Text

Final - Outlines (Change Summaries - Optional)
	ML023100265
Person / Time
Site:	Limerick
Issue date:	10/04/2002
From:	Wasong A; Exelon Nuclear
To:	Conte R; NRC/RGN-I/DRS/OSB
	Conte R
References
	50-352/02-302, 50-353/02-302
	Download: ML023100265 (44)
	v • d • e

Rev 2 ES-401 BWR RO Examination Outline Form ES-401-2 Facility: Limerick Generating Station Date of Exam: 10/07/02 Exam Level: RO Tier Group K/A Category Points Point Total

1. 2 3 3 3 1 1 13 Emergency &

Abnormal Plant 2 2 3 2 5 6 1 19 Evolutions 3 1 2 0 1 0 0 4 Tier 5 8 5

9 7 2 36 Totals

2. 1 1 3 3 3 2 2 3 4 4 2 1 28 Plant Systems 2 2 0 4 3 2 3 1 1 0 2 1 19 3 0 0 0 0 0 1 0 1 0 2 0 4 Tier 3 3 7 6 4 6 4 6 4 6 2 51 Totals

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 3 3 3 4 13 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., the "Tier Totals" in each K/A category shall not be less than two).

2. Actual point totals must match those specified in the table.

3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

4. Systems/evolutions within each group are identified on the associated outline.

5. The shaded areas are not applicable to the category/tier.

6.* The generic K/As in Tiers I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the RO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

NUREG 1021, Revision 8

( ( Rev 2 ES-401 BWR RO Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier l/Group I EIAPE # / Name / Safety Function KI K2 K3 Al A2 G K/A Topic(s) Imp. Pts 295005 Main Turbine Generator Trip / III 74R AA1.05 Reactor/turbine pressure regulating system 3.6 1 295006 SCRAM / I 10 AK3.03 Reactor pressure response 3.8 1 295007 High Reactor Pressure / Ill 42 AK3.03 RCIC operation: Pit. Sp. 3.4 1 295009 Low Reactor Water Level / II 43 AK2.02 Reactor water level control 3.9 1 295010 High Drywell Pressure / V 92 AK3.01 Drywell venting 3.8 1 295014 Inadvertent Reactivity Addition / I 44 AK1.05 Fuel thermal limits 3.7 1 45 AA1.02 Recirculation flow control system 3.6 1 295015 Incomplete SCRAM / I 46 AK2.01 CRD Hydraulics 3.8 1 295024 High Drywell Pressure / V 47 2.1.23 Ability to perform specific system and integrated plant procedures 3.9 1 1__ __o during different modes of plant operation 295025 High Reactor Pressure / III 93 EK2.04 ARI/RPT/ATWS: PIt. Sp. 3.9 1 295031 Reactor Low Water Level / II 48 EA1.06 Automatic depressurization system 4.4 1 295037 SCRAM Condition Present and Power 49 EA2.02 Reactor water level 4.1 1 Above APRM Downscale or Unknown / I 500000 High Containment Hydrogen Conc. / V 50 EK1.01 Containment integrity 3.3 1 KIA Category Totals: 12 3 3 13 i1 i11 Group PointTotal: J13 NUREG 1021, Revision 8 Numbers Denote Exam Question Number.

"R" - RO Only; All others - Common with SRO Exam

( ( Rev 2 ES-401 Emergency andBWR RO Examination Abnormal Outline- Tier llGroup 2 Plant Evolutions Form ES-401-2 EIAPE # / Name I Safety Function KI K2 K3 Al A2 G K/A Topic(s) Imp. Pts 295001 Partial or Complete Loss of Forced Core 76 AK1.02 Power/flowwndistribution 3.3 1 Flow Circulation / I & IV L o7w 295002 Loss of Main Condenser Vacuum / Ill 77 AK1.04 Increased offgas flow 3.0 1 295003 Partial or Complete Loss of AC Pwr / VI 94 AA2.02 Reactor power, pressure, and level 4.2 1 295004 Partial or Complete Loss of DC Pwr / VI 95 AA1.02 Systems necessary to assure safe plant shutdown 3.8 1 295008 High Reactor Water Level / II 78 AK2.08 Main turbine: Pit. Sp. 3.4 1 295012 High Drywell Temperature / V 96 AK2.01 Drywell ventilation 3.4 1 295013 High Suppression Pool Temp. / V 97 AK2.01 Suppression pool cooling 3.6 1 295016 Control Room Abandonment / VII 295017 High Off-site Release Rate / IX 79 AA1.04 Stack gas monitoring system: Pit. Sp. 3.6 1 295018 Partial or Complete Loss of CCW / VIII 75R AA2.01 Component temperatures 3.3 1 295019 Partial or Complete Loss of Inst. Air / VIII 80 AA1.01 Backup air supply 3.5 1 295020 Inadvertent Cont. Isolation / V &VII 98 AA1.02 Drywell ventilation/cooling system 3.2 1 295022 Loss of CRD Pumps / I 81 AK3.01 Reactor SCRAM 3.7 1 295026 High Suppression Pool Water Temp. / V 82 EK3.04 SBLC injection 3.7 1 mmmmminmm- m 295028 High Drywell Temperature / V 99 2.1.32 Ability to explain and apply system limits and precautions 3.4 1 295029 High Suppression Pool Water Level / V 83 EA2.03 Drywell/containment water level 3.4 1 295030 Low Suppression Pool Water Level / V 84 EA2.04 Drywell/suppression chamber differential pressure: Marl II&11l 3.5 1 295033 High Secondary Containment Area 85 EA2.01 Area radiation levels 3.8 1 Radiation Levels / IX 295034 Secondary Containment Ventilation High Radiation / IX 295038 High Off-site Release Rate / IX 86 EA1.06 Plant ventilation 3.5 1 600000 Plant Fire On Site / VIII 87 AA2.04 The fire's extent of potential operational damage to plant 2.8 1 equipment K/A Category Point Totals: 12 13 12 15 J6 I1 [ Group Point Total: 1 NUREG 1021, Revision 8 Numbers Denote Exam Question Number.

"R" - RO Only; All others - Common with SRO Exam

( Rev 2 ES-401 BWR RO Examination Outline Form ES-401-2 I Emergency and Abnormal Plant Evolutions - Tier llGroup 3 E/APE # Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Pts 295021 Loss of Shutdown Cooling / IV 100 AK1.04 Natural circulation 3.6 1 295023 Refueling Accidents / VIII 295032 High Secondary Containment Area 88 EK2.07 Leak detection system concept: Pit. Sp. 3.6 1 Temperature / V 295035 Secondary Containment High Differential 89 EK2.04 Blow-out panels: Pit. Sp. 3.3 1 Pressure / V I I II_1_

295036 Secondary Containment High Sump/Area 90 EA1.01 Secondary containment and floor drain systems 3.2 1 Water Level / V I I I____

[K/A Category Point Totals: 1_12 10 1 1 0 10 1 Group Point Total: - 4 NUREG 1021, Revision 8 Numbers Denote Exam Question Number.

