ML15100A035

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Final Outlines (Folder 3)
ML15100A035
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 01/12/2015
From: Peter Presby
Operations Branch I
To: Ruffe R
Exelon Generation Co
Shared Package
ML14245A223 List:
References
TAC U01892
Download: ML15100A035 (26)
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Text

Limerick Op-Test Change Summary Changed alternate path initiator Admin JPM A-3 Replaced JPM Admin JPM A-4 Added additional complexity to offsite release JPM Scenario #3

  • Deleted CT-1
  • Deleted Event 1

562188ES-401 BWR Examination Outline - NRC - RO Form ES-401-1 Facili : Limerick Generatin Station Date of Exam: Jan 23, 2015 RO KIA Category Points Tier Group K K K K K K A A A A G 1 2 3 4 5 6 1 2 3 4

  • Total
1. 3 5 4 3 3 2 20 Emergency&

Abnormal Plant 2 N/A N/A 2 7 Evolutions Tier Totals 4 6 5 4 4 4 27 4 4 3 2 3 2 2 3 26 2.

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

3. Generic Knowledge and Abilities 2 3 4 10 Categories 2 3 2 3 Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section 0 .1.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 an importance rating (IA) 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) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KlAs.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (I Rs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, I Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.

ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline - RO Form ES-401-1 Erner enc and Abnormal Plant Evolutions - Tier 1/Grou 1 RO E/APE #I Name I Safety Function K K K A A G KIA Topic(s) IR #

1 2 3 1 2 Ability to operate and/or monitor the following as 295001 Partial or Complete Loss of Forced x they apply to PARTIAL OR COMPLETE LOSS OF 3.1 11 H Core Flow Circulation / 1 & 4 FORCED CORE FLOW CIRCULATION: AAI.07 Nuclear boiler instrumentation s stem Knowledge of the reasons for the following responses 295003 Partial or Complete Loss of AC I 6 x as they apply to PARTIAL OR COMPLETE LOSS 3.7 12 H OF A.C. POWER: AK3.05 Reactor SCRAM Knowledge of the interrelations between PARTIAL 295004 Partial or Total Loss of DC Pwr / 6 x OR LOSS OF D.C. POWER and the following: 3.3 35 H AK2.03 D.C. bus loads 295005 Main Turbine Generator Trip I 3 x Ability to determine and/or interpret the following as 3.2 51 H they apply to MAIN TURBINE GENERATOR TRIP:

AA2.08 Electrical distribution status Knowledge of the interrelations between SCRAM and 295006 SCRAM / 1 x the followin : AK2.04 Turbine tri lo ic: Plant-S cific 3.6 41 L Ability to determine and/or interpret the following as 295016 Control Room Abandonment I 7 x they apply to CONTROL ROOM ABANDONMENT: 3.3 13 H AA2.06 Cooldown rate Knowledge of the operational implications of the 295018 Partial or Total Loss of CCW I 8 x following concepts as they apply to PARTIAL OR 3.5 40L COMPLETE LOSS OF COMPONENT COOLING WATER : AKl .01 Effects on component/system o rations Knowledge of the interrelations between PARTIAL 295019 Partial or Total Loss of Inst. Air/ 8 x OR COMPLETE LOSS OF INSTRUMENT AIR and 3.2 58 H the followin : AK2.03 Reactor feedwater 295021 Loss of Shutdown Coolin I 4 X 2.4.11 Knowled e of abnormal condition rocedures. 4.0 52 L 295023 Refueling Ace I 8 x Knowledge of the operational implications of the 3.7 53 L following concepts as they apply to REFUELING ACCIDENTS: AKI.03 Inadvertent criticalit 295024 High Drywall Pressure I 5 x Knowledge of the reasons for the following responses 3.7 61 L as they apply to HIGH DRYWELL PRESSURE:

EK3.04 tEmer enc de ressurization 2.2.39 Knowledge of less than or equal to one hour 295025 High Reactor Pressure I 3 X Technical S ecification action statements for s stems 3.9 14 L Ability to operate and/or monitor the following as 295026 Suppression Pool High Water x they apply to SUPPRESSION POOL HIGH WATER 3.9 59 H Temp./ 5 TEMPERATURE: EAI.03 Tern rature monitorin Knowledge of the reasons for the following responses 295028 High Drywall Temperature I 5 x as they apply to HIGH DRYWELL 3.6 39 L TEMPERATURE: EK3.01 Erner enc de ressurization 295030 Low Suppression Pool Wtr Lvl I 5 x Ability to determine and/or interpret the following as 4.1 62H they apply to LOW SUPPRESSION POOL WATER LEVEL: EA2.01 Su ression ool level Knowledge of the operational implications of the 295031 Reactor Low Water Level I 2 x following concepts as they apply to REACTOR LOW 3.8 36L WATER LEVEL: EKI.02 Natural circulation: Plant-s cific Knowledge of the interrelations between SCRAM 295037 SCRAM Condition Present x CONDITION PRESENT AND REACTOR POWER 4.1 38L and Reactor Power Above APRM ABOVE APRM DOWNSCALE OR UNKNOWN and Downscale or Unknown / 1 the followin : EK2.03 ARI/RPT/ATWS: Plant-S ecific

