ML18067A417

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Draft Written Examination and Operating Test Outlines (Folder 2)
ML18067A417
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 03/08/2018
From: Brian Fuller
Operations Branch I
To:
Exelon Generation Co
Shared Package
ML17138A091 List:
References
U01956
Download: ML18067A417 (23)
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ES-301 Administrative Topics Outline Form ES-301-1 Facility: Limerick - NRC Date of Examination: 12/18/17 Examination Level: RO [Zl SRO D Operating Test Number: 1 Administrative Topic (see Note) Type Describe activity to be performed Code*

G 2.1 .5 (Ability to use procedures related to shift staffing, such as minimum crew Conduct of Operations complement, overtime limitations, etc. (CFR:

R,D 41.10 / 43.5/ 45.12) !IMPORTANCE RO 2.9 SRO 3.9) Evaluate Overtime Work Reguest (RO) (LOJPM6704)

G 2.1. 7 (Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and Conduct of Operations R,D instrument interpretation. (CFR: 41.5 / 43.5 I 45.12 / 45.13) IMPORTANCE RO 4.4 SRO 4.7)

Administrative Actions on a Thermal Limit Violation. (LOJPM6714)

G 2.2.12 (Knowledge of surveillance procedures. (CFR: 41.10 / 45.13)

IMPORTANCE RO 3. 7 SRO 4.1) Review Equipment Control R,D DrYY!!'.ell Floor Drain Sumg/Eguigment Drain Tank Logs and Determine Comgliance with TS 3.4.3.2 (LOJPM6708)

G 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel Radiation Control R,N monitoring equipment, etc.(CFR: 41.12 / 43.4 I 45.9) IMPORTANCE RO 2.9 SRO 3.1)

Determination of actions for ARM downscale condition (LOJPM6718)

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 (s 3 for ROs; s 4 for SROs and RO retakes)

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

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

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Limerick - NRC Date of Examination: 12/18/17 Examination Level: RO D SRO [Zl Operating Test Number: 1 Administrative Topic (see Note) Type Describe activity to be performed Code*

G 2.1.5 (Ability to use procedures related to shift staffing, such as minimum crew Conduct of Operations R,D complement, overtime limitations, etc. (CFR:

41.10 / 43.5/ 45.12) IMPORTANCE RO 2.9 SRO 3.9) Determination of Adeguate Shift Staffina (LOJPM6725)

G2.1.37 (Knowledge of procedures, guidelines or limitations associated with reactivity Conduct of Operations R,D management. (CFR: 41.1 / 43.6 / 45.6)

IMPORTANCE RO 4.3 SRO 4.6) Review and AQQrove RMSI (LOJPM6727)

G2.2.12 (Knowledge of surveillance procedures. (CFR: 41.10 / 45.13)

IMPORTANGE RO 3. 7 SRO 4.1) Review Equipment Control R,D D~ell Floor Drain SumQ/EguiQment Drain Tank Logs and Determine ComQliance with TS 3.4.3.2 (LOJPM6708)

G2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel Radiation Control R,N monitoring equipment, etc.(CFR: 41.12 / 43.4 /

45.9) IMPORTANCE RO 2.9 SRO 3.1)

Determination of actions for ARM downscale condition (LOJPM6718)

G2.4.41 (Knowledge of the emergency action level thresholds and classifications. (CFR:

Emergency Plan S,D 41.10 / 43.5 / 45.11) IMPORTANCE RO 2.9 SRO 4.6) ERP Classification and ReQorting (LOJPM3101)

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 (s 3 for ROs; s 4 for SROs and RO retakes)