"R" - RO Only; All others - Common with SRO Exam

( Rev 2 ES-401 BWR RO Examination Outline Form ES-401-2 Plant Systems - Tier 21Group I System # I Name KI K2 K3 1K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Pts 201001 CRD Hydraulic 1 A4.04 Drive water pressure control valve 3.1 1 201002 RMCS 11 A2.04 Control rod block

umimmmmmmnmu 3.2 1 202002 Recirculation Flow Control 12 A2.01 Recirculation pump trip 3.4 1 51R A3.03 Scoop tube operation: BWR 2,3,4 3.1 1 203000 RHR/LPCI: Injection Mode 13 A2.04 A.C. failures 3.5 1 52R A3.08 System initiation sequence 4.1 1 206000 HPCI 14 K5.08 Vacuum breaker operation:BWR- 3.0 1 mm m mmmmmmm 2,3,24- m 209001 LPCS 15 K2.03 Initiation Iogic 2.9 1 211000 SLC 2 A1.10 Lights and alarms 3.7 1 212000 RPS (K4.05Functional testing of the system 3.4 1 while maintaining power operation 215003 IRM 53R K3.02 Reactor manual control 3.6 1 215004 SRM 16 A2.04 Upscale and downscale trips 3.5 1 17 2.1.30 Ability to locate and operate 3.9 1

-omponents, including local controls 215005 APRM / LPRM 18 K2.02 APRM channels 2.6 1 216000 Nuclear Boiler Instrumentation 19 K3.29 Jet pump flow monitoring: Pit. Sp. 3.1 1 217000 RCIC 20 A3.02 Turbine startup 3.6 1 54R K4.04 Prevents turbine damage: Pit Sp. 3.0 1 218000 ADS 21 K6.07 Primary containment instrumentation 3.4 1 223001 Primary CTMT and Auxiliaries 22 K2.09 Drywell cooling fans: Pit. Sp. 2.7 1 223002 PCIS/Nuclear Steam Supply Shutoff 23 K4.08 Manual defeating of selected 3.3 1 isolations during specified emergency conditions 55R A1.03 SPDS/ERIS/CRIDSIGDS: Pit. Sp. 2.5 1 239002 SRV's 4 A4.01 SRVs 4.4 1 241000 Reactor/Turbine Pressure Regulator 24 K6.17 Main turbine PMG: Pit. Sp. 2.7 1 259001 Reactor Feedwater 25 A3.03 System flow 3.3 1 259002 Reactor Water Level Control 5 K1.05 Reactor Feedwater system 3.6 1 56R K5.01GEMAC/Foxboro/Bailey controller 3.1 1 operation: PIt. Sp.

261000 SGTS 26 K3.05 Secondary containment 3.2 1 radiation/contamination levels 264000 EDG's 27 A1.09 Maintaining minimum load on 3.0 1 emergency power'r generator (to prevent reverse KIA Category Point Totals: 1 3 3 2 2 4 4 2 1 Group PointTotal:

28 NUREG 1021, Revision 8 Numbers Denote Exam Question Number.

"R" - RO Only; All others - Common with SRO Exam

/

Rev 2 ES-401 BWR RO Examination Outline Form ES-401-2 Plant Systems - Tier 21Group 2 System # I Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Pts 201003 Control Rod and Drive Mechanism 6 A4.02 CRD mechanism position: Pit. Sp. 3.5 1 201006 RWM 28 K5.10 Withdraw error: Pit. Sp (Not BWR6) 3.2 1 202001 Recirculation 57R K4.06 Automatic voltage/frequency 2.6 1 regulation : Pit Sp.

204000 RWCU 58R KI.15 Leak Detection: Pit. Sp. 3.1 1 205000 Shutdown Cooling 29 K5.02 Valve operation 2.8 1 214000 RPIS 30 K1.05 Full core display: Pit. Sp. 3.3 1 215002 RBM 31 2.4.31 Knowledge of annunciators, 3.3 1 alarms, and indications, and the use of the response instructions 219000 RHR/LPCI: Torus/Pool Cooling 32 K3.01 Suppression pool temperature 3.9 1 Mode control 226001 RHR/LPCI: CTMT Spray Mode 33 K6.05 Suppression pool (temperature, 3.4 1 level, and pressure) 230000 RHR/LPCI: Torus/Pool Spray 34 A2.04 Valve openings 2.8 1 Mode 239001 Main and Reheat Steam 35 A1.06 Air ejector process radiation 3.4 1 monitor 245000 Main Turbine Gen. and Auxiliaries 59R K3,07 Reactor protection system 3.6 1 256000 Reactor Condensate 7 K4.08 Dedicated ECCS water supply: Pit. 3.6 1 Sp.

262001 AC Electrical Distribution 262002 UPS (AC/DC) 60R K3.11 MSIVs: Pit. Sp. 2.8 1 263000 DC Electrical Distribution 8 K3.02 Components using D.C. control 3.5 1 power (i.e. breakers) 271000 Offgas 61R K6.09 Fuel cladding integrity 3.4 1 272000 Radiation Monitoring 36 K4.02 Automatic actions to contain the 3.7 1 radioactive release in the event that the predetermined release rates are exceeded 286000 Fire Protection 290001 Secondary CTMT 9 K6.08 Plant air systems 2.7 1 290003 Control Room HVAC 62R A4.01 Initiate/Reset system 3.2 1 300000 Instrument Air 400000 Component Cooling Water K/A Category Point Totals: 2 1O 14 13 1213 1 1 12 II Group Point Total: -19 NUREG 1021, Revision 8 Numbers Denote Exam Question Number.

"R" - RO Only; All others - Common with SRO Exam

I (

Rev 2 ES-401 BWR RO Examination Outline Form ES-401-2 I _ __ Plant Systems - Tier 21Group 3 _

System # / Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Pts 215001 Traversing In-core Probe 233000 Fuel Pool Cooling and Cleanup 63R K6.10 Reactor cavity seal failure 2.9 1 234000 Fuel Handling Equipment 37 A4.01 Neutron monitoring system 3.7 1 268000 Radwaste 288000 Plant Ventilation 38 A4.01 Start and stop fans 3.1 1 290002 Reactor Vessel Internals 64R A2.04 Excessive heatup/cooldown rate 3.7 1 K/A Category Point Totals: O 0 0l 0 10 I1 0 1 0 2 0I Group Point Total: I 4 NUREG 1021, Revision 8 Numbers Denote Exam Question Number.

"R" - RO Only; All others - Common with SRO Exam

Rev 2 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 Facility: Limerick Generating Station Date of Exam: 10/07/02 Exam Level: RO Category K/A # Topic Imp. Points Conduct of 2.1.3 Knowledge of shift turnover practices 39 3.0 1 Operations 2.1.25 Ability to obtain and interpret station reference material such as 2.8 1 graphs, monographs, and tables which contain performance data 65R 2.1.32 Ability to explain and apply system limits and precautions - 66R 3.4 1 Total 3 Equipment 2.2.2 Ability to manipulate the console controls as required to operate 4.0 1 Control the facility between shutdown and designated power levels --40 2.2.3 (Multi Unit) Knowledge of the design, procedural, and operational 3.1 1 differences between units - 67R 2.2.24 Ability to analyze the affect of maintenance activities on LCO 2.6 1 status - 68R Total 3 Radiation Control 2.3.1 Knowledge of IOCFR20 and related facility radiation control 2.6 1 requirements - 91 2.3.4 Knowledge of radiation exposure limits and contamination control, 2.5 1 including permissible levels inexcess of those authorized - 69R 2.3.11 Ability to control radiation releases - 70R 2.7 1 Total 3 Emergency Procedures and 2.4.6 Knowledge of symptom based EOP mitigation strategies 41 3.1 1 Plan 2.4.17 Knowledge of EOP terms and definitions- 71 R 3.1 1 2.4.48 Ability to interpret control room indications to verify the status and 3.5 1 operation of systems and understand how operator actions and directives affect plant snd system conditions- 72R 2.4.49 Ability to perform without reference to procedures those actions 4.0 1 that require immediate operation of system components and controls - 73R Total 4 Tier 3 Point Total (RO) 13 NUREG 1021, Revision 8 Numbers Denote Exam Question Number.