295038 High Off-site Release Rate I 9 x Ability to operate and/or monitor the following as 3.9 63H they apply to HIGH OFF-SITE RELEASE RATE:

EAi .01 Stack-gas monitoring svstern Knowledge of the interrelations between PLANT 600000 Plant Fire On Site I 8 x FIRE ON SITE and the following: AK2.01 Sensors I 2.6 15 L detectors and valves Knowledge of the reasons for the following responses I 700000 Generator Voltage and Electric Grid x as they apply to GENERATOR VOLTAGE AND 3.6 16H Disturbances I 6 ELECTRIC GRID DISTURBANCES: AK3.02 Actions contained in abnormal operating procedure for voltage and grid disturbances KIA Cateaorv Totals: 3 5 4 3 3 2 Grouo Point Total: 20

ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline - RO Form ES-401-1 Erner enc and Abnormal Plant Evolutions - Tier 1/Grou 2 RO E/APE #I Name I Safety Function K K K A A G KIA Topic(s) IA #

1 2 3 1 2 295002 Loss of Main Condenser Vac I 3 2.1.31 Ability to locate control room switches, controls, 295007 High Reactor Pressure I 3 X and indications, and to determine that they correctly 4.6 17H reflect the desired !ant lineu

  • 295008 Hi h Reactor Water Level I 2 295009 Low Reactor Water Level I 2 295010 High Drywall Pressure I 5 x Knowledge of the operational implications of the 3.2 !SH following concepts as they apply to HIGH DRYWELL PRESSURE: AKI .03 Tern rature increases 295013 Hi h Su ression Pool Tern . I 5 295014 Inadvertent Reactivi Addition I 1 295015 lncom late SCRAM I 1 295017 Hi h Off-site Release Rate I 9 295020 Inadvertent Cont. Isolation I 5 & 7 295022 Loss of CAD Pum s I 1 Ability to operate and/or monitor the following as they 295029 High Suppression Pool Wtr Lvl I 5 x apply to HIGH SUPPRESSION POOL WATER 2.9 19H LEVEL: EAl .03 RHR/LPCI Ability to determine and/or interpret the following as 295032 High Secondary Containment x they apply to HIGH SECONDARY CONTAINMENT 3.3 20 L Area Temperature I 5 AREA TEMPERATURE: EA2.02 ui ment o rabilit 295033 High Secondary Containment Area Radiation Levels I 9 295034 Secondary Containment X 2.4.1 Knowledge ofEOP entry conditions and immediate 4.6 34 L Ventilation Hi h Radiation I 9 action ste s.

295035 Secondary Containment High x Knowledge of the reasons for the following responses as 2.8 60H Differential Pressure I 5 they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: EK3.01 Blow-out panel o ration: Plant-S cific 295036 Secondary Containment High x Knowledge of the interrelations between SECONDARY 3.1 64 L Sump/Area Water Level I 5 CONTAINMENT HIGH SUMP/AREA WATER LEVEL and the following: EK2.01 Secondary Containment e ui ment and floor drain s stem 500000 Hi h CTMT H dro en Cone. I 5 KIA Cate o Point Totals: 2 Grou Point Total: 7

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline - RO Form ES-401-1 Plant S stems - Tier 2/Grou 1 RO System # I Name K K K K K K A A A A G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 Knowledge of the operational implications of x the following concepts as they apply to 2.7 28 H RHR/LPCI: INJECTION MODE (PLANT 203000 RHR/LPCI: Injection SPECIFIC): K5.0l Testable check valve Mode o ration 2.1.20 Ability to interpret and execute X rocedure ste s. 4.6 71 H Ability to manually operate and/or monitor in 205000 Shutdown Cooling x the control room: A4.07 Reactor tern ratures 3.7 42H Ability to (a) predict the impacts of the x following on the HIGH PRESSURE 3.9 43H COOLANT INJECTION SYSTEM; and (b) based on those predictions, use procedures to 206000 HPCI correct, control, or mitigate the consequences of those abnormal conditions or operations: A2. l 7 tHPCl inadvertent initiation: BWR-2,3,4 Knowledge of the physical connections and/or 209001 LPCS x cause-effect relationships between LOW PRESSURE CORE SPRAY SYSTEM and the followin :