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

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Limerick - NRC Date of Examination: 12/18/17 Exam Level: RO [X] SRO-I D SRO-U D 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 a 42% Recirculation System Runback (System 202002 - Recirculation A,N,S 1 - Reactivity Flow Control System, A4.07; 3.3 / 3.2)(LOJPM3119) Control
b. Start a Condensate Pump (System 256000 - Reactor Condensate System, A4.03; A,N,S 2 - Reactor Water 3.2 I 3.1 )(LOJPM3530) Inventory
c. EHC Pump Operability Test (System 241000 - Reactor I Turbine Pressure A,N,S 3- Reactor Regulating System, A4.19; 3.5/3.4) (LOJPM3140) Pressure Control
d. Secure Unit 1 HPCI Following Full Flow Functional Test (System 20600- High D, EN, S 4 - Heat Removal Pressure Coolant Injection, A4.12; 4.0/3.9) (LOJPM3020) From Core
e. Perform a Group Ill NSSSS Isolation Reset (System 223002- Primary D,EN,S 5 - Containment Containment Isolation System / NSSSS; A4.03, 3.6/3.5)(LOJPM3037) Integrity
f. Supplying power to a 480 VAC Non-Safeguard Load Center From its Alternate A,D,S 6 - Electrical Source (System 262001 - A. C. Electrical Distribution A4.05; 3.3/3.3)(LOJPM3525)
g. Placing Alternate RECW Pump in Service (System 400000 - Component Cooling A,D,S 8 - Plant service Water; A2.01; 3.3/3.4) (LOJPM3129) Systems
h. Reset Refuel Area Seconda!Y Containment Isolation (System 288000 - Plant EN, N, S 9 - Radioactivity Ventilation Systems; A4.01; 3.1/2.9) (LOJPM3514) Release In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
i. Alternate Injection From the Fire System (295031 - EPE Reactor Low Water Level, D,E,L,R 2 - Reactor Water EA 1.08; 3.8/3.9) (LOJPM2260) (Unit 2) Inventory Control
j. Inadvertent Opening of a Relief Valve (239002 - Safety Relief Valves, A2.03; D,E,R 3- Reactor 4.1/4.1) (LOJPM2204) Pressure Control
k. Manual Isolation and Vent of the Scram Air Header (212000 - Reactor Protection D,E,R 7 - Instrumentation System, A4.17; 4.1/4.1)(LOJPM2210)
  • 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 /SR0-1/SRO-U (A)lternate path 4-6/4-6 /2-3 5 (C)ontrol room (D)irect from bank :S 9/S 8/S 4 7 (E)mergency or abnormal in-plant ~1,~1,~1 3 (EN)gineered safety feature ~ 1/~ 1/~ 1 (control room system) 3 (L )ow-Power/Shutdown ~ 1/~ 1/~ 1 1 (N)ew or (M)odified from bank including 1(A) ~ 2/~ 2/~ 1 4 (P)revious 2 exams :S 3/s 3/s 2 (randomly selected) 0 (R)CA ~ 1/~ 1/~ 1 3 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Limerick - NRC Date of Examination: 12/18/17 Exam Level: RO D SRO-I [Zl SRO-U D 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 a 42% Recirculation Sl£stem Runback (System 202002 - Recirculation A,N,S 1 - Reactivity Flow Control System, A4.07; 3.3 / 3.2)(LOJPM3119) Control
b. Start a Condensate Pump (System 256000 - Reactor Condensate System, A4.03; A,N,S 2 - Reactor Water 3.2 I 3.1 )(LOJPM3530) Inventory
c. EHC Pump Operabilitll Test (System 241000- Reactor/ Turbine Pressure A,N,S 3- Reactor Regulating System, A4.19; 3.5/3.4) (LOJPM3139) Pressure Control
e. Perform a Group Ill NSSSS Isolation Reset (System 223002 - Primary D,EN,S 5 - Containment Containment Isolation System / NSSSS; A4.03, 3.6/3.5)(LOJPM3037) Integrity
f. Suppll£ing power to a 480 VAC Non-Safeguard Load Center From its Alternate A,D,S 6 - Electrical Source (System 262001 -A. C. Electrical Distribution A4.05; 3.3/3.3)(LOJPM3525)
g. Placing Alternate RECW Pump in Service (System 400000 - Component Cooling A,D,S 8 - Plant service Water; A2.01; 3.3/3.4) (LOJPM3129) Systems
h. Reset Refuel Area Seconda[ll Containment Isolation (System 288000 - Plant EN,N,S 9 - Radioactivity Ventilation Systems; A4.01; 3.1/2.9) (LOJPM3514) Release In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
i. Alternate Injection From the Fire Sl£stem (295031 - EPE Reactor Low Water Level, D,E, L, R 2 - Reactor Water EA 1.08; 3.8/3.9) (LOJPM2260) (Unit 2) Inventory Control
j. Inadvertent Opening of a Relief Valve (239002 - Safety Relief Valves, A2.03; D,E,R 3- Reactor 4.1/4.1) (LOJPM2204) Pressure Control
k. Manual Isolation and Vent of the Scram Air Header (212000 - Reactor Protection D,E,R 7 - Instrumentation System, A4.17; 4.1/4.1)(LOJPM2210)
  • 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.

I

  • Type Codes I Criteria for R /SR0-1/SRO-U I

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Limerick - NRC Date of Examination: 12/18/17 Exam Level: RO D SRO-I ~ SRO-U D 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 a 42% Recirculation Sllstem Runback (System 202002 - Recirculation A,N,S 1 - Reactivity Flow Control System, A4.07; 3.3 / 3.2)(LOJPM3119) Control
b. Start a Condensate Pump (System 256000 - Reactor Condensate System, A4.03; A,N,S 2 - Reactor Water 3.2 I 3.1)(LOJPM3530) Inventory
c. EHC Pump Operability Test (System 241000- Reactor/ Turbine Pressure A,N,S 3- Reactor Regulating System, A4.19; 3.5/3.4) (LOJPM3139) Pressure Control
e. Perform a Group Ill NSSSS Isolation Reset (System 223002 - Primary D,EN,S 5 - Containment Containment Isolation System / NSSSS; A4.03, 3.6/3.5)(LOJPM3037) Integrity
f. Suppljling power to a 480 VAC Non-Safeguard Load Center From its Alternate A,D,S 6 - Electrical Source (System 262001 - A. C. Electrical Distribution A4.05; 3.3/3.3)(LOJPM3525)
g. Placing Alternate RECW Pump in Service (System 400000 - Component Cooling A,D,S 8 - Plant service Water; A2.01; 3.3/3.4) (LOJPM3129) Systems
h. Reset Refuel Area Seconda!Y Containment Isolation (System 288000 - Plant EN,N,S 9 - Radioactivity Ventilation Systems; A4.01; 3.1/2.9) (LOJPM3514) Release In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
i. Alternate Injection From the Fire System (295031 - EPE Reactor Low Water Level, D,E,L,R 2 - Reactor Water EA 1.08; 3.8/3.9) (LOJPM2260) (Unit 2) Inventory Control
j. Inadvertent Opening of a Relief Valve (239002 - Safety Relief Valves, A2.03; D,E,R 3- Reactor 4.1 /4.1) (LOJPM2204) Pressure Control
k. Manual Isolation and Vent of the Scram Air Header (212000 - Reactor Protection D,E,R 7 - Instrumentation System, A4.17; 4.1/4.1 )(LOJPM2210)
  • 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 /SR0-1/SRO-U (A}lternate path 4-6/4-6 /2-3 5 (C)ontrol room (D)irect from bank :s; 9/S 8/::s; 4 6 (E)mergency or abnormal in-plant ~1P-1/~1 3 (EN)gineered safety feature ~ 1P- 1/~ 1 (control room system) 2

