Text

Indian Point, Unit 3 - Draft - Outlines (Folder 2)
	ML103080910
Person / Time
Site:	Indian Point
Issue date:	07/02/2010
From:	Silk D M; Operations Branch I
To:	;
	Hansell S
Shared Package
ML100980645	List: IR 05000286/2010301; ML102670379; ML102720572; ML103080903; ML103080910; ML103080920; ML103080923; ML103090017; ML103090020; ML103090036; ML103090054; ML103410223;
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Description of program used to generate IPEC Unit 3 July 2010 Written Exam KlAs Generated the RO and SRO sample plan using the "NKEG" Database Program, version 1.1, developed by Westinghouse Electric Company. This program will automatically produce a Random Sample Plan based on NUREG 1122, Rev. 2, Supplement 1 KlAs. KlAs were suppressed prior to the outline generation process as provided for in the examiner standard, the list of suppressed KlAs is provided as required by the examiners standard.

Inappropriate and inapplicable KlAs were discarded during the outline development process and are included in the record of rejected KlAs. The replacement KlAs were replaced using the random sample function of the NKEG database program. NUREG 1021 6 ES-401 PWR Examination Outline Form ES-401-2 Facilitv:

Indian Point Unit 3 Printed: 06/28/2010 Date Of Exam: 10104/2010 RO KIA Category SRO-Only Points Tier Group K1 K2 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total 1. 1 3 3 3 3 3 18 3 3 Emergency

3. & 2 2 2 I N/A 2 I N/A I I 9 2 2 4 Abnormal Tier Plant Evolutions Totals 5 5 4 5 4 4 27 5 5 10 2. 1 3 2 3 3 3 2 3 3 I 3 2 28 3 2 5 Plant 2 I 1 0 I 1 I I 1 1 I J 10 1 I I I 3 Systems Tier Totals 4 3 3 4 4 3 4 4 2 4 3 38 5 3 8 1 2 3 4 1 2 3 4 Generic Knowledge And 7 Abilities Categories 2 3 2 3 1 2 2 2 Note: Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two). 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. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements. 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. Absent a plant-specific priority, only those KlAs having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories. The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KlAs. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (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 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. 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 KlAs that are linked to 10 CFR 55.43. NUKt:l::i I

PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3

___ 1 EJAPE # J l'Jame I Safety Function 000007 Reactor Trip -Stabilization

-Recovery Ability to determine and interpret the I 4.3 I following as they apply to a reactor trip: Proper actions to be taken if the automatic functions have not taken (!Iace 000009 Small Break LOCA I Conduct of Operations

-Ability to I 4.3 I 2 identify and interpret diverse indications to validate the response of another indication.

000011 Large Break LOCA 1 Ability to operate and/or monitor the 4.0 I 4 following as they apply to a Large Break LOCA::-: Securing of RCPs 0000 I S/0000I7 RCP Malfunctions 14 :h 4.3 76 XI AK3.04 I Knowledge of the reasons for the I 3.5 I 5 following responses as they apply to the Loss of Component Cooling Water: -Effect on the CCW flow header of a loss ofCCW 000029 A TWS / 1 2.4.13 I

-Knowledge I 4.0 I 7 of crew roles and responsibilities during EOP use. 000038 Steam Gen. Tube Rupture I 3 I X I _EK3.09 I of the reasons for the I 4.1 I 8 following responses as they apply to the SGTR: -Criteria for securing/throttling ECCS 000040 Transfer NUREG PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 NRC Written Examination Outline Form ES-401-2 ES-401 ------e----J

EfAPE # I I Safety Function I I I I 000040 Steam Line Rupture

-Excessive Heat X Knowledge of the reasons for the I 4.2 6 Transfer / 4 following responses as they apply to the Steam Line Rupture: -Operation of steam line isolation valves Ability to detennine and interpret the following as they apply to a Station Blackout:

-Existing valve positioning on a loss of instrument air 000056 Loss of Off-site Power /6 I X I I AKl.03 I Knowledge of the operational I 3.1 I 10 -implications of the following concepts as they apply to Loss of Offsite Power: Definition of subcooling:

use of steam tables to detennine it 000057 Loss of Vital AC Inst. Bus / 6 I X _AAl.05 I AbilitY to operate and/or monitor the I 3.2 I 11 following as they apply to the Loss of Vital AC Instrument Bus: -Backup instrument indications 000058 Loss of DC Power 16 I X I AKl.OI I Knowledge ofthe operational 2.8 I 12 implications of the following concepts as they apply to Loss of DC Power: -Battery and instrumentation r 'I *c '" " **

I .... . r' Ability to detennine and interpret the -following as they apply to the Loss of Nuclear Service Water: -Location of a leak in the SWS NUREG 1021 Facility:

Indian Pont Unit 3 ES-401 EI APE # I Name I Safetv Function 000077 Generator Voltage and Electric Grid x Disturbances / 6 W/E05 Inadequate Heat Transfer -Loss of Secondary Heat Sink! 4 of Emergency Coolant Recirc. / 4 x Ability to operate and/or monitor the 14 following as they apply to the Loss of Instrument Air: -Emergency air Knowledge of the interrelations between I 3.1 15 Generator Voltage and Electrical Grid Disturbances and the for . Knowledge ofthe interrelations between the Loss of Secondary Heat Sink and the following:

-Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual I Ifeatures........_...-________--Knowledge interrelations between I 3.6 17 the Loss of Emergency Coolant Recirculation and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features NUREG 1021 PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 NRC Written Examination Outline ES-401 Emergency and Abnormal Plant Evolutions

-Tier 11 Group 1 Form ES-401-2 I E/APE # / Name / Safety Function I Kl Lag I K3 JALI A21 G Number I KIA Topic

-Steam Line Rupture -Excessive Heat 14 x Knowledge of the operational implications ofthe following concepts as they apply to the Uncontrolled Depressurization of all Steam Generators:

-Components:, capacity, and function of propnf"

I 3.4 18 NUREG 1021

PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 ES-401 E/APE # I Name I Safety Function 00000 I Continuous Rod Withdrawal 1 1 x 000033 Loss of Intermediate Rang NI 17 x 000036 Fuel Handling Accident 1 8 000068 Control Room Evac. 1 8 Knowledge of the operational implications of the following concepts as they apply to Loss of Source Range Nuclear Instrumentation:

-Effects of I--___-llvoltage changes on perfon Knowledge ofthe reasons for the following responses as they apply to the Loss ofIntermediate Range Nuclear Instrumentation:

-Guidance contained EOP for loss of intermediate-range 1----:---+

instrumentation Ability to operate and/or monitor the following as they apply to the Fuel Handling Incidents:

-ARM """1-a..,,, Conduct of Operations

-Knowledge of procedures, guidelines, or limitations associated with roaro1-:,,:1-., 19 3.6 21 3.1 22 4.3 23 NUREG 1021 PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 _I' Form ES-401-2 ! ... --l ..........

L I .'II ""n_..,,,. W/E02 SI Termination I 3 Knowledge of the operational implications of the following concepts as they apply to the Sl Termination: Normal, abnormal and emergency operating procedures associated with SI and interpret the W IE03 LOCA Cooldown -Depress. I 4 following as they apply to the LOCA Cooldown and Depressurization: Facility conditions and selection of appropriate procedures during abnormal and arno...rroft"" l""It.'I"'\a.

....o ... ; W/E06 lnad. Core Cooling I 4 Ability to operate and/or monitor the following as they apply to the Degraded Core Cooling: -Desired operating results during abnormal and emergency 1 situations ky*to Knowledge of the interrelations between the High Containment Pressure and the following:

-Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual 1---___--\1 features Ilm_p_. 3.4 24 I 3.4 +-1---1 25 3.7 26 15 27 NUREG PWR RO/SRO Examination Outline Facility:

Indian Pont Unit NRC Written Examination Plant .irs-Tier 21 Group System #lName II<lTk2[K}]

K4TKSTK6 TAL A3 [ A4

Number I KIA I"up I 003 Reactor Coolant Pump I Knowledge of the physical connections 2.6 and/or cause-effect relationships the RCPS and the following RCP lube 004 Chemical and Volume Ability to manually operate and/or I 3.2 monitor in the control room: -

of boron concentration

-"--0--I 004 Chemical and Volume Knowledge of limiting conditions for 4.0 operations and safety limits 005 Residual Heat x Knowledge of bus power supplies to the I 3.0 following:

-RHR pumps 005 Residual Heat Ability to (a) predict the impacts of the I 2.9 following 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:

-RHR 006 Emergency Core x Knowledge of the effect that a loss or I 4.2 malfunction of the ECCS will have on the NUREG PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 ES-40l 5>ystem #/N 007 Pressurizer Ability to (a) predict the impacts of the 2.5 34 Relief/Quench Tank following malfunctions or operations on the PRTS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