"R" - RO Only; All others - Common with SRO Exam

(

ES-401 Record of Rejected K/As Form ES-401-10 Tier/Group Randomly Selected K/A Reason for Rejection 1/ 1 295014AK1.03 GFE topic 1/ 1 295009AK3.02 Not applicable at LGS 1/ 1 295016AA1.02 Not applicable at LGS (MSIVs are closed as part of control room abandonment) 1/ 1 295006AK3.02 Does not support a question of acceptable discriminating value 1 /2 295012AK1.02 Does not support question of acceptable discriminating value 2/1 2110002.4.49 SLC system has no immediate action steps driven from memory 2/1 211 00OA1.03 Does not support question of acceptable discriminating value 2/1 215004K5.01 GFE topic 2 /1 261000A2.04 No procedure driven actions support a question of acceptable discriminating value 2/2 226001A3.01 Does not support a question of acceptable discriminating value 2 /2 300000K5.13 Does not support a question of acceptable discriminating value Generic 2.1.16 Does not support question of acceptable discriminating value Generic 2.2.31 N/A at LGS. Covered under 2.2.28 1/1 (SRO) 295024EA2.03 Pool level already being tested in several questions. Re-selected EA2.04 pool pressure to provide wider testing of containment topics 2/2 (SRO) 286000 2.4.30 Fire instrumentation no longer Tech Spec system, so only remaining report is for generic fire impairment, which is not made by operations and does not support an acceptable question. Re-selected 2.4.25 - Knowledge of fire protection procedures 1 / 2 (SRO) 295032 EK3.01 Does not support question of acceptable discriminating value. NRC authorized 1/3 (RO) replacing with randomly selected K/A EK2.07 during review. (Question 88)

____ I _______ ]

I .1 NUREG-1021, Revision 8, Supplement 1 Revision 2

Rev 2 ES-401 BWR SRO Examination Outline Form ES-401-1 Facility: Limerick Generating Station Date of Exam: 10/07/02 Exam Level: SRO Tier Group KIA Category Points Point Total

1. 1 2 4 44 75 2 Emergency &

Abnormal Plant 217 Evolutions Tier Totals 8 5 8 10 43

2. 1 1 3 2 2 1 4 2 3 1 1 3 23 Plant Systems 2 1 0 2 1 2 0 0 2 1 2 2 13 3 0 0 0 1 0 0 1 0 0 2 0 4 Tier Totals 2 3 4 4 3 4 3 5 2 5 5 40

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 4 4 4 5 17 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., the "Tier Totals" in each K/A category shall not be less than two).

2. Actual point totals must match those specified in the table.

3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

4. Systems/evolutions within each group are identified on the associated outline.

5. The shaded areas are not applicable to the category/tier.

6.* The generic K/As in Tiers I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the RO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

NUREG-1021, Revision 8

Rev 2 ES-401 BWR SRO Examini.,on Outline Form ES-401-,

Emergency and Abnormal Plant Evolutions - Tier llGroup I E/APE # I Name I Safety Function KI K2 K3 Al A2 G K/A Topic(s) Imp. Pts 295003 Partial or Complete Loss of AC Pwr I VI 94 AA2.02 Reactor power, pressure, and level 4.3 1 295006 SCRAM /I 10 AK3.03 Reactor pressure response 3.9 1 295007 High Reactor Pressure / 111 42 AK3.03 RCIC operation: Pit. Sp. 3.5 1 295009 Low Reactor Water Level / Il 43 AK2.02 Reactor water level control 3.9 1 67S AA2.01 Reactor water level 4.2 1 295010 High Drywell Pressure /V 92 AK3.01 Drywell venting 4.0 1 295013 High Suppression Pool Temp. /V 97 AK2.01 Suppression pool cooling 3.7 1 68S AA2.01 Suppression pool temperature 4.0 1 295014 Inadvertent Reactivity Addition /I 44 AK1.05 Fuel thermal limits 4.2 1 45 AA1.02 Recirculation flow control system 3.8 1 295015 Incomplete SCRAM / I 46 AK2.01 CRD Hydraulics 3.9 1 69S 2.4.6 Knowledge symptom based EOP mitigation strategies 4.0 1 295016 Control Room Abandonment / VII 70S 2.4.49 Ability to perform without reference to procedures those actions 4.0 1 that require immediate operation of system components and controls 295017 High Off-site Release Rate / IX 79 AA1.04 Stack gas monitoring system: Pit. Sp. 3.8 1 295023 Refueling Accidents Cooling Mode / VIII 71$ 2.2.22 Knowledge of limiting conditions for operation and safety limits 4.1 1 295024 High Drywell Pressure / V 47 2.1.23 Ability to perform specific system and integrated plant 4.0 1 72S procedures during different modes of plant operation 3.9 1 EA2.04 Suppression chamber pressure: Pit. Sp.

295025 High Reactor Pressure / III 93 EK2.04 ARI/RPT/ATWS: Pit. Sp. 4.1 1 295026 Suppression Pool High Water Temp. / V 82 EK3.04 SBLC injection 4.1 1 73S EA2.02 Suppression pool level 3.9 1 295030 Low Suppression Pool Water Level / V 84 EA2.04 Drywell/suppression chamber differential pressure: Marl II&1I1 3.7 1 295031 Reactor Low Water Level / II 48 EA1.06 Automatic depressurization system 4.4 1 295037 SCRAM Condition Present and Power 49 EA2.02 Reactor water level 4.2 1 Above APRM Downscale or Unknown / I 74S 2.4.49 Ability to perform without reference to procedures those actions 4.0 1 that require immediate operation of system components and controls 295038 High Off-site Release Rate / IX 86 EA1.06 Plant ventilation 3.6 1 500000 High Containment Hydrogen Conc. / V 50 EK1.01 Containment integrity 3.9 1 K/A Category Totals: 12 4 I4 1 4 7 I Group Point Total: 26 NUREG 1021, Revision 8 "S" - SRO Only; All other ortt Number.

