ML21050A119

Final Written Examination and Operating Test Outlines (Folder 3)

ML21050A119
Person / Time
Site:	Limerick
Issue date:	02/19/2021
From:	Byers T Exelon Nuclear Generation Corp
To:	Brian Fuller Operations Branch I
Shared Package
ML19098B511	List: ML21043A207 ML21043A220 ML21050A084 ML21050A119 ML22025A372
References
CAC 000500
Download: ML21050A119 (20)

Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Limerick Date of Examination: 12/02/19 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic (see Note) Type Describe activity to be performed Code*

G2.1.7 (Ability to evaluate plant performance and make operational judgments based on Conduct of Operations operating characteristics, reactor behavior, and R, M instrument interpretation. IMPORTANCE RO 4.4 / SRO 4.7) Administrative Actions on a Thermal Limit Violation (LOJPM6732)

G2.1.25 (Ability to interpret reference materials, Conduct of Operations such as graphs, curves, tables, etc.

R, N IMPORTANCE RO 3.9 / SRO 4.2) Loss of MCR Annunciators (LOJPM6730)

G2.2.37 (Ability to determine operability and/or Equipment Control availability of safety related equipment.

R, N IMPORTANCE RO 3.6 / SRO 4.6) Evaluate Jet Pump Operability (LOJPM6731)

G2.3.14 (Knowledge of radiation or contamination hazards that may arise during Radiation Control R, D normal, abnormal, or emergency conditions or activities, IMPORTANCE RO 3.4) Radioactive Substance Spill (LOJPM3122)

Emergency Plan NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

(P)revious 2 exams ( 1, randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Limerick Date of Examination: 12/02/19 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic (see Note) Type Describe activity to be performed Code*

G2.1.7 (Ability to evaluate plant performance and make operational judgments based on Conduct of Operations operating characteristics, reactor behavior, and R, M instrument interpretation. IMPORTANCE RO 4.4 / SRO 4.7) Administrative Actions on a Thermal Limit Violation (LOJPM6732)

G2.1.25 (Ability to interpret reference materials, Conduct of Operations such as graphs, curves, tables, etc.

R, N IMPORTANCE RO 3.9 / SRO 4.2) Loss of MCR Annunciators (LOJPM6730)

G2.2.37 (Ability to determine operability and/or Equipment Control availability of safety related equipment.

R, N IMPORTANCE RO 3.6 / SRO 4.6) Evaluate Jet Pump Operability (LOJPM6731)

G2.3.14 (Knowledge of radiation or contamination hazards that may arise during Radiation Control normal, abnormal, or emergency conditions or R, D activities, IMPORTANCE SRO 3.8)

Transportation Accident Involving Radioactive Material (LOJPM6123)

G2.4.41 (Knowledge of the emergency action Emergency Plan N, S level thresholds and classifications.

IMPORTANCE SRO 4.6) ERP Classification and Reporting (Time Critical) (LOJPM3143)

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

(P)revious 2 exams ( 1, randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Limerick Date of Examination: 12/02/19 Exam Level: RO SRO-I SRO-U Operating Test Number: 1 Control Room Systems: 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U Safety System/JPM Title Type Code* Function

a. Resetting ASD Speed Hold (System 202002 - Recirculation Flow Control A, D, S 1 - Reactivity System, A1.01; 3.6)(LOJPM3529) Control

b. Correct FWLCS Feed Flow Error (System 259002 - Reactor Water Level Control N, S 2 - Rx Water System, A2.02; 3.3) (LOJPM3157) Inventory Control

c. Main Turbine Bypass Valve Exercising (System 241000 - Reactor / Turbine D, S 3 - Reactor Pressure Regulating System; A4.06; 3.9)(LOJPM3083) Pressure Control

d. HPCI Manual Slow Start (System 206000 - High Pressure Coolant Injection A, D, EN, S 4 - Heat Removal System; A4.12; 4.0) (LOJPM3522) From Core

e. Perform a Unit 1 Group 2A NSSSS Isolation Reset (System 223002 - Primary D, EN, L, S 5 - Containment Containment Isolation System/ NSSSS; A4.03; 3.6)(LOJPM3071) Integrity

f. Shutdown the D11 Diesel Generator (System 264000 - Emergency Generators; D, EN, S 6 - Electrical A4.04; 3.7)(LOJPM3027)

g. Transfer RHRSW from Bypass to Spray (System 400000 - Component Cooling EN, N, S 8 - Plant Service Water System (CCWS), A4.01; 3.1) (LOJPM3158) Systems

h. Swap of in service RERS Fans (System 288000 - Plant Ventilation Systems, A, EN, N, S 9 - Radioactivity A4.01; 3.1) (LOJPM3156) Release In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. HPCI / RCIC High Area Temperature Isolation Bypass (System - 206000, HPCI 2 - Rx Water D, E, R System/ 217000 RCIC System; A2.10 / A2.15; 4.0 / 3.8) (LOJPM2263) Inventory Control

j. T-363, Vent Main Generator During ELAP (System 295003 - Abnormal Plant D, E, L, R 6 - Electrical Evolutions; AK2.06; 3.4) (LOJPM2271)

k. Start ESW Pump Per SE-1 (System 400000 - Component Cooling Water A, D, E, L, R 8 - Plant Service System (CCWS), A2.01; 3.1/3.2) (LOJPM2258) Systems

