ML102650152

Initial Exam 2010-301 Draft Administrative Documents

ML102650152
Person / Time
Site:	Mcguire, McGuire
Issue date:	08/30/2010
From:	NRC/RGN-II
To:	Duke Energy Carolinas, Duke Power Co
References
50-369/10-301, 50-370/10-301, ES-401 50-369/10-301, 50-370/10-301
Download: ML102650152 (25)

Text

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2010 MNS SR( RC Examination ES 401, Rv9 Combined PWR Written Examination Outline Form ES-4ui-2/3 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description K5.01 Reactor Coolant Pump System (RCPS) TIG 2/1 RO 3.3 SRO 3.9 SYSOO3 2501 Knowledge of the operational implications of the following The relationship between the RCPS flow rate and the nuclear core operating concepts as they apply to the RCPS: (CFR: 41.5 I 45.7) parameters (quadrant power tilt, imbalance, DNB rate, local power density, difference in loop T-hot pressure)

SYSOO4 K6.02 Chemical and Volume Control System T/G 2/1 RO 2 2.5 SRO 2.6 2502 Knowledge of the effect of a loss or malfunction on the Demineralizers and ion exchangers following CVCS components: (CFR: 41.7 / 45.7)

SYSOO5 A1.02 Residual Heat Removal System (RHRS) TIG 2/1 RO 3.3 3 SRO 3.4 2503 Ability to predict and/or monitor changes in parameters RHR flow rate (to prevent exceeding design limits) associated with operating the RHRS controls including: (CFR: 41.5 / 45.5)

SYSOO5 K3.01 Residual Heat Removal System (RHRS) T/G 2/1 RO 4 3.9 SRO 4.0 2504 Knowledge of the effect that a loss or malfunction of the RCS RHRS will have on the following: (CFR: 41.7 / 45.6)

SYSOO6 K1.14 Emergency Core Cooling System (ECCS) T/G 2/1 RO 34*

5 3.0 SRO 2505 Knowledge of the physical connections and/or cause- lAS effect relationships between the ECCS and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)

SYSOO6 K6.02 Emergency Core Cooling System (ECCS) TIG 2/1 RO 6 3.4 SRO 3.9 2506 Knowledge of the effect of a loss or malfunction on the Core flood tanks (accumulators) following will have on the ECCS: (CFR: 41.7 I 45.7)

SYSOO7 K5.02 Pressurizer Relief TanklQuench Tank System (PRTS) T/G2/1 7 RO 3.1 SRO 3.4 2507 Knowledge of the operational implications of the following Method of forming a steam bubble in the PZR concepts as they apply to PRTS: (CFR: 41.5 / 45.7)

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2010 MNS SR 1 RC Examination ES 401 rv 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question K/A Number K/A System TierlGroup Importance RO/SRO K/A Description 8 SYSOO8 K4.02 Component Cooling Water System (CCWS) T!G 2 / 1 RO 2.9 SRO 2.7 2508 Knowledge of CCWS design feature(s) and/or interlock(s) Operation of the surge tank, including the associated valves and controls which provide for the following: (CFR: 41.7) 9 SYSOI 0 Al .07 Pressurizer Pressure Control System (PZR PCS) T/G 2/1 RO 3.7 SRO 3.7 2509 Ability to predict and/or monitor changes in parameters RCS pressure (to prevent exceeding design limits) associated with operating the PZR PCS controls including: (CFR: 41.5 /

45.5) 10 SYSOI2 A2.02 Reactor Protection System (RPS) T/G 2/1 RO 3.6 SRO 3.9 2510 Ability to (a) predict the impacts of the following Loss of instrument power malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43.5/45.3/45.5) -___________________________________________

II SYSOI3 K2.01 Engineered Safety Features Actuation System (ESFAS) TIG 2 / 1 RO 3.6* SRO 3.8 2511 Knowledge of bus power supplies to the following: (CFR: ESFAS/safeguards equipment control 41.7) 12 SYSO22 2.4.45 Containment Cooling System (CCS) TIG 2! 1 RO 4.1 SRO 4.3 2512 SYSO22 GENERIC Ability to prioritize and interpret the significance of each annunciator or alarm.

(CFR: 41.101 43.5 145.3/ 45.12) 13 SYSO22 Kl.0l Containment Cooling System (CCS) T/G 2! 1 RO 3.5 SRO 3.7 2513 Knowledge of the physical connections and/or cause- SWS/cooling system effect relationships between the CCS and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)

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2010 MNS SR( RC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-4ui-2/3 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description 14 SYSO59 A2.06 Main Feedwater (MFW) System TIG 2/1 RO 2.7* SRO 2.9*

2514 Ability to (a) predict the impacts of the following Loss of steam flow to MFW system malfunctions or operations on the MEW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CER: 41.5 / 43.5 / 45.3 /45.13) 15 SYSO25 K6.O1 Ice Condenser System T/G 2/1 RO 34* SRO 3.6*

2515 Knowledge of the effect of a loss or malfunction of the Upper and lower doors of the ice condenser following will have on the ice condenser system: (CFR:

41.7 / 45.7) 16 SYSO26 A2.09 Containment Spray System (CSS) T/G 2/1 RO 2.5* SRO 2.9*

2516 Ability to (a) predict the impacts of the following Radiation hazard potential of BWST malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13) 17 SYSO39 K4.05 Main and Reheat Steam System (MRSS) T/G 2/1 RO 3.7 SRO 3.7 2517 Knowledge of MRSS design feature(s) and/or interlock(s) Automatic isolation of steam line which provide for the following: (CFR: 41.7) 18 SYSO59 2.4.31 Main Feedwater (MFW) System T/G 2/1 RO 4.2 SRO 4.1 2518 SYSO59 GENERIC Knowledge of annunciator alarms, indications, or response procedures. (CFR:

41.10 /45.3) 19 SYSO6I K2.O1 Auxiliary I Emergency Feedwater (AFW) System T/G 2/1 RO 3.2* SRO 3.3 2519 Knowledge of bus power supplies to the following: (CFR: AFW system MOVs 41.7)