Rev 2

( ! i ES-401 BWR SRO Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier llGroup 2 EIAPE # / Name I Safety Function KI K2 K3 Al A2 G KIA Topic(s) Imp. Pts 295001 Partial or Complete Loss of Forced Core 76 AK1.02 Power/flow distribution 3.5 1 Flow Circulation / I & IV 295002 Loss of Main Condenser Vacuum / III 77 AK1.04 Increased offgas flow 3.3 1 295004 Partial or Total Loss of DC Pwr / VI 95 AA1.02 Systems necessary to assure safe plant shutdown 4.1 1 295005 Main Turbine Generator Trip / III 295008 High Reactor Water Level/ Il 78 AK2.08 Main turbine: Pit. Sp. 3.5 1 295012 High Drywell Temperature / V 96 AK2.01 Drywell ventilation 3.5 1 295018 Partial or Total Loss of CCW / VIII 295019 Partial or Total Loss of Inst. Air / VIII 80 AA1.01 Backup air supply 3.3 1 295020 Inadvertent Cont. Isolation / V &VII 98 AA1.02 Drywell ventilation/cooling system 3.2 1 295021 Loss of Shutdown Cooling / IV 100 AK1.04 Natural circulation 3.7 1 295022 Loss of CRD Pumps /I 81 AK3.01 Reactor SCRAM 3.9 1 295028 High Drywell Temperature / V 99 2.1.32 Ability to explain and apply system limits and precautions 3.8 1 295029 High Suppression Pool Water Level / V 83 EA2.03 Drywell/containment water level 3.5 1 295032 High Secondary Containment Area 88 EK2.07 Leak detection system concept: Pit. Sp. 3.8 1 Temperature / V 295033 High Secondary Containment Area 85 EA2.01 Area radiation levels 3.9 1 Radiation Levels / IX I 295034 Secondary Containment Ventilation High 75S 2.2.22 Knowledge of limiting conditions for operations and safety limits 4.1 1 Radiation / IX 295035 Secondary Containment High Differential 89 EK2.04 Blow-out panels: Pit. Sp. 3.7 1 Pressure / V 295036 Secondary Containment High Sump/Area 90 EA1.01 Secondary containment and floor drain systems 3.3 1 Water Level / V II 600000 Plant Fire On Site / VIII 87 AA2.04 The fire's extent of potential operational damage to plant 3.1 1 I equipment KIA Category Point Totals: 3 1 4 1 1 4 1 3 1 2 1 Group Point Total: ]17 NUREG 1021, Revision 8 "S" - SRO Only; All othebepnn trROQg °n Number.

Rev 2 ES-401 BWR SRO Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group I K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Pts System # I Name K1 12 A2.01 Recirculation pump trip 3.4 1 202002 Recirculation Flow Control 13 A2.-04 A.C. failures 3.6 1 203000 RHRJLPCI: Injection Mode 206000 HPCI Smmmmm*mm 14 mmuin" K5.08 Vacuum breaker operation:BWR-2,3,4 3.2 1 209001 LPCS 152.03 Initiation logic 3.1 1 211000 SLC 2 - -A1.10 Lights and alarms 3.7 1 3 K4.05 Functional testing of the system while 3.6 1 212000 RPS maintaining power operation 16 A2.04 Upscale and downscale trips 3.7 1 215004 Source Range Monitor 17 2.1.30 Ability to locate and operate 3.4 1 I -components, including local controls K2.02 APRM channels 2.8 1 215005 APRM I LPRM 18 19 K3.29 Jet pump flow monitoring: Pit. Sp. 3.2 1 216000 Nuclear Boiler Instrumentation 20 A3.02 Turbine startup 3.5 1 217000 RCIC 21 K6.07 Primary containment instrumentation 3.5 1 218000 ADS K2.09 Drywell cooling fans: Pit. Sp. 2.9 1 223001 Primary CTMT and Auxiliaries 22 23 K4.08 Manual defeating of selected 3.7 1 223002 PCIS/Nuclear Steam Supply Shutoff isolations during specified emergency conditions 51S 2.4.6 Knowledge of symptom based EOP 4.0 1 mitigation strategies 33 K6.05 Suppression pool (temperature, level, 3.6 1 226001 RHR/LPCI: CTMT Spray Mode and pressure) 4 A4.01 SRVs 4.4 1 239002 SRVs 24 K6.17 Main turbine PMG: Pit. Sp. 2.8 1 241000 Reactor/Turbine Pressure Regulator K1.05 Reactor Feedwater system 3.7 1 259002 Reactor Water Level Control 5 26 K3.05 Secondary containment 3.5 1 261000 SGTS radiation/;contamination levels 52S 2.2.22 Knowledge of limiiting conditions for 4.1 1 262001 AC Electrical Distribution operation and safety limits 27 A1.09 Maintaining minimum load on 3.1 1 264000 EDG's emergency generator (to prevent reverse power) 9 K6.08 Plant air systems 2.8 1 290001 Secondary CTMT K/A Category PointTotals: 11 3 212 11 41 2 I __L II 1 I 3 [ Group Point Total: 231 NUREG 1021, Revision 8 "S" - SRO Only; All otherb now Number.

Rev 2 ES-401 BWR SRO Examination Outline Form ES-401-1 Plant Systems - Tier 21Group 2 System # Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Pts 201001 CRD Hydraulic 1 A4.04 Drive water pressure control valve 3.0 1 201002 RMCS 11 A2.04 Control rod block 3.1 1 201006 RWM 1 28 K5.10 Withdraw error: P-spec (Not BWR6) 3.3 1 202001 Recirculation 204000 RWCU 205000 Shutdown Cooling 29 K5.02 Valve operation 2.9 1 214000 RPIS 30 K1.05 Full core display: P-Spec 3.3 1 215002 RBM 31 2.4.31 Knowledge of annunciators, alarms, 3.4 1 and indications, and the use of the response instructions 215003 IRM 219000 RHRILPCI: Torus/Pool Cooling Mode 32 K3.01 Suppression pool temperature control 4.1 1 230000 RHRILPCI: Torus/Pool Spray Mode 1 34 A2.04 Valve openings 3.1 1 234000 Fuel Handling Equipment mummEmum minim 37A4.01 Neutron monitoring system -'

3.91 245000 Main Turbine Gen. And Auxiliaries 259001 Reactor Feedwater 25 A3.03 System flow 3.2 1 262002 UPS (AC/DC) 263000 DC Electrical Distribution 8 K3.02 Components using D.C. control power 3.5 1 (i.e. breakers) 271000 Offgas 272000 Radiation Monitoring 36 K4.02 Automatic actions to contain the 4.1 1 radioactive release in the event that the predetermined release rates are exceeded 286000 Fire Protection 53S 2.4.25 Knowledge of fire protection 3.4 1 procedures 290003 Control Room HVAC 300000 Instrument Air 400000 Component Cooling Water K/A Category Point Totals: [ 10121112101 0 2 1 21 [ Group PointTotal: 13 NUREG 1021, Revision 8 iA ntePtrgoRgAsn Number.

"S" - SRO Only; All otAenbe

Rev 2

(

ES-401 BWR SRO Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 3 _

System # I Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Pts 201003 Control Rod and Drive Mechanism 6 A4.02 CRD mechanism position: Pit. Sp. 3.5 1 215001 Traversing In-core Probe 233000 Fuel Pool Cooling and Cleanup 239001 Main and Reheat Steam 35 A1.06 Air ejector process radiation monitor 3.4 1 256000 Reactor Condensate 7 K4.08 Dedicated ECCS water supply: Pit. Sp. 3.6 1 268000 Radwaste 288000 Plant Ventilation 38 A4.01 Start and stop fans 2.9 1 290002 Reactor Vessel Internals KIACategoryPointTotals: [ I 0 0I° I1 I 0 0 I I°0 0 Grou Point Total:

NUREG 1021, Revision 8 "S" - SRO Only; All oth 'Ie horew~ 9 pn Number.

