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&

2 2

7 Abnormal Plant N/A N/A 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.

Note:

Generic Knowledge and Abilities 2

3 4

10

1.

Categories 2

3 2

3 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) Kl As 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 Kl As.

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 295001 Partial or Complete Loss of Forced 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 295006 SCRAM / 1 295016 Control Room Abandonment I 7 295018 Partial or Total Loss of CCW I 8 295019 Partial or Total Loss of Inst. Air/ 8 295021 Loss of Shutdown Coolin I 4 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 I 5 295031 Reactor Low Water Level I 2 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 K K K A A G 1 2 3

1 2 x

x x

x x

x x

x KIA Topic(s)

Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: AAI.07 Nuclear boiler instrumentation s stem Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: AK3.05 Reactor SCRAM Knowledge of the interrelations between PARTIAL OR LOSS OF D.C. POWER and the following:

AK2.03 D.C. bus loads Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP:

AA2.08 Electrical distribution status Knowledge of the interrelations between SCRAM and the followin : AK2.04 Turbine tri lo ic: Plant-S cific Ability to determine and/or interpret the following as they apply to CONTROL ROOM ABANDONMENT:

AA2.06 Cooldown rate Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER : AKl.01 Effects on component/system o rations Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the followin : AK2.03 Reactor feedwater X 2.4.11 Knowled e of abnormal condition rocedures.

x x

x x

x x

x Knowledge of the operational implications of the following concepts as they apply to REFUELING ACCIDENTS: AKI.03 Inadvertent criticalit Knowledge of the reasons for the following responses 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 X Technical S ecification action statements for s stems Ability to operate and/or monitor the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: EAI.03 Tern rature monitorin Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL TEMPERATURE: EK3.01 Erner enc de ressurization Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL: EA2.01 Su ression ool level Knowledge of the operational implications of the following concepts as they apply to REACTOR LOW WATER LEVEL: EKI.02 Natural circulation: Plant-s cific Knowledge of the interrelations between SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN and the followin : EK2.03 ARI/RPT/ATWS: Plant-S ecific IR 3.1 11 H 3.7 12 H 3.3 35 H 3.2 51 H 3.6 41 L 3.3 13 H 3.5 40L 3.2 58 H 4.0 52 L 3.7 53 L 3.7 61 L 3.9 14 L 3.9 59 H 3.6 39 L 4.1 62H 3.8 36L 4.1 38L

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 600000 Plant Fire On Site I 8 Knowledge of the interrelations between PLANT 2.6 15 L x

FIRE ON SITE and the following: AK2.01 Sensors I detectors and valves 700000 Generator Voltage and Electric Grid Knowledge of the reasons for the following responses I 3.6 16H x

as they apply to GENERATOR VOLTAGE AND 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 295002 Loss of Main Condenser Vac I 3 295007 High 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 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 295029 High Suppression Pool Wtr Lvl I 5 295032 High Secondary Containment Area Temperature 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 Sump/Area Water Level I 5 500000 Hi h CTMT H dro en Cone. I 5 KIA Cate o Point Totals:

K K K A A G 1

2 3

1 2

KIA Topic(s) x x

x 2.1.31 Ability to locate control room switches, controls, X

and indications, and to determine that they correctly reflect the desired !ant lineu

  • Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL PRESSURE: AKI.03 Tern rature increases Ability to operate and/or monitor the following as they apply to HIGH SUPPRESSION POOL WATER LEVEL: EAl.03 RHR/LPCI Ability to determine and/or interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE: EA2.02 ui ment o rabilit IA 4.6 17H 3.2

!SH 2.9 19H 3.3 20 L X 2.4.1 Knowledge ofEOP entry conditions and immediate 4.6 34 L x

x action ste s.