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

• Type Codes Criteria for R /SRO-I/SRO-U (A)lternate path 4-6/4-6 /2-3 4 (C)ontrol room (D)irect from bank 9/ 8/ 4 8 (E)mergency or abnormal in-plant 1/ 1/ 1 3 (EN)gineered safety feature 1/ 1/ 1 (control room system) 5 (L)ow-Power/Shutdown 1/ 1/ 1 3 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 3 (P)revious 2 exams 3/ 3/ 2 (randomly selected) 0 (R)CA 1/ 1/ 1 3 (S)imulator 8

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Limerick Date of Examination: 12/02/19 Exam Level: RO SRO-I SRO-U Operating Test Number: 1 Control Room Systems: 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code* Safety Function

a. Resetting ASD Speed Hold (System 202002 - Recirculation Flow Control A, D, S 1 - Reactivity System, A1.01; 3.6)(LOJPM3529) Control

b. Correct FWLCS Feed Flow Error (System 259002 - Reactor Water Level Control N, S 2 - Rx Water System, A2.02; 3.3) (LOJPM3157) Inventory Control

c. Main Turbine Bypass Valve Exercising (System 241000 - Reactor / Turbine D, S 3 - Reactor Pressure Regulating System; A4.06; 3.9)(LOJPM3083) Pressure Control

d. HPCI Manual Slow Start (System 206000 - High Pressure Coolant Injection A, D, EN, S 4 - Heat Removal System; A4.12; 4.0) (LOJPM3522) From Core

e. Perform a Unit 1 Group 2A NSSSS Isolation Reset (System 223002 - Primary D, EN, L, S 5 - Containment Containment Isolation System/ NSSSS; A4.03; 3.6)(LOJPM3071) Integrity

g. Transfer RHRSW from Bypass to Spray (System 400000 - Component Cooling EN, N, S 8 - Plant Service Water System (CCWS), A4.01; 3.1) (LOJPM3158) Systems

h. Swap of in service RERS Fans (System 288000 - Plant Ventilation Systems, A, EN, N, S 9 - Radioactivity A4.01; 3.1) (LOJPM3156) Release In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. HPCI / RCIC High Area Temperature Isolation Bypass (System - 206000, HPCI 2 - Rx Water D, E, R System/ 217000 RCIC System; A2.10 / A2.15; 4.0 / 3.8) (LOJPM22363) Inventory Control

j. T-363, Vent Main Generator During ELAP (System 295003 - Abnormal Plant D, E, L, R 6 - Electrical Evolutions; AK2.06; 3.4) (LOJPM2271)

k. Start ESW Pump Per SE-1 (System 400000 - Component Cooling Water A, D, E, L, R 8 - Plant Service System (CCWS), A2.01; 3.1/3.2) (LOJPM2258) Systems

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

• Type Codes Criteria for R /SRO-I/SRO-U (A)lternate path 4-6/4-6 /2-3 4 (C)ontrol room (D)irect from bank 9/ 8/ 4 7 (E)mergency or abnormal in-plant 1/ 1/ 1 3 (EN)gineered safety feature 1/ 1/ 1 (control room system) 4 (L)ow-Power/Shutdown 1/ 1/ 1 3 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 3 (P)revious 2 exams 3/ 3/ 2 (randomly selected) 0 (R)CA 1/ 1/ 1 3 (S)imulator 7

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Limerick Date of Examination: 12/02/19 Exam Level: RO SRO-I SRO-U Operating Test Number: 1 Control Room Systems: 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code* Safety Function

a. Resetting ASD Speed Hold (System 202002 - Recirculation Flow Control A, D, S 1 - Reactivity System, A1.01; 3.6)(LOJPM3529) Control

h. Swap of in service RERS Fans (System 288000 - Plant Ventilation Systems, A, EN, N, S 9 - Radioactivity A4.01; 3.1) (LOJPM3156) Release In-Plant Systems: 3 for RO, for SRO-I, and 3 or 2 for SRO-U

i. HPCI / RCIC High Area Temperature Isolation Bypass (System - 206000, HPCI 2 - Rx Water D, E, R Inventory Control System/ 217000 RCIC System; A2.10 / A2.15; 4.0 / 3.8) (LOJPM22363)

j. T-363, Vent Main Generator During ELAP (System 295003 - Abnormal Plant D, E, L, R 6 - Electrical Evolutions; AK2.06; 3.4) (LOJPM2271)

k. Start ESW Pump Per SE-1 (System 400000 - Component Cooling Water A, D, E L, R 8 - Plant Service System (CCWS), A2.01; 3.1/3.2) (LOJPM2258) Systems

