ML13066A337

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Indian Point Unit 3 - Final Outlines (Folder 3)
ML13066A337
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 02/12/2013
From: D'Antonio J M
Operations Branch I
To:
Entergy Nuclear Indian Point 3
Jackson D E
Shared Package
ML12214A189 List:
References
ES-401, ES-401-2, TAC U01866
Download: ML13066A337 (33)
v • d • e


Text

ES-401 PWR Examination Outline Form ES-401*2 Facility:

Indian Point Unit 3 Printed: 12/12/2012 Date Of Exam: 02/11/2013

3. Generic Knowledge And RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total 1. 1 3 3 3 3 3 3 18 3 3 6 Emergency

& 2 2 2 2 N/A 1 1 N/A 1 9 2 2 4 Abnormal Tier Plant Evolutions Totals 5 5 5 4 4 4 27 5 5 10 2. 1 2 2 3 3 3 2 3 3 2 3 2 28 3 2 5 Plant 2 1 1 0 1 1 1 1 1 1 1 1 10 0 I 2 1 3 Systems Tier Totals 4 3 3 4 4 3 4 4 3 4 2 38 5 3 8 1 2 3 4 1 2 3 4 7 Abilities Categories 3 3 2 2 2 2 1 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 t01als 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.

1 PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 000008 Pressurizer Vapor Space Accident 1 3 000009 Small Break LOCA 1 3 000011 Large Break LOCA 13 000015/000017 RCP Malfunctions 1 4 000022 Loss of Rx Coolant Makeup 1 2 000022 Loss of Rx Coolant Makeup / 2 000025 Loss of RHR System /4 000025 Loss of RHR System /4 NRC Written Examination Knowledge of the interrelations between I the Pressurizer Vapor Space Accident I 2.7 I X and the following:

-Sensors Knowledge of the reasons for I following responses as they apply to the I X I I 4.1 I 2 small break LOCA: -ECCS throttling or termination criteria Ability to determine and interpret the following as they apply to a Large Break EA2.08 I LOCA: -Conditions necessary for I 3.4 I 3 recovery when accident reaches stable Qhase Ability to determine and interpret the following as they apply to the Reactor I AA2.08 I Coolant Pump Malfunctions:

-When to I 3.5 I 76 secure RCPs on high bearing tem Knowledge of the reasons for the I following responses as they apply to the I X I I 3.2 I 5 Loss of Reactor Coolant Makeup: -RCP thermal barrier cooli Ability to determine and interpret the I following as they apply to the Loss of I 3 8 I II 77* Reactor Coolant Makeup: -How long PZR . level can be maintained within limits Knowledge of the operational implications of the following concepts as they apply to I X I AK1.01 I Loss of Residual Heat Removal System: -I 3.9 I 6 Loss of RHRS during all modes of on Emergency Procedures/Plan

-Knowledge I of low power / shutdown implications in I 3.8 I 81 accident (e.g. LOCA or loss of RHR) m NUREG PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 1 000026 Loss of Component Cooling Water /8 AA2.01 Ability to determine and interpret the I following as they apply to the Loss of Component Cooling Water: -Location of a I 2 9 . I 7 leak in the CCWS 000029 ATWS /1 I X I EK2.06 Knowledge of the interrelations between I the A TWS and the following:

-Breakers, I 2.9 I 9 and disconnects Conduct of Operations

-Ability to perform 000029 A TWS /1 2.1.23 I specific system and integrated plant procedures during all modes of plant I 4.4 I 78 000038 Steam Gen. Tube Rupture / 3 X EK1.03 Knowledge of the operational imp I of the following concepts as they apply to 3.9 10 the SGTR: -Natural circulation 000038 Steam Gen. Tube Rupture I 3 2.4.11 I Emergency Procedures/Plan

-Knowledge of abnormal condition 4.2 79 000054 Loss of Main Feedwater / 4 2.1.20 I Conduct of Operations

-Ability to interpret I and execute 4 6 . 11 Equipment Control -Knowledge of the 000055 Station Blackout / 6 2.2.18 process for managing maintenance I activities during shutdown operations, I 2.6 I 12 such as risk assessments, work etc. Ability to operate and/or monitor the 000056 Loss of Off-Site Power /6 I X AA1.10 I following as they apply to the Loss of Offsite Power: -Auxiliary/emergency I 3.6 I 4 feedwater (motor d Ability to operate and/or monitor the 000057 Loss of Vital AC Inst. Bus / 6 IX AA1.03 I following as they apply to the Loss of Vital AC Instrument Bus: -Feedwater pump I 3 6 . I 13 e to control eressure and level in S/G Ability to determine and interpret the 000058 Loss of DC Power / 6 AA2.03 I following as they apply to the Loss of DC Power: -DC loads lost; impact on to I 3.9 I 80 000062 Loss of Nuclear Svc Water /4 _2.1.20 and monitor I Conduct of

    • " -'.'......"y LV .. m ........ vL and execute I 4.6 I 14 NUREG 1021 PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 ES-401 000077 Generator Voltage and Electric Grid Disturbances I 6 W/E04 LOCA Outside Containment / 3 W/E05 Inadequate Heat Transfer -Loss of Secondary Heat Sink / 4 W/E11 Loss of Emergency Coolant Recirc./4 W/E12 Steam Line Rupture -Excessive Heat Transfer I 4 AK3.02 I X I EA2.2 EK2.2 I X I Ix EA1.3 EK1.03 I X I 1 Knowledge of the reasons for the following responses as they apply to I Generator Voltage and Electrical Grid I 3.6 I 15 Disturbances:

-Actions contained abnormal operating procedure for and grid Ability to determine and interpret following as they apply to the I Outside Containment:

-Adherence to 3.6 I 16 appropriate procedures and within the limitations in the license and Knowledge of the interrelations the Loss of Secondary Heat Sink and following:

-Facility's heat I systems, including primary coolant, 3.9 I 17 emergency coolant, the decay removal systems, and relations the proper operation of these systems the of the Ability to operate and/or monitor following as they apply to the Loss Emergency Coolant Recirculation:

-I 3.7 I 18 Desired operating results during abnormal and emergency situations Knowledge of the operational implications of the following concepts as they apply to the Uncontrolled Depressurization of all I Steam Generators:

-Annunciators and 3.4 I 8 conditions indicating Signals, remedial actions associated with Uncontrolled Depressurization of Steam NUREG PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 2 Equipment Control -Ability to interpret control room indications to verify the I status and operation of a system, and 000003 Dropped Control Rod 11 2.2.44 I 4.4 182 understand how operator actions and directives affect plant and system conditions.

Knowledge of the interrelations between 1 the Pressurizer Level Control 000028 Pressurizer Level Malfunction I 2 I IX I AK2.02 I 2.6 124 Malfunctions and the following:

-Sensors and detectors Knowledge of the reasons for the following responses as they apply to the I Loss of Intermediate Range Nuclear 000033 