-Overpressurization of the waste gas vent header 008 Component Cooling x Knowledge of the physical connections 3.1 35 Water and/or cause-effect relationships between the CCWS and the following systems: SWS 008 Component Cooling Ability to manually operate and/or 3.1* 36 Water monitor in the control room: -CCW 010 Pressurizer Pressure 2.6 37 Control 013 Engineered Safety x Knowledge of the effect of a loss or I 2.7* 39 Features Actuation malfunction of the following will have on the ESF AS: -Sensors and detectors f--------i 013 Engineered Safety x Knowledge of bus power supplies to the I 3.6 40 Features Actuation following:

-ESF AS/safeguards control NUREG 1021 PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 022 Containment Cooling x 039 Main and Reheat x Steam 059 Main Feedwater 061 Auxiliary/Emergency Feedwater Form ES-401-2 Knowledge ofCCS design feature(s) 3.6 41 and/or interlock(s) which provide for the following:

-Automatic containment isolation Ability to manually operate andlor monitor in the control room: -CSS controls Knowledge of the effect that a loss or I 2.8* I 43 malfunction of the MRSS will have on the following:

-SDS Ability to predict andlor monitor changes I 2.7* 44 in parameters (to prevent exceeding design limits) associated with operating the MFW System controls including: Power level restrictions for operation of MFW DumDS and valves Knowledge of the operational implications of the following concepts as they apply to the AFW System: Relationship between AFW flow and L-__----i! I{CSheat transfer NUREG 1021 PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 Form ES-401-2 061 Auxiliary/Emergency III K4.01 IX Feedwater

062 AC Electrical II1II A2.12 Distribution

063 DC Electrical III K4.01 I X I Distribution

064 Emergency Diesel x Generator I Knowledge of AFW System design I 4.1 I 46 feature(s) and/or interlock(s) which provide for the fonowing:

-Water sources and priority of use I Ability to (a) predict the impacts of the I 3.2 I 47 following malfunctions or operations on the A.C. Distribution System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

-Restoration of power to a with a fault on it I Knowledge of D.C. Electrical System I 2.7 I 48 design feature(s) and/or interlock(s) which provide for the following:

-ManuaVautomatic transfers of control Knowledge of the effect ofa loss or malfunction of the following will have on the ED/G Svstem: -Air receivers Ability to predict and/or monitor changes I 3.1 50 in parameters (to prevent exceeding design limits) associated with operating the ED/G System controls including: Maintaining minimum load on ED/G (to nrpvpnt reverse NUREG 1021 PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 NRC Written Examination Outline ES-401 .... . .. ... Plant mJie.. 21 Group 1 ........ I System #lName I KI jK2TK3Tl(4JKSI K61 Ai A4=-Number I KIA T()pic 073 Process Radiation x 3.6 51 Monitoring 073 Process Radiation x 2.5 52 Monitoring un _ Al.02 076 Service Water Ix" lAbility to and/or monitor changes I 2.6* I 53 in parameters (to prevent exceeding design limits) associated with operating the SWS controls including:

-Reactor and turbine building closed cooling water I temI!eratures 078 Instrument Air

A3.01 Ability to monitor automatic operation of 3.1 54.xl........ I the lAS, including:

-....n 103 Containment

2. Conduct of Operations

-Ability to 4.3 55 identify and interpret diverse indications to validate the response of another indication.

NUREG PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 AI()Qi£ """ 002 Reactor Coolant 011 Pressurizer Level Control x 1------+ Knowledge of the physical connections and/or cause-effect relationships between the RCS and the following systems: PRT Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR LCS controls including:

-and letdown flows 3.2 3.3 56 57 Instrumentation 017 In-core Temperature Monitor 034 Fuel Handling Equipment x Knowledge ofthe effect of a loss or malfunction of the following will have on the ITM System components:

-Sensors and detectors Knowledge of Fuel Handling System design feature(s) and/or interlock(s) which provide for the following:

-Fuel I 2.7 I 2.5 59 63 NUREG 1021 PWR RO/SRO Examination Facility:

Indian Pont Unit NRC Written Examination ES-401 ... Plant liirs-Tier 2/ GrollJlJ .._I System #lName I Kl I K2 I KJJK4 I K5 I K61 AI A3 I A4

KJA I

I 035 Steam Ability to (a) predict the impacts of the I 4.5 60 following malfunctions or operations on the S/GS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

-Small break LOCA 041 Steam Dump/Turbine Ability to monitor automatic operation of I 2.7 61 Bypass Control the SDS, including:

-Stearn flow 045 Main Turbine 4.1 62 Generator 075 Circulating Water 2.6 64 93 65 NUREG Generic Knowledge and Abilities Outline (Tier 3) PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 Indian Point Unit 3 Date of Exam Cate or KfA # Topic L Conductof Operations 2.1.39 Knowledge of conservative dt:cision making practices. Conduct of Operations

-Knowledge of refuel in administrative re uirements. t\bUity:to the

",\

Subtotal Equipment 2.2.25 Equipment Control -Knowledge of bases in technical specifications for limiting Control conditions for 0 erations and safe limits. Equipment Control -Ability to determine operability and/or availability of safety related e ui ment. Knowledge of less than or equal to one hour Technical Specification action statements for systems. p/.m.the.prooess for controlling

....

or status. Subtotal Form ES-401-3 10/4/2010 RO SRO-O IR Q# IR 3.6 67 2.8 68 3.2 69 3.6 66 3.9 70 NUREG 2 Generic Knowledge and Abilities Outline (Tier 3) PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 Indian Point Unit 3 KIA # Topic 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to lo(;ked radiation areas, aligning filters, etc. 3. 2.3.14 Knowledge ofradiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

Radiological Controls Knowledge of operational implications of EOP warnings, cautions, and notes. Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects. Ability to prioritize and interpret the significance of each annunciator or alarm. 4. Emergency Procedures/plan 3.4 3.8 4.2 4.1 Form ES-401-3 72 73 74 75 NUREG

Tier I Randomly Selected Reason for Rejection Group Knowledge of the operational implications of the following concepts as they apply to a Pressurizer R-1/1 000008 Vapor Space Accident:

-Change in leak rate with Rejected due to similarities to Question # 2 change in pressure Equipment Control -Ability to apply technical This Generic KA is not applicable to R-1/1 000009 G 2.2.40 specifications for a system. normal procedures Ability to determine and interpret the following as KA is not applicable.

Natural Circulation does they apply to a Large Break LOCA: -Existence of R-1/1 000011 EA2.09 not exist during a Large Break LOCA. adequate natural circulation Ability to operate and/or monitor the following as KA is not applicable.

Makeup to RCP they apply to the Loss of Reactor Coolant Pump R-1/1 0000221.08 standpipe if from primary water not CVCS Makeup: -VCT level Equipment Control-Ability to determine the This Generic KA is not applicable for expected plant configuration using design and APE/EPE written This KA is R-1/1 000027 G2.2.15 configuration control documentation, such as evaluated during Simulator and/or JPM drawings, line ups, tag outs, etc. Examinations.

Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure KA Rejected due to similarity with Simulator R-1/1 Q00027 AK3.03 Control Malfunctions:

-Actions contained in EOP for Examination PZR PCS malfunction f**** Conduct of Operations

-Ability to perform specific This Generic KA is evaluated during system and integrated plant procedures during all R-1/1 000062 G2.1.3 Simulator Exam modE:)s of plant This Generic KA is not applicable for Ability to obtain and interpret station electrical and APE/EPE written This KA is R-1/2 000076 G2.2.41 mechanical drawings.

evaluated during Simulator and/or JPM Examinations.

Knowledge of the reasons for the following R-1/2 000024 AK3.02 responses as they apply to the Emergency Boration:

This concept is evaluated on JPM exam -Actions contained in EOP for em*lrgency boration S-1/2 R-1/2 S-1I2 000051 G2.3.14 000067 AA 1.08 000068 G2.3.14 Radiological Controls -Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or or activities.

Ability to operate and/or monitor the following as they apply to the Plant Fire on Site: -Fire fighting equipment used on each class of fire Radiological Controls -Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergenq conditions or activities.

This Generic KA is not applicable to Loss of Condenser Vacuum off-normal procedure.

Unable to write a discriminatory RO level question for this KA Unable to write a discriminatory SRO level question for this KA I S-1/2 000068 G2.2.37 Equipment Control-Ability to determine operability and/or availability of safety related equipment.

This generic KA is not applicable to Control Room Evacuation APE. R-1/2 W/E16 G2.4.47 Emergency Procedures/Plan

-Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

This Generic KA is evaluated during Simulator Exam R-2/1 004000 K4.13 Knowledge of CVCS design feature(s) and/or interlock(s) which provide for the following:

-Interlock between letdown isolation valve and flow NA at IPEC -No Interlock exists. control valve R-2/1 R-211 R-2/1 006000 K3.02 007000 G2.2.42 010000 G2.4.47 Knowledge of the effect that a loss or malfunction of the E:G£§vvill have on the following:

-Fuel Equipment Control-Ability to recognize system parameters that are entry level conditions for Technical Specifications.