  • Kl 02 Torus/su ression ol 209002HPCS Suppressed Ability to predict and/or monitor changes in 211000 SLC x parameters associated with operating the 4.0 3L STANDBY LIQUID CONTROL SYSTEM controls includin2: Al.09 SBLC system lineuo Knowledge of the effect that a loss or 212000 RPS x malfunction of the REACTOR PROTECTION 4.0 7H SYSTEM will have on following: K3.06 Scram air header solenoid operated valves Ability to monitor automatic operations of the 215003 IRM x INTERMEDIATE RANGE MONITOR (IRM) 3.7 21 L SYSTEM includin2: A3.03 RPS status Knowledge of the effect that a loss or 215004 Source Range Monitor x malfunction of the following will have on the 2.9 26H SOURCE RANGE MONITOR (SRM)

SYSTEM: K6.04 Detectors Ability to monitor automatic operations of the 215005 APRM I LPRM x AVERAGE POWER RANGE MONITOR I 3.3 37 H LOCAL POWER RANGE MONITOR SYSTEM includin2: A3.03 Meters and recorders Knowledge of the effect that a loss or 217000 RCIC x malfunction of the REACTOR CORE 3.6 22H ISOLATION COOLING SYSTEM (RCIC) will have on followin2: K3.02 Reactor vessel oressure Knowledge of the physical connections and/or 218000 ADS x cause-effect relationships between 3.9 4H AUTOMATIC DEPRESSURIZA TION SYSTEM and the following: Kl.06 Safety/relief valves

Knowledge of the physical connections and/or 223002 PCIS/Nuclear Steam x cause-effect relationships between PRIMARY 3.1 8H Supply Shutoff CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF and the following: Kl.12 Standby l!as treatment svstem Knowledge of the effect that a loss or 239002 SRVs x malfunction of the RELIEF/SAFETY VALVES 4.2 25 L will have on following: K3.02 Reactor over nressurization Knowledge of REACTOR WATER LEVEL 259002 Reactor Water Level x CONTROL SYSTEM design feature(s) and/or 3.1 29L Control interlocks which provide for the following:

K4.06 Control siimal failure 261000 SGTS x 2.2.12 Knowledl!e of surveillance orocedures. 3.7 24L Knowledge of the operational implications of 262001 AC Electrical x the following concepts as they apply to A.C. 3.1 23 H Distribution ELECTRICAL DISTRIBUTION: K5.0l Principle involved with paralleling two A.C.

sources Knowledge of the physical connections and/or x cause-effect relationships between 2.8 27 H UNINTERRUPTABLE POWER SUPPLY 262002 UPS (AC/DC)

(A.CJD.C.) and the following: Kl.14 Main steam line radiation monitors Knowledge of the effect that a loss or x malfunction of the following will have on the 2.8 72L UNINTERRUPTABLE POWER SUPPLY (A.CJD.C.): K6.02 D.C. electrical power Knowledge of the operational implications of x the following concepts as they apply to D.C. 2.6 9L ELECTRICAL DISTRIBUTION: K5.0l 263000 DC Electrical Hvdro!!en l!eneration durin!! battery charginl!

Distribution Ability to (a) predict the impacts of the x following on the D.C. ELECTRICAL 2.8 44H DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or ooerations: A2.01 Grounds Ability to predict and/or monitor changes in 264000 EDGs x parameters associated with operating the 3.0 6L EMERGENCY GENERATORS (DIESEUJET) controls including: Al .09 Maintaining minimum load on emergency

!!enerator (to orevent reverse oower).

x Knowledge of electrical power supplies to the 2.8 IL followinl!: K2.0l Instrument air comoressor 300000 Instrument Air Knowledge of the effect that a loss or x malfunction of the (INSTRUMENT AIR 3.3 45H SYSTEM) will have on the following: K3.02 Svstems havin!! pneumatic valves and controls 400000 Component Cooling x Ability to predict and I or monitor changes in 2.8 66H Water parameters associated with operating the CCWS controls includin2: Al .0 I CCW flow rate KIA Cateoorv Point Totals: 4 I 4 I 3 2 3 2 2 I 3 Grouo Point Total: 26

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline - RO Form ES-401-1 Plant S stems - Tier 2/Grou 2 RO System # I Name K K K K K K A A A A G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 Knowledge of electrical power supplies to 201001 CAD Hydraulic x the following: K2.05 Alternate rod insertion 4.5 46H valve solenoids: Plant-S cific 2.1.23 Ability to perform specific system 201002 RMCS x and integrated plant procedures during I 4.3 SL all modes of !ant o ration.

Ability to (a) predict the impacts of the 201006 RWM x following on the ROD WORTH 3.1 70H MINIMIZER SYSTEM (RWH) (PLANT SPECIFIC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.05 Out of se uence rod movement 202001 Recirculation Ability to monitor automatic operations of 202002 Recirculation Flow Control x the RECIRCULATION FLOW 3.4 47 L CONTROL SYSTEM including: A3.02 Li hts and alarms 204000 RWCU 214000 RPIS x Knowledge of the operational implications 2.7 67H of the following concepts as they apply to ROD POSITION INFORMATION SYSTEM: K5.0l Reed switches 215001 Traversin In-core Probe 215002 ABM 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling 219000 RHR/LPCI: Torus/Pool Cooling x Knowledge of RHR/LPCI: TORUS I 3.0 68H Mode SUPPRESSION POOL COOLING MODE design feature(s) and/or interlocks which provide for the following: K4.05 Pum minimum flow rotection 223001 Prima CTMT and Aux.