Rev 2 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 Facility: Limerick Generating Station Date of Exam: 10/7/02 Exam Level: SRO Category K/A # Topic Imp. Points Conduct of 2.1.3 Knowledge of shift turnover practices - 39 3.4 1 Operations 2.1.10 Knowledge of conditions and limitations in the facility license - 3.9 1 54S 2.1.22 Ability to determine Mode of Operation - 55S 3.3 1 2.1.32 Ability to explain and apply system limits and precautions - 56S 3.8 1 Total 4 Equipment 2.2.2 Ability to manipulate the console controls as required to operate 3.5 1 Control the facility between shutdown and designated power levels - 40 2.2.11 Knowledge of the process for controlling temporary changes - 3.4 1 57S 2.2.20 Knowledge of the process for managing troubleshooting activities 3.3 1

- 58S 2.2.26 Knowledge of refueling administrative requirements - 59S 3.7 1 Total 4 Radiation Control 2.3.1 Knowledge of 10CFR20 and related facility radiation control 3.0 1 requirements - 91 2.3.2 Knowledge of the facility ALARA program- 60S 2.9 1 2.3.4 Knowledge of radiation exposure limits and contamination 3.1 1 controls, including permissible levels in excess of those specified

-61S 2.3.10 Ability to perform procedures to reduce excessive levels of 3.3 1 radiation and guard against personnel exposure - 62S Total 4 2.4.6 Knowledge of symptom based EOP mitigation strategies - 41 4.0 1 Emergency 2.4.32 Knowledge of operator responses to loss of all annunciators -63S 3.5 1 Procedures and Plan 2.4.33 Knowledge of the process used to track inoperable alarms -64S 2.8 1 2.4.38 Ability to take actions called for in the facility emergency plan, 4.0 1 including (if required) supporting or acting as emergency coordinator - 65S 2.4.44 Knowledge of emergency plan protective action 4.0 1 recommendations -66S Total 5 Tier 3 Point Total (SRO) 17 NUREG 1021, Revision 8 Numbers Denote Exam Question Number.

"S" - SRO Only; All others - Common with RO Exam

Rev 2 Rev. I ES-301 Administrative Topics Outline Form ES-301-1 Facility: Limerick Generating Station Date of Examination: 10/07/02 Examination Level SRO Operating Test Number:

Administrative Describe method of evaluation:

Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Process computer 2.1.19 (3.0) Ability to use plant computer to obtain and evaluate parametric information on system or component status JPM: Evaluate jet pump operability License 2.1.1 (3.8) Knowledge of conduct of operation requirements Maintenance JPM: Determine status of license from working hour records A.2 Safety Systems 2.2.10 (3.3) Knowledge of the process for determining the proposed Status change, test, or experiment increases the probability of occurrence or consequences of an accident during the change, test, or experiment JPM: Determine required compensatory actions for barrier breach (SRO ONLY)

A.3 Release Controls 2.3.3 (2.9) Knowledge of SRO responsibilities for auxiliary systems that are outside the control room JPM: Determine compensatory actions for a failed radiation monitor prior to a planned liquid release (SRO ONLY)

A.4 Emergency Plan 2.4.41 (4.1) Knowledge of emergency action level thresholds and classifications JPM: Evaluate plant conditions and determine EAL (SRO ONLY) 21 of 26 NUREG-1021, Revision 8

Rev 2 ES-301 Administrative Topics Outline Form ES-301-1 Facility: Limerick Generating Station Date of Examination: 10/07/02 Examination Level RO Operating Test Number:

Administrative Describe method of evaluation:

Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A. 1 Process computer 2.1.19 (3.0) Ability to use plant computer to obtain and evaluate parametric information on system or component status JPM: Evaluate jet pump operability License 2.1.1 (3.7) Knowledge of conduct of operation requirements Maintenance JPM: Determine status of license from working hour records A.2 Partial Procedures 2.2.11 (2.5) Knowledge of the process for controlling temporary changes JPM: Partial procedure preparation A.3 Release Control 2.3.11 (2.7) Ability to control radiation releases JPM: Determine offgas effluent activity release rate A.4 Emergency Plan 2.4.29 (2.6) Knowledge of Emergency Plant procedures JPM: Activate the Site Evacuation Alarm and make station Announcement NUREG-1021, Revision 8

Rev 2 ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: Limerick Generating Station Date of Examination: 10/07/02 Exam Level: SRO(I) Operating Test No.: __

B.1 Control Room Systems System / JPM Title Type Safety Code* Function

a. Manual Depressurization of RHR (Alternate Path - Drain Valve NAS 2 trips on thermals)

b. Operate RCIC Full Flow test CST to CST (Alternate Path - Test NAS 4 valve pressure locks)

c. Venting Primary Containment (OT-101) (Alternate Path - High Rad NAS 5 alarm annunciates)

d. Control Rod Exercise Test (ST-6-107-760-*)(Alternate Path - Rod NAS 1 stuck)

e. Shutdown D14 Diesel Generator MS 6

f. Bypass Isolations and Restore RECW (ON-1 13) DS 8

g. Establish Main Condenser Vacuum Using the 2 nd Stage SJAE NSL 9 B.2 Facility Walk-Through

a. Install SLC Squib Valve Bypass Line DR 1

b. Defeat HPCI and RCIC High Temperature Isolation DR 4

c. Supply Emergency DIV 1 Power to RCIC Inboard Isolation Valve DR 6

Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA Rev. 1

Rev 2 ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: Limerick Generating Station Date of Examination: 10/07/02 Exam Level: SRO(U) Operating Test No.:

B. 1 Control Room Systems System / JPM Title Type Safety Code* Function

a. Operate RCIC Full Flow test CST to CST (Alternate Path - Test NAS 4 valve pressure locks)

b. Venting Primary Containment (OT-101) (Alternate Path - High Rad NAS 5 alarm annunciates)

c. Establish Main Condenser Vacuum Using the 2 nd Stage SJAE NSL 9 d.

e.

f.

g.

B.2 Facility Walk-Through

a. Install SLC Squib Valve Bypass Line DR 1

b. Supply Emergency DIV 1 Power to RCIC Inboard Isolation Valve DR 6 C.

SType Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)ltemate path, (C)ontrol room, IS)imulator, (L)ow-Power, (R)CA NUREG-1021, Revision 8 22 of 26

Rev 2 ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: Limerick Generating Station Date of Examination: 10/07/02 Exam Level: RO Operating Test No.:

B.1 Control Room Systems System / JPM Title Type Safety Code* Function

a. Manual Depressurization of RHR (Alternate Path - Drain Valve NAS 2 trips on thermals)

b. Operate RCIC Full Flow test CST to CST (Alternate Path - Test NAS 4 valve pressure locks)

c. Venting Primary Containment (OT-101) (Alternate Path - High Rad NAS 5 alarm annunciates)

d. Control Rod Exercise Test (ST-6-107-760-*) (Alternate Path - Rod NAS 1 stuck)

e. Shutdown D14 Diesel Generator MS 6

f. Bypass Isolations and Restore RECW (ON-1 13) DS 8

g. Establish Main Condenser Vacuum Using the 2 nd Stage SJAE NSL 9 B.2 Facility Walk-Through

a. Install SLC Squib Valve Bypass Line DR 1

b. Defeat HPCI and RCIC High Temperature Isolation DR 4

c. Supply Emergency DIV 1 Power to RCIC Inboard Isolation Valve DR 6 Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA Rev. 1

Appendix D Scenario Outline Form ES-D-1 Facility: Limerick Scenario No.: Al (2,3,4) Op-Test No.:

Examiners: Operators:

Initial Conditions: 100% Power Turnover: "IM" SRV is leaking. Place "IA" RHR Loop in Suppression Pool Cooling (90%