Knowledge of the reasons for the following responses as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: EK3.01 Blow-out panel o ration: Plant-S cific Knowledge of the interrelations between SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL and the following: EK2.01 Secondary Containment e ui ment and floor drain s stem 2

Grou Point Total:

2.8 60H 3.1 64 L 7

ES-401 ES-401 System # I Name 203000 RHR/LPCI: Injection Mode 205000 Shutdown Cooling 206000 HPCI 209001 LPCS 209002HPCS 211000 SLC 212000 RPS 215003 IRM 215004 Source Range Monitor 215005 APRM I LPRM 217000 RCIC 218000 ADS 4

Form ES-401-1 BWR Examination Outline - RO Plant S stems - Tier 2/Grou 1 RO Form ES-401-1 K K K K K K A A A A G 1 2 3 4 5 6 1 2 3 4 x

KIA Topic(s)

Knowledge of the operational implications of the following concepts as they apply to RHR/LPCI: INJECTION MODE (PLANT SPECIFIC): K5.0l Testable check valve o ration 2.1.20 Ability to interpret and execute X

rocedure ste s.

x x

x x

x x

x x

x x

Ability to manually operate and/or monitor in the control room: A4.07 Reactor tern ratures Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM; and (b) based on those predictions, use procedures to 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 cause-effect relationships between LOW PRESSURE CORE SPRAY SYSTEM and the followin

SYSTEM includin2: A3.03 RPS status Knowledge of the effect that a loss or malfunction of the following will have on the SOURCE RANGE MONITOR (SRM)

SYSTEM: K6.04 Detectors Ability to monitor automatic operations of the AVERAGE POWER RANGE MONITOR I LOCAL POWER RANGE MONITOR SYSTEM includin2: A3.03 Meters and recorders Knowledge of the effect that a loss or malfunction of the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) will have on followin2: K3.02 Reactor vessel oressure Knowledge of the physical connections and/or cause-effect relationships between AUTOMATIC DEPRESSURIZA TION SYSTEM and the following: Kl.06 Safety/relief valves IR 2.7 28 H 4.6 71 H 3.7 42H 3.9 43H 4.0 3L 4.0 7H 3.7 21 L 2.9 26H 3.3 37 H 3.6 22H 3.9 4H

Knowledge of the physical connections and/or 3.1 8H 223002 PCIS/Nuclear Steam x

cause-effect relationships between PRIMARY 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 3.1 29L 259002 Reactor Water Level x

CONTROL SYSTEM design feature(s) and/or 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 3.1 23 H 262001 AC Electrical x

the following concepts as they apply to A.C.

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 262002 UPS (AC/DC)

UNINTERRUPTABLE POWER SUPPLY (A.CJD.C.) and the following: Kl.14 Main steam line radiation monitors Knowledge of the effect that a loss or 2.8 72L x

malfunction of the following will have on the UNINTERRUPT ABLE POWER SUPPLY (A.CJD.C.): K6.02 D.C. electrical power Knowledge of the operational implications of 2.6 9L x

the following concepts as they apply to D.C.

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 ES-401 System # I Name K

K K

K 1

2 3

4 201001 CAD Hydraulic x

201002 RMCS 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 215001 Traversin In-core Probe 215002 ABM 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling x

Mode 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

234000 Fuel Handling Equipment 5

Form ES-401-1 BWR Examination Outline - RO Plant S stems - Tier 2/Grou 2 RO K

K A

A A A G KIA Topic(s) 5 6

1 2

3 4

Knowledge of electrical power supplies to the following: K2.05 Alternate rod insertion valve solenoids: Plant-S cific x 2.1.23 Ability to perform specific system and integrated plant procedures during I all modes of !ant o ration.

x Ability to (a) predict the impacts of the following on the ROD WORTH 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 x

Ability to monitor automatic operations of the RECIRCULATION FLOW CONTROL SYSTEM including: A3.02 Li hts and alarms x