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2010 MNS SR 1 RC Examination ES 401, v9 Combined PWR Written Examination Outline Form ES-4U1-2/3 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description 20 SYSO62 A3.05 AC Electrical Distribution System T/G 2 I 1 RO 3.5 SRO 3.6 2520 Ability to monitor automatic operation of the ac Safety-related indicators and controls distribution system, including: (CFR: 41.7 / 45.5) 21 SYSO63 A3.O1 DC Electrical Distribution System TIG 2/1 RO 2.7 SRO 3.1 2521 Ability to monitor automatic operation of the DC electrical Meters, annunciators, dials, recorders, and indicating lights system, including: (CFR: 41.7 / 45.5)

SYSO63 K4.O1 DC Electrical Distribution System T/G 2 I 1 3*Q*

22 RO 2.7 SRO 2522 Knowledge of DC electrical system design feature(s) Manual/automatic transfers of control and/or interlock(s) which provide for the following: (CFR:

41.7) 23 SYSO64 A4.08 Emergency Diesel Generator (EDIG) System T/G 2 / 1 RO 3.2* SRO 3.2*

2523 Ability to manually operate and/or monitor in the control Opening of the ring bus room: (CFR: 41.7/45.5 to 45.8) 24 SYSO73 K1.O1 Process Radiation Monitoring (PRM) System T/G 2/1 RO 3.6 SRO 3.9 2524 Knowledge of the physical connections and/or cause- Those systems served by PRMs effect relationships between the PRM system and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) 25 SYSO76 K3.07 Service Water System (SWS) T/G 2/1 RO 3.7 SRO 3.9 2525 Knowledge of the effect that a loss or malfunction of the ESF loads SWS will have on the following:_(CFR: 41.7 / 45.6) 26 SYSO78 A4.O1 Instrument Air System (lAS) T/G 2 / 1 RO 3.1 SRO 3.1 2526 Ability to manually operate and/or monitor in the control Pressure gauges room: (CFR: 41.7/45.5 to 45.8)

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2010 MNS SR 1 RC Examination ES 401, tv9 Combined PWR Written Examination Outline Form ES-4U1-213 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description 27 SYSO78 K3.02 Instrument Air System (lAS) TIG 2 I 1 RO 3.4 SRO 3.6 2527 Knowledge of the effect that a loss or malfunction of the Systems having pneumatic valves and controls lAS will have on the following: (CFR: 41.7 / 45.6)

SYSIO3 A4.04 Containment System TIG 2/1 RO 35* 3*5*

28 SRO 2528 Ability to manually operate and/or monitor in the control Phase A and phase B resets room: (CFR: 41.7 / 45.5 to 45.8) 29 SYSOOI K6.13 Control Rod Drive System T/G 212 RO 3.6 SRO 3.7 2529 Knowledge of the effect of a loss or malfunction on the Location and operation of RPIS following CRDS components: (CFR: 41.7/45.7) 30 SYSOII K3.02 Pressurizer Level Control System (PZR LCS) T/G 2/2 RO 3.5 SRO 3.7 2530 Knowledge of the effect that a loss or malfunction of the RCS PZR LCS will have on the following: (CFR: 41.7 / 45.6) 31 SYSOI4 2.4.31 Rod Position Indication System (RPIS) T/G 2/2 RO 4.2 SRO 4.1 2531 SYSO14 GENERIC Knowledge of annunciator alarms, indications, or response procedures. (CFR:

41.10/45.3) 32 SYSOI5 K2.O1 Nuclear Instrumentation System (NIS) T/G 2/2 RO 3.3 SRO 3.7 2532 Knowledge of bus power supplies to the following: NIS channels, components, and interconnections (CFR: 41.7) 33 SYSOI6 K4.O1 Non-Nuclear Instrumentation System (NNIS) T/G 2 / 2 RO 2.8* SRO 2.9*

2533 Knowledge of NNIS design feature(s) and/or interlock(s) Reading of NNIS channel values outside control room which provide for the following: (CFR: 41.7)

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2010 MNS SR RC Examination ES 401, rv9 Combined PWR Written Examination Outline Form ES-401-2/3 Question K/A Number K/A System Tier/Group Importance ROISRO K/A Description SYSO28 A2.01 Hydrogen Recombiner and Purge Control System (HRPS) TIG 2/2 RO 3*4* SRO 3.6*

34 2534 Malfunctions or operations on the HRPS; and (b) based Hydrogen recombiner power setting, determined by using plant data book on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 /43.5 /45.3 I 45.13) 35 SYSO33 A1.02 Spent Fuel Pool Cooling System (SFPCS) TIG 2/2 RO 2.8 SRO 3.3 2535 Ability to predict and/or monitor changes in parameters Radiation monitoring systems (to prevent exceeding design limits) associated with Spent Fuel Pool Cooling System operating the controls including: (CFR: 41.5/45.5) 36 SYSO35 KI .01 Steam Generator System (SIGS) T/G 2/2 RO 4.2 SRO 4.5 2536 Knowledge of the physical connections and/or cause- MFWIAFW systems effect relationships between the S/GS and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) 37 SYSO45 K5.23 Main Turbine Generator (MTIG) System T/G 2 / 2 RO 2.7 SRO 2.8 2537 Knowledge of the operational implications of the following Relationship between rod control and RCS boron concentration during T/G concepts as the apply to the MT/B System: (CFR: 41.5 / load increases 45.7)

SYSO7I K4.06 Waste Gas Disposal System (WGDS) T/G 2 / 2 2.7* 35*

38 RO SRO 2538 Knowledge of design feature(s) and/or interlock(s) which Sampling and monitoring of waste gas release tanks provide for the following: (CFR: 41.7) 39 EPEOO7 EK3.01 Reactor Trip T/G 1/1 RO 4.0 SRO 4.6 2539 Knowledge of the reasons for the following as the apply Actions contained in EOP for reactor trip to a reactor trip: (CFR 41.5/41.10 / 45.6 / 45.13)

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2010 MNS SR( RC Examination ES 401, ev 9 Combined PWR Written Examination Outline Form ES-4Ui-2/3 Question K/A Number KIA System Tier/Group Importance ROISRO K/A Description 40 APEOO8 AK1.01 Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck 0 TIG 1 Il RO 3.2 SRO 3.7 2540 Knowledge of the operational implications of the following Thermodynamics and flow characteristics of open or leaking valves concepts as they apply to a Pressurizer Vapor Space Accident: (CFR 41.8 / 41.10 / 45.3)