RMSI)

Event Malf. Event Event No. No. Type* Description 1

MAD148A N (CRS) Place Suppression Pool Cooling in Service (PRO) 2 MHP451B I (CRS) HPCI Inadvertent Isolation - Tech Spec (PRO) 3 MFW046B I (ALL) "1B1FW Steam Flow Transmitter Fails Low 4 MFH522A C (ALL) Loss of Feedwater Heating MFH516A 5 N/A R (ALL) Power Reduction with Rods and Recirc to 85%

6 MAD148B C (ALL) "IM" SRV fails open and will not close MAD148C 7 MRP029C M (ALL) ATWS (Electrical)

NRP407C 8 MSL196D C (CRS) SLC Failure prevents SLC Injection (PRO)

J. 4 4

+ I 4 1

_____ _______ j ______ I ____________________________

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 39 of 40 NUREG-1021, Revision 8

Appendix D Scenario Outline Form ES-D-1 Facility: Limerick Scenario No.: B1 (2,3,4) Op-Test No.:

Examiners: Operators:

Initial Conditions: 90% power Turnover: Secure from drywell N2 makeup. (85% RMSI)

[Event Malr. Event Event No. NO. Type* Description 1 N/A N (CRS) Secure from N2 Makeup (PRO) 2 MRD016A C (CRS) Rod Drift / Thermal Limit Violation - Tech Spec (RO) 3 N/A R (ALL) Power Reduction To 80%

4 MCW483C I (CRS) "IA" RECW pump trips, "1B" RECW fails to (PRO) start 5 MRR433A C (ALL) Both "IA" RRP Seals Fail MRR434A 6 HS43-FO31A C (CRS) "IA" RRP Discharge Valve Fails Open (PRO) 7 MRR440A M (ALL) Reactor Coolant Leak 8 MRH528C C (CRS) "IA" Drywell Spray Valve Fails to Open (PRO) 9 MRH171B I (CRS) "IB" RHR Pump Fails to Start (PRO)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 39 of 40 NUREG-1021, Revision 8

Appendix D Scenario Outline Form ES-D-1 Facility: Limerick Scenario No.: Cl (Spare) Op-Test No.:

Examiners: Operators:

Initial Conditions: 95% power with power ascension in progress. HPCI is in CST to CST Full Flow Test.

Turnover: Secure HPCI Event Malf. Event Event No. No. Type* Description 1 N/A N (CRS) Secure HPCI from Full Flow Test (PRO) 2 MED282B C (ALL) Loss Division 2 DC Loss - Tech Spec 3 MMC074 C (ALL) Loss of Condenser Vacuum 4 N/A R (ALL) Power Reduction with Rods and recirc due to loss of Condenser Vacuum 5 MMC548 M (ALL) Loss of Feedwater due to a Main Condenser Hotwell Leak 6 MRC466 C (CRS) RCIC Overspeed trip (PRO) 7 MAD139B C (CRS) "1C" SRV Fails Open / Stuck MAD139E (PRO) 8 MCR547 I (CRS) Both CRD Pumps Trip due to suction pressure (RO) instrument failure

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)aJor 39 of 40 NUREG-1021, Revision 8

(

Limerick Generating Station Exam Date: 10/7/02 Summary of Exam Changes Following Review Written Exam Change 1 Added "per S46.1.A, CONTROL ROD DRIVE HYDRAULIC SYSTEM STARTUP" 3 Revised stem to ask for the final status of the system instead of response.

5 Revised stem to ask "in the direction indicated" to clarify what is being asked 11, 30 Minor editorial or punctuation change made to enhance consistency, readability, or intent 33, 34 46, 52 54, 60 64, 66 70, 72R 74R, 78, 79, 85 86, 95 51S, 52S, 58S, 61S 62S, 67S 13 Added"per _ "to each choice 16 Changed "quadrant(s) to "quadrants" because all choices are two or more 38 Unsat question. Removed "and the reason" from the stem because only C and D had clear reasons 88 Unsat question. Replaced with new question.

Various Replaced "Procedure T- is provided" to "Selected TRIP procedures are provided" to prevent undue (7 total) cueing

Limnrick Generating Station (

Exam Date: 10/7/02 Summary of Exam Changes Following Review Operating Exam Exam Item Change Sim JPM 0105 Corrected typo Step 6 Sim JPM 0106 Note added to suppress alarm bells if administered with other candidates in simulator to prevent cueing the alternate path Removed OT-101 step number from cue Sim JPM 0103 Correct annunciator in Step 9 from 120 panel to 123 panel

Rev 2 ES-401 BWR RO Examination Outline Form ES-401-2 Facility: Limerick Generating Station Date of Exam: 10/07/02 Exam Level: RO Tier Group K/A Category Points Point Total

1. 2 3 3 3 1

13 Emergency &

Abnormal Plant 2 2 3 2 5 6 1 19 Evolutions 3 1 2 0 1 0 0 4 Tier 5 8 5 9 7 2 36 Totals

2. 1 1 3 3 3 2 2 3 4 4 2 1 28 Plant Systems 2 2 0 4 3 2 3 1 1 0 2 1 19 3 0 0 0 0 0 1 0 1 0 2 0 4 Tier 3 3 7 6 4 6 4 6 4 6 2 51 Totals

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 3 3 3 4 13 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., the "Tier Totals" in each K/A category shall not be less than two).

2. Actual point totals must match those specified in the table.

3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

4. Systems/evolutions within each group are identified on the associated outline.

5. The shaded areas are not applicable to the category/tier.

6.* The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the RO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

NUREG 1021, Revision 8

( ( ( Rev 2 ES-401 BWR RO Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier llGroup I E/APE # / Name / Safety Function KI K2 K3 Al A2 G KIA Topic(s) Imp. Pts 295005 Main Turbine Generator Trip / III 74R AA1.05 Reactor/turbine pressure regulating system 3.6 1 295006 SCRAM / I 10 AK3.03 Reactor pressure response 3.8 1 295007 High Reactor Pressure / III 42 AK3.03 RCIC operation: Pit. Sp. 3.4 1 295009 Low Reactor Water Level Ill 43 AK2.02 Reactor water level control 3.9 1 295010 High Drywell Pressure / V 92 AK3.01 Drywell venting 3.8 1 295014 Inadvertent Reactivity Addition /I 44 AK1.05 Fuel thermal limits 3.7 1 45 AA1.02 Recirculation flow control system 3.6 1 295015 Incomplete SCRAM / I 46 AK2.01 CRD Hydraulics 3.8 1 295024 High Drywell Pressure/ V 47 2.1.23 Ability to perform specific system and integrated plant procedures 3.9 1 during diferent modes of plant operation 295025 High Reactor Pressure / II1 93 EK2.04 ARI/RPT/ATWS: Pit. Sp. 3.9 1 295031 Reactor Low Water Level / II 48 EAt.06 Automatic depressurization system 4.4 1 295037 SCRAM Condition Present and Power 49 EA2.02 Reactor water level 4.1 1 Above APRM Downscale or Unknown / I 500000 High Containment Hydrogen Conc. / V 50 EK1.01 Containment integrity 3.3 1 FIKA Category Totals: [2 3 3 3 1 1 1 Group Point Total: 113 NUREG 1021, Revision 8 Numbers Denote Exam Question Number.