Knowledge of the operational implications of the following concepts as they apply to ROD POSITION INFORMATION SYSTEM: K5.0l Reed switches 219000 RHR/LPCI: Torus/Pool Cooling Knowledge of RHR/LPCI: TORUS I SUPPRESSION POOL COOLING MODE design feature(s) and/or interlocks which provide for the following: K4.05 Pum minimum flow rotection Knowledge of the effect that a loss or malfunction of the FUEL POOL COOLING AND CLEAN-UP will have on followin : K3.03 Fuel ool water clarit x

Ability to predict and/or monitor changes in parameters associated with operating the FUEL HANDLING EQUIPMENT controls including: Al.03 core reactivity level Form ES-401-1 IR 4.5 46H 4.3 SL 3.1 70H 3.4 47 L 2.7 67H 3.0 68H 2.6 48H 3.4 JOH

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 REGULA TING 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

2.

2.2.14 Knowledge of the process for controlling equipment configuration 3.9 74L or status.

Equipment Control Subtotal 3

2.3.11 Ability to control radiation releases.

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

3.

Subtotal 2

Radiation Control 2.4.27 Knowledge of "fire in the plant" procedures.

3.4 33 L 2.4.8 Knowledge of how abnormal operating procedures are used in 3.8 57 L

4.

co unction with EOPs.

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 Kl As - RO Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected Kl A 2 I 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.

1 I 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)

DW IT 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 Systems 2

Tier Totals 2

3 2

6 8

3. Generic Knowledge and Abilities Categories 2

3 4

7 Note:

1.

2 2

2 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, I Rs, 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 295001 Partial or Complete Loss of Forced 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 295006 SCRAM / 1 295016 Control Room Abandonment 17 295018 Partial or Total Loss of CCW I 8 295019 Partial or Total Loss of Inst. Air/ 8 295021 Loss of Shutdown Cooling/ 4 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 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 Disturbances I 6 KIA Category Totals:

K K K A A G 1 2 3

1 2 KIA Topic(s)

X 2.2.12 Knowledge of surveillance procedures.

IA 4.1 81 L x

Ability to determine and/or interpret the following as 3.1 86 H x

x they apply to MAIN TURBINE GENERA TOR TRIP:

AA2.03 Turbine valve position Ability to determine and/or interpret the following as 4.2 87 H they apply to SCRAM: AA2.03 Reactor water level X 2.4.30 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

X 2.4.21 Knowledge of the parameters and logic used to 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.

X 2.2.40 Ability to apply Technical Specifications for a system.

4.1 78H 4.6 77 H 4.7 79L Ability to determine and/or interpret the following as I 3.8 80 H they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: AA2.05 Operational status of offsite circuit 3

4 Group Point Total:

7

ES-401 BWR Examination Outline - NRC - SRO Form ES-401-1 ES-401 BWR Examination Outline - SRO Erner enc and Abnormal Plant Evolutions - Tier 1/Grou 2 SRO E/APE #I Name I Safety Function 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 295012 Hi erature I 5 295013 Hi ression Pool Tern. I 5 295014 Inadvertent Reactivi Addition I 1 295015 lncom lete SCRAM I 1 295017 High Off-site Release Rate I 9 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 KIA Cate o Point Totals:

K K

K A A

G 1

2 3

1 2 KIA Topic(s) x X 2.1.25 Ability to interpret reference materials, such as ra hs, curves, tables, etc.

Ability to determine and/or interpret the following as they apply to mGH OFF-SITE RELEASE RATE:

AA2.0l tOff-site release rate X 2.4.6 Knowled e of EOP miti ation strate ies.