Emergency Procedures/Plan

-Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

KA Rejected due to similarity with question 26 NA at IPEC -No Tech Spec or TRM exist for the PRT This KA is evaluated during Simulator Exam R-2/1 039000 K3.06 Knowledge of the effect that a loss or malfunction of the MRSS will have on the following:

-SOS Rejected due to similarity with question 61

Ability to (a) predict the impacts of the following malfunctions or operations on the RPS and (b) based on those predictions, use procedures to S-2/1 012000 correct, control, or mitigate the consequences of Rejected due to similarities with Question 38 those malfunctions or operations:

-Failure of RPS signal to trip the reactor Ability to monitor automatic operation of the A.G. NA at IPEG -Not able to monitor Vital AG Distribution System, including:

-Vital ac bus R-2/1 062000 A3.01 bus amp in the control room amperage Knowledge of bus power supplies to the following: Unable to write a discriminatory question for R-2/2 028000 K2.01 Hydrogen recombiners this KA Knowledge of Fuel Handling System design Rejected RO are not directly involved in Fuel feature(s) and/or interlock(s}

which provide for R-2/2 034000 K4.02 Handling activities at IPEG. the following:

-Fuel movement Knowledge of ARM system design feature(s) and/or interlock(s}

which provide for the following:

-Fuel R-2/2 072000 KA rejected due to similarity with question 22 building isolation Ability to manually operate and/or monitor in the R-212 079000 A4.01 KA rejected due to similarity with question 14 control room: -Cross-tie valves with lAS Ability to use plant computers to evaluate system or R-3 This is evaluated during Simulator Exam component status. R-3 Knowledge of tagging and clearance procedures.

This concept is evaluated during JPM Exam Knowledge of the process for managing KA rejected because ROs do not manage R-3 2.2.20 troubleshooting troubleshooting activities.

Suppressed KlAs IKA KA Statement (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

Knowledge of the operational implications of the following concepts as they apply to Continuous Rod Withdrawal:

Interaction of ICS control stations as well as purpose, function, and modes of operation of ICS (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

Knowledge of the operational implications of the following concepts as they apply to Dropped Control Rod: Interaction of ICS control stations as well as purpose, function, and modes of operation of ICS Knowledge of the reasons for the following responses as they apply to the Dropped Control Rod: When ICS logic has failed on a dropped rod, the load must be reduced until flux is within specified target bank (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

Knowledge of the operational implications of the following concepts as they apply to Inoperable/Stuck Control Rod: Definitions of axial imbalance, neutron error, power demand, actual power tracking mode, ICS tracking (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0000082204 a facility. (multi-unit license) Knowledge of the design, procedural 0000092203 and operational differences between units. Basis for Supression NA for IPEC NA for IPEC Equipment NA at IPEC NA for IPEC NA for IPEC Equipment NA at IPEC Equipment NA at IPEC NA for IPEC NA for IPEC Equipment NA at IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC I Suppressed KlAs (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0000092204 a facility.

NA for IPEG (multi-unit license) Knowledge of the design, procedural 0000112203 and operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0000112204 a facility.

NA for IPEG (multi-unit license) Knowledge of the design, procedural 0000152203 and operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0000152204 a facility.

NA for IPEG Iti-unit license) Knowledge of the design, procedural 000022 operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0000222204 a facility.

I (multi-unit license) Knowledge of the design, procedural NA for IPEG 0000242203 and operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0000242204 a facility.

NA for IPEG (multi-unit license) Knowledge of the design, procedural 0000252203 and operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0000252204 a facility.

NA for IPEG (multi-unit license) Knowledge of the design, procedural 0000262203 and operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0000262204 a facility.

NA for IPEG (multi-unit license) Knowledge of the design, procedural 0000272203 i ,al differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at NA for IPEG ense) Knowledge of the design, pro 000028220 I differences between units. G (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 10000282204 a facility.

NA for IPEG 2 I Suppressed KlAs (multi-unit license) Knowledge of the design, procedural and operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEG (multi-unit license) Knowledge of the design, procedural and operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEG (multi-unit license) Knowledge of the design, procedural and operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0000512204 a facility.

NA for (multi-unit license) Knowledge of the design, 0000542203 and operational differences between units. NA for I Suppressed KJAs (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0000542204 a facili NA for IPEC wledge of the design, procedural nces between units. NA for IPEC (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEC (multi-unit license) Knowledge of the design, procedural and operational differences between units. NA for IPEC (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEC (multi-unit license) Knowledge of the design, procedural and operational differences between (multi-unit license) Ability to explain the variations control board/control room layouts, instrumentation, and procedural actions between units 0000592204 a facility.

NA for IPEC license) Knowledge of the design, procedural 0000602203 ational differences between units. NA for IPEC (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEC :'Iti-unit license) Knowledge of the design, procedural 0000612203 operational differences between units. NA for IPEC (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEC (multi-unit license) Knowledge of the design, procedural and operational differences between units. NA for IPEC (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 10000622204 a

NA for IPEC 4 I Suppressed KlAs (multi-unit license) Knowledge of the desig and operational differences between units. NA for IPEC (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEG (multi-unit license) Knowledge of the design, procedural and operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEG (multi-unit license) Knowledge of the design, pro and operational differences between units. *....C (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEG (multi-unit license) Knowledge of the design, procedural and operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for fPEG (multi-unit license) Knowledge of the design, proce and operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEG (multi-unit license) Knowledge of the design, procedural and operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEG (multi-unit license) Knowledge of the design, procedural and operational differences between units. INA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEG (multi-unit license) Knowledge of the design, procedural and operational differences between units. NA for IPEC (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0010002204 a facility.

NA for IPEG (multi-unit license) Knowledge of the design, proce 0020002203 and operational differences between units. INA for IPEG I Suppressed KJAs (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0030002204 a facility.

Knowledge of the effect that a loss or malfunction of the 003000K305 RCPS will have on the following:

ICS (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 00WE012204 a facility. (multi-unit license) Knowledge of the design, procedural 00WE022203 and operational differences between units. NA for IPEC NA for IPEC NA for IPEC Equipment NA at IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC I Suppressed KJAs (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEG (multi-unit license) Knowledge of the design, procedural and operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEG (multi-unit license) Knowledge of the deSign, procedural and operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEG (multi-unit license) Knowledge of the design, procedural and operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEG 7 Suppressed KlAs I')OWE 112203 00WE112204 00WE122204 00WE132203 00WE132204 00WE142203 OOWE142204 00WE152203 00WE152204 00WE162203 00WE162204 0100002203 0100002204 0110002203 0110002204 0120002203 (multi-unit license) Knowledge of the design, and operational differences between (multi-unit license) Ability to explain the variations control board/control room layouts, instrumentation, and procedural actions between units a (multi-unit license) Knowledge of the design, and operational differences between (multi-unit license) Ability to explain the variations control board/control room layouts, instrumentation, and procedural actions between units a (multi-unit license) Knowledge of the design, and operational differences between (multi-unit license) Ability to explain the variations control board/control room layouts, instrumentation, and procedural actions between units a (multi-unit license) Knowledge of the design, and operational differences between (multi-unit license) Ability to explain the variations control board/control room layouts, instrumentation, and procedural actions between units a (multi-unit license) Knowledge of the design, and operational differences between (multi-unit license) Abitity to explain the variations control board/control room layouts, instrumentation, and procedural actions between units a (multi-unit license) Knowledge of the design, and operational differences between (multi-unit license) Ability to explain the variations control board/control room layouts, instrumentation, and procedural actions between units a Iti-unit license) Knowledge of the deSign, procedural operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. NA for NA for NA for NA for NA for NA for I NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC I Suppressed KlAs (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0130002204 a facility.