{L )ow-Power/Shutdown ~1P-1/~1 1 (N)ew or (M)odified from bank including 1(A) ~ 2P- 2/~ 1 4 (P)revious 2 exams :s; 3/S 3/::5 2 (randomly selected) 0 (R)CA ~1P-1/~1 3 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Limerick - NRC Date of Examination: 12/18/17 Exam Level: RO D SRO-I D SRO-U [X] 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 a 42% Recirculation System Runback (System 202002 - Recirculation A,N,S 1 - Reactivity Flow Control System, A4.07; 3.3 / 3.2)(LOJPM3119) Control
c. EHC Pump Operability Test (System 241000 - Reactor/ Turbine Pressure A,N,S 3- Reactor Regulating System, A4.19; 3.5/3.4) (LOJPM3139) Pressure Control
h. Reset Refuel Area Seconda[Y Containment Isolation (System 288000 - Plant EN, N, S 9 - Radioactivity Ventilation Systems; A4.01; 3.1/2.9) (LOJPM3514) Release In-Plant Systems:* 3 for RO, for SRO-I, and 3 or 2 for SRO-U
i. Alternate Injection From the Fire System (295031 - EPE Reactor Low Water Level, D,E,L,R 2 - Reactor Water EA1.08; 3.8/3.9) (LOJPM2260) (Unit 2) Inventory Control
k. Manual Isolation and Vent of the Scram Air Header (212000 - Reactor Protection D,E,R 7 - Instrumentation System, A4.17; 4.1/4.1)(LOJPM2210)
  • 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 /SR0-1/SRO-U I I I (A)lternate path 4-6/4-6 /2-3 2 (C)ontrol room (D)irect from bank s 9/S 8/S 4 2 (E)mergency or abnormal in-plant <! 1/<! 1P- 1 2 (EN)gineered safety feature <! 1/<! 1P- 1 (control room system) 1 (L )ow-Power/Shutdown <! 1/<! 1P-1 1 (N)ew or (M)odified from bank including 1(A) <! 2/<! 2P- 1 3(2)

(P)revious 2 exams s 3/s 3/S 2 (randomly selected) 0 (R)CA <! 1/<! 1P-1 2 (S)imulator

SEG-3005E Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: SEG-3005E Rev _1_ Op-Test No.:_1_.

Examiners: Operators:

Initial Conditions:

Unit 1 is at 5.0 % power. Unit 2 is at 100% power.

Turnover:

D12 D/G is running 12arallel to 201 Safeguard Bus following maintenance. D12 D/G has been running loaded for 11/2 hours of the reguired 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 12er S92.2.N ste12 4.6.4.

Planned Evolutions :

When the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> loaded run is com12lete, secure D12 D/G 12er S92.2.N beginning with ste12 4.6.5.

Critical Tasks:

1. Manually Insert Control Rods
2. Direct performance of T-290 to personnel outside the control room
3. Perform Emergency Slowdown per T-112 Event Malfunction Event Event No. Number Type* Description C-PRO 1 MESW600B 'OB' ESW Pump trip TS-SRO MCU002A MCU002B C-PRO 2 RWCU Isolation failure on differential flow MCU193 TS-SRO HS44-1F004 C-RO 3 MED280A Trip of 1AY160, RPS/UPS Distribution Panel C-PRO 4 MRD016G C-RO Failure of 3 (three) Control Rods to scram.

MFW251B 5 C-RO S/U Level Control Valve and HV-06-108A fail closed HS06-108A 6 MHP445 M-ALL T-103 Steam Leak in HPCI MHP446A 7 C-PRO HPCI Steam Isolation Valves fail to close MHP446B MFW245B '1 B' Reactor Feedpump Loss of HP steam supply 8 C-PRO MRC460 RCIC injection valve fails to open Automatically (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor I I

SEG-4158E Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: SEG- 4158E Rev _o_ Op-Test No.:_1_.

