormal in-plant 2 1 / > I I21 (EN)gineered safety feature - I - / r l (control room system)

(L)ow-Power / Shutdown 2 1 I21 I 2 1 (N)ew or (M)odified from bank including 1(A) 52/52/21 (P)revious 2 exams C 3 I S 3 I S 2 (randomly selected)

(R)CA 2 1I 2 1 I21 (S)imulator

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Ir I1 Facility: Limerick 1 & 2 Date of Examination: 10/20/2008 Exam Level: RO SRO-I w SRO-U E Operating Test No.: 1 Control Room Systems@( 8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code* Function

a. CRD Hydraulic System / Perform Reactor Startup A, L, N, S 1 I b. Low Pressure Core Spray / Manually Initiate Core Spray 2 1 c. Main Steam / Open an MSlV I N 7 S I 3 1 d. High Pressure Coolant Injection / Manually Start HPCl 4 1 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 1 In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or :Zfor SRO-U)

I

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 I Criteria for RO I SRO-I I SRO-U

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l (A)lternate path 4-6 14-6 12-3 (C)ontrol room

, (D)irect from bank 1911ai14 (E)mergency or abnormal in-plant 2 1 I 2 1 I21 (EN)gineered safety feature - I - I rl (control room system)

(L)ow-Power I Shutdown 21 1 2 1 1 2 1 (N)ew or (M)odified from bank including 1(A) r21r21r1 (P)revious 2 exams I3 I I 3 I I2 (randomly selected)

(RFA r 11 2 1 1 2 1 (S)imulator

ES-301 Control Roomlln-P ant Systems Outline Form ES-301-2 Facility: Limerick 1 & 2 Date of Examination: 10/20/2008 Exam Level: RO SRO-I c] SRO-U cfi1 Operating Test No.: 1 1 Control Room Systems@(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. CRD Hydraulic System I Perform Reactor Startup A , L N, s 1

b. Low Pressure Core Spray / Manually Initiate Core Spray A, L, M, p, 2 EN, S C.

d.

I f.

g. Component Cooling Water / Align RECW for Drywell Cooling A, N, EN, S 8 1 Implant Systems@(3 for RO); (3 for SRO-I); (3 or ?: for SRO-U)

I.

j. Low Pressure Coolant Injection / Transfer RWST to CST N, E, L, R 4

~

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.

I

• Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank S ~ I S ~ I S ~

(E)mergency or abnormal in-plant 2 1 1 2 1 121 (EN)gineered safety feature - I - I 21 (control room system)

(L)ow-Power I Shutdown 2 1 I 2 1/ ? I (N)ew or (M)odifted from bank including 1(A) 2212212 1 (P)revious 2 exams s 3 I 5 3 I S 2 (randomly selected)

(WCA ~ 1 1 ~ 1 / 2 1 (S)imulator I

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

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.

Event No. 1 Malf. No. Event Type*

Event Description N-BOP Perform Loaded Run-In on D12 Diesel Generator R-RO 100 MWe Load Reduction For Minimum Generation Emergency MHP450 C-BOP, HPCl Inadvertent Startup TS-SRO MCN078C C-RO, Condensate Pump C Trips, RRP A Fails to Runback MRR507A TS-SRO 5 MPR020B I-RO APRM Channel 2 Fails to 96%

TSOSRO MRDOl6F MRP029B 2 Control Rods Scram, ATWS, 1A SLC Pump Spurious Stop, B &

MRP407C MSLl96B M C SLC Squib Valves Fail to Open, RDCS Failure - Inability to Drive Rods MSLl96C MRD024 1 MEH104B OR Bkrs M Main Turbine Trip, Transfer Failure of Unit Aux Buses 11 and 12 IP MRC457B MRC458 (N)ormal, RClC F l o \ Controller

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RClC Turbine Trip Fails Low in Automatic with Subsequent (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRC Scenario # I - 2008 Limerick Operating T e d Page 1 of 21

Appendix D Scenario Outline Form ES-D-1

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

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' Initial Conditions:

1 Unit 1 at 70% power. Unit 2 is at 100% power.

'

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.

Event Malf. No. Event Event No. Type* Description 1 NIA R-RO Perform Rod Pattern Adjustment 2 MRDol 6B C-Ro TS-SRO Control Rod XX-YY Drifts Out MCU195B C-RO 3 MRP0276 C-BOP RPS Channel B Breaker Trip, RWCU Fails to Isolate TS-SRO MRR433B C-RO RRP 1B Lower Seal Failure, Followed By Upper Seal Failure, 4

MRR434B C-BOP RRP Suction Valve Fails As-Is OR F023B 5 MRR441 M Steam Leak in Drywell MED261 6 MED263A M Loss of Offsite Power, D11 and D13 Lockouts

__ MED263C

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• I MHP447A MHP449 I C-BOp 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

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Appendix D Scenario Outline Form ES-D-1 _-

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

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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 No. 1 Malf. No. Event Type* I Event Description N-BOP Start C Reactor Feed Pump R-RO Raise Power to 75%

MRDOIGD C-Ro Stuck Control Rod X X - W TS-SRO 4 I MED282C Pump B Trip MAD145E An SRV Fails Open, Manual Reactor Scram Requires ARI MV1231D OR 112/E5 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 #3 - 2008 Limerick Operating Test Page 1 of 29