226001 RHR/LPCI: CTMT S ra Mode 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup x Knowledge of the effect that a loss or 2.6 48H malfunction of the FUEL POOL COOLING AND CLEAN-UP will have on followin : K3.03 Fuel ool water clarit Ability to predict and/or monitor changes 234000 Fuel Handling Equipment x in parameters associated with operating 3.4 JOH the FUEL HANDLING EQUIPMENT controls including: Al .03 core reactivity level

239001 Main and Reheat Steam x Ability to predict and/or monitor changes 3.7 49H in parameters associated with operating the MAIN AND REHEAT STEAM SYSTEM controls including: Al.07 Reactor water level 239003 MSIV Leakage Control Suppressed 241000 Reactor!Turbine Pressure x Knowledge of the physical connections 3.8 73 H Regulator and/or cause-effect relationships between REACTOR!fURBINE PRESSURE REGULATING SYSTEM and the followin2: Kl.06 Bypass valves 245000 Main Turbine Gen. I Aux.

256000 Reactor Condensate 259001 Reactor Feedwater x Knowledge of the effect that a loss or 3.8 69H malfunction of the following will have on the REACTOR FEEDWATER SYSTEM:

K6.07 Reactor water level control system 268000 Radwaste 271000 Offaas 272000 Radiation Monitorina 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC x Ability to manually operate and/or 3.2 SOL monitor in the control room: A4.01 Initiate/reset system 290002 Reactor Vessel Internals KIA Cateaorv Point Totals: I I I I I I 2 l I I l Group Point Total: 12

ES-401 Generic Knowledge and Abilities Outline {Tier 3)- RO Form ES-401-3 Facili : Limerick Generatin Station Date of Exam: 01/23/15 Category KIA# Topic RO IA #

2.1.7 Ability to evaluate plant performance and make operational 4.4 30H judgments based on operating characteristics, reactor behavior,

1. and instrument inte retation.

Conduct 2.1 .21 Ability to verify the controlled procedure copy. 3.5 54L of Operations Subtotal 2 2.2.22 Knowledge of limiting conditions for operations and safety limits. 4.0 31 L 2.2.13 Knowledge of tagging and clearance procedures. 4.1 55 H Knowledge of the process for controlling equipment configuration

2. 2.2.14 3.9 74L or status.

Equipment Control Subtotal 3 Ability to control radiation releases.

2.3.11 3.8 32H Knowledge of radiation or contamination hazards that may arise 2.3.14 durin normal abnormal or emer enc conditions or activities. 3.4 56H

3. Subtotal 2 Radiation Control 2.4.27 Knowledge of "fire in the plant" procedures. 3.4 33 L Knowledge of how abnormal operating procedures are used in 2.4.8 co unction with EOPs. 3.8 57 L 4.

Emergency 2.4.11 Knowledge of abnormal condition procedures. 4.0 75L Procedures I Plan Subtotal 3 Tier 3 Point Total 10

ES-401 Record of Rejected KlAs - RO Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KlA 2I 1 264000 Al.01 Cannot write an RO question with sufficient LOD. Randomly re-selected within 264000 Al; replaced with Al.09.

1/2 295010 2.4.49 With the latest revision of OT-101 (High Drywell Pressure), there are no "immediate operator actions", nor any "subsequent" (follow-up) actions that are of an immediate nature. Therefore, KA 2.4.49 is not operationally valid. Randomly re-selected within 2.4 Generics; replaced with 2.4.11.

1I 1 295028 EK3.04 For LGS, this KA lacks sufficient operational validity for the following reason: At rated power the "normal" drywell temperature is such that it demands that drywell cooling be maximized at all times; in other words, upon entry into the T-102 (PC Control)

DWIT leg, LGS operators take no specific action to "operate all available drywell cooling" (as directed by step DW/T-2).

Randomly re-selected within 295028 EK3; replaced with EK3.0l.

3 2.2.39 This KA is inappropriate for Tier 3. The KA necessarily requires a connection to a Tech Spec "system", which is not permitted by ES-401, Section D.2.a, first paragraph. Randomly re-selected among all Generics; replaced with 2.2.14.

2/2 239001 A 1.10 Question #49 (tied to Al.10) had already been drafted and validated when the Exam Author discovered an unacceptable amount of overlap existed between the original version of the question and the "Normal" evolution component of Scenario #1 of the Operating Test. Exam Author opted for maintaining the Scenario #1 evolution as-is and randomly re-selecting within 239001 Al for revising the question to avoid the overlap; replaced with Al.07.