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

• Type Codes Criteria for R /SRO-I/SRO-U (A)lternate path 4-6/4-6 /2-3 3 (C)ontrol room (D)irect from bank 9/ 8/ 4 4 (E)mergency or abnormal in-plant 1/ 1/ 1 3 (EN)gineered safety feature 1/ 1/ 1 (control room system) 1 (L)ow-Power/Shutdown 1/ 1/ 1 2 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 1 (P)revious 2 exams 3/ 3/ 2 (randomly selected) 0 (R)CA 1/ 1/ 1 3 (S)imulator 2

Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: SEG-4056E Rev 3 Op-Test No.: 1 .

Examiners: Operators:

Initial Conditions: Unit 1 is at 5 % power with a startup in progress. Unit 2 is at 100% power.

Turnover: Startup is in progress per GP-2. Crew is to continue withdrawing control rods IAW rod move sheet until 1 Bypass Valve full open in preparation to enter OPCON 1.

Critical Tasks:

1. Inhibit Auto ADS

2. Perform Emergency Blowdown per T-112 Event Malfunction Event Event No. Number Type* Description 1 N/A R-RO Withdraw control rods to raise power 2 MRD016D C-RO Control Rod (50-35) stuck MPC482B '1B' Drywell Chiller trip with both DW H fans C-PRO tripping 3 MPC471H TS-SRO MPC472H C-PRO 4 MNS160A Inadvertent Group 7 isolation TS-SRO 5 MMC074 C-RO Loss of Main Condenser Vacuum Grid Instability Resulting in Loss of Offsite 6 MED261 M-All Power 7 MHP447B C-PRO HPCI Aux Oil Pump Trips 8 MDG420C C-PRO D13 Diesel Auto Start Failure (Recoverable) 9 MRR440A M-All LOCA RCIC Turbine trip on overspeed 10 MRC466 C-PRO (Recoverable after RPV Level reaches -100)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: SEG-4159E Rev 000 Op-Test No.: 1 .

Examiners: Operators:

Initial Conditions:

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

Turnover: Maintain 100% Power Critical Tasks:

1. Inhibit Auto ADS

2. Perform Emergency Blowdown per T-112 Event Malfunction Event Event No. Number Type* Description 1 MFW248A C-RO Inadvertent opening of 1A RFP min flow valve C-RO 2 MHP450 C-PRO Inadvertent HPCI Start Up TS-SRO R-RO 3 VIM105A06-A09 C-PRO Rising vibration on the 1A Reactor Recirculation TS-SRO Pump requiring shutdown 4 MMC548 C-PRO Condensate Pump Discharge Header Rupture 5 MMC548 M-ALL Loss of all condensate and feedwater pumps 6 MHP446B C-PRO HPCI fails to un-isolate 7 MRR440 C-PRO Coolant Leak into Drywell 8 MCS183A C-PRO '1A' Core Spray Pump fails to auto start

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: SEG-6213E Rev 3 Op-Test No.: 1 .

Examiners: Operators:

Initial Conditions:

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

Turnover:

Crew is required to swap the lube oil pumps for the 1B RFPT from the 1B1 to 1B2 for CMO Base line data collection. __________________

Critical Tasks:

1. Manually Scram the Reactor

2. Insert Control Rods Manually

3. Perform Emergency Blowdown per T-112 Event Malfunction Event Event No. Number Type* Description 1 N/A N-PRO Swap 1B RFP Lube Oil Pumps (S39.6.C)

MVIC108C R-RO 2 MCN601C C-PRO 1C Cond PP vibes with ASD failure to Runback MRR507B 3 MMS063A C-RO Closure of Inboard MSIV A 4 MRP406A TS-SRO Loss of power to Div I RRCS C-PRO 5 MED263A TS-SRO D11 Bus Lockout - Start C ESW pp or secure D11 EDG MRC465 Steam Leak into RCIC room requiring reactor Shutdown 6 MRD556 C-RO with 3 control rods failure to Scram MRC465 RCIC steam leak with failure to auto isolate results in MSO 7 MRC464A M-ALL exceeded in 2 areas MRC464B 1B Reactor Feed Pump Turbine High Pressure steam 8 MFW245B C-RO supply fails closed

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: SEG-7017E Rev 000 Op-Test No.: _1___

Examiners: Operators:

Initial Conditions:

Unit 1 100% power. Unit 2 100% power.

Turnover: Maintain 100%.