Examiners: Operators:

Initial Conditions:

Unit 1 Reactor Power is 100%

Unit 2 Reactor Power is 100%

Turnover:

  • Maintain 100% power Critical Tasks:
1. Inhibit Automatic ADS
2. Perform actions to maintain/restore RPV water level above Top of Active Fuel (TAF)
3. Spray the Drywell Event Malfunction Event Event No. Number Type* Description Ann. 118-15 C-PRO 1 C-RO Loss of lsophase Bus Cooling 2 R-RO MHP450 C-PRO Inadvertent HPCI Start Up TS-SRO MNS161B I-PRO Inadvertent NSSSS ISOLATION 3

MNS001 TS-SRO Failure of PCIG to Isolate MCN002 4 Trip of 1B Condensate Pump with Failure of the 1A Reactor MRR507A C-RO Recirc Pump to automatically run back.

5 MED262A M-ALL Loss of the 11 BUS / Loss of All Condensate & Feed MRR440A 6 MHP447B C-PRO LOCA, HPCI Aux Oil Pump Failure, RCIC Overspeed trip.

MRC466 MDG420A D11 Bus fails to auto swap on Dead Bus Transfer, and failure 7 MED011 C-PRO of D11 EDG to auto start.

MED015A

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

SEG-6217E Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: SEG-6217E Rev _o_ Op-Test No.:_1_.

Examiners: Operators:

Initial Conditions:

Unit 1 Reactor Power is 80%

Unit 2 Reactor Power is 100%

Turnover:

  • Restore Unit 1 power to 100% using by withdrawing Control Rods and raising Core Flow Critical Tasks:
1. Inhibit Auto ADS
2. Terminate and Prevent injection into the RPV (first lowering)
3. Terminate and prevent injection into the RPV (second lowering)
4. Direct performance of control rod insertion via T-217 to personnel located outside the MCR Event Malfunction Event Event No. Number Type* Description 1 None R-RO Continue raising reactor power 2 MRD016D C-RO Control Rod (42-43) fails stuck C-PRO 3 MPC257 '1 D' RHR Pump suction leak TS-SRO C-PRO 4 MED2828 Loss of Div 2 DC TS-SRO MVl232B C-RO 5 Reactor Level Transmitter Failure / Failure to Half Scram.

MRP029C TS-SRO 6 MRR441 C-PRO Small coolant leak into Drywell MSL559 7 M-ALL Hydraulic A TWS with failure of Standby Liquid Control MRD556 8 MRD024 C-RO RDCS Inoperative 9 MAD145E C-PRO 1J SRV Fails Open Mechanically I* (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor I

SEG-2159 (Proposed Spare)

Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: SEG-2159E Rev _o_ Op-Test No.:_1_.

Examiners: Operators:

Initial Conditions:

Unit 1 Reactor Power is 100%

Unit 2 Reactor Power is 100%

Turnover:

5. Manually Scram the Reactor
6. Spray the Drywell
7. Perform Emergency Slowdown per T-112 Event Malfunction Event Event No. Number Type* Description 1 None N-PRO Perform Drywell Unit Cooler Hydrogen Mixing System Operability Test Run MFW246A C-RO 2 MFW552C C-PRO Trip of "1 C" RFP with discharge check valve stuck open 3 MCR547 C-RO Running CRD Pump Trip HCU accumulator Trouble for HCU MRD016C TS-SRO 18-47 C-PRO 4 MRR433B R-RO Sequential failures of 1B Recirc Pump Seals MRR434B TS-SRO 5 MMS067 M-AII Steam leak in the Drywell 6 MRP029C C-RO RPS 'A' fails to scram (ARI successful)

Downcomer break results in Suppression Pool pressure 7 MPC476 C-PRO equalizing with Drywell pressure requiring blowdown on Pressure Suppression Curve HS-51-F016A First Drywell spray method selected will be un-successful 8 or C-PRO requiring use of other train HS-51-F016B

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

ES-401 Written Examination Outline Form ES-401-1 Facility: Date of Exam: 12/18/17 RO Kl A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4 *

1. 1 3 4 3 4 3 3 20 3 4 7 Emergency Plant 2

Tier 2 1 1 T 1 1 1 7 2 1 3 Evolutions 5 5 4 5 4 4 27 5 5 10 Totals I 2 2 2 3 2 3 2 3 3 2 2 26 2 3 5 2.

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

3. Generic Knowledge & Abilities JO 7 Categories 3 2 2 3 1 2 2 2 Note: 1. Ensure that at least two topics from every applicable KIA 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 KIA category shall not be less than two). (One Tier 3 radiation control KIA is allowed if it is replaced by a KIA 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 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 (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 KIA categories.
7. The generic (G) KIAs 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 KIAs.
8. On the following pages, enter the KIA 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 KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.

G* Generic KIAs

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

ES-401 2 Form ES-401-1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #/Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

AA2.0 I - Ability to determine and/or 295021 Loss of Shutdown Cooling interpret the following as they apply to X 3.6 76

/4 LOSS OF SHUTDOWN COOLING :

Reactor water heatup/cooldown rate EA2.06 - Ability to determine and/or interpret the following as they apply to 295024 High Drywell Pressure/ 5 X 4.1 77 HIGH DRYWELL PRESSURE:

Suppression pool temperature AA2.05 - Ability to determine and/or interpret the following as they apply to 700000 Generator Voltage and X GENERATOR VOLTAGE AND 3.8 78 Electric Grid Disturbances ELECTRIC GRID DISTURBANCES:

Operational status of offsite circuit.