212 201002 2.4.11 Had to replace original Question #5 (tied to 2.4.11) due to overlap with Operating Test. Had to re-select the Generic KA to accommodate a new question. Randomly re-selected; replaced with 2.1.23.

ES-401 BWR Examination Outline - NRC - SRO Form ES-401-1 Facility: Limerick Generating Station Date of Exam: Jan 23, 2015 SRO-Only Points Tier Group A2 G* Total

1. 3 4 7 Emergency&

Abnormal Plant 1----2_ __ 2 3 Evolutions Tier Totals 4 6 10 4 5 2.

Plant 2 2 3 Systems Tier Totals 2 6 8

3. Generic Knowledge and Abilities 2 3 4 7 Categories 2 2 2 Note: 1. Ensure that at least two topics from every applicable KJA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KJA 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 +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section 0.1 .b of ES-401 for guidance regarding the elimination of inappropriate KJA 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 KJAs having an importance rating (IA) 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 KJA categories.

7.* The generic (G) KJAs in Tiers 1 and 2 shall be selected from Section 2 of the KJA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KJAs.

8. On the following pages, enter the KJA numbers, a brief description of each topic, the topics' importance ratings (I Rs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the KJA catalog, and enter the KJA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KJAs that are linked to 10 CFR 55.43.

ES-401 BWR Examination Outline - NRC - SRO Form ES-401-1 BWR Examination Outline - SRO Form ES-401-1 Erner enc and Abnormal Plant Evolutions - Tier 1/Grou 1 SRO E/APE #I Name I Safety Function K K K A A G KIA Topic(s) IA #

1 2 3 1 2 295001 Partial or Complete Loss of Forced X 2.2.12 Knowledge of surveillance procedures. 4.1 81 L Core Flow Circulation / 1 & 4 295003 Partial or Complete Loss of AC I 6 295004 Partial or Total Loss of DC Pwr / 6 295005 Main Turbine Generator Trip I 3 x Ability to determine and/or interpret the following as 3.1 86 H they apply to MAIN TURBINE GENERA TOR TRIP:

AA2.03 Turbine valve position 295006 SCRAM / 1 x Ability to determine and/or interpret the following as 4.2 87 H they apply to SCRAM: AA2.03 Reactor water level 295016 Control Room Abandonment 17 295018 Partial or Total Loss of CCW I 8 X 2.4.30 Knowledge of events related to system 4.1 78H operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

295019 Partial or Total Loss of Inst. Air/ 8 295021 Loss of Shutdown Cooling/ 4 X 2.4.21 Knowledge of the parameters and logic used to 4.6 77 H assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

295023 Refueling Ace I 8 295024 High Drywall Pressure I 5 295025 High Reactor Pressure I 3 295026 Suppression Pool High Water Temp./ 5 295028 High Drywall Temperature I 5 295030 Low Suppression Pool Wtr Lvl / 5 X 2.2.40 Ability to apply Technical Specifications for a 4.7 79L system.

295031 Reactor Low Water Level I 2 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 295038 High Off-site Release Rate I 9 600000 Plant Fire On Site/ 8 700000 Generator Voltage and Electric Grid x Ability to determine and/or interpret the following as I 3.8 80 H Disturbances I 6 they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: AA2.05 Operational status of offsite circuit KIA Category Totals: 3 4 Group Point Total: 7

ES-401 BWR Examination Outline - NRC - SRO Form ES-401-1 ES-401 BWR Examination Outline - SRO Form ES-401-1 Erner enc and Abnormal Plant Evolutions - Tier 1/Grou 2 SRO E/APE #I Name I Safety Function K K K A A G KIA Topic(s) IR #

1 2 3 1 2 295002 Loss of Main Condenser Vac I 3 295007 Hi h Reactor Pressure I 3 295008 Hi h Reactor Water Level I 2 295009 Low Reactor Water Level I 2 295010 High Drywall Pressure I 5 X 2.1.25 Ability to interpret reference materials, such as 4.2 88 H ra hs, curves, tables, etc.