"R" - RO Only; All others - Common with SRO Exam

( l Rev 2 ES-401 BWR RO Examination Outline Emergency and Abnormal Plant Evolutions - Tier lIGroup 2 Form ES-401-2 E/APE # / Name I Safety Function KI K2 K3 Al A2 G K/A Topic(s) Imp. Pts 295001 Partial or Complete Loss of Forced Core 76 AK1.02 Power/flow distribution Flow Circulation / I & IV 3.3 1 295002 Loss of Main Condenser Vacuum / Ill 77 AK1.04 Increased offgas flow 3.0 1 295003 Partial or Complete Loss of AC Pwr / VI 94 AA2.02 Reactor power, pressure, and level 4.2 1 295004 Partial or Complete Loss of DC Pwr / VI 95 AA1.02 Systems necessary to assure safe plant shutdown 3.8 1 295008 High Reactor Water Level/ Il 78 AK2.08 Main turbine: Pit. Sp. 3.4 1 295012 High Drywell Temperature / V 96 AK2.01 Drywell ventilation 3.4 1 295013 High Suppression Pool Temp. / V 97 AK2.01 Suppression pool cooling 3.6 1 295016 Control Room Abandonment / VII 295017 High Off-site Release Rate / IX 79 AA1.04 Stack gas monitoring system: Pit. Sp. 3.6 1 295018 Partial or Complete Loss of CCW / VIII 75R AA2.01 Component temperatures 3.3 1 295019 Partial or Complete Loss of Inst. Air/ VIII 80 AA1.01 Backup air supply 3.5 1 295020 Inadvertent Cont. Isolation / V &VII 98 AA1.02 Drywell ventilation/cooling system 3.2 1 295022 Loss of CRD Pumps / I 81 AK3.01 Reactor SCRAM 3.7 1 295026 High Suppression Pool Water Temp. / V 82 EK3.04 SBLC injection 3.7 1 Bmumu 295028 High Drywell Temperature / V 99 2.1.32 Ability to explain and apply system limits and precautions 3.4 1 295029 High Suppression Pool Water Level / V 83 EA2.03 Drywell/containment water level 3.4 1 295030 Low Suppression Pool Water Level / V 84 EA2.04 Drywell/suppression chamber differential pressure: Marl II&lll 3.5 1 295033 High Secondary Containment Area 85 EA2.01 Area radiation levels Radiation Levels / IX 3.8 1 I

295034 Secondary Containment Ventilation High Radiation / IX 295038 High Off-site Release Rate / IX 86 EA1.06 Plant ventilation 3.5 1 600000 Plant Fire On Site / VIII 87 AA2.04 The fire's extent of potential operational damage to plant 2.8 1 equipment K/VA Category Point Totals: = I. 1 [3 15 I21,6 11 Group Point Total: - 7179i NUREG 1021, Revision 8 Numbers Denote Exam Question Number.

"R" - RO Only; All others - Common with SRO Exam

( ( Rev 2 ES-401 BWR RO Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier llGroup 3 EIAPE # I Name I Safety Function K1 K2 K3 Al A2 G KIA Topic(s) Imp. Pts 295021 Loss of Shutdown Cooling / IV 100 AK1.04 Natural circulation 3.6 1 295023 Refueling Accidents / VIII 295032 High Secondary Containment Area 88 EK2.07 Leak detection system concept: Pit. Sp. 3.6 1 Temperature / V 295035 Secondary Containment High Differential 89 EK2.04 Blow-out panels: Pit. Sp. 3.3 1 Pressure / V 295036 Secondary Containment High Sump/Area 90 EA1.01 Secondary containment and floor drain systems 3.2 1 Water Level / V I____

K/A Category Point Totals: 11 12 10 10 Group Point Total: 1 41 NUREG 1021, Revision 8 Numbers Denote Exam Question Number.

"R" - RO Only; All others - Common with SRO Exam

( ( ( Rev 2 ES-401 BWR RO Examination Outline Form ES-401-2 Plant Systems - Tier 21Group 1 System # / Name KI K2 K3 K4 K6 K6 Al A2 A3 A4 G KIA Topic(s) Imp. Pts 201001 CRD Hydraulic 1 A4.04 Drive water pressure control valve 3.1 1 201002 RMCS 11 A2.04 Control rod block 3.2 1 202002 Recirculation Flow Control 12 A2.01 Recirculation pump trip 3.4 1 51R _A3.03 Scoop tube operation: BWR 2,3,4 3.1 1 203000 RHRPLPCI: Injection Mode 13 A2.04 A.C. failures 3.5 1 52R A3.08 System initiation sequence 4.1 1 206000 HPCI 14 K5.08 Vacuum breaker operation:BWR- 3.0 1 4

mW m3 209001 LPCS 15 K2.03 Initiation logic 2.9 1 21100 Lm mm A....Lights a 211000 SL2 A1.10 Lights and alarms 3.7 1 212000 RPS 3 K.4.05 Functional testing of the system 3.4 1 while maintaining power operation 215003 IRM 53R K3.02 Reactor manual control 3.6 1 215004 SRM 16 A2.04 Upscale and downscale trips 3.5 1 17 2.1.30 Ability to locate and operate 3.9 1 components, including local controlss 215005 APRM / LPRM 18 K2.02 APRM channels 2.6 1 216000 Nuclear Boiler Instrumentation 19 K3.29 Jet pump flow monitoring: Pit. Sp. 3.1 1 217000 RCIC 20 A3.02 Turbine startup 3.6 1 54R I I K4.04 Prevents turbine damage: Pit Sp. 3.0 1 218000 ADS 21 K6.07 Primary containment instrumentation 3.4 1 223001 Primary CTMT and Auxiliaries 22 K2.09 Drywell cooling fans: PIt. Sp. 2.7 1 223002 PCIS/Nuclear Steam Supply Shutoff 23 K4.08 Manual defeating of selected 3.3 1 isolations during specified emergency conditions 55R A1.03 SPDSIERIS/CRIDSIGDS: Pit. Sp. 2.5 1 239002 SRV's 4 A4.01 SRVs 4.4 1 241000 Reactor/Turbine Pressure Regulator 24 K6.17 Main turbine PMG: Pit. Sp. 2.7 1 259001 Reactor Feedwater 25 A3.03 System flow 3.3 1 259002 Reactor Water Level Control 5 K1.05 Reactor Feedwater system 3.6 1 56R K5.01 GEMAC/Foxboro/Bailey controller 3.1 1 operation: Pit. Sp.

261000 SGTS 26 K3.05 Secondary containment 3.2 1 radiation/contamination levels 264000 EDG's 27 A1.09 Maintaining minimum load on 3.0 1 emergency generator (to prevent reverse power)

[K/A Category Point Totals: fi1 3 3 _312 12 13 f 4 4 2 1 Group Point Total: -2:8 NUREG 1021, Revision 8 Numbers Denote Exam Question Number.

"R" - RO Only; All others - Common with SRO Exam

Rev 2 ES-401 BWR RO Examination Outline Form ES-401-2 Plant Systems - Tier 21Group 2 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KIA Topic(s) Imp. Pts 201003 Control Rod and Drive Mechanism 6 A4.02 CRD mechanism position: Pit. Sp. 3.5 1 201006 RWM 28 K5.10 Withdraw error: Pit. Sp (Not BWR6) 3.2 1 202001 Recirculation 57R K4.06 Automatic voltage/frequency 2.6 1 regulation : Pit Sp.