2.2.37 - Equipment Control: Ability to 295018 Partial or Total Loss of X determine operability and/ or availability of 4.6 79 ccw /8 safety related equipment.

2.4.3 - Emergency Procedures/ Plan:

295025 High Reactor Pressure/ 3 X Ability to identify post-accident 3.9 80 instrumentation.

2.4.2 - Emergency Procedures/ Plan:

295037 SCRAM Conditions Knowledge of system set points, interlocks Present and Reactor Power Above X 4.6 81 and automatic actions associated with EOP APRM Downscale or Unknown / I entry conditions.

2.2.39 - Equipment Control: Knowledge of 295031 Reactor Low Water Level/

X less than one hour technical specification 4.5 82 2

action statements for systems.

AKl.03 - Knowledge of the operational 295001 Partial or Complete Loss implications of the following concepts as of Forced Core Flow Circulation/ I X they apply to PARTIAL OR COMPLETE 3.6 39

&4 LOSS OF FORCED CORE FLOW CIRCULATION : Thermal limits EKl.01 - Knowledge of the operational 295031 Reactor Low Water Level implications of the following concepts as X 4.6 40

/2 they apply to REACTOR LOW WATER LEVEL : Adequate core cooling EK 1.02 - Knowledge of the operational 295038 High Off-site Release Rate implications of the following concepts as X 4.2 41

/9 they apply to HIGH OFF-SITE RELEASE RATE: Protection of the general public AK2.0I - Knowledge of the interrelations 295004 Partial or Total Loss of between PARTIAL OR COMPLETE LOSS X 3.1 42 DCPwr/6 OF D.C. POWER and the following: Battery charger AK2.03 - Knowledge of the interrelations 600000 Plant Fire On-site / 8 X between PLANT FIRE ON SITE and 2.5 43 the followina: Motors AK2.02 - Knowledge of the interrelations between PARTIAL OR COMPLETE 295018 Partial or Total Loss of X LOSS OF COMPONENT COOLING 3.4 44 CCW/8 WATER and the following: Plant operations AK3.02 - Knowledge of the reasons for 295021 Loss of Shutdown Cooling the following responses as they apply to X 3.3 45

/4 LOSS OF SHUTDOWN COOLING :

Feedina and bleedina reactor vessel AK3.06 - Knowledge of the reasons for 295003 Partial or Complete Loss the following responses as they apply to X 3.7 46 of AC/ 6 PARTIAL OR COMPLETE LOSS OF A.C. POWER : Containment isolation

ES-401 2 Form ES-401-1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #/Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s)

AK3.01 - Knowledge of the reasons for the following responses as they apply to 295019 Partial or Total Loss of X PARTIAL OR COMPLETE LOSS OF 3.3 47 Inst. Air/ 8 INSTRUMENT AIR : Backup air system supply: Plant-Specific AA 1.01 - Ability to operate and/or monitor the following as they apply to 700000 Generator Voltage and Electric Grid Disturbances X GENERATOR VOLTAGE AND 3.6 48 ELECTRIC GRID DISTURBANCES:

Grid frequency and voltaae.

EA 1.04 - Ability to operate and/or monitor the following as they apply to 295024 High Drywell Pressure/ 5 X HIGH DRYWELL PRESSURE:

4.1 49 RHR/LPCI AA 1.03 - Ability to operate and/or monitor the following as they apply to 295005 Main Turbine Generator X MAIN TURBINE GENERATOR TRIP: 2.7 50 Trip/ 3 Reactor manual control/Rod control and information system EA2.03 - Ability to determine and/or 295026 Suppression Pool High interpret the following as they apply to X 3.9 51 Water Temp./ 5 SUPPRESSION POOL HIGH WATER TEMPERATURE: Reactor pressure EA2.03 - Ability to determine and/or 295028 High Drywell Temperature interpret the following as they apply to X 3.7 52 I5 HIGH DRYWELL TEMPERATURE :

Reactor water level EA2.04 - Ability to determine and/or interpret the following as they apply to 295037 SCRAM Conditions SCRAM CONDITION PRESENT AND Present and Reactor Power Above X REACTOR POWER ABOVE APRM 4.0 53 APRM Downscale or Unknown / 1 DOWNSCALE OR UNKNOWN :

Suppression pool temperature 2.2.38 - Equipment Control: Knowledge 295006 SCRAM I 1 X of conditions and limitations in the 3.6 54 facility license.

2.4.46 - Emergency Procedures/ Plan:

295023 Refueling Ace Cooling X Ability to verify that the alarms are 4.2 55 Mode/ 8 consistent with the plant conditions.

2.4.31 - Emergency Procedures/ Plan:

295030 Low Suppression Pool X Knowledge of annunciator alarms, 4.2 56 Water Level / 5 indications, or response procedures.