Critical Tasks:

1. Inhibit Automatic ADS

2. Terminate and prevent injection per T-270 - First Lowering

3. Terminate and prevent injection per T-270 - Second Lowering

4. Implement T-215

5. Close the stuck open main steam safety relief valve Event Malfunction Event Event No. Number Type* Description C-PRO 1 118 I-5 Loss of Iso-Phase Bus Cooling R-RO MCW481A 1A TECW Pump trip 2 C-PRO MCW486B 1B TECW fails to auto start MHP001 C-PRO 3 MFP001 Fire in HPCI with failure of Fire Pumps to Auto Start MFP002 TS-SRO C-RO 4 MRD016I Control Rod Drifts Out TS-SRO 5 MPR003B C-RO Core Power Oscillations MRP029D ATWS 6 MSL559 M-ALL The ATWS is mitigated by the insertion of control rods via MRP407C T-215.

7 MRD024 C-RO RDCS Inoperative after reactor shutdown MAD140C C-PRO 1D SRV fails open (electrical) 8 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

ES-401 1 Form ES-401-1 Facility: Limerick Generating Station Units 1 and 2 Date of Exam: December 2019 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 3 3 3 4 4 3 20 4 3 7 Emergency and N/A N/A 2 1 1 1 1 1 2 7 1 2 3 Abnormal Plant Evolutions Tier Totals 4 4 4 5 5 5 27 5 5 10 1 2 1 3 3 3 3 2 3 2 1 3 26 3 2 5 2.

Plant 2 1 1 1 1 1 1 1 2 1 1 1 12 0 2 1 3 Systems Tier Totals 3 2 4 4 4 4 3 5 3 2 4 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)

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 outline. Systems or evolutions that do not apply at the facility should be deleted with justification. Operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A 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 K/As having an importance rating (IR) of 2.5 or higher. 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 K/A categories.

7. The generic (G) 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. Refer to Section D.1.b of ES-401 for the applicable K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics IRs for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel-handling equipment is sampled in a category 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 K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

G* Generic K/As

• These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.

• • These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.

ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

AA2.06 Ability to determine and/or interpret 295001 (APE 1) Partial or Complete Loss of X the following as they apply to PARTIAL OR 3.3 76 Forced Core Flow Circulation / 1 & 4 COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: Nuclear boiler instrumentation G2.2.38 Knowledge of conditions and 295026 (EPE 3) Suppression Pool High Water X limitations in the facility license. 4.5 77 Temperature / 5 AA2.03 Ability to determine and/or interpret 295018 (APE 18) Partial or Complete Loss of X the following as they apply to PARTIAL OR 3.5 78 CCW / 8 COMPLETE LOSS OF COMPONENT COOLING WATER:

Cause for partial or complete loss G2.2.12 Knowledge of surveillance 295038 (EPE 15) High Offsite Radioactivity X procedures. 4.1 79 Release Rate / 9 AA2.04 Ability to determine and/or interpret 295021 (APE 21) Loss of Shutdown Cooling / X the following as they apply to LOSS OF 3.6 80 4 SHUTDOWN COOLING:

Reactor water temperature G2.4.45 Ability to prioritize and interpret the 295024 High Drywell Pressure / 5 X significance of each annunciator or alarm. 4.3 81 EA2.02 Ability to determine and/or interpret 295031 (EPE 8) Reactor Low Water Level / 2 X the following as they apply to REACTOR 4.2 82 LOW WATER LEVEL: Reactor power AA1.02 Ability to operate and/or monitor the 295001 (APE 1) Partial or Complete Loss of X following as they apply to PARTIAL OR 3.3 1 Forced Core Flow Circulation / 1 & 4 COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: RPS AA2.04 Ability to determine and/or interpret 295003 (APE 3) Partial or Complete Loss of X the following as they apply to PARTIAL OR 3.7 2 AC Power / 6 COMPLETE LOSS OF A.C. POWER:

System lineups G2.1.7 Ability to evaluate plant performance 295004 (APE 4) Partial or Total Loss of DC X and make operational judgments based on 4.4 3 Power / 6 operating characteristics, reactor behavior, and instrument interpretation AK1.01 Knowledge of the operational 295005 (APE 5) Main Turbine Generator Trip / X implications of the following concepts as 4.0 4 3 they apply to MAIN TURBINE GENERATOR TRIP: Pressure effects on reactor power AK2.02 Knowledge of the interrelations 295006 (APE 6) Scram / 1 X between SCRAM and the following: Reactor 3.8 5 water level control system AK3.01 Knowledge of the reasons for the 295016 (APE 16) Control Room Abandonment X following responses as they apply to 4.1 6

/7 CONTROL ROOM ABANDONMENT:

Reactor SCRAM AA1.02 Ability to operate and/or monitor the 295018 (APE 18) Partial or Complete Loss of X following as they apply to PARTIAL OR 3.3 7 CCW / 8 COMPLETE LOSS OF COMPONENT COOLING WATER: System loads AA2.02 Ability to determine and/or interpret 295019 (APE 19) Partial or Complete Loss of X the following as they apply to PARTIAL OR 3.6 8 Instrument Air / 8 COMPLETE LOSS OF INSTRUMENT AIR:

Status of safety-related instrument air system loads G2.4.35 Knowledge of local auxiliary 295021 (APE 21) Loss of Shutdown Cooling / X operator tasks during an emergency and the 3.8 9 4 resultant operational effects.