Iti-unit license) Knowledge of the design, procedural operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a

Knowledge of the physical connections and/or effect relationships between the NIS and the systems: ICS Knowledge of the effect that a loss or malfunction of the NIS will have on the following:

ICS (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0160002204 a facility. license) Knowledge of the design, procedural ational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0220002204 a

0250002101 System 025 is Ice Condenser 0250002102 System 025 is Ice Condenser 0250002103 System 025 is Ice Condenser 0250002104 System 025 is Ice Condenser 0250002105 System 025 is Ice Condenser 0250002106 System 025 is Ice Condenser System 025 is Ice Condenser System 9 NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC Equipment NA at IPEC Equipment NA at IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEG NA for IPEC NA for IPEC NA for IPEC NA for IPEG Suppressed KfAs 0250002108 System 025 is Ice Condenser System NA for IPEC 0250002109 System 025 is Ice Condenser System NA for IPEC 0250002113 System 025 is Ice Condenser System NA for IPEC 11 Esystem 025 is Ice Condenser System NA for IPEC 2115 System 025 is Ice Condenser System NA for IPEC 2117 System 025 is Ice Condenser System NA for IPEC System 025 is Ice Condenser System NA for 'PEC System 025 is Ice Condenser System NA for IPEC 0250002120 System 025 is Ice Condenser System NA for IPEC 0250002121 System 025 is Ice Condenser System NA for IPEC 0250002123 System 025 is Ice Condenser System NA for IPEC 0250002125 System 025 is Ice Condenser System NA for IPEC 0250002126 System 025 is Ice Condenser System NA for IPEC System 025 is Ice Condenser System NA for IPEC 2128 System 025 is Ice Condenser System NA for IPEC 0250002129

! System 025 is Ice Condenser System NA for IPEC 0250002130 System 025 is Ice Condenser System NA for IPEC 0250002131 System 025 is Ice Condenser System NA for IPEC 0250002132 System 025 is Ice Condenser System NA for IPEC 0250002134 System 025 is Ice Condenser System NA for IPEC 0250002135 System 025 is Ice Condenser System NA for IPEC 0250002136 System 025 is Ice Condenser System NA for IPEC 0250002137 System 025 is Ice Condenser System NA for IPEC 0250002138 System 025 is Ice Condenser System NA for IPEC 0250002139 System 025 is Ice Condenser System NA for IPEC 0250002140 System 025 is Ice Condenser System NA for IPEC 0250002141 System 025 is Ice Condenser System NA for IPEC 0250002142 System 025 is Ice Condenser System NA for IPEC 2143 System 025 is Ice Condenser System NA for IPEC 2144 System 025 is Ice Condenser System NA for IPEC 2145 System 025 is Ice Condenser System NA for IPEC 002201 System 025 is Ice Condenser System NA for IPEC System 025 is Ice Condenser System NA for IPEC (multi-unit license) Knowledge of the design, procedural and operational differences between units. NA for IPEC (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0250002204 a facility.

NA for IPEC 0250002205 System 025 is Ice Condenser System NA for IPEC 0250002206 System 025 is Ice Condenser System NA for IPEC 0250002207 System 025 is Ice Condenser System NA for IPEC 0250002211 System 025 is Ice Condenser System NA for IPEC 0250002212 System 025 is Ice Condenser System NA for IPEC 0250002213 System 025 is Ice Condenser System NA for IPEC 0250002214 System 025 is Ice Condenser System NA for IPEC 0250002215 System 025 is Ice Condenser System NA for IPEC 0250002217 System 025 is Ice Condenser System NA for IPEC 0250002218 System 025 is Ice Condenser System NA for IPEC 0250002219 System 025 is Ice Condenser System NA for IPEC 0250002220 System 025 is Ice Condenser System NA for IPEC 10250002221 System 025 is Ice Condenser System NA for IPEC 10 Suppressed KJAs 0250002222 System 025 is Ice Condenser System NA for IPEC 0250002223 System 025 is Ice Condenser System NA for IPEC 0250002225 System 025 is Ice Condenser System NA for IPEC 0250002235 System 025 is Ice Condenser System NA for IPEC 0250002236 System 025 is Ice Condenser System NA for IPEC 0250002237 System 025 is Ice Condenser System NA for IPEC 0250002238 System 025 is Ice Condenser System NA for IPEC 0250002239 System 025 is Ice Condenser System NA for IPEC 0250002240 System 025 is Ice Condenser System NA for IPEC 0250002241 System 025 is Ice Condenser System NA for IPEC 0250002242 System 025 is Ice Condenser System NA for IPEC 0250002243 System 025 is Ice Condenser System NA for IPEC 0250002244 System 025 is Ice Condenser System NA for IPEC 0250002304 System 025 is Ice Condenser System NA for IPEC 0250002305 System 025 is Ice Condenser System NA for IPEC 0250002306 System 025 is Ice Condenser System NA for IPEC 0250002307 System 025 is Ice Condenser System NA for IPEC 0250002311 System 025 is Ice Condenser System NA for IPEC 0250002312 System 025 is Ice Condenser System NA for IPEC 0250002313 System 025 is Ice Condenser System NA for IPEC 0250002314 System 025 is Ice Condenser System NA for IPEC 0250002315 System 025 is Ice Condenser System NA for IPEC 0250002401 System 025 is Ice Condenser System NA for IPEC 0250002402 System 025 is Ice Condenser System NA for IPEC 0250002403 System 025 is Ice Condenser System NA for IPEC 0250002404 System 025 is Ice Condenser System NA for IPEC 0250002405 System 025 is Ice Condenser System NA for IPEC 0250002406 System 025 is Ice Condenser System NA for IPEC 0250002408 System 025 is Ice Condenser System NA for IPEC 0250002409 System 025 is Ice Condenser System NA for IPEC 0250002411 System 025 is Ice Condenser System NA for IPEC 0250002412 System 025 is Ice Condenser System NA for IPEC 0250002413 System 025 is Ice Condenser System NA for IPEC 0250002414 System 025 is Ice Condenser System NA for IPEC 0250002416 System 025 is Ice Condenser System NA for IPEC 0250002417 System 025 is Ice Condenser System NA for IPEC 0250002418 System 025 is Ice Condenser System NA for IPEC 0250002419 System 025 is Ice Condenser System NA for IPEC 0250002420 System 025 is Ice Condenser System NA for IPEC 0250002421 System 025 is Ice Condenser System NA for IPEC 0250002422 System 025 is Ice Condenser System NA for IPEC 0250002423 System 025 is Ice Condenser System NA for IPEC 0250002425 System 025 is Ice Condenser System NA for IPEC 0250002426 System 025 is Ice Condenser System NA for IPEC 0250002427 System 025 is Ice Condenser System NA for IPEC 0250002428 System 025 is Ice Condenser System NA for IPEC 0250002429 System 025 is Ice Condenser System NA for IPEC 0250002430 System 025 is Ice Condenser System NA for IPEC 0250002431 System 025 is Ice Condenser System NA for IPEC 0250002432 System 025 is Ice Condenser System NA for IPEC 0250002434 System 025 is Ice Condenser System NA for IPEC 10250002435 System 025 is Ice Condenser System NA for IPEC 11 Suppressed KlAs 10250002437 System 025 is Ice Condenser System NA for IPEC J250002438 System 025 is Ice Condenser System NA for IPEC 0250002439 System 025 is Ice Condenser System NA for IPEC 0250002440 System 025 is Ice Condenser System NA for IPEC 0250002441 System 025 is Ice Condenser System NA for IPEC 0250002442 System 025 is Ice Condenser System NA for IPEC 0250002443 System 025 is Ice Condenser System NA for IPEC 0250002444 System 025 is Ice Condenser System NA for IPEC 0250002445 System 025 is Ice Condenser System NA for IPEC 0250002446 System 025 is Ice Condenser System NA for IPEC 0250002447 System 025 is Ice Condenser System NA for IPEC 0250002449 System 025 is Ice Condenser System NA for IPEC 0250002450 System 025 is Ice Condenser System NA for IPEC 025000A101 System 025 is Ice Condenser System NA for IPEC 025000A102 System 025 is Ice Condenser System NA for IPEC 025000A103 System 025 is Ice Condenser System NA for IPEC 025000A201 System 025 is Ice Condenser System NA for IPEC 025000A202 System 025 is Ice Condenser System NA for IPEC 025000A203 System 025 is Ice Condenser System NA for IPEC 025000A204 System 025 is Ice Condenser System NA for IPEC 025000A205 System 025 is Ice Condenser System NA for IPEC 025000A206 System 025 is Ice Condenser System NA for IPEC 025000A301 System 025 is Ice Condenser System NA for IPEC 025000A302 System 025 is Ice Condenser System NA for IPEC 025000A401 System 025 is Ice Condenser System NA for IPEC 025000A402 System 025 is Ice Condenser System NA for IPEC 025000A403 System 025 is Ice Condenser System NA for IPEC 025000K101 System 025 is Ice Condenser System NA for IPEC 025000K102 System 025 is Ice Condenser System NA for IPEC 025000K103 System 025 is Ice Condenser System NA for IPEC 025000K201 System 025 is Ice Condenser System NA for IPEC 025000K202 System 025 is Ice Condenser System NA for IPEC 025000K203 System 025 is Ice Condenser System NA for IPEC 025000K301 System 025 is Ice Condenser System NA for IPEC 025000K401 System 025 is Ice Condenser System NA for IPEC 025000K402 System 025 is Ice Condenser System NA for IPEC 025000K501 System 025 is Ice Condenser System NA for IPEC 025000K502 System 025 is Ice Condenser System NA for IPEC 025000K503 System 025 is Ice Condenser System NA for IPEC 025000K601 System 025 is Ice Condenser System NA for IPEC (multi-unit license) Knowledge of the design, procedural 0260002203 and operational differences between units. NA for IPEC (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0260002204 a facility.

NA for IPEC (multi-unit license) Knowledge of the design, procedural 0270002203 and operational differences between units. NA for IPEC (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 10270002204 a facility.