EK2.09 - Knowledge of the interrelations 295025 High Reactor Pressure / 3 X between HIGH REACTOR PRESSURE 3.9 57 and the followina: Reactor power AA 1.04 - Ability to operate and/or 295016 Control Room monitor the following as they apply to X 3.1 58 Abandonment / 7 CONTROL ROOM ABANDONMENT :

A.C. electrical distribution KIA Category Totals: 3 4 3 4 3/3 3/4 Group Point Total:

I 2017

ES-401 3 Form ES-401-1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE # / Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

AA2.03 - Ability to determine and/or interpret the following as they apply to 295022 Loss of CRD Pumps / 1 X 3.2 83 LOSS OF CRD PUMPS : CRD mechanism temperatures 2.4.34 - Emergency Procedures/ Plan:

295032 High Secondary Knowledge of RO tasks performed outside X 4.1 84 Containment Area Temperature/ 5 the main control room during an emergency and the resultant operational effects.

AA2.02 - Ability to determine and/or 295012 High Drywell Temperature interpret the following as they apply to X 4.1 85 I5 HIGH DRYWELL TEMPERATURE:

Drywell pressure EKl.03 - Knowledge of the operational implications of the following concepts as 295032 High Secondary they apply to HIGH SECONDARY 3.

X 59 Containment Area Temperature/ 5 CONTAINMENT AREA 5 TEMPERATURE: Secondary containment leakage detection: Plant-Specific EK2.01 - Knowledge of the interrelations between SECONDARY CONTAINMENT 295036 Secondary Containment 3.1 X HIGH SUMP/AREA WATER LEVEL and 60 High Sump/Area Water Level/ 5 the following: Secondary containment equipment and floor drain system AK3.01 - Knowledge of the reasons for the 295009 Low Reactor Water Level following responses as they apply to LOW 3.

X 61

/2 REACTOR WATER LEVEL : Recirculation 2 pump run back: Plant-Specific AA! .07 - Ability to operate and/or monitor 295002 Loss of Main Condenser the following as they apply to LOSS OF 3.

X 62 Vac / 3 MAIN CONDENSER VACUUM : 1 Condenser circulating water system AA2.0 I - Ability to determine and/or 295008 High Reactor Water Level interpret the following as they apply to 3.

X 63

/2 HIGH REACTOR WATER LEVEL: 9 Reactor water level 2.4.9 - Emergency Procedures/ Plan:

Knowledge oflow power/ shutdown 295014 Inadvertent Reactivity 3.

X implications in accident (e.g., loss of coolant 64 Addition/ I 8 accident or loss of residual heat removal) mitigation strategies.

AK 1.0 I - Knowledge of the operational implications of the following concepts as 295020 Inadvertent Cont. 3.

X they apply to INADVERTENT 65 Isolation / 5 & 7 7 CONTAINMENT ISOLATION: Loss of normal heat sink KIA Category Totals: 2 1 1 1 1/2 1/1 Group Point Total:

I 7/3

ES-401 4 Form ES-401-1 Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # / Name A2 G Q#

1 2 3 4 5 6 1 3 4 A2.02 - Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES ; and (b) ba~ed on those predictions, use 239002 SRVs X 3.2 86 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Leaky SRV A2.05 - Ability to (a) predict the impacts of the following on the EMERGENCY GENERA TORS (DIESEL/JET); and (b) based on those predictions, use procedures to 264000 EDGs X correct, control, or mitigate the 3.6 87 consequences of those abnormal conditions or operations:

Synchronization of the emergency generator with other electrical supplies 2.2.42 - Equipment Control::

Ability to recognize system 205000 Shutdown Cooling X parameters that are entry-level 4.6 88 conditions for Technical Specifications.

2.4.6 - Emergency Procedures/

206000 HPCI X Plan: Knowledge of EOP mitigation 4.7 89 strategies.

2.1.31 - Conduct of Operations:

Ability to locate control room 215005 APRM / LPRM X switches, controls, and indications, 4.3 90 and to detennine that they correctly reflect the desired plant lineup.

Kl .04 - Knowledge of the physical connections and/or cause- effect 239002 SRVs X relationships between 3.6 1 RELIEF/SAFETY VAL YES and the following: Main steam K1 .07 - Knowledge of the physical connections and/or cause- effect relationships between AVERAGE POWER 215005 APRM / LPRM X RANGE MONITOR/LOCAL 2.6 2 POWER RANGE MONITOR SYSTEM and the following:

Process computer, performance monitoring system K2.01 - Knowledge of electrical 217000 RCIC X power supplies to the following: 2.8 3 Motor operated valves K2.04 - Knowledge of electrical power supplies to the following:

206000 HPCI X 2.5 4 Turbine control circuits: BWR-2,3,4 K3.01 - Knowledge of the effect that a loss or malfunction of the SHUTDOWN COOLING 205000 Shutdown Cooling X 3.3 5 SYSTEM (RHR SHUTDOWN COOLING MODE) will have on following: Reactor pressure

ES-401 4 Form ES-401-1 Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # I Name A2 G Q#

1 2 3 4 5 6 1 3 4 K3.03 - Knowledge of the effect that a loss or malfunction of the LOW PRESSURE CORE 209001 LPCS X 2.9 6 SPRAY SYSTEM will have on following: Emergency generators K4.01 - Knowledge of REACTOR WATER LEVEL CONTROL SYSTEM design 259002 Reactor Water Level feature(s) and/or interlocks X 3.0 7 Control which provide for the following:

Ensuring adequate NPSH for recirculation pumps: Plant-Specific K4.01 - Knowledge of INTERMEDIATE RANGE MONITOR (IRM) SYSTEM 215003 !RM X 3.7 8 design feature(s) and/or interlocks which provide for the following: Rod withdrawal blocks K5.01 - Knowledge of the operational implications of the following concepts as they apply 263000 DC Electrical X to D.C. ELECTRICAL 2.6 9 Distribution DISTRIBUTION : Hydrogen generation during battery charaina.