ES-401 3 Form ES-401-1 AK1.03 Knowledge of the operational 295023 (APE 23) Refueling Accidents / 8 X implications of the following concepts as 3.7 10 they apply to REFUELING ACCIDENTS:

Inadvertent criticality EK2.11 Knowledge of the interrelations 295024 High Drywell Pressure / 5 X between HIGH DRYWELL PRESSURE and 4.2 11 the following: Drywell spray (RHR) logic:

Mark-I&II EK3.05 Knowledge of the reasons for the 295025 (EPE 2) High Reactor Pressure / 3 X following responses as they apply to HIGH 3.6 12 REACTOR PRESSURE: RCIC operation:

Plant-Specific EA1.03 Ability to operate and/or monitor the 295026 (EPE 3) Suppression Pool High Water X following as they apply to SUPPRESSION 3.9 13 Temperature / 5 POOL HIGH WATER TEMPERATURE:

Temperature monitoring EA2.06 Ability to determine and/or interpret 295028 (EPE 5) High Drywell Temperature X the following as they apply to HIGH 3.4 14 (Mark I and Mark II only) / 5 DRYWELL TEMPERATURE:

Torus/suppression chamber air space temperature: Plant-Specific G2.2.44 Ability to interpret control room 295030 (EPE 7) Low Suppression Pool Water X indications to verify the status and operation 4.2 15 Level / 5 of a system, and understand how operator actions and directives affect plant and system conditions.

EK1.03 Knowledge of the operational 295031 (EPE 8) Reactor Low Water Level / 2 X implications of the following concepts as 3.7 16 they apply to REACTOR LOW WATER LEVEL: Water level effects on reactor power EK2.02 Knowledge of the interrelations 295037 (EPE 14) Scram Condition Present X between SCRAM CONDITION PRESENT 4.0 17 and Reactor Power Above APRM Downscale AND REACTOR POWER ABOVE APRM or Unknown / 1 DOWNSCALE OR UNKNOWN and the following: RRCS: Plant-Specific EK3.02 Knowledge of the reasons for the 295038 (EPE 15) High Offsite Radioactivity X following responses as they apply to HIGH 3.9 18 Release Rate / 9 OFF-SITE RELEASE RATE: System isolations AA1.09 Ability to operate and / or monitor 600000 (APE 24) Plant Fire On Site / 8 X the following as they apply to PLANT FIRE 2.5 19 ON SITE: Plant fire zone panel (including detector location)

AA2.08 Ability to determine and/or interpret 700000 (APE 25) Generator Voltage and X the following as they apply to GENERATOR 4.3 20 Electric Grid Disturbances / 6 VOLTAGE AND ELECTRIC GRID DISTURBANCES: Criteria to trip the turbine or reactor K/A Category Totals: 3 3 3 4 4/ 3/ Group Point Total: 20 / 7 4 3

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

G2.2.25 Knowledge of the bases in 295012 (APE 12) High Drywell Temperature / X Technical Specifications for limiting 4.2 83 5 conditions for operations and safety limits.

AA2.01 Ability to determine and/or interpret 295022 (APE 22) Loss of Control Rod Drive X the following as they apply to LOSS OF 3.6 84 Pumps / 1 CRD PUMPS : Accumulator pressure 2.1.32 Ability to explain and apply system 295032 (EPE 9) High Secondary Containment X limits and precautions. 4.0 85 Area Temperature / 5 G2.1.25 Ability to interpret reference 295002 (APE 2) Loss of Main Condenser X materials, such as graphs, curves, tables, 3.9 21 Vacuum / 3 etc.

AK1.03 Knowledge of the operational 295007 (APE 7) High Reactor Pressure / 3 X implications of the following concepts as 3.8 22 they apply to HIGH REACTOR PRESSURE: Pressure effects on reactor power AK2.09 Knowledge of the interrelations 295014 (APE 14) Inadvertent Reactivity X between INADVERTENT REACTIVITY 3.4 23 Addition / 1 ADDITION and the following: Rod control and information system: Plant-Specific AK3.01 Knowledge of the reasons for the 295015 (APE 15) Incomplete Scram / 1 X following responses as they apply to 3.4 24 INCOMPLETE SCRAM : Bypassing rod insertion blocks EA1.01 Ability to operate and/or monitor 295033 (EPE 10) High Secondary X the following as they apply to HIGH 3.9 25 Containment Area Radiation Levels / 9 SECONDARY CONTAINMENT AREA RADIATION LEVELS: Area radiation monitoring system EA2.02 Ability to determine and/or interpret 295035 (EPE 12) Secondary Containment X the following as they apply to 2.8 26 High Differential Pressure / 5 SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: Off-site release rate: Plant-Specific G2.4.50 Ability to verify system alarm 295036 (EPE 13) Secondary Containment X setpoints and operate controls identified in 4.2 27 High Sump/Area Water Level / 5 l the alarm response manual.