NA for IPEC 12 Suppressed KJAs (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0290002204 a facility.

design, procedural n units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the deSign, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0410002204 a facility.

the control Knowledge of bus power supplies to the following:

ICS, 041000K201 normal and alternate power supply Knowledge of bus power supplies to the following:

ICS, 041000K202 normal and alternate power su ply NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC Equipment NA at IPEC Equipment NA at IPEC Equipment NA at I PEC Knowledge of SOS design feature(s) and/or 041000K401 which provide for the following:

RRGIICS system Equipment NA at 13 I Suppressed KlAs Knowledge of SOS design feature(s) and/or interlock(s) which provide for the following: "Measured variable" readings on ICS hand-automatic stations and required action if reading is out of the acceptable band (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a

Ability to monitor automatic operation of the System, including: Knowledge of MFW System design feature(s) interlock(s) which provide for the following:

Bearing signal to the turning gear start Knowledge of the physical connections and/or effect relationships between the MFW System and following systems: ICS (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (multi-unit license) Knowledge of the design, procedural and operational differences between units. (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0620002204 a facility. (multi-unit license) Knowledge of the design, procedural 0630002203 and operational differences between units. Equipment NA at IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC Equipment NA at IPEC Equipment NA at IPEC Equipment NA at IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC NA for IPEC 14 I Suppressed KlAs (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEC (multi-unit license) Knowledge of the design, procedural and operational differences between units. NA for IPEC (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEC (multi-unit license) Knowledge of the design, procedural 0710002 ational differences between units. NA for IPEC (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEC (multi-unit license) Knowledge of the design, procedural and operational differences between units. NA for IPEC (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEC (multi-unit license)

Knowledge of the design, procedural 0730002203 I differences between units. INA for IPEC (multi-unit license)

Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a faCility.

NA for IPEC (multi-unit license)

Knowledge of the deSign, procedural and operational differences between units. NA for IPEC (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEC (multi-unit license) Knowledge of the deSign, procedural and operational differences between units. NA for IPEC (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0760002204 a facili NA for IPEC ense) Knowledge of the design, procedural 0780002 nal differences between units. NA for IPEC (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

NA for IPEC 15 Suppressed KlAs I (multi-unit license) Knowledge of the design, procedural

)790002203 and operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0790002204 a facility.

NA for IPEG (multi-unit license) Knowledge of the design, procedural 0860002203 and operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 0860002204 a facility.

NA for IPEG (multi-unit license) Knowledge of the design, procedural 1030002203 and operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 1030002204 a facility.

NA for IPEG (multi-unit license) Knowledge of the design, procedural 1940012203 and operational differences between units. NA for IPEG (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at 1940012204 a facility.

NA for IPEG Administrative Tc)pics Outline Form ES-301-1 Facility:

Indian Point Unit 3 Examination Level: RO D SRO X Date of Examination:

October 4,2010 Operating Test Number: Administrative Topic (see Note) Type Code* Describe activity to be performed Review a gross leakrate determination calculation Conduct of Operations N, R 2.1.7 (4.7) Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretations Conduct of Operations M, R, Determine Reactor Vessel Venting Time Per FR-1.3, Attachment 4 2.1.25 (4.2) Ability to interpret reference materials, such as graphs, curves, tables, etc. Equipment Control N,R Perform a Safety Function Determination 2.2.37 (4.6) Ability to determine operability and/or availability of safety related equipment Radiation Control N,R Review a Manual Gaseous Rad Waste Release Permit 2.3.6 (:1.8) Ability to approve release permits Classify E-Plan Event and Complete Part 1 Form Emergency Procedures/Plan M,R,P 2.4.38 (4.4) Ability to take actions called for in the facility ,emergency plan, including supporting or acting as emergency coordinator if required. All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:5 3 for ROs; :5 4 for SROs & RO retakes) (N)ew or (M)odified from bank 1) (P)revious 2 exams (:5 1; randomly selected)

Control Roomlln-Plant Systems Outline Form ES-301-2 Facility:

Indian Point Unit 3 Date of Examination:

October 4,2010 Exam Level: RO D SRO-I X SRO-U Operating Test No.: Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System I JPM Title Type Code* Safety Function Emergency Borate M.A, P, S. L 1 Transfer to Cold Leg Recirculation D,A, E, EN. L 2 Respond to a Pressurizer Controlling Channel Fail High D 3 Respond to Loss of Main Boiler Feedpump Speed Control N,A 4-S Start the Hydrogen Recombiner N,E, L 5 Remove a Power Range Nuclear Instrument from Service D 7 Transfer a Circ Water Pump from Standby Drive to Normal N 8 h. NA for In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or .2 for Locally Start 32 Auxiliary Boiler Feed Pump D,A, E,L 4-S Start a CCW Pump from MCC 310A 6 Perform Local Containment Isolation Valve Lineup IVSW N. EN, L. R 5 (SOP-CB-II steps 1-5) All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Criteria for RO I SRO-II SRO-U (A)lternate path 4-6 14-6/2-3 (C)ontrol room (D)irect from bank S9/S8/S4 (E)mergency or abnormal in-plant ;::1/;::1/;::1 (EN)gineered safety feature / ;::1 (control room system) (L)ow-Power 1 Shutdown ;::1/;::1/;::1 (N)ew or (M)odified from bank including 1 (A) ;::2/;::2/;::1 (P)revious 2 exams S 31 s 31 s 2 (randomly selected) (R)CA ;::1/;::1/;::1 (S)imulator ES-301 Administrative Topics Outline Form ES-301-1 INDIAN POINT UNIT 3 NRC .R6EXAMINATION CONDUCT OF OPERATIONS:

Review a gross leakrate determination calculation.

The candidate will be given a set of conditions and appropriate indications and a manualleakrate calculation.

The candidate will review the leakrate calculation and locate errors.

This is a New JPM

SRO Only CONDUCT OF OPERATIONS:

Determine Reactor Vessel Venting Time Per FR-1.3, Attachment 4 The candidate will be given a set of plant conditions with a void in the reactor vessel head. The candidate will be given directions to calculate the reactor vessel venting time in accordance with Functional Restoration Procedure FR-1.3

This is a bank JPM

Ths JPM is common to both RO and SRO candidates EQUIPMENT CONTROL: Perform a Safety Function Determination.

The candidate will be given a set of plant/equipment conditions including l:Jegraded power sources and equipment failures.

The candidate will be directed to perform a Safety Function Determination in accordance with OAP-034.

This is a New .1 PM

SRO Only. RADIATION CONTROL: Review a Manual Gaseous Rad Waste Release Permit. The candidate will be given a set of plant conditions for the VC Pressure Relief and a manually prepared release permit. The candidate will be directed to review the release permit in accordance with 3-S0P-WDS-013.

The candidate must locate errors on the permit.

This is a Modified Bank JPM

SRO Only. EMERGENCY PROCEDURES/PLAN:

Classify E-Plan Event and Complete Part 1 Form. The candidate will be given a set of plant conditions.

The candidate must evaluate the conditions, determine the emergency plan classification and complete the New York State Part 1 form

This is a Modified Bank JPM.

This is a Time Critical .'PM

SRO Only.

Control Room/In-Plant Systems Outline Form ES-301-2 Emergency Borate: The candidate will enter the simulator following a reactor trip with 2 stuck rods. The turbine failed to automatically trip on the reactor trip resulting in a cooldown below 540°F. Emergency boration valve MOV-333 will not open. The candidate must use Attachment 1 of ONOP-CVCS-3 to establish emergency boration Using Normal Boration.

The candidate must first borate for temperature and then borate for the additional stuck rod. This is an Alternate Path JPM. This is a Modified Bank JPM Failure to properly perform this task will result in possible inadequate shutdown margin. Transfer to Cold Leg Recirculation:

The candidate will enter the simulator following a large break LOCA. The RWST will be at the level requiring transfer to cold leg recirculation.

The candidate will be directed to establish cold leg recirculation using ES-1.3. The recirculation pumps will not start and the candidate will be required to establish recirculation using the RHR pumps This is a bank JPM. Failure to properly perform this JPM will result in inadequate cooling of the core and possible core damage. Respond to a Pressurizer Controlling Channel Fail High: The candidate will enter the simulator at normal full power lineup. The controlling pressurizer pressure channel will fail resulting in maximum spray flow and pressurizer pressure decreasing rapidly. The candidate must take manual control of the master pressurizer pressure controller and stabilize pressure.

The candidate must then take appropriate actions to trip bistables associated with pressurizer pressure. This is a bank JPM. Failure to properly perform this task will result in a reactor trip. Respond to Loss of Main Boiler Feedpump Speed Control: The candidate will enter the simulator with the plant at 100% power. (NOTE: Actual power level is not required.

Any simulator Initial Condition with both Main Boiler Feed Pumps operating is satisfactory.)

One of the Main Boiler Feed Pumps has experienced a malfunction and is in Track and Hold. The candidate will be directed to respond to a loss of Main Boiler Feed Pump Speed Control in accordance with 3-AOP-FW-1.