EPEOO9 EK2.03 Small Break LOCA TIG 1 /1 RO 3.0 SRO 33*

41 2541 Knowledge of the interrelations between the small break S/Gs LOCA and the following: (CFR 41.7 / 45.7) 42 APEOI 51017 2.1.32 Reactor Coolant Pump (RCP) Malfunctions T/G 1 / I RO 3.8 SRO 4.0 2542 APEO15/017 GENERIC Ability to explain and apply system limits and precautions. (CFR: 41.10/43.2/

45.12)

APEO22 AAI .09 Loss of Reactor Coolant Makeup T/G 1 1 RO 3.2 SRO 3.3 43 2543 Ability to operate and / or monitor the following as they RCP seal flows, temperatures, pressures, and vibrations apply to the Loss of Reactor Coolant Makeup: (CFR 41.7 I 45.5 / 45.6) 44 APEO25 AAI.12 Loss of Residual Heat Removal System (RHRS) T/G 1 / I RO 3.6 SRO 3.5 2544 Ability to operate and / or monitor the following as they RCS temperature indicators apply to the Loss of Residual Heat Removal System:

(CFR 41.7 / 45.5 I 45.6) 45 APEO27 AK2.03 Pressurizer Pressure Control System (PZR PCS) Malfunction T/G 1 /1 RO 2.6 SRO 2.8 2545 Knowledge of the interrelations between the Pressurizer Controllers and positioners Pressure Control Malfunctions and the following: (CFR 41.7 I 45.7) 46 APEO4O AA2.03 Steam Line Rupture T/G 1 Il RO 4.6 SRO 4.7 2546 Ability to determine and interpret the following as they Difference between steam line rupture and LOCA apply to the Steam Line Rupture: (CFR: 43.5 / 45.13)

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2010 MNS SR RC Examination ES 401, rv9 Combined PWR Written Examination Outline Form ES-401-2/3 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description 47 APEO54 AKI .02 Loss of Main Feedwater (MFW) TIG 1 /1 RO 3.6 SRO 4.2 2547 Knowledge of the operational implications of the following Effects of feedwater introduction on dry S/G concepts as they apply to Loss of Main Feedwater (MFW):_(CFR 41.8/41.10 / 45.3) 48 EPEO55 EA2.01 Loss of Offsite and Onsite Power (Station Blackout) T/G 1 / 1 RO 3.4 SRO 3.7 2548 Ability to determine or interpret the following as they apply Existing valve positioning on a loss of instrument air system to a Station Blackout: (CFR 43.5 / 45.13) 49 APEO56 AA2.50 Loss of Offsite Power T/G 1 I 1 RO 2.8* SRO 3.1 2549 Ability to determine and interpret the following as they That load and VAR limits, alarm setpoints, frequency and voltage limits for apply to the Loss of Offsite Power: (CFR: 43.5 / 45.13) ED/Gs are not being exceeded 50 APEO58 2.1.27 Loss of DC Power TIG 1 /1 RO 3.9 SRO 4.0 2550 APEO58 GENERIC Knowledge of system purpose and/or function. (CFR: 41.7) 51 APEO62 AK3.04 Loss of Nuclear Service Water T/G 1 Il RO 3.5 SRO 3.7 2551 Knowledge of the reasons for the following responses as Effect on the nuclear service water discharge flow header of a loss of CCW they apply to the Loss of Nuclear Service Water: (CFR 41.4, 41.8 /45.7) 52 APEO65 2.4.20 Loss of Instrument Air T/G 1 /1 RO 3.8 SRO 4.3 2552 APL065 GENERIC Knowledge of the operational implications of EOP warnings, cautions, and notes. (CFR: 41.10/43.5/45.13) 53 APEO77 AK2.03 Generator Voltage and Electric Grid Disturbances T/G 1 /0 RO 3.0 SRO 3.1 2553 Knowledge of the interrelations between Generator Sensors, detectors, indicators Voltage and Electric Grid Disturbances and the following:

(CFR: 41.4, 41.5, 41.7, 41.10/45.8)

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2010 MNS SR RC Examination ES 401 Rev 9 Combined PWR Written Examination Outline Form ES-4u i-213 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description 54 WEO4 EKI.3 LOCA Outside Containment TIG i/l RO 3.5 SRO 3.9 2554 Knowledge of the operational implications of the following Annunciators and conditions indicating signals, and remedial actions concepts as they apply to the (LOCA Outside associated with the (LOCA Outside Containment).

Containment)

(CFR: 41.8 /41.10, 45.3) 55 WEO5 EK3.2 Loss of Secondary Heat Sink TIG 1/1 RO 3.7 SRO 4.1 2555 Knowledge of the reasons for the following responses as Normal, abnormal and emergency operating procedures associated with (Loss they apply to the (Loss of Secondary Heat Sink) of (CFR: 41.5/41.10, 45.6, 45.13) Secondary Heat Sink).

56 WEI I EAI .1 Loss of Emergency Coolant Recirculation T/G 1/1 RO 3.9 SRO 4.0 2556 Ability to operate and / or monitor the following as they Components, and functions of control and safety systems, including apply to the (Loss of Emergency Coolant Recirculation) instrumentation, signals, interlocks, failure modes, and automatic and manual (CFR: 41.7 /45.5/45.6) features.

57 APEO24 AK2.04 Emergency Boration T/G 1 /2 RO 2.6 SRO 25 2557 Knowledge of the interrelations between Emergency Pumps Boration and the following: (CFR 41.7 / 45.7) 58 APEO28 AKI.01 Pressurizer (PZR) Level Control Malfunction T/G 112 RO 2.8* SRO 3.1*

2558 Knowledge of the operational implications of the following PZR reference leak abnormalities concepts as they apply to Pressurizer Level Control Malfunctions: (CFR 41.8 141.10 /45.3) 59 APEO32 2.1.27 Loss of Source Range Nuclear Instrumentation T/G 1/2 RO 3.9 SRO 4.0 2559 APEO32 GENERIC Knowledge of system purpose and/or function. (CFR: 41.7) 60 APEO33 AAI.03 Loss of Intermediate Range Nuclear Instrumentation TIG 1/2 RO 3.0* SRO 3.2*