K/A Category Point Totals: 1 1 1 1 1/ 2/ Group Point Total: 7/3 1 2

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 1 (RO/SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

203000 (SF2, SF4 RHR/LPCI) X A2.02 Ability to (a) predict the impacts of the 3.5 86 RHR/LPCI: Injection Mode following on the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Pump trips 211000 (SF1 SLCS) Standby Liquid X 2.1.23 Ability to perform specific system and 4.4 87 Control integrated plant procedures during l all modes of plant operation.

215005 (SF7 PRMS) Average Power X A2.01 Ability to (a) predict the impacts of the 3.1 88 Range Monitor/Local Power Range following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE Monitor MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Power supply degraded 263000 (SF6 DC) DC Electrical X G2.2.22 Knowledge of limiting conditions for 4.7 89 Distribution operations and safety limits.

300000 (SF8 IA) Instrument Air X A2.01 Ability to (a) predict the impacts of the 2.8 90 following on the INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:

Air dryer and filter malfunctions 203000 (SF2, SF4 RHR/LPCI) X K1.09 Knowledge of the physical connections 3.8 28 RHR/LPCI: Injection Mode and/or cause/effect relationships between RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) and the following: Emergency generators 205000 (SF4 SCS) Shutdown Cooling X K2.01 Knowledge of electrical power supplies 3.1 29 to the following: Pump motors 205000 (SF4 SCS) Shutdown Cooling X K5.03 Knowledge of the operational 2.8 30 implications of the following concepts as they apply to SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE): Heat removal mechanisms 206000 (SF2, SF4 HPCIS) X K3.01 Knowledge of the effect that a loss or 4.0 31 High-Pressure Coolant Injection malfunction of the HIGH-PRESSURE COOLANT INJECTION SYSTEM will have on following: Reactor water level control:

BWR-2,3,4 209001 (SF2, SF4 LPCS) X K4.09 Knowledge of LOW-PRESSURE 3.3 32 Low-Pressure Core Spray CORE SPRAY SYSTEM design feature(s) and/or interlocks which provide for the following: Load sequencing 211000 (SF1 SLCS) Standby Liquid X K5.06 Knowledge of the operational 3.0 33 Control implications of the following concepts as they apply to STANDBY LIQUID CONTROL SYSTEM: Tank level measurement 212000 (SF7 RPS) Reactor Protection X K6.04 Knowledge of the effect that a loss or 2.8 34 malfunction of the following will have on the REACTOR PROTECTION SYSTEM : D.C.

electrical distribution 212000 (SF7 RPS) Reactor Protection X K4.12 Bypassing of selected SCRAM signals 3.9 35 (manually and automatically): Plant-Specific 215003 (SF7 IRM) X A1.03 Ability to predict and/or monitor 3.6 36 Intermediate-Range Monitor changes in parameters associated with operating the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM controls including:

RPS status

ES-401 6 Form ES-401-1 215004 (SF7 SRMS) Source-Range X A2.02 Ability to (a) predict the impacts of the 3.4 37 Monitor following on the SOURCE RANGE MONITOR (SRM) SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

SRM inop condition 215005 (SF7 PRMS) Average Power X A3.04 Ability to monitor automatic operations 3.2 38 Range Monitor/Local Power Range of the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE Monitor MONITOR SYSTEM including: Annunciator and alarm signals 217000 (SF2, SF4 RCIC) Reactor X G2.2.36 Ability to analyze the effect of 3.1 39 Core Isolation Cooling maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

218000 (SF3 ADS) Automatic X K1.03 Knowledge of the physical connections 3.7 40 Depressurization and/or cause/effect relationships between AUTOMATIC DEPRESSURIZATION SYSTEM and the following: Nuclear boiler instrument system 223002 (SF5 PCIS) Primary X K3.01 Knowledge of the effect that a loss or 3.7 41 Containment Isolation/Nuclear Steam malfunction of the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM Supply Shutoff SUPPLY SHUT-OFF will have on following:

Reactor water level 239002 (SF3 SRV) Safety Relief X K3.01 Knowledge of the effect that a loss or 3.9 42 Valves malfunction of the RELIEF/SAFETY VALVES will have on following: Reactor pressure control 239002 (SF3 SRV) Safety Relief X K5.04 Knowledge of the operational 3.3 43 Valves implications of the following concepts as they apply to RELIEF/SAFETY VALVES: Tail pipe temperature monitoring 259002 (SF2 RWLCS) Reactor Water X K4.04 Knowledge of REACTOR WATER 2.9 44 Level Control LEVEL CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following: Reactor water level setpoint setdown following a reactor scram 261000 (SF9 SGTS) Standby Gas X G2.1.31 Ability to locate control room 4.6 45 Treatment switches, controls, and indications, and to l determine that they correctly reflect the desired plant lineup.