The candidate will not be able to reset Track and Hold initially and will be required to override the FW signal and control the Feed Pump speed using manual startup control. This is an Alternate Path JPM. This JPM directly from the JPM bank; however, it has not been used on the previous 2 NRC Exams. Failure to properly perform this task will result in trip of an operating Main Boiler Feed Pump Start a Hydrogen Recombiner:

The candidate will enter the simulator following a large break LOCA. The plant will be lined up for cold leg recirculation near the end of 1.3, Transfer to Cold Leg Recirculation.

The hydrogen concentration has been determined to be approximately 2%. The candidate will be directed to place the hydrogen recombiner in service using 3-S0P-CB-007. (NOTE: The hydrogen recombiner panel is a separate panel and the actual simulator setup conditions are not required). This is a New ,IPM.

Remove a Power Range Nuclear Instrument from Service: The candidate will enter the simulator at any power level. The candidate will be told that one Power Range NI channel is indicating erratically and the Shift Manager has declared the channel inoperable.

The candidate will be directed to remove the Power Range Channel from service in accordance with 3-S0P-NI-001. This is a bank JPM. Failure to properly perform this task will result in a Tech Spec violation/ Transfer a Circ Water Pump from Standby Drive to Normal: The candidate will enter the simulator with one of the Circulating Water Pumps operating on the Standby LCI drive. The repairs to the normal drive will be completed and the candidate will be directed to return the Circulating Water Pump to the Normal Drive. This is a New JPM. Failure to properly perform this task will result in possible loss of a circulating water pump. Not Used for SRO-I candidates.

In Plant JPMs Locally Start 32 Auxiliary Boiler Feed Pump: This JPM locally starts the Steam Driven Aux Feedwater Pump. During the startup the steam pressure control valve will not maintain pressure at 600 psig. The candidate will be required to control steam pressure using PCV-1139 Auto/Manual station. In Plant JPM This is an Alternate Path ,IPM This is a Bank JPM. Failure to properly perform this task will result in inability to control SG level during a control room evacuation. Start a CCW Pump from MCC 310A: This JPM locally starts a CCW pump from outside the control room due to a control room evacuation.

Loads must be stripped from the MCC that supplies the Appendix R MCC. In Plant JPM This is a Bank ,IPM. Failure to properly perform this task will result in loss of cooling to the RCP seals Perform Local Containment Isolation Valve Lineup IVSW (SOP-CB-11 steps 1-5). This JPM isolates lines that penetrate containment when equipment is shutdown during a post-accident condition.

The candidate will be required to locate and simulate opening/closing valves and circuit breakers for containment isolation valves. In Plant JPM This a New JPM. Failure to properly perform this task will result in inability to maintain RCS inventory and possible core damage.

Administrative Topics Outline Form ES-301-1 Facility:

Indian Point Unit 3 Date of Examination:

October 4, 2010 Examination Level: RO X SRO D Operating Test Number: Administrative Topic Type Describe activity to be (see Note) Calculate a Power Reduction Reactivity Plan per POP-2.1 Conduct of Operations N,R 2.1.43 (4.1) Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plan, fuel depletion, etc .. Determine Reactor Vessel Venting Time Per FR-1.3, Attachment 4 M,R Conduct of Operations 2.1.25 (3.9)Ability to interpret reference materials, such as graphs, curves, tables, etc. Perform a Peer Review of a Surveillance Test M,R Equipment Control 2.2.21 (2.9) Knowledge of pre-and post-maintenance operability requirements Perform a SG Tube Leakrate Determination using AOP-SG-1 Radiation N,R 2.3,5 (2.9)Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, ets. Emergency Procedures/Plan na NA for ROs All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required,

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:S 3 for ROs; :S 4 for SROs & RO retakes) (N)ew or (M)odified from bank (;?: 1) (P)revious 2 exams (:S 1; randomly selected)

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

Indian Point Unit 3 Date of Examination:

October 4, Exam Level: RO X SRO-I D SRO-U Operating Test Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System I JPM Title Emergency Borate b. Transfer to Cold Leg Recirculation

! c. Respond to a Pressurizer Controlling Channel Fail High Respond to Loss of Main Boiler Feedpump Speed Control Start the Hydrogen Recombiner Remove a Power Range Nuclear Instrument from Service Transfer a Circ Water Pump from Standby Drive to Normal h. Transfer buses 1 -4 to the Station Aux In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or .2 for Locally Start 32 Auxiliary Boiler Feed Pump Start a CCW Pump from MCC 31 OA Perform Local Containment Isolation Valve Lineup IVSW (SOP-CB-11 steps 1-5) Type Code* Safety Function M,A, P,S, L 1 D,A,E,EN, L 2 D 3 N,A 4-S N,E, L 5 D 7 N 8 N 6 D,A, E, L D,E, L N, EN, L, R @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power

/ Shutdown (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams (R)CA (S)imulator Criteria for RO / SRO-II SRO-U 4-6 /4-6 /2-3 2::1/2::1/2::1

/ 1 2::1 (control room system) 2::1/2::1/2::1

?: 2 I::?: 2 I::?: 1 3 I 3 I 2 (randomly selected)

?:1/::?:1/2::1 I

ES-301 Administrative T4:>pics Outline Form ES-301-1 INDIAN POINT UNIT 3 NRC RO EXAMINATION CONDUCT OF OPERATIONS:

Calculate a Power Reduction Reactivity Plan per POP 2.1. The candidate will be given appropriate graphs and tables and directed to calculate a reactivity plan for a power reduction from 100% to 75% power.

This is a New JPM

SRO Only CONDUCT OF OPERATIONS:

Perform a Peer Review of a Surveillance Test. The candidate will be given a completed Surveillance Test and directed to perform a Peer Review. The Surveillance Test will have inaccurate information

This is a New JPM

The SRO Only EQUIPMENT CONTROL: Prepare a Tagout for 31 Auxiliary Feed Water Pump. The candidate will be given plant prints and associated procedures and directed to prepare a manual tagout for the 31 Auxiliary Feedwater Pump for bearing replacement.

NOTE: Manual tagout exist in the JPM Bank; however, this component (31 Auxiliary Feedwater Pump) is new and has not been used before.

This is a New

RO Only RADIATION CONTROL: Perform a SG Tube Leakrate Determination using 3-AOP-SG-1.

The candidate will be given Radiation Monitor and the worksheet from 3-AOP-SG-1 and directed to calculate SG Tube leakage.

This is a New JPM

RO Only.

Control Room/In-Plant Systems Outline Form ES-301-2 Emergency Borate: The candidate will enter the simulator following a reactor trip with 2 stuck rods. The turbine failed to automatically trip on the reactor trip resulting in a cooldown below 540°F. Emergency boration valve MOV-333 will not open. The candidate must use Attachment 1 of ONOP-CVCS-3 to establish emergency boration Using Normal Boration.

The candidate must first borate for temperature and then borate for the additional stuck rod. This is an Alternate Path JPM. This is a Modified Bank JPM Failure to properly perform this task willi result in possible inadequate shutdown margin. Transfer to Cold Leg Recirculation:

The candidate will enter the simulator following a large break LOCA The RWST will be at the level requiring transfer to cold leg recirculation.

The candidate will be directed to establish cold leg recirculation using ES-1.3. The recirculation pumps will not start and the candidate will be required to establish recirculation using the RHR pumps This is a bank JPM. Failure to properly perform this JPM will result in inadequate cooling of the core and possible core damage. Respond to Loss of Main Boiler Feedpump Speed Control: The candidate will enter the simulator with the plant at 100% power. (NOTE: Actual power level is not required.

Any simulator Initial Condition with both Main Boiler Feed Pumps operating is satisfactory.)

One of the Main Boiler Feed Pumps has experienced a malfunction and is in Track and Hold. The candidate will be directed to respond to a loss of Main Boiler Feed Pump Speed Control in accordance with 3-AOP-FW-1.

The candidate will not be able to reset Track and Hold initially and will be required to override the FW Signal and control the Feed Pump speed using manual startup control. This is an Alternate Path JPM. This JPM directly from the JPM bank; however, it has not been used on the previous 2 NRC Exams. Failure to properly perform this task will result in Respond to a Pressurizer ContrOlling Channel Fail High: The candidate will enter the simulator at normal full power lineup. The controlling pressurizer pressure channel will fail resulting in maximum spray flow and pressurizer pressure decreasing rapidly. The candidate must take manual control of the master pressurizer pressure controller and stabilize pressure.

The candidate must then take appropriate actions to trip bistables associated with pressurizer pressure. This is a bank JPM. Failure to properly perform this task will result in a reactor trip. Start a Hydrogen Recombiner:

The candidate will enter the simulator following a large break LOCA The plant will be lined up for cold leg recirculation near the end of 1.3, Transfer to Cold Leg Recirculation.

The hydrogen concentration has been determined to be approximately 2%. The candidate will be directed to place the hydrogen recombiner in service using 3-S0P-CB-007. (NOTE: The hydrogen recombiner panel is a separate panel and the actual simulator setup conditions are not required). This is a New JPM.