2560 Ability to operate and / or monitor the following as they Manual restoration of power apply to the Loss of Intermediate Range Nuclear Instrumentation: (CFR 41.7 I 45.5 I 45.6)

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2010 MNS SR RC Examination ES 401, cev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description 61 APEO59 AK1.01 Accidental Liquid Radioactive-Waste Release T/G 1/2 RO 2.7 SRO 3.1 2561 Knowledge of the operational implications of the following ypes of radiation, their units of intensity and the location of the sources of concepts as they apply to Accidental Liquid Radwaste radiation in a nuclear power plant Release: (CFR 41.8/41.10 /45.3) 62 APEO68 AAI.01 Control Room Evacuation T!G 1/2 RO 4.3 SRO 4.5 2562 Ability to operate and I or monitor the following as they S/G atmospheric relief valve apply to the Control Room Evacuation: (CFR 41.7 / 45.5 /

45.6) 63 APEO69 2.4.50 Loss of Containment Integrity T/G 1 / 2 RO 4.2 SRO 4.0 2563 APEO69 GENERIC Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. (CFR: 41.10/43.5/45.3) 64 EPEO74 EA2.01 Inadequate Core Cooling T/G 1 /2 RO 4.6 SRO 4.9 2564 Ability to determine or interpret the following as they apply Subcooling margin to a Inadequate Core Cooling: (CFR 43.5 /45.13) 65 WEO9 EK3.1 Natural Circulation Operations T/G 1/2 RO 3.3 SRO 3.6 2565 Knowledge of the reasons for the following responses as Facility operating characteristics during transient conditions, including coolant they apply to the (Natural Circulation Operations) chemistry and the effects of temperature, pressure, and reactivity changes and (CFR: 41.5 / 41.10, 45.6, 45.13) operating limitations and reasons for these operating characteristics.

66 GEN2.1 2.1.25 GENERIC -Conduct of Operations T/G 3/0 RO 3.9 SRO 4.2 2566 Conduct of Operations Ability to interpret reference materials, such as graphs, curves, tables, etc.

(CFR: 41.10 /43.5 /45.12) 67 GEN2.1 2.1.26 GENERIC Conduct of Operations T/G / 0 RO 3.4 SRO 3.6 2567 Conduct of Operations Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen). (CFR: 41.10 /45.12)

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2010 MNS SR( RC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-4ui-2/3 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description 68 GEN2.2 2.2.25 GENERIC Equipment Control TIG 3/0 RO 3.2 SRO 4.2 2568 Equipment Control Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 / 41.7 / 43.2) 69 GEN2.2 2.2.42 GENERIC - Equipment Control T/G 3/0 RO 3.9 SRO 4.6 2569 Equipment Control Ability to recognize system parameters that are entry-level conditions for Technical Specifications. (CFR: 41.7 / 41.10 / 43.2 / 43.3 / 45.3) 70 GEN2.3 2.3.14 GENERIC Radiation Control TIG 3O RO 3.4 SRO 3.8 2570 Radiation Control Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12 / 43.4 / 45.10) 71 GEN2.3 2.3.5 GENERIC Radiation Control TIG 30 RO 2.9 SRO 2.9 2571 Radiation Control Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

(CFR: 41.11 /41.12/43.4/45.9) 72 GEN2.3 2.3.7 GENERIC Radiation Control T/G 3/0 RO 3.5 SRO 3.6 2572 Radiation Control Ability to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12 / 45.10) 73 GEN2.4 2.4.17 GENERIC - Emergency Procedures! Plan T/G 30 RO 3.9 SRO 4.3 2573 Emergency Procedures I Plan Knowledge of EOP terms and definitions. (CFR: 41.10/ 45.13) 74 GEN2.4 2.4.39 GENERIC Emergency Procedures I Plan T/G /0 RO 3.9 SRO 3.8 2574 Emergency Procedures / Plan Knowledge of RO responsibilities in emergency plan implementation. (CFR:

41.10/45.11) 75 GEN2.4 2.4.50 GENERIC Emergency Procedures I Plan TIG 3/0 RO 4.2 SRO 4.0 2575 Emergency Procedures / Plan Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. (CFR: 41.10 / 43.5 / 45.3)

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2010 MNS SR RC Examination ES 401, rv 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description 76 SYSOO3 2.1.20 Reactor Coolant Pump System (RCPS) TIG 2/1 RO 4.6 SRO 4.6 2576 SYSOO3 GENERIC Ability to interpret and execute procedure steps. (CFR: 41.10/43.51 45.12) 77 SYSOO5 A2.02 Residual Heat Removal System (RHRS) TIG 2/1 RO 3.5 SRO 3.7 2577 Ability to (a) predict the impacts of the following Pressure transient protection during cold shutdown malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13) 78 SYSO6I A2.06 Auxiliary! Emergency Feedwater (AFW) System TIG 2/1 RO 2.7 SRO 3.0 2578 Ability to (a) predict the impacts of the following Back leakage of MFW malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)

SYSO76 A2.01 Service Water System (SWS) 3*5* 37*

79 T/G 2/1 RO SRO 2579 Ability to (a) predict the impacts of the following Loss of SWS malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45/3 / 45/13) 80 SYSO63 2.1.23 DC Electrical Distribution System T/G 2/1 RO 4.3 SRO 4.4 2580 SYSO63 GENERIC Ability to perform specific system and integrated plant procedures during all modes of plant operation. (CFR: 41.10 / 43.5 / 45.2 / 45.6)

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2010 MNS SR RC Examination ES 401, Rev9 Combined PWR Written Examination Outline Form ES-4ui-2/3 a

Question K/A Number K/A System Tier/Group Importance ROISRO K/A Description 81 SYSOI5 A2.01 Nuclear Instrumentation System (NIS) TIG 2)2 RO 3.5 SRO 3.9 2581 Ability to (a) predict the impacts of the following Power supply loss or erratic operation malfunctions or operations on the NIS; and (b based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 I 43.5 / 45.3 / 45.5) 82 SYSO41 2.4.11 Steam Dump System (SDS)!Turbine Bypass Control T/G 2/2 RO 4.0 SRO 4.2 2582 SYSO41 GENERIC Knowledge of abnormal condition procedures. (CFR: 41.10 /43.5 /45.13) 83 SYSOO2 A2.02 Reactor Coolant System (RCS) T/G 2 / 2 RO 4.2 SRO 4.4 2583 Ability to (a) predict the impacts of the following Loss of coolant pressure malfunctions or operations on the RCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.5) 84 APEOI 51017 AA2.02 Reactor Coolant Pump (RCP) Malfunctions T/G 1 /1 RO 2.8 SRO 3.0 2584 Ability to determine and interpret the following as they Abnormalities in RCP air vent flow paths and/or oil cooling system apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): (CFR43.5145.13) 85 APEO22 2.4.46 Loss of Reactor Coolant Makeup T/G 1 1 RO 4.2 SRO 4.2 2585 APEO22 GENERIC Ability to verify that the alarms are consistent with the plant conditions. (CFR:

41.10 /43.5 / 45.3 /45.12) 86 APEO27 AA2.10 Pressurizer Pressure Control System (PZR PCS) Malfunction T/G 1 / 1 RO 3.3 SRO 3.6 2586 Ability to determine and interpret the following as they PZR heater energized/de-energized condition apply to the Pressurizer Pressure Control Malfunctions:

(CFR: 43.5/45.13)

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2010 MNS SR RC Examination ES 401, Rev9 Combined PWR Written Examination Outline Form ES-4U1-2/3 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description 87 EPEO38 2.4.11 Steam Generator Tube Rupture (SGTR) TIG 1 I 1 RO 4.0 SRO 4.2 2587 EPEO38 GENERIC Knowledge of abnormal condition procedures. (CFR: 41.10 /43.5 /45.13) 88 APEO58 AA2.02 Loss of DC Power T/G 1 /1 RO 33* SRO 3.6 2588 Ability to determine and interpret the following as they 1 25V dc bus voltage, low/critical low, alarm apply to the Loss of DC Power: (CFR: 43.5/ 45.13) 89 APEO62 2.4.47 Loss of Nuclear Service Water TIG 1 1 RO 4.2 SRO 4.2 2589 APEO62 GENERIC Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material. (CFR: 41.10/43.5/

45.12) 90 APEOO3 2.2.40 Dropped Control Rod T/G 1/2 RO 3.4 SRO 4.7 2590 APEOO3 GENERIC Ability to apply Technical Specifications for a system. (CFR: 41.10 / 43.2 I 43.5

/45.3) 91 APEO69 AA2.02 Loss of Containment Integrity T/G 1/2 RO 3.9 SRO 4.4 2591 Ability to determine and interpret the following as they Verification of automatic and manual means of restoring integrity apply to the Loss of Containment Integrity: (CFR: 43.5 /

45.13) 92 APEO76 2.4.11 High Reactor CoolantActivity T/G 1/2 RO 4.0 SRO 4.2 2592 APEO76 GENERIC Knowledge of abnormal condition procedures. (CFR: 41.10 / 43.5 I 45.13) 93 WEO3 2.4.46 LOCA Cooldown and Depressurization T/G 1 /2 RO 4.2 SRO 4.2 2593 WEO3 GENERIC Ability to verify that the alarms are consistent with the plant conditions. (CFR:

41.10/43.5/45.3/45.12)

Page 14 of 15

2010 MNS SR RC Examination ES 401, l-cev 9 Combined PWR Written Examination Outhne Form ES-4u 1-2/3 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description 94 GEN2.1 2.1.4 GENERIC -Conduct of Operations TIG 3/0 RO 3.3 SRO 3.8 2594 Conduct of Operations Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc. (CFR: 41.10/43.2) 95 GEN2.1 2.1.8 GENERIC-Conductof Operations T/G 3/0 RO 3.4 SRO 4.1 2595 Conduct of Operations Ability to coordinate personnel activities outside the control room. (CFR: 41.10

/45.5/45.12/45.13) 96 GEN2.2 2.2.40 GENERIC Equipment Control TIC 3 / 0 RO 3.4 SRO 4.7 2596 Equipment Control Ability to apply Technical Specifications for a system. (CFR: 41.10/43.2/ 43.5

/45.3) 97 GEN2.2 2.2.6 GENERIC Equipment Control T/G ° RO 3.0 SRO 3.6 2597 Equipment Control Knowledge of the process for making changes to procedures. (CFR: 41.10 I 43.3 /45.13) 98 GEN2.3 2.3.12 GENERIC Radiation Control TIC 30 RO 3.2 SRO 3.7 2598 Radiation Control Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 41.12 /45.9/

45.10) 99 GEN2.3 2.3.14 GENERIC Radiation Control T/G 30 RO 3.4 SRO 3.8 2599 Radiation Control Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12/43.4/ 45.10) 100 GEN2.4 2.4.40 GENERIC Emergency Procedures I Plan T/G 3/0 RO 2.7 SRO 4.5 2600 Emergency Procedures I Plan Knowledge of SRO responsibilities in emergency plan implementation. (CFR:

41.10 I 43.5 I 45.11)

Page 15 of 15

FOR REVIEW ONLY DO NOT DISTRIBUTE -

Reference Listfor: 2010 MNS RO NRC Examination Question Reference List Number 34 u-I Data BookCurve 1.8 EP Generic Enc G-1 End. 4 37 Data Book Sect. 1.3 Enc. 4.3 40 Steam Tables 53 unit i & 2 Generator Capability Curves 66 EPI1IAI5000IF-0 Page 5 of 11 Printed 5/14/2010 2:55:16PM Page 1 of 1

ES-3d Administrative Topics Outline Form ES-301-1 Draft Facility: McGuire Date of Examination: 8/2/10 Examination Level: RO Operating Test Number: Nb-i Administrative Topic Type Code* Describe activity to be performed (see Note) 2.1.37 (4.3) Knowledge of procedures, guidelines or Conduct of Operations limitations associated with reactivity M, R management JPM: Perform an ECP 2.1.25 (3.9) Ability to interpret reference materials, such Conduct of Operations as graphs, curves, tables, etc.

D, P, R JPM: Determine Boric Acid Addition to FWST 2.2.12 (3.7) Knowledge of Surveillance Procedures.