2 Grou Point Total:

Form ES-401-1 IR 4.2 88 H 4.2 89 L 4.7 95 L 3

ES-401 ES-401 System # I Name 203000 RHR/LPCI: Injection Mode 205000 Shutdown Coolin 206000 HPCI 211000 SLC 212000 RPS 215003 IRM 215004 Source Ran e Monitor 215005 APRM I LPRM 217000 RCIC 218000ADS 223002 PCIS/Nuclear Steam Su I Shutoff 239002 SRVs 259002 Reactor Water Level Control 261000 SGTS 262001 AC Electrical Distribution 262002 UPS AC/DC 263000 DC Electrical Distribution 264000 EDGs 300000 Instrument Air 400000 Component Cooling Water KIA Cate o Point Totals:

BWR Examination Outline - NRC - SRO Form ES-401-1 BWR Examination Outline - SRO Plant S stems - Tier 2/Grou 1 SRO Form ES-401-1 K K K K K K A A A A G 1234561234 x

x x

x x

4 KIA Topic(s) 2.2.40 Ability to apply Technical Specifications for as stem.

2.2.22 Knowledge of limiting conditions for 0

rations and safet limits.

Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL 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 2.4.41 Knowledge of the emergency action level thresholds and classifications.

2.4.11 Knowledge of abnormal condition rocedures.

Grau Point Total:

IA 4.7 82 H 4.7 90H 3.7 91 H 4.6 92L 4.2 83L 5

ES-401 ES-401 System # I Name 201001 CRD H draulic 201002 RMCS 201003 Control Rod and Drive Mechanism 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 215001 Traversin In-core Probe 215002 RSM 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.

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 BWR Examination Outline - NRC - SRO Form ES-401-1 BWR Examination Outline - SRO Plant S stems - Tier 2/Grou 2 SRO KKKKKKAA AAG KIA Topic(s) 12345612 34 x

x X

2.2.38 Knowledge of conditions and limitations in the facilit license.

Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND 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 2

Grou Point Total:

Form ES-401-1 IA 4.7 94 L 4.5 84 L 3.8 93 H 3

ES-401 BWR Examination Outline - NRC - SRO Facili : Limerick Generatin Station Date of Exam: Jan 23, 2015 Category

1.

Conduct of Operations

2.

Equipment Control

3.

Radiation Control

4.

Emergency Procedures I Plan Tier 3 Point Total KIA#

2.1.42 2.1.1 Subtotal 2.2.23 2.2.17 Subtotal 2.3.4 Subtotal 2.4.38 2.4.41 Subtotal Topic Knowledge of new and spent fuel movement procedures.

Knowledge of conduct of operations requirements.

Ability to track Technical Specification limiting conditions for o rations.

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

Knowledge of radiation exposure limits under normal or emer en conditions.

Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if re uired.

Knowledge of the emergency action level thresholds and classifications.

Form ES-401-3 SRO-On I IR 3.4 85 L 98L 2

76L 99H 2

96L 97L IOOL 2

7

ES-401 BWR Examination Outline - NRC - SRO Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected Kl A 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 R-N Determine Blocking Required per OP-MA-109-101, 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 R-N Determination of Adequate Shift Staffing (SRO)

SRO 2.1-1 (Generic 2.1.5)

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

Equipment Control R-N Review and Verify Blocking Required per OP-MA-109-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 R-D ERP Upgrade Classification and Reporting (Time Critical)

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 V AC 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 V AC 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 V AC 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 Perform RT-6-019-310-1, REACTOR FEEDPUMP TURBINE LUBE OIL PUMP OPERABILITY Event Malfunction Event Event No.

Number Type*

Description 1

N/A N-PRO Perform RT-6-019-310-1 Reactor Feedpump Turbine Lube Oil 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 5

MRR441 MRR440A LOCA, HPCI Aux Oil Pump Failure, Loss of Condensate, MHP447B RCIC overspeed trip MCN001 M-ALL MCN002 MRC466 6

MRD016G C-RO Failure of 3 (three) Control Rods to scram 7

MDG420A C-PRO 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

Ll-42-150A

'1C' Core Spray Pump suction leak (Abnormal)

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 9

HS-51-F017D 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 1 00%

2 MPR011B C-RO ABM 'B' fails INOP TS-SRO 3

VIM116A01 C-PRO

'1A' EHC Pump vibrations MRE001A 4

MRE311A C-PRO 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 7

MMT100 C-RO Turbine High Vibration requiring manual trip/Bypass Valves 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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