Remove a Power Range Nuclear Instrument from Service: The candidate will enter the simulator at any power level. The candidate will be told that one Power Range NI channel is indicating erratically and the Shift Manager has declared the channel inoperable.

The candidate will be directed to remove the Power Range Channel from service in accordance with 3-S0P-NI-001. This is a bank JPM. Failure to properly perform this task will result in a Tech Spec violation/ Transfer a Circ Water Pump from Standby Drive to Normal: The candidate will enter the simulator with one of the Circulating Water Pumps operating on the Standby LCI drive. The repairs to the normal drive will be completed and the candidate will be directed to return the Circulating Water Purnp to the Normal Drive. This is a New JPM. Failure to properly perform this task will result in possible loss of a circulating water pump. Transfer buses 1 -4 to the Station Aux Transformer.

The candidate will enter the simulator at low power during a plant shutdown.

Turbine load will be less than 40 MWe. The candidate will be directed to transfer 6.9 kV buses 1 -4 from the Unit Aux Transformer to the Station Aux Transformer in preparation for a turbine shutdown. This is a New JPM. Failure to properly perform this task may result in the loss of 6.9 kV buses 1 -4. In Plant JPMs Locally Start 32 Auxiliary Boiler Feed Pump: This JPM locally starts the Steam Driven Aux Feedwater Pump. During the startup the steam pressure control valve will not maintain pressure at 600 psig. The candidate will be required to control steam pressure using PCV -1139 Auto/Man ual station. In Plant .IPM This is an Alternate Path JPM This is a Bank JPM. Failure to properly perform this task will result in inability to control SG level during a control room evacuation. Start a CCW Pump from MCC 310A: This JPM locally starts a CCW pump from outside the control room due to a control room evacuation.

Loads must be stripped from the MCC that supplies the Appendix R MCC. In Plant JPM This is a Bank JPM. Failure to properly perform this task will result in loss of cooling to the RCP seals Perform Local Containment Isolation Valve Lineup IVSW (SOP-CB-11 steps 1-5). This JPM isolates lines that penetrate containment when equipment is shutdown during a post-accident condition.

The candidate will be required to locate and simulate opening/closing valves and circuit breakers for containment isolation valves. In Plant JPM This a New JPM. Failure to properly perform this task will result in inability to maintain RCS inventory and possible core damage.

Administrative Topics Outline Form ES-301-1 Facility:

Indian Point Unit 3 Examination Level: ROO SRO X Date of Examination:

October 4, 2010 Operating Test Number: Administrative Topic (see Note) Type Code* Describe activity to be performed Review a gross leakrate determination calculation Conduct of Operations N,R 2.1.7 (4.7) Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretations Conduct of Operations M,R Determine Reactor Vessel Venting Time Per FR*I.3, Attachment 4 2.1.25 (4.2) Ability to interpret reference materials, such as graphs, curves, tables, etc. Equipment Control N,R Perform a Safety Function Determination 2.2.37 (4.6) Ability to determine operability and/or availability of safety related equipment Radiation Control N,R Review a Manual Gaseous Rad Waste Release Permit 2.3.6 (3.8) Ability to approve release permits Emergency Procedures/Plan M,R,P Classify E*Plan Event and Complete Part 1 Form 2.4.38 (4.4) Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required. All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required . .. Type Codes &(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (S 3 for ROs; S 4 for SROs &RO retakes) (N}ew or (M)odified from bank (;::: 1) (P)revious 2 exams (S 1; randomly selected)

Control Roomlln-Plant Systems Outline Form ES-301-2 Facility:

Indian Point Unit 3 Date of Examination:

October Exam Level: RO D SRO-I D SRO-U X Operating Test Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System I J PM Title NA forSRO-U Transfer to Cold Leg Recirculation NA forSRO-U NA for SRO-U NA for SRO-U Remove a Power Range Nuclear Instrument from Service Transfer a Circ Water Pump from Standby Drive to Normal h. NA for In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for Locally Start 32 Auxiliary Boiler Feed NA for Perform Local Containment Isolation Valve Lineup IVSW (SOP-CB-11 steps 1-5) Type Code* Safety Function na na D,A, E, EN, L 2 na na na na na na D 7 N 8 na na D,A, E, L 4-S na na N, EN, L, R 5 @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room. "Type Codes (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature {L)ow-Power 1 Shutdown {N)ew or {M)odified from bank including 1 (A) (P)revious 2 exams (R)CA (S)imulator Criteria for RO 1 SRO-II SRO-U 4-6/4-6/2-3

$9/$8/$4 1 1 (control room system) ;::1/;::1/;::1

$ 31::; 3 I::; 2 (randomly selected)

ES-301 Administrative TOp'ics Outline Form ES-301-1 INDIAN POINT UNIT 3 NRC R((EXAMINATION CONDUCT OF OPERATIONS:

Review a gross leakrate determination calculation.

The candidate will be given a set of conditions and appropriate indications and a manualleakrate calculation.

The candidate will review the leakrate calculation and locate errors.

This is a New JPM

SRO Only CONDUCT OF OPERATIONS:

Determine Reactor Vessel Venting Time Per FR-I.3, Attachment 4 The candidate will be given a set of plant conditions with a void in the reactor vessel head. The candidate will be given directions to calculate the reactor vessel venting time in accordance with Functional Restoration Procedure FR-1.3

This is a bank JPM

Ths JPM is common to both RO and SRO candidates EQUIPMENT CONTROL: Perform a Safety Function Determination.

The candidate will be given a set of plant/equipment conditions including degraded power sources and equipment failures.

The candidate will be directed to perform a Safety Function Determination in accordance with OAP-034.

This is a New JPM

SRO Only. RADIATION CONTROL: Review a Manual Gaseous Rad Waste Release Permit. The candidate will be given a set of plant conditions for the VC Pressure Relief and a manually prepared release permit. The candidate will be directed to review the release permit in accordance with 3-S0P-WDS-013.

The candidate must locate errors on the permit.

This is a Modified Bank JPM

SRO Only. EMERGENCY PROCEDURES/PLAN:

Classify E ..Plan Event and Complete Part 1 Form. The candidate will be given a set of plant conditions.

The candidate must evaluate the conditions, determine the emergency plan classification and complete the New York State Part 1 form

This is a Modified Bank JPM.

This is a Time Critical ,IPM

SRO Only.

Control Room/In-Plant Systems Outline Form ES-301-2 NA for SRO-U Transfer to Cold Leg Recirculation:

The candidate will enter the simulator following a large break LOCA. The RWST will be at the level requiring transfer to cold leg recirculation.

The candidate will be directed to establish cold leg recirculation using ES-1.3. The recirculation pumps will not start and the candidate will be required to establish recirculation using the RHR pumps This is a bank JPM. Failure to properly perform this JPM will result in inadequate cooling of the core and possible core damage. NA for SRO-U NA for SRO-U NA for SRO-U Remove a Power Range Nuclear Instrument from Service: The candidate will enter the simulator at any power level. The candidate will be told that one Power Range NI channel is indicating erratically and the Shilt Manager has declared the channel inoperable.

The candidate will be directed to remove the Power Range Channel from service in accordance with 3-S0P-NI-001. This is a bank JPM. Failure to properly perform this task will result in a Tech Spec violation/ Transfer a Circ Water Pump from Standby Drive to Normal: The candidate will enter the simulator with one of the Circulating Water Pumps operating on the Standby LCI drive. The repairs to the normal drive will be completed and the candidate will be directed to return the Circulating Water Pump to the Normal Drive. This is a New JPM. Failure to properly perform this task willi result in possible loss of a circulating water pump. NA for SRO-U In Plant .IPMs Locally Start 32 Auxiliary Boiler Feed Pump: This JPM locally starts the Steam Driven Aux Feedwater Pump. During the startup the steam pressure control valve will not maintain pressure at 600 pSig. The candidate will be required to control steam pressure using PCV-1139 Auto/Manual station. In Plant JPM This is an Alternate Path .1 PM This is a Bank JPM. Failure to properly perform this task willi result in inability to control SG level during a control room evacuation.

j. NA for SRO-U.

Perform Local Containment Isolation Valve Lineup IVSW (SOP-CB-11 steps 1-5). This JPM isolates lines that penetrate containment when equipment is shutdown during a post-accident condition.

The candidate will be required to locate and simulate opening/closing valves and circuit breakers for containment isolation valves. In Plant JPM This a New JPM. Failure to properly perform this task will result in inability to maintain ReS inventory and possible core damage.

--Appendix 0 Scenario Outline Form ES-D-1 Facility:

IPEC Unit 3 Scenario No.: 1 Op-Test No.: Examiners:

Operators:

Initial Plant is at 65%. 31 EDG is OOS for an oil system Return power to 100%. 31 EDG is OOS and not expected back on this Event Malf. Event Event No. No. Type* Description 1 N/A R(ATC) Perform power ascension.