Equipment Control M, R JPM: Perform a Manual NC Leakage Calculation 2.3.11 (3.8) Ability to control radiation releases Radiation Control M,R JPM: Perform a Unit Vent Flow Calculation of a Containment Air Release 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, (0) (S)imulator, (0) or Class(R)oom (4)

(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) (1)

(N)ew or (M)odified from bank (> 1) (3)

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

NUREG-1 021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-l Draft RO Admin JPM Summary Ala This is a modified JPM using Bank JPM-RT-RB:073 as its basis. The operator will be told that Reactor Startup is an hour away, and provided with a set of initial conditions.

The operator will be asked to perform an Estimated Critical Position (ECP) in accordance with OPIO/A16100/06 (Reactivity Balance Calculation), Enclosure 4.2 (Estimated Critical Rod Position). During the course of the ECP, the operator will be given a set of power history conditions, and asked to perform a Shutdown Fission Product Correction calculation in accordance with OP/0/A/61 00/06 (Reactivity Balance Calculation), Enclosure 4.8 (Shutdown Fission Product Correction Calculation) in support of the ECP. This is the same JPM as the SRO Exam.

Aib This is a bank JPM, and previously used on the 2009 NRC Operating Test. The operator wHI be told that a leak, which is now isolated has lowered the FWST level to 440 inches, and that it has been decided to use the Recycle Holdup Tank (RHT) to refill the FWST. The operator will be told that Enclosure 4.4, (FWST Makeup Using the RHT), of OP/l/A/6200/014 (Refueling Water System) is in progress and completed through Step 3.9, and provided with Chemistry Data for the BAT and RHT. The operator will then be directed to determine the amount of Boric Acid needed to raise the FWST level to 480 using the RHT in accordance with Step 3.10 of Enclosure 4.4 of OP/l/A/6200/014 (Refueling Water System). The operator will be expected to calculate the amount of Boric Acid that must be added from the BAT to refill the FWST.

A2 This is a modified JPM using Bank JPMs ADM-NRC-A2-05 and 12 as its basis. The operator will be told that Unit I is at 100% power, the Unit I QAC point M1L4554 is out of service, and that PT/l/A14200/040 (Reactor Coolant Leakage Detection) has been completed showing that NCS Leakage is 1.6 gpm. The operator will be given Enclosure 13.2 (NC Leakage Determination Using Manual Calculations) of PT/1/A/4150/OOIB (Reactor Coolant Leakage Calculation) with the necessary raw data compiled on a Data Sheet; and directed to complete the calculations within the Enclosure. The operator will be expected to complete all calculations, and identify any Technical Specification Limits that have been exceeded.

A3 This is a modified JPM using Bank JPM ADM-NRC-A3-010 as its basis. The operator will be told that GWR Package # 2010013 for Unit I Containment Air Release is currently in use to conduct a series of Containment air releases, and that during the first release, conducted using Enclosure 4.2 (Air Release Mode With VQ Flow Monitor Operable) of OP/l/A16450/017 (Containment Air Addition and Release), the Unit 1 VQ Monitor became inoperable. The operator will be told that the crew stopped the release and continued the air release using Enclosure 4.3 (Air Release Mode with VQ Flow Monitor Inoperable) of OP/l/A16450/017 (Containment Air Addition and Release), and that three previous releases have been made; including the one which was made with the Unit 1 VQ Flow Monitor in operation. Finally, the operator will be provided with the pertinent data for the current release, and then be directed to calculate the volume released for the current release and to determine the total volume released from the Containment during all releases. The operator will be expected to calculate the volume of air released from the Containment during the final release, and determine the total volume of air released in the series of four releases.

NUREG-1 021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Draft Facility: McGuire Date of Examination: 8/2/10 Examination Level: SRO Operating Test Number: Nb-i Administrative Topic Type Code* Describe activity to be performed (see Note) 2.1.37 (4.6) Knowledge of procedures, guidelines or Conduct of Operations limitations associated with reactivity M, R management JPM: Perform an ECP 2.1.25 (4.2) Ability to interpret reference materials, such Conduct of Operations as graphs, curves, tables, etc.

D, P, R JPM: Determine Boric Acid Addition to FWST 2.2.12 (4.1) Knowledge of Surveillance Procedures.

Equipment Control M,R JPM: Perform/Review a Manual NC leakage Calculation 2.3.11 (3.8) Ability to control radiation releases Radiation Control M,R JPM: Perform a Unit Vent Flow Calculation of a Containment Air Release 2.4.44 (4.4) Knowledge of emergency plan protective Emergency action recommendations.

Procedures/Plan N, R JPM: Provide an updated PAR 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, (0) (S)imulator, (0) or Class(R)oom (5)

(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) (1)

(N)ew or (M)odified from bank ( 1) (4)

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

NUREG-1 021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-l Draft SRO Admin JPM Summary Ala This is a modified JPM using Bank JPM-RT-RB:073 as its basis. The operator will be told that Reactor Startup is an hour away, and provided with a set of initial conditions. The operator will be asked to perform an Estimated Critical Position (ECP) in accordance with 0P101A16100106 (Reactivity Balance Calculation),

Enclosure 4.2 (Estimated Critical Rod Position). During the course of the ECP, the operator will be given a set of power history conditions, and asked to perform a Shutdown Fission Product Correction calculation in accordance with OP/0/A/6100/06 (Reactivity Balance Calculation), Enclosure 4.8 (Shutdown Fission Product Correction Calculation) in support of the ECP. This is the same JPM as the RO Exam.

Aib This is a bank JPM, and previously used, on the 2009 Operating Test. The operator will be told that a leak, which is now isolated has lowered the FWST level to 440 inches, below the Technical Specification Limit, and that it has been decided to use the Recycle Holdup Tank (RHT) to refill the FWST. The operator will be told that Enclosure 4.4 (FWST Makeup Using the RHT), of OP/l/A/6200/014 (Refueling Water System) is in progress and completed through Step 3.10, and provided with Chemistry Data for the BAT and RHT. The operator will then be directed to perform the Independent Verification (SRO aspect) of the calculation in Step 3.10 of Enclosure 4.4 to determine the amount of Boric Acid that must be added from the Boric Acid Tank (BAT), in order to raise the FWST Level to 480 using the RHT. The operator will discover two errors within the previous calculation, and determine the correct volume of Boric Acid to add. Following this, the operator will be given a makeup flowrate to the FWST and asked to identify the impact on the Technical Specification ACTION.

The operator will be required to identify that ACTION C is applicable after one hour.