204000 RWCU 58R K1.15 Leak Detection: Pit. Sp. 3.1 1 205000 Shutdown Cooling 29 K5.02 Valve operation 2.8 1 214000 RPIS 30 K1.05 Full core display: Pit. Sp. 3.3 1 215002 RBM 31 2.4.31 Knowledge of annunciators, 3.3 1 alarms, and indications, and the use of the response instructions 219000 RHR/LPCI: Tows/Pool Cooling 32 K3.01 Suppression pool temperature 3.9 1 Mode control 226001 RHRPLPCI: CTMT Spray Mode 33 K6.05 Suppression pool (temperature, 3.4 1 level, and pressure) 230000 RHR/LPCh: Torus/Pool Spray 34 A2.04 Valve openings 2.8 1 Mode 239001 Main and Reheat Steam 35 A1.06 Air ejector process radiation 3.4 1 monitor 245000 Main Turbine Gen. and Auxiliaries 59R K3.07 Reactor protection system 3.6 1 256000 Reactor Condensate 7 K4.08 Dedicated ECCS water supply: Pit. 3.6 1 Sp.

262001 AC Electrical Distribution 262002 UPS (AC/DC) 60R K3.11 MSIVs: Pit. Sp. 2.8 1 263000 DC Electrical Distribution 8 K3.02 Components using D.C. control 3.5 1 power (i.e. breakers) 271000 Offgas 61R K6.09 Fuel cladding integrity 3.4 1 272000 Radiation Monitoring 36 K4.02 Automatic actions to contain the 3.7 1 radioactive release in the event that the predetermined release rates are exceeded 286000 Fire Protection 290001 Secondary CTMT 9 K6.08 Plant air systems 2.7 1 290003 Control Room HVAC 62R A4.01 Initiate/Reset system 3.2 1 300000 Instrument Air 400000 Component Cooling Water K/A Category Point Totals: 2 10 4 13 12 13 1 I1 10 2 1I1 Group Point Total: 119 NUREG 1021, Revision 8 Numbers Denote Exam Question Number.

"R" - RO Only; All others - Common with SRO Exam

( ( (

Rev 2 ES.401 BWR RO Examination Outline Form ES-401-2 IPlant Systems - Tier 2/Group 3 System # I Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Pts 215001 Traversing In-core Probe 233000 Fuel Pool Cooling and Cleanup 63R K6.10 Reactor cavity seal failure 2.9 1 234000 Fuel Handlig Equipment 37 A4.01 Neutron monitoring system 3.7 1 268000 Radwaste 288000 Plant Ventilation 38 A4.01 Start and stop fans 3.1 1 290002 Reactor Vessel Internals 64R A2.04 Excessive heatup/cooldown rate 3.7 1

[K/A Category Point Totals: T 0 10 10 10 o0 1 10. 1 O 12 101 Group Point Total: - I 4 NUREG 1021, Revision 8 Numbers Denote Exam Question Number.

"R" - RO Only; All others - Common with SRO Exam

Rev 2 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 Facility: Limerick Generating Station Date of Exam: 10/07/02 Exam Level: RO Category K/A # Topic Imp. Points Conduct of 2.1.3 Knowledge of shift turnover practices 39 3.0 1 Operations 2.1.25 Ability to obtain and interpret station reference material such as 2.8 1 graphs, monographs, and tables which contain performance data 65R 2.1.32 Ability to explain and apply system limits and precautions - 66R 3.4 1 Total 3 Equipment 2.2.2 Ability to manipulate the console controls as required to operate 4.0 1 Control the facility between shutdown and designated power levels -40 2.2.3 (Multi Unit) Knowledge of the design, procedural, and operational 3.1 1 differences between units - 67R 2.2.24 Ability to analyze the affect of maintenance activities on LCO 2.6 1 status - 68R Total 3 Radiation Control 2.3.1 Knowledge of 10CFR20 and related facility radiation control 2.6 1 requirements - 91 2.3.4 Knowledge of radiation exposure limits and contamination control, 2.5 1 including permissible levels inexcess of those authorized - 69R 2.3.11 Ability to control radiation releases - 70R 2.7 1 Total 3 Emergency Procedures and 2.4.6 Knowledge of symptom based EOP mitigation strategies 41 3.1 1 Plan 2.4.17 Knowledge of EOP terms and definitions- 71R 3.1 1 2.4.48 Ability to interpret control room indications to verify the status and 3.5 1 operation of systems and understand how operator actions and directives affect plant snd system conditions- 72R 2.4.49 Ability to perform without reference to procedures those actions 4.0 1 that require immediate operation of system components and controls - 73R Total 4 Tier 3 Point Total (RO) 13 NUREG 1021, Revision 8 Numbers Denote Exam Question Number.

"R" - RO Only; All others - Common with SRO Exam

Rev 2 ES-301 Administrative Topics Outline Form ES-301-1 Facility: Limerick Generating Station Date of Examination: 10/07/02 Examination Level RO Operating Test Number:

Administrative Describe method of evaluation:

Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Process computer 2.1.19 (3.0) Ability to use plant computer to obtain and evaluate parametric information on system or component status JPM: Evaluate jet pump operability License 2.1.1 (3.7) Knowledge of conduct of operation requirements Maintenance JPM: Determine status of license from working hour records A.2 Partial Procedures 2.2.11 (2.5) Knowledge of the process for controlling temporary changes JPM: Partial procedure preparation A.3 Release Control 2.3.11 (2.7) Ability to control radiation releases JPM: Determine offgas effluent activity release rate A.4 Emergency Plan 2.4.29 (2.6) Knowledge of Emergency Plant procedures JPM: Activate the Site Evacuation Alarm and make station Announcement NUREG-1021, Revision 8

Rev 2 ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: Limerick Generating Station Date of Examination: 10/07/02 Exam Level: RO Operating Test No.:

B.1 Control Room Systems System / JPM Title Type Safety Code* Function

a. Manual Depressurization of RHR (Alternate Path - Drain Valve NAS 2 trips on thermals)

b. Operate RCIC Full Flow test CST to CST (Alternate Path - Test NAS 4 valve pressure locks)

c. Venting Primary Containment (OT-101) (Alternate Path - High Rad NAS 5 alarm annunciates)

d. Control Rod Exercise Test (ST-6-107-760-*) (Alternate Path - Rod NAS 1 stuck)

e. Shutdown D14 Diesel Generator MS 6

f. Bypass Isolations and Restore RECW (ON-1 13) DS 8

g. Establish Main Condenser Vacuum Using the 2nd Stage SJAE NSL 9 B.2 Facility Walk-Through

a. Install SLC Squib Valve Bypass Line DR 1

b. Defeat HPCI and RCIC High Temperature Isolation DR 4

c. Supply Emergency DIV 1 Power to RCIC Inboard Isolation Valve DR 6 kType Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA Rev. I

D*,o PI IWV "

ES-401 BWR SRO Examination Outline Form ES-401-1 Facility: Limerick Generating Station Date of Exam: 10/07/02 Exam Level: SRO Tier Group K/A Category Points Point Total l 2i K3iK4T 5FK;6F1l A2 A3 Aý4 G*oa Emergency &

Abnormal Plant 2 3 4 1 Evolutions Tier Totals Evltos8 5 8 5 58 4

1 342317 7 43 IJ