N(BOP) N(CRS) 2 I(ALL) Controlling PZR level instrument fails low causing letdown to PRSOO6 B TS{CRS) isolate. Channel is defeated and letdown is restored.

3 C(ALL) Letdown leak inside containment. Leak will be isolated.

CVCOO3 TS(CRS) 4 C(ALL) 480V Bus 6A fault. EPSOO5 0 5 M(ALL) Sequential loss of lVIain Feedwater Pumps leading to plant trip ATSOO4 AlB 6 C(ALL) PORV fails open, cannot be isolated.

PRSOO3 D 7 C(CRS) 31 and 32 Safety Injection Pumps will not auto-start. (Neither SISOO4A board operator credited since either one may start pump.) IB 8 C(ALL) Loss of Station Aux Transformer when Containment Phase A is EPS006 reset. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Session Outline: The session begins with power at 65% and 31 EDG out of service for an oil system modification.

The team has been instructed to return the plant to 100% at 10% an hour. They will begin raising power per POP-2.1, "Operation above 45% Power". When sufficient load ascension has been observed, the controlling PZR Level channel will fail low causing Letdown to isolate. The team will respond and restore Letdown per AOP-INST-1, "Instrument or Controller Failures".

When Letdown has been restored, a leak will occur on the Letdown line inside containment.

This can be isolated per AOP-LEAK-1, "Sudden Increase in Reactor Coolant System Leakage".

Following leak isolation, a fault of 480V Bus 6A will occur. The team will respond per AOP-480V-1, "Loss of Normal Power to any Safeguards 480V Bus". When the team has had time to address Charging, Service Water and RCP seal cooling, the Main Boiler Feed Pumps will sequentially trip. In response, the Team will trip the reactor as per the guidance of AOP _FW-1, "LeiSS of Feedwater" (although formal entry into the AOP is not required).

On the trip, PORV PCV-456 will fail open. Since Bus 6A is faulted, the MOV Block valve for this PORV cannot be closed. 31 and 32 SI pumps will not auto-start, but can be started manually.

RCPs will be tripped due to loss of subcooling.

A LOOP will occur when Containment Isolation Phase A is reset. The team will have to respond per EOP LOOP-1, "Loss of Offsite Power after SI Reset". When the team announces transition to E-1, the scenario will be terminated.

Procedure flowpath:

POP-2.1, AOP-INST-1, AOP-Leak-1, AOP-480V-1, E-O, LOOP-1, E-1 Critical Tasks: CT 1: Start at least 1 High Head Safety Injection Pump. CT 2: Trip RCPs when RCP trip criteria are met.

I Appendix Scenario Outline Form ES-O-1 Facility:

IPEC Unit 3 Scenario No.: 2 Op-Test No.: -.1 Examiners:

Operators:

Initial Plant is at 5%.31 Charging Pump is OOS for Come up to 10% power, then warm up the MTG and place it in service. 31 Charging Pump is OOS not expected back on this shift. Event No. N/A 040A CCWOO 1A1B CCWOO SA MSSOO9 A RPS002 AlB HVAOO1 A1 .. Event Type* R(ATC) N(CRS) I(ALL) TS(CRS) C(CRS) C(BOP) TS(CRS) C(CRS) C(BOP} TS(CRS) C(CRS) C(ATC) M(ALL) C(BOP}

Perform ascension.

32 SG Pressure Channel Failure causing ADV to open. 31 CCW Pump trips and 32 CCW fails to auto-start.

CCW leak at 31 HX. Can be isolated Main Steam header break with no MSIVs auto-closing and 1 MSIV failing open. Failure of the Reactor to trip both Auto and Manual. Team will emergency borate and manually insert control rods. 31 Fan Cooler Unit fails to auto-start. (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Session Outline: The evaluation begins with the plant at 5% power ready to raise power and place the MTG in service. The following equipment is out of service: 31 Charging pump for PM. The team has been instructed to raise power to 10 and begin warming up the MTG to bring the unit on line. ?o....,.:;e.,.(" When sufficienttmsd-ascension has occurred, a failure of the 32 SG Pressure C channel 429C) will occur.

This will cause the Atmospheric Dump Valve for that SG to go full open. The ATC will place the valve in manual and closed. The team will enter AOP-INST-1 and trip bistables to satisfy Tech Specs. When PT -429C bistables are tripped, 31 CCW pump will trip and 32 will fail to auto-start.

Manual start of 32 CCW pump will work. After flow has been re-established a leak in CCW will occur at 31 CCW HX. The team will take actions in accordance with AOP-CCW-1, Loss of Component Cooling. Prior to completion of the Subsequent Actions of AOP-CCW-1, a steam break will occur in the Turbine Building.

The team will attempt to manually trip the plant, close MSIVs, and perform actions of E-O, Reactor Trip or Safety Injection.

The reactor will not trip from the Control Room and the team will respond per FR-S.1, Response to Nuclear Power Generation I ATWS and will SID the reactor by manually inserting control rods and initiating Emergency Boration.

The reactor trip breakers will be locally opened and the team will transition to E-O, Reactor Trip or Safety Injection.

Following SI actuation, 31 FCU does not auto start. A loss of the Station Auxiliary Transformer will occur when the control rods are inserted.

The MSIVs will fail to auto close. All but 34 MSIV will be able to be closed in manual from the control room. The team will respond to the faulted SG per E-2, Faulted Steam Generator Isolation and transition to E-1, Loss of Reactor or Secondary Coolant. The scenario may be terminated when after the transition.

Procedure flow path: POP-1.3, AOP-INST-1, AOP-CCW-1, AOP-UC-1, E-O, FR-S.1, E-O, E-2, 1 Critical Task: CT 1: Insert negative reactivity when reactor fails to trip. CT 2: Isolated faulted SG.

Appendix Scenario Outline Form ES-D-1 Facility:

IPEC Unit3 Scenario No.: Op-Test No.: -.-1 Initial Plant is at 100%. 31 AFW Pump is OOS due to vibrations.

PORV 455C is inoperable due blowing Maintain 100% power conditions.

31 AFW Pump is OOS due to high vibrations.

PORV 455C inoperable due to blowing poo. t Malf. Event J;:JDescription XMT-I(ALL) VCT level instrument fails MAL-C(ALL) 33 Charginlg Pump TS(CRS) 3 SGN005C 4 5 SGNOO5C 6 EPSOO6 6 CFWOO1C 7 SISOO4A 8 PRSOO3D CVC031A C(ALL) TS(CRS) R(ATC} N(CRS) N(BOP) M(ALL) C(ALL) C(CRS) C(ATC) C(BOP) C(ALL) 900 gpd SGTL on 33 SG. Tech Spec required shutdown.

SGTL becomes SGTR PORV failure, LOOP and Aux Valve failure will lead to loss of pressure Loss of Station Auxiliary 33 AFW Pump fails to 31 Safety Injection Pump fails to PORV and Aux Spray failures lead to loss of pressure * (N)ormal, (R)eactivity. (I)nstrument, (C)omponent, (M}ajor SESSION OUTLINE: The evaluation begins with the plant at 100% power steady state operation.

The following equipment is out of service: # 31 ABFP was declared inoperable 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ago due to high vibrations during its PT (TS 3.7.5 -72 hr AOT) PORV 455C was declared inoperable 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago due to blowing its control power fuses. TIS is in progress.

Per TS 3.4.11, the block valve has been closed with power removed and a 7 day AOT entered. After taking the watch, the VCT Level instrument fails low. The team will respond per AOP-CVCS-1, "Chemical and Volume Control Malfunction".

When the VCT level failure has been addressed, the running Charging Pump will trip. The team will re-enter and take actions per AOP-CVCS-1, "Chemical and Volume Control Malfunction".

After performing actions for the Charging pump trip, a SG tube leak ramped to a SGTR will occur. The team should take actions per AOP-SG-1, "Steam Generator Tube Leak". This will include begin a plant shutdown.

When the team has sufficiently progressed through the shutdown, the SGTL will become a SGTR. The team will trip the Reactor and initiate SI.# 33 ABFW pump will trip after auto starting requiring manual action to be taken in E-O. 31 SI pump will have to be manually started. The station auxiliary transform will fail resulting in a loss of offsite power when 6.9KV buses transfer following the reactor trip. The team will transition to and take actions per E-3, "Steam Generator Tube Rupture".

Spray will not be available due to the loss of offsite power. This, along with the PORV failure to open, will require the team to transition to ECA-3.3, 'SGTR Response without Pressurizer Pressure Control" until SI pumps are secured. Procedure flow path: AOP-CVCS-1, AOP-SG-1, E-O, E-3, ECA-3.3 Critical Tasks: CT 1: Establish 365 gpm AFW flow. CT 2: Isolate AFW flow to ruptured SG. CT 3: Establish and maintain cooldown in E-3. CT 4: Terminate SI before SG overfill in ECA-3.3.

ML103080910

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