295012 Hi erature I 5 295013 Hi ression Pool Tern . I 5 295014 Inadvertent Reactivi Addition I 1 295015 lncom lete SCRAM I 1 Ability to determine and/or interpret the following as 295017 High Off-site Release Rate I 9 x they apply to mGH OFF-SITE RELEASE RATE: 4.2 89 L AA2.0l tOff-site release rate 295020 Inadvertent Cont. Isolation I 5 & 7 295022 Loss of CAD Pum s I 1 295032 High Secondary Containment Area Tern erature I 5 295033 High Secondary Containment Area Radiation Levels I 9 295034 Secondary Containment Ventilation Hi h Radiation I 9 295035 Secondary Containment High Differential Pressure I 5 295036 Secondary Containment High Sum /Area Water Level I 5 500000 Hi h CTMT H dro en Cone. I 5 X 2.4.6 Knowled e of EOP miti ation strate ies. 4.7 95 L KIA Cate o Point Totals: 2 Grou Point Total: 3

ES-401 BWR Examination Outline - NRC - SRO Form ES-401-1 ES-401 BWR Examination Outline - SRO Form ES-401-1 Plant S stems - Tier 2/Grou 1 SRO System # I Name K K K K K K A A A A G KIA Topic(s) IA #

1234561234 203000 RHR/LPCI: Injection Mode 205000 Shutdown Coolin 206000 HPCI 211000 SLC x 2.2.40 Ability to apply Technical Specifications for 4.7 82 H as stem.

212000 RPS x 2.2.22 Knowledge of limiting conditions for 4.7 90H 0 rations and safet limits.

215003 IRM 215004 Source Ran e Monitor 215005 APRM I LPRM 217000 RCIC 218000ADS 223002 PCIS/Nuclear Steam Su I Shutoff 239002 SRVs Ability to (a) predict the impacts of the following 259002 Reactor Water Level x on the REACTOR WATER LEVEL CONTROL 3.7 91 H Control SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or 0 rations: A2.03 Loss of reactor water level in ut 261000 SGTS 262001 AC Electrical Distribution 262002 UPS AC/DC 263000 DC Electrical Distribution x 2.4.41 Knowledge of the emergency action level 4.6 92L thresholds and classifications.

264000 EDGs 300000 Instrument Air x 2.4.11 Knowledge of abnormal condition 4.2 83L rocedures.

400000 Component Cooling Water KIA Cate o Point Totals: 4 Grau Point Total: 5

ES-401 BWR Examination Outline - NRC - SRO Form ES-401-1 ES-401 BWR Examination Outline - SRO Form ES-401-1 Plant S stems - Tier 2/Grou 2 SRO System # I Name KKKKKKAA AAG KIA Topic(s) IA #

12345612 34 201001 CRD H draulic 201002 RMCS 201003 Control Rod and Drive Mechanism x 4.7 94 L 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU X 2.2.38 Knowledge of conditions and limitations in 4.5 84 L the facilit license.

214000 RPIS 215001 Traversin In-core Probe 215002 RSM 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling Mode Ability to (a) predict the impacts of the following on 223001 Primary CTMT and Aux. x the PRIMARY CONTAINMENT SYSTEM AND 3.8 93 H AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or o rations: A2. IO Hi h d well tern rature 239001 Main and Reheat Steam 241000 Reactor/Turbine Pressure Re ulator 245000 Main Turbine Gen. I Aux.

256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 271000 Off as 272000 Radiation Monitorin 286000 Fire Protection 288000 Plant Ventilation 290001 Seconda CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals 2 Grou Point Total: 3

ES-401 BWR Examination Outline - NRC - SRO Form ES-401-3 Facili : Limerick Generatin Station Date of Exam: Jan 23, 2015 Category KIA# Topic SRO-On I IR #

2.1.42 Knowledge of new and spent fuel movement procedures. 3.4 85 L 1.

Conduct 2.1.1 Knowledge of conduct of operations requirements. 98L of Operations Subtotal 2 2.2.23 Ability to track Technical Specification limiting conditions for 76L o rations.

2. Knowledge of the process for managing maintenance activities 2.2.17 during power operations, such as risk assessments, work 99H Equipment prioritization, and coordination with the transmission system Control o rator.

Subtotal 2

3. Knowledge of radiation exposure limits under normal or 2.3.4 emer en conditions. 96L Radiation Control Subtotal Ability to take actions called for in the facility emergency plan, 2.4.38 including supporting or acting as emergency coordinator if 97L 4.

Emergency re uired.

Procedures I Knowledge of the emergency action level thresholds and 2.4.41 classifications. IOOL Plan Subtotal 2 Tier 3 Point Total 7

ES-401 BWR Examination Outline - NRC - SRO Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KlA 2/1 300000 2.1.20 Chief Examiner determined that original Question #83 was unsat due to overlap with SRO Cert Exam. Had to re-select Generic KA to accommodate a new question. Randomly re-selected; replaced by 2.4.11.

2/1 217000 A2.10 Chief Examiner requested that the total number of Tech Spec-related SRO questions be reduced by 1; recommended that Question

  1. 92 be considered for replacement because it also had a weak KA match. Agreed and replaced as requested. Had to randomly re-select the System and Category to accommodate a new question.

Replaced by 263000 2.4.41.

1/2 295014 2.1.37 Chief Examiner determined that original Question #95 lacked adequate Operational Validity. Agreed and replaced as suggested.