A2 This is a modified JPM using Bank JPMs ADM-NRC-A2-05 and 12 as its basis.

The operator will be told that Unit 1 is at 100% power, the Unit 1 QAC point Ml L4554 is out of service, and that PT/1/A14200/040 (Reactor Coolant Leakage Detection) has been completed showing that NCS Leakage is 1.6 gpm. The operator will be given Enclosure 13.2 (NC Leakage Determination Using Manual Calculations) of PT/1/A/4150/OOIB (Reactor Coolant Leakage Calculation) with the necessary raw data compiled on a Data Sheet; and directed to complete the calculations within the Enclosure. The operator will be expected to complete all calculations in accordance with the provided Key, identify any Technical Specification Limits that have been exceeded, and (SRO aspect) identify with all Technical Specification ACTION.

A3 This is a modified JPM using Bank JPM ADM-NRC-A3-010 as its basis. The operator will be told that GWR Package # 2010013 for Unit 1 Containment Air Release is currently in use to conduct a series of Containment air releases, and that during the first release, conducted using Enclosure 4.2 (Air Release Mode NUREG-l 021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Draft With VQ Flow Monitor Operable) of OPI1/A164501017 (Containment Air Addition and Release), the Unit 1 VQ Monitor became inoperable. The operator will be told that the crew stopped the release and continued the air release using Enclosure 4.3 (Air Release Mode with VQ Flow Monitor Inoperable) of 0P111A164501017 (Containment Air Addition and Release), and that three previous releases have been made; including the one which was made with the Unit I VQ Flow Monitor in operation. Finally, the operator will be provided with the pertinent data for the current release, and then be directed to calculate the volume released for the current release and to determine the total volume released from the Containment during all releases. The operator will be expected to calculate the volume of air released from the Containment during the final release, and determine the total volume of air released in the series of four releases. This is the same JPM as the RO Exam.

A4 This is a new JPM. The operator will be placed in a post-accident condition with a Large Break LOCA with a release from the Containment. The operator will be told that a General Emergency has been declared, and provided with the initial Protective Action Recommendation (PAR). The operator will be given a subsequent set of plant conditions and meteorological data, and asked to provide an updated PAR in accordance with Enclosure 4.4 (Offsite Protective Recommendations) of RP101B157001029 (Notifications to Offsite Agencies from the Control Room). The operator will be expected to determine the Updated PAR for the subsequent conditions.

NUREG-1 021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Draft Facility: McGuire Date of Examination: 8/2/10 Exam Level (circle one): RO (only) / SRO(l) I SRO (U) Operating Test No.: N 10-1 Control Room Systems@ (8 for RO; 7 for SRO-l; 2 or 3 for SRO-U, including I ESF)

Type Code*

System / JPM Title Funn

a. 006 Emergency Core Cooling System S,D,EN 2 Transfer the NI Pumps from Cold Leg Recirc to Hot Leg Recirc

b. 005 Residual Heat Removal System S,D,A,L 4P Respond to ND System Malfunction While at Mid Loop

c. 056 Condensate System S,N,A 4S Swap HotwelllCM Booster Pumps

d. 026 Containment Spray System S,P,D,A,EN 5 Manually Actuate Containment Spray System

e. APE 077 Generator Voltage and Electric Grid Disturbances S,N,A 6 Separate From the Electrical Grid Due to Low Grid Frequency

f. 015 Nuclear Instrumentation System S,P,M 7 Restore Repaired Power Range Channel to Service

g. 075 Circulating Water System S, N 8 Isolate the Circulating Water System During Turbine Building Flooding

h. 010 Pressurizer Pressure Control System S,N,A 3 Remove Pressurizer Heaters from Service In-Plant Systems@ (3 for RO; 3 for SRO-l; 3 or 2 for SRO-U)

i. EPE 029 ATWS D,E 1 Locally Trip the Reactor

j. 008 Component Cooling Water System D,R,E 8 Makeup to the Unit I KC Surge Tanks

k. APE 057 Loss of Vital AC Electrical Instrument Bus D,R,E 6 Restore Power to KXB Power Panel Board Using Inverter SKX NUREG-1 021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Draft

@ All RO and SRO-l 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 / SRO-l / SRO-U (A)ternate path 4-6 (5) /4-6 (4) / 2-3 (3)

(C)ontrol room (D)irect from bank 9 (6) / 8 (6) I 4 (4)

(E)mergency or abnormal in-plant 1 (3) / 1 (3) / 1 (2)

(EN)gineered Safety Feature - / - I 1 (1) (Control Room system)

(L)ow-Power / Shutdown 1 (1) / 1 (1) / 1 (1)

(N)ew or (M)odified from bank including 1(A) 2(5)! 2 (4) / 1 (1)

(P)revious 2 exams 3 (2) / 3 (2)/i 2 (1) (Randomly Selected)

(R)CA 1 (2)/1 (2)!:l (2)

(S)imulator JPM Summary JPM A This is bank JPM-PS-NC-1 17. The operator will be told Unit 1 experienced a Loss of Coolant Accident six (6) hours ago, and that the plant is operating in the Cold Leg Recirculation mode. The operator will be directed to Transfer Recirculation to Hot Leg Recirc EP/1/A15000/ES-1.4 (Transfer to Hot Leg Recirculation). The operator will be expected to align the NI System to the Hot Leg Recirc Mode.

JPM B This is bank JPM PS-ND-183A. The operator will be told that Unit 1 is in Mode 5 with the NC System drained to approximately 10 inches, that 1A ND Pump is in service to all four Cold Legs, and that ND flow has suddenly increased. The operator will be directed to implement AP/1/A15500/19 (Loss of ND or ND System Leakage). The operator will be expected to take manual action to control flow, but recognize that attempts to manually control the RHR HX Outlet Valve and the Bypass Valve are ineffective (Alternate Path).

The operator will be expected to throttle ND flow to less than 3000 gpm using the Cold Leg injection valve(s) and position the ND Heat Exchanger Outlet Manual Loaders so that when these valves are repaired, the ND flow will not be affected.