K5.01 - Knowledge of the operational implications of the following concepts as they apply 215004 Source Range Monitor X 2.6 10 to SOURCE RANGE MONITOR (SRM) SYSTEM : Detector operation K6.03 - Knowledge of the effect that a loss or malfunction of the 262001 AC Electrical X following will have on the A.C. 3.5 II Distribution ELECTRICAL DISTRIBUTION:

Generator trip K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the 261000 SGTS X 2.9 12 STANDBY GAS TREATMENT SYSTEM : Process radiation monitoring A 1.09 - Ability to predict and/or monitor changes in parameters associated with operating the EMERGENCY GENERATORS 264000 EDGs X 3.0 13 (DIESEL/JET) controls including:

Maintaining minimum load on emergency generator (to prevent reverse power)

A 1.01 - Ability to predict and/or monitor changes in parameters associated with operating the 218000 ADS X AUTOMATIC 3.4 14 DEPRESSURIZATION SYSTEM controls including: ADS valve tail pipe temperatures

ES-401 4 Form ES-401-1 Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # I Name A2 G Q#

1 2 3 4 5 6 1 3 4 A2.03 - Ability to (a) predict the impacts of the following on the CCWS and (b) based on those 400000 Component Cooling predictions, use procedures to Water X 2.9 15 correct, control, or mitigate the consequences of those abnormal operation: High/low CCW temperature A2.01 - Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM 223002 PCIS/Nuclear Steam SUPPLY SHUT-OFF; and (b)

Supply Shutoff X based on those predictions, use 3.2 16 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:,A.C. electrical distribution failures A3.07 - Ability to monitor automatic operations of the 203000 RHR/LPCI: Injection Mode X RHR/LPCI: INJECTION MODE 4.2 17 (PLANT SPECIFIC) including:

Loop selection: Plant-Specific A3.02 - Ability to monitor automatic operations of the 211000 SLC X STANDBY LIQUID CONTROL 3.9 18 SYSTEM including: Tank level:

Plant-Specific A4.05 - Ability to manually 212000 RPS X operate and/or monitor in the 4.3 19 control room: Reactor power A4.01 - Ability to manually 300000 Instrument Air X operate and/or monitor in the 2.6 20 control room: Pressure gauges 2.1.20 - Conduct of Operations:

262002 UPS (AC/DC) X Ability to interpret and execute 4.6 21 procedure steps.

2.4.1 - Emergency Procedures/

Plan: Knowledge of EOP entry 261000 SGTS X conditions and immediate action 4.6 22 steps.

A2.03 - Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) 209001 LPCS X based on those predictions, use 3.4 23 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A.C. failures A3.08 - Ability to monitor automatic operations of the 218000 ADS X AUTOMATIC 4.2 24 DEPRESSURIZATION SYSTEM including: Reactor pressure

ES-401 4 Form ES-401-1 Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # I Name A2 G Q#

1 2 3 4 5 6 1 3 4 K4.01 - Knowledge of UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) design 262002 UPS (AC/DC) X feature(s) and/or interlocks 3.1 25 which provide for the following:

Transfer from preferred power to alternate power supplies K6.01 - Knowledge of the effect that a loss or malfunction of the following will have on the 215005 APRM / LPRM X AVERAGE POWER RANGE 3.7 26 MONITOR/LOCAL POWER RANGE MONITOR SYSTEM :

RPS KIA Category Totals: 2 2 2 3 2 3 2 3/2 3 2 2/3 Group Point Total:

I 26/5

ES-401 5 Form ES-401-1 Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System # I Name A2 G Imp.

1 2 3 4 5 6 1 3 4 #

A2.07 - Ability to predict the impacts of the following on the RADIATION MONITORING SYSTEM: and (b) based on those 272000 Radiation Monitoring X predictions, use procedures to 2.8 91 correct, control, or mitigate the consequences of those abnormal conditions or operations: Hydrogen injection operation: Plant-Specific 2.4.49 - Emergency Procedures/

Plan: Ability to perfonn without 202002 Recirculation Flow reference to procedures those X 4.4 92 Control actions that require immediate operation of system components and controls.