Had to randomly re-select the System and Category to accommodate a new question. Replaced by 500000 2.4.6.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Limerick Date of Examination: Jan 12-23. 2015 Examination Level: ROX SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note) Code*

Conduct of Operations R-M Evaluate Overtime Work Request (Generic 2.1.5)

RO 2.1-1 Conduct of Operations R-D Prepare Valve Stroke Data Sheet (Generic 2.1.7)

RO 2.1-2 Equipment Control Determine Blocking Required per OP-MA-109-101, R-N RO 2.2-1 "Clearance and Tagging" (Generic 2.2.13)

Radiation Control Determine Off gas Effluent Activity Release Rate R-D-P RO 2.3-1 (Generic 2.3.11)

Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank Cs 3 for ROs; .s 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (?. 1)

(P)revious 2 exams (.s 1; randomly selected)

ES 301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Limerick Date of Examination: Jan 12-23, 2015 Examination Level: RO SRO X Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note) Code*

Conduct of Operations Determination of Adequate Shift Staffing (SRO)

R-N SRO 2.1-1 (Generic 2.1.5)

Conduct of Operations Authorize a Reactor Maneuvering Shutdown Instruction R-M SRO 2.1-2 (RMSI) (Generic 2.1.37)

Equipment Control Review and Verify Blocking Required per OP-MA-109-R-N SRO 2.2-1 101, "Clearance and Tagging" (Generic 2.2.13)

Radiation Control Review and Approve Inventory Release from Equipment R-M-P Drain Sample Tank to Cooling Tower Slowdown Line SRO 2.3-1 (Generic 2.3.11)

Emergency Procedures/Plan ERP Upgrade Classification and Reporting (Time Critical)

R-D SRO 2.4-1 (Generic 2.4.41)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ($. 3 for ROs; .$. 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~ 1)

(P)revious 2 exams (.$. 1; randomly selected)

ES 301, Page 22 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Limerick Generating Station Date of Examination: Jan 12-23. 2015 Exam Level: RO X SRO-ID SRO-U D Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function

a. Start a Reactor Recirc Pump (202001 A3.02) A,D,S,P 1
b. Manually Place 3rd Reactor Feed Pump in Service (259001 A4.02) A,D,S,P 2
c. Open a Single Isolated MSIV (239001 A4.02) D,S 3
d. Operate Unit 1 RCIC in Full Flow Test (217000 A2.12) M,S 4
e. Perform a Group Ill NSSSS Isolation Reset (223002 A4.03) D,S 5
f. Supplying Power to a 480 VAC Non-Safeguard Load Center from its A,D,S 6 Alternate Source (262001 A4.05)
g. Place Alternate RECW Pump in Service (400000 A2.01) A,D,S 8
h. Manually Isolate the Reactor Enclosure (223002 A4.02) A,N,S,EN 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Maximizing CRD Flow After Shutdown During Emergency Conditions D, R, E, L, P 2 (295031 EA 1.10)
j. Install Air Jumper to Provide Long Term ADS Operation from D*1 D/G Air D,R,L 8 Compressor (218000 A2.03)
k. Drywell Spray Interlock Bypass (226001 A2.15) D,R,E,L 5

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank :59/:58/:54 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature - I - I ~1 (control room system)

(L)ow-Power I Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1(A) ~2/~2/~1 (P)revious 2 exams :5 3 I :5 3 I :5 2 (randomly selected)

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Limerick Generating Station Date of Examination: Jan 12-23, 2015 Exam Level: ROD SRO-IX SRO-U D Operating Test No.: 1 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function

a. Start a Reactor Recirc Pump (202001 A3.02) A,D,S,P 1
b. Manually Place 3rd Reactor Feed Pump in Service (259001 A4.02) A,D,S,P 2
c. Open a Single Isolated MSIV (239001 A4.02) D,S 3
d. Operate Unit 1 RCIC in Full Flow Test (217000 A2.12) M,S 4 e.
f. Supplying Power to a 480 VAC Non-Safeguard Load Center from its A,D,S 6 Alternate Source (262001 A4.05)
g. Place Alternate RECW Pump in Service (400000 A2.01) A,D,S 8
h. Manually Isolate the Reactor Enclosure (223002 A4.02) A,N,S,EN 9 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Maximizing CRD Flow After Shutdown During Emergency Conditions D, R, E, L, P 2 (295031 EA 1.10)
j. Install Air Jumper to Provide Long Term ADS Operation from D*1 D/G Air D,R,L 8 Compressor (218000 A2.03)
k. Drywell Spray Interlock Bypass (226001 A2.15) D,R,E,L 5

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank S9/S8/S4 (E)mergency or abnormal in-plant <!:1/<!:1/<!:1 (EN)gineered safety feature - I - I <!:1 (control room system)

(L)ow-Power I Shutdown <!:1/<!:1/<!:1 (N)ew or (M)odified from bank including 1(A) <!:2/<!:2/<!:1 (P)revious 2 exams s 3 Is 3 Is 2 (randomly selected)