JPM C This is a new JPM. The operator will be told that Unit I is operating at 90% power in preparation for a Condensate System Pump Swap. The operator will be directed to start the C Hotwell Pump, and place the A Hotwell Pump in standby, and then start the C Condensate Booster Pump and place the A Condensate Booster Pump in standby using Enclosure 4.5 of OP/1/A16250/001 (Condensate and Feedwater System). The operator will be expected to swap both sets of pumps in accordance with the procedure. During the course of swapping the Condensate Booster Pumps, the operator will recognize that the C Hotwell Pump Strainer High t2P Annunciator will alarm (Alternate Path). The operator will be expected to use the Annunciator Response Procedure and re-start the A Hotwell Pump, and stop the C Hotwell Pump.

JPM D This JPM is a bank JPM, and was previously used on the 2008 NRC Operating Test.

The operator will be placed in a Post-Reactor Trip situation and told that the crew has progressed from EP/1/A15000/E-0 (Reactor Trip and/or Safety Injection) to EP/1/N5000/ES-0.1 (Reactor Trip Response) due to a reactor trip. The operator will be told that after entry into ES-0.1 a LOCA occurs inside the Containment causing a Safety NUREG-1 021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Draft Injection; and that the crew has now left ES-0.1 for EP/1/A15000/FR-Z.1 (Response to High Containment Pressure) due to the Orange Path condition on the Containment Critical Safety Function, completing steps 1-9. The operator will be directed to check the NS System in Operation in accordance with step 10 of FR-Z.1. Although Containment Pressure will be > 3 psig, automatic actuation of Containment Spray (NS) will have failed. Additionally, the NS manual actuators will fail to operate requiring that the operator take manual action to start the NS Pumps and open the discharge valves. The operator will need to manually open the NS Pump discharge valves and manually start the NS Pumps. When attempts are made to manually open the A Train discharge valves, they will not open (Alternate Path), requiring the operator to make no attempt to start the IA NS pump.

JPM E This is a new JPM. With the plant at 77% power, the operator will be told that the crew has entered AP/1/A15500/05 (Generator Voltage and Electrical Grid Disturbances) due to low Electrical Grid frequency, and that the procedure is completed up to Step 15. The operator will be directed to separate from the Electrical Grid without delay in accordance with Step 15 of AP/1/A15500/05 (Generator Voltage and Electrical Grid Disturbances).

Since plant power is greater than 60%, the operator will be required to reduce load.

When the operator attempts to operate the turbine in automatic, Turbine power will fail to lower (Alternate Path). The operator will be expected to recognize that the Turbine has failed, and lower power manually, and then disconnect the Turbine Generator from the Electrical Grid.

JPM F This JPM is a modified version of a similar JPM used on the 2009 NRC Operating Test.

The Operator will be placed in a situation with Unit 1 at 100% power. The operator will be told that Power Range Channel N43 has previously failed low, and that the channel has been defeated in accordance with AP/1/A15500/16, Malfunction of Nuclear Instrumentation, Case Ill, Power Range Malfunction. The operator will be asked to restore Power Range Channel N43 to service in accordance with Step 21 of AP16, Malfunction of Nuclear Instrumentation, Case Ill, Power Range Malfunction. The operator will be required to restore the channel to service in accordance with the procedure.

JPM G This is a new JPM. The operator will be told that there is massive flooding in the Turbine Building and that the crew has implemented AP/0/N5500/44 (Plant Flooding), Enclosure I (Unit 1 Turbine Bldg Flooding). The operator will be directed to isolate the RC System by performing steps 6.d-v of the procedure, while the crew continues with EP/1/A15000/E-0 (Reactor Trip and/or Safety Injection). The operator will be expected to take all pump and valve control switch manipulations to isolate the RC System. This task was chosen because Internal Flooding events are a large PRA contributor (15%

CDF). This is a Time Critical JPM that must be complete in 40 Minutes.

JPM H This is a new JPM. The operator will be told that plant power has just been raised to 100% per OP/1/A16100/003 (Controlling Procedure for Unit Operation). The operator will be directed to remove Pzr Heater Groups A, B and D from service per Enclosure 4.6 (Operation of Pzr Heaters) of OP/1/A16100/003. The operator will be expected to remove the A, B and D Pzr Heater Groups from service in accordance with Step 3.4.4 of Enclosure 4.6. After the Pzr Pressure Master has been placed in MANUAL and its output has been adjusted, the Pzr variable Heaters (Group C) will fail (Alternate Path).

The operator will be required to respond to MCB Annunciator 1AD6/D6 (PZR HTR CONTROLLER TROUBLE), and manually control pressure using the other heater NUREG-1 021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Draft groups. The operator will be expected to place at least one Pzr Heater Group in service in accordance with Step 3.3.1 (or equivalent) of Enclosure 4.6.

JPM I This is Bank JPM IC-RTB-016. The Operator will be told that Unit I is at 100% power when an ATWS occurred, and that the operating crew has entered EP/1/A/5000/FR-S.1 (Response to Nuclear Power Generation/ATVVS). The operator will be directed to locally trip the reactor in accordance with Step 8.a RNO of FR-S. 1. The operator will be expected to locally trip both Unit I Reactor Trip Breakers and shutdown both Rod Drive MG Sets.

JPM J This is bank JPM PSS-KC-165T. The operator will be told that Unit I is operating at 100% power when the KC Surge Tank A and B lo level computer alarms are received, that the surge tank levels are 3.9 feet and decreasing, and that AP/1/A15500/21 (Loss of KC or KC System Leakage) has been implemented. Since the YM System will be out of service, the operator will be directed to initiate makeup to both Unit I KC Surge Tanks j AP/I/A5500/21 (Loss of KC or KC System Leakage), Enclosure 3 (Aligning RN Makeup to KC Surge Tank). This is a Time Critical JPM. The operator will be expected to manipulate valves, and communicate with the C/R to restore KC Surge Tank level within ten minutes of dispatch. This is a Time Critical JPM that must be complete in 10 Minutes.

JPM K This is bank JPM EL-EPK-199. The operator will be told that AP/1/A15500/15 (Loss of Vital or Aux Control Power) has been implemented due to a loss of Aux Control Power Panel Board KXB, and that prior to the event, all electrical systems were aligned in their normal operating configurations. The operator will be directed to energize KXB using inverter SKX per Enclosure 24 of AP/1/A15500/15 (Loss of Vital or Aux Control Power).

The operator will be expected to align Inverter SKX to provide power to KXB power panel board.

NUREG-1 021, Revision 9