2.2.38 - Equipment Control:

239001 Main and Reheat X Knowledge of conditions and 4.5 93 Steam limitations in the facility license.

Kl .22 - Knowledge of the physical connections and/or cause- effect 216000 Nuclear Boiler Inst. X relationships between NUCLEAR 3.6 27 BOILER INSTRUMENTATION and the following: Reactor vessel K2.03 - Knowledge of electrical 215002RBM X power supplies to the following: 2.8 28 APRM channels: BWR-3,4,5 K3.0l - Knowledge of the effect that a loss or malfunction of the RHR/LPCI:

219000 RHR/LPCI:

X TORUS/SUPPRESSION POOL 3.9 29 Torus/Pool Cooling Mode COOLING MODE will have on following: Suppression pool temperature control K4.03 - Knowledge of REACTOR CONDENSATE SYSTEM design feature(s) 256000 Reactor Condensate X 2.8 30 and/or interlocks which provide for the following: Condensate and/or booster pump protection KS.02 - Knowledge of the operational implications of the 202002 Recirculation Flow following concepts as they apply X 2.6 31 Control to RECIRCULATION FLOW CONTROL SYSTEM :

Feedback signals K6.03 - Knowledge of the effect that a loss or malfunction of the 245000 Main Turbine Gen. / following will have on the MAIN X 2.8 32 Aux. TURBINE GENERATOR AND AUXILIARY SYSTEMS:

Hydrogen seal oil A 1.07 - Ability to predict and/or monitor changes in parameters associated with operating the PRIMARY CONTAINMENT 22300 I Primary CTMT and SYSTEM AND AUXILIARIES X 3.2 33 Aux. controls including:

Drywell/suppression chamber differential pressure (drywell to containment building): Plant-Specific

ES-401 5 Form ES-401-1 Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System # / Name A2 G Imp.

1 2 3 4 5 6 1 3 4 #

A2.05 - Ability to (a) predict the impacts of the following on the REACTOR VESSEL INTERNALS; and (b) based on 290002 Reactor Vessel those predictions, use Internals X procedures to correct, control, 3.7 34 or mitigate the consequences of those abnormal conditions or operations: Exceeding thermal limits A3.01 - Ability to monitor automatic operations of the 230000 RHR/LPCI: RHR/LPCI:

Torus/Pool Spray Mode X 3.4 35 TORUS/SUPPRESSION POOL SPRAY MODE including: Valve operation A4.01 - Ability to manually 268000 Radwaste X operate and/or monitor in the 3.4 36 control room: Sump integrators 2.2.40 - Equipment Control:

201006RWM X Ability to apply technical 3.4 37 specifications for a system.

A3.07 - Ability to monitor automatic operations of the 226001 RHR/LPCI: CTMT Spray Mode X RHR/LPCI: CONTAINMENT 3.5 38 SPRAY SYSTEM MODE including: Pump start KIA Category Totals: 1 1 1 1 1 1 1 1/1 2 1 1/2 Group Point Total: 12/3 I

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date: 12/18/17 RO SRO-Only Category KIA# Topic IR Q# IR Q#

Ability to explain and apply all system limits 2.1.32 4.0 94 and precautions.

1. Knowledge of shift or short-term relief Conduct 2.1.3 3.7 66 turnover practices.

of Operations Knowledge of refueling administrative 2.1.40 2.8 67 requirements Ability to use plant computers to evaluate 2.1.19 system or component status.

3.9 74 Subtotal 3 1 Knowledge of the process used to track 2.2.43 inoperable alarms.

3.3 95 Knowledge of the process for conducting 2.2.7 special or infrequent tests.

3.6 100

2. (multi-unit license) Knowledge of the design, Equipment 2.2.3 procedural, and operational differences 3.8 68 Control between units.

Knowledge of the process for controlling 2.2.14 3.9 69 equipment configuration or status.

Subtotal 2 2 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3.5 2.9 96 portable survey instruments, personell monitoring equipment, etc.

Knowledge of radiation or containment hazards that may arise during normal, 2.3.14 3.8 98 abnormal, or emergency conditions or activities.

3.

Radiation Control Ability to comply with radiation work permit 2.3.7 requirements during normal or abnormal 3.5 70 conditions.

2.3.11 Ability to control radiation releases. 3.8 71 Subtotal 2 2

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Knowledge of how abnormal operating 2.4.8 procedures are used in conjunction with 4.5 97 EOP's.

2.4.27 Knowledge of "fire in the plant" procedures. 3.9 99 Knowledge of the bases for prioritizing

4. 2.4.23 emergency procedure implementation during 3.4 72 Emergency emergency operations.

Procedures I Ability to perform without reference to Plan procedures those actions that require 2.4.49 4.6 73 immediate operation of system components and controls.

Knowledge of low power I shutdown implications in accident (e.g., loss of coolant 2.4.9 3.8 75 accident or loss of residual heat removal) mitiqation strateqies.

Subtotal 3 2 Tier 3 Point Total 10 7

ES-401 Record of Rejected K/A's Form ES-401-4 Randomly Selected Tier/ Group Reason for Rejection KIA Reactor Low Water Level/ Equipment Control: Knowledge of less than one hour technical specification action statements for systems.

One hour Tech spec actions are RO level of knowledge per SRO only screening per 10CFR55.43 (ES-401 Attachment 2 1 /1 Fig.2-1 Flowchart) 295031 2.2.39 Q#82 Random number generator used to select from remaining generics of section 2.2 Equipment Control. KA 2.2.22, "Knowledge of limiting conditions for operations and safety limits" was selected.

295031 was retained Original KIA does not meet the threshold of SRO:

295022 AA2.03 - Ability to determine and/or interpret the following as they apply to LOSS OF CRD PUMPS : CRD mechanism temperatures 1/ 1 295022 AA2.01 Q#83 Limerick does not have a CRD Mechanism temperature component to Tech Specs.

Random number generator used to select from remaining 295022 AA's.

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