(R)CA <!:1/<!:1/<!:1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Limerick Generating Station Date of Examination: Jan 12-23, 2015 Exam Level: RO D SR0-10 SRO-U X Operating Test No.: 1 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function

a. Start a Reactor Recirc Pump (202001 A3.02) A,D,S,P 1 b.

c.

d.

e.

f. Supplying Power to a 480 VAC Non-Safeguard Load Center from its A,D,S 6 Alternate Source (262001 A4.05) g.
h. Manually Isolate the Reactor Enclosure (223002 A4.02) A,N,EN,S 9 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Maximizing CAD Flow After Shutdown During Emergency Conditions D,R, E,L, P 2 (295031 EA 1.10) j.
k. Drywell Spray Interlock Bypass (226001 A2.15) D,R,E,L 5

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank S9/S8/S4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature - I - I ~1 (control room system)

(L)ow-Power I Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1(A) ~2/~2/~1 (P)revious 2 exams s 3 Is 3 Is 2 (randomly selected)

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

~ LIMERICK GENERATING STATION

,. w Exelon Generation SIMULATOR EVALUATION GUIDE Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: 2 Rev _o_ Op-Test No.:_1_

Examiners: Operators:

Initial Conditions:

Unit 1 Reactor Power is 90% due to '1 A' ASD cell failure Unit 2 Reactor Power is 100%

Turnover:

  • '1 A' ASD cell failure troubleshooting in progress

Pump Operability 2 MFW245A R-RO "1 B" RFP Trip C-PRO 3 MRD0161 C-RO Control Rod Drifts Out TS-SRO 4 MNS161B I-PRO Inadvertent NSSS ISOLATION TS-SRO MRR441 5

MRR440A LOCA, HPCI Aux Oil Pump Failure, Loss of Condensate, RCIC overspeed trip MHP447B M-ALL MCN001 MCN002 MRC466 6 MRD016G C-RO Failure of 3 (three) Control Rods to scram MDG420A C-PRO 7 011 Bus fails to auto swap on Dead BusTransfer, and failure MED011 of D 11 EOG to auto start MED015A I* (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor I SEG-4155E RevOOO.doc SRRS: 30.126 Page 2 of 61

Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: 3 Rev _o_ Op-Test No.:_1_.

Examiners: Operators:

Initial Conditions:

Unit 1 is at-1.fL% power with a startup in progress per GP-2. Unit 2 is at 100% power.

Turnover:

GP-2 is complete through step with the Main Generator synchronization just completed. The crew is expected to continue raising power per GP-2.

Event Malfunction Event Event No. Number Type* Description 1 N/A A-RO Continue raising power 2 MRD016D C-RO Control Rod fails stuck 113 A-3 127 H-4 C-PRO 3 '1C' Core Spray Pump suction leak (Abnormal)

Ll-42-150A TS-SRO Ll-42-1508 C-PRO 4 MED282A Loss of Div 1 DC (Abnormal)

TS-SRO 5 MRR441 C-PRO Small coolant leak in Drywell (Abnormal) 6 MRP029C C-RO RPS 'A' fails to scram (ARI successful}

7 MMS067 M Steam leak in the Drywell Downcomer break results in Suppression Pool pressure 8 MPC476 C-PRO equalizing with Drywell pressure requiring blowdown on Pressure Suppression Curve HS-51-F017D 9 C-PRO 'D' LPCI Valve handswitch fails Override 1* (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor I SEG-2158E RevOOO.doc Page 2 of 55

....., LIMERICK GENERATING STATION

~ Exelon Generation. SIMULATOR EVALUATION GUIDE Appendix D Scenario Outline Form ES-0-1 Facility: Limerick 1 & 2 Scenario No.: 4 Rev _o_ Op-Test No.: 1 Examiners: Operators:

Initial Conditions:

Unit 1 is at J.!§_% power for rod recovery following control rod maintenance. Refuel floor personnel are loading spent fuel into shipping casks Turnover:

The crew is expected to withdraw the 2 maintenance rods per the ReMA and restore power to 100% with Recirc flow.

Event Malfunction Event Event No. Number Type* Description 1 N/A R-RO Withdraw control rods and restore power to 100%

C-RO 2 MPR011B ABM 'B' fails INOP TS-SRO 3 VIM116A01 C-PRO '1A' EHC Pump vibrations MRE001A MRE311A C-PRO 4 Refuel Floor isolates with failure of SGTS MRE311B TS-SRO MRE311C MMS063D 5 MRD556 M MSIV closure with Hydraulic ATWS and SLC Line rupture MSL559 6 MRD024 C-RO RDCS fails MMT100 C-RO Turbine High Vibration requiring manual trip/Bypass Valves 7

MEH108 C-PRO fail closed

  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor SEG-6215E RevOOO.doc SRRS: 30.126 Page 2 of 41
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