261000 (SF9 SGTS) Standby Gas X K6.03 Knowledge of the effect that a loss or 3.0 46 Treatment malfunction of the following will have on the STANDBY GAS TREATMENT SYSTEM:

Emergency diesel generator system 262001 (SF6 AC) AC Electrical X K6.03 Knowledge of the effect that a loss or 3.5 47 Distribution malfunction of the following will have on the A.C. ELECTRICAL DISTRIBUTION:

Generator trip 262001 (SF6 AC) AC Electrical X A1.01 Ability to predict and/or monitor 3.1 48 Distribution changes in parameters associated with operating the A.C. ELECTRICAL DISTRIBUTION controls including: Effect on instrumentation and controls of switching power supplies 262002 (SF6 UPS) Uninterruptable X A2.01. Ability to (a) predict the impacts of the 2.6 49 Power Supply (AC/DC) following on the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Under voltage

ES-401 7 Form ES-401-1 263000 (SF6 DC) DC Electrical X A2.01 Ability to (a) predict the impacts of the 2.8 50 Distribution following on the D.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Grounds 264000 (SF6 EGE) Emergency X A3.05 Ability to monitor automatic operations 3.4 51 Generators (Diesel/Jet) EDG of the EMERGENCY GENERATORS (DIESEL/JET) including: Load shedding and sequencing 300000 (SF8 IA) Instrument Air X A4.01 Ability to manually operate and / 2.6 52 or monitor in the control room: Pressure gauges 400000 (SF8 CCS) Component X G2.4.47 Ability to diagnose and recognize 4.2 53 Cooling Water trends in an accurate and timely manner l utilizing the appropriate control room reference material.

K/A Category Point Totals: 2 1 3 3 3 3 2 3/ 2 1 3 / Group Point Total: 26 /

3 2 5

ES-401 8 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 2 (RO/SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

215001 (SF7 TIP) Traversing In-Core Probe A2.02 Ability to (a) predict the X 3.0 91 impacts of the following on the TRAVERSING IN-CORE PROBE; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

High primary containment pressure:

Mark-l&II 226001 (SF5 RHR CSS) RHR/LPCI: Containment G2.4.41 Knowledge of the X 4.6 92 Spray Mode emergency action level thresholds and classifications.

233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup A2.05 Ability to (a) predict the X 2.5 93 impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Valve closures 201001 (SF1 CRDH) CRD Hydraulic A2.04 Ability to (a) predict the X 3.8 54 impacts of the following on the CONTROL ROD DRIVE HYDRAULIC SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Scram conditions 201003 (SF1 CRDM) Control Rod and Drive A3.01 Ability to monitor automatic X 3.7 55 Mechanism operations of the CONTROL ROD AND DRIVE MECHANISM including:

Control rod position 202002 (SF1 RSCTL) Recirculation Flow Control A4.08 Ability to manually operate X 3.3 56 and/or monitor in the control room:

Recirculation system flow 204000 (SF2 RWCU) Reactor Water Cleanup G2.1.20 Ability to interpret and X 4.6 57 execute procedure steps.

215002 (SF7 RBMS) Rod Block Monitor K1.04 Knowledge of the physical X 3.1 58 connections and/or cause/effect relationships between ROD BLOCK MONITOR SYSTEM and the following: Recirculation system:

BWR-3,4,5 223001 (SF5 PCS) Primary Containment and K2.09 Knowledge of electrical power X 2.7 59 Auxiliaries supplies to the following: Drywell cooling fans: Plant-Specific 234000 (SF8 FH) Fuel-Handling Equipment K3.03 Knowledge of the effect that a X 3.1 60 loss or malfunction of the FUEL HANDLING EQUIPMENT will have on following: Fuel handling operations 241000 (SF3 RTPRS) Reactor/Turbine Pressure K4.16 Knowledge of X 3.3 61 Regulating REACTOR/TURBINE PRESSURE REGULATING SYSTEM design feature(s) and/or interlocks which provide for the following: Reactor cooldown 256000 (SF2 CDS) Condensate K5.08 Knowledge of the operational X 2.6 62 implications of the following concepts as they apply to REACTOR CONDENSATE SYSTEM : Heat removal (transfer) mechanisms

ES-401 9 Form ES-401-1 271000 (SF9 OG) Offgas K6.02 Knowledge of the effect that a X 3.0 63 loss or malfunction of the following will have on the OFFGAS SYSTEM :

Process radiation monitoring system 290001 (SF5 SC) Secondary Containment A1.01 Ability to predict and/or X 3.1 64 monitor changes in parameters associated with operating the SECONDARY CONTAINMENT controls including: System lineups 290003 (SF9 CRV) Control Room Ventilation A2.04 Ability to (a) predict the X 3.1 65 impacts of the following on the CONTROL ROOM HVAC ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Initiation/failure of fire protection system K/A Category Point Totals: 1 1 1 1 1 1 1 2/ 1 1 1 / Group Point Total: 12 / 3 2 1

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Limerick Generating Station Units 1 and 2 Date of Exam: December 2019 Category K/A # Topic RO SRO-only IR # IR #

2.1.41 Knowledge of the refueling process. 3.7 94 2.1.9 Ability to direct personnel activities inside the control room. 4.5 95 Ability to use procedures to determine the effects on reactivity 2.1.43 of plant changes, such as reactor coolant system temperature, 4.1 66

1. Conduct of secondary plant, fuel depletion, etc.

Operations Knowledge of the purpose and function of major system 2.1.28 4.1 67 components and controls.

Ability to interpret reference materials, such as graphs, curves, 2.1.25 tables, etc. 3.9 68 Subtotal 3 2 2.2.21 Knowledge of pre- and post-maintenance operability 4.1 96 requirements.

2.2.20 Knowledge of the process for managing troubleshooting 3.8 97 activities.

2. Equipment 2.2.41 Ability to obtain and interpret station electrical and mechanical 3.5 69 Control drawings.

Ability to analyze the effect of maintenance activities, such as 2.2.36 3.1 70 degraded power sources, on the status of limiting conditions for operations.

Subtotal 2 2 2.3.6 Ability to approve release permits. 3.8 98 2.3.11 Ability to control radiation releases. 3.8 71 Knowledge of radiological safety procedures pertaining to

3. Radiation 2.3.13 licensed operator duties, such as response to radiation monitor 3.4 72 Control alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Subtotal 2 1 2.4.11 Knowledge of abnormal condition procedures. 4.2 99 Knowledge of crew roles and responsibilities during EOP 2.4.13 usage. 4.6 100 Ability to recognize abnormal indications for system operating 2.4.4 parameters that are entry-level conditions for emergency and 4.5 73

4. Emergency abnormal operating procedures.

Procedures/Plan Knowledge of facility protection requirements, including fire 2.4.26 3.1 74 brigade and portable fire fighting equipment usage.

Knowledge of low power/shutdown implications in accident 2.4.9 3.8 75 (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

Subtotal 3 2 Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/1 295026 G2.2.38 #77 - 295005 (APE 5) Main Turbine Generator Trip / 3; G2.2.38 Knowledge of conditions and limitations in the facility license. LGS does not have facility license items associated with the Main Turbine Generator Trip 1/1 295038 G2.2.12 #79 - 295019 (APE 19) Partial or Complete Loss of Instrument Air / 8; G2.2.12 Knowledge of surveillance procedures. LGS does not have surveillance requirements associated with Instrument Air System 1/2 295012 G2.2.25 #83 - 295012 (APE 12) High Drywell Temperature / 5; G2.2.42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications. We can not write an SRO level question to this generic K/A.

1/2 295032 G2.1.32 #85 - 295032 (EPE 9) High Secondary Containment Area Temperature / 5; G2.1.28 Knowledge of the purpose and function of major system components and controls.

We can not write an SRO level question to this generic K/A.

2/1 211000 G2.1.23 #87 - 211000 (SF1 SLCS) Standby Liquid Control; G2.4.34 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects. We can not write an SRO level question to this generic K/A.

1/2 295036 G2.4.50 #27 - 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5; G2.4.3 Ability to identify post-accident instrumentation. LGS does not have Post-Accident instruments associated with this EPE 2/1 261000 G2.1.31 #45 - 261000 (SF9 SGTS) Standby Gas Treatment; G2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.; The SGTS does not have any immediate Operator Actions 2/1 262002 A2.01 #49 - 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC); A1.02 Ability to predict and/or monitor changes in parameters associated with operating the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) controls including: Motor generator outputs - This K/A is on the LGS Suppressed K/A list - LGS does not have UPS Motor Generators 2/1 400000 G2.4.47 #53 - 400000 (SF8 CCS) Component Cooling Water; G2.4.2 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.;

LGS has no EOP entry conditions for Component Cooling Water 1/1 295037 EK2.02 #17 - 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1; EK2.10 Knowledge of the interrelations between SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN and the following: Reactor pressure: Over sampling with Questions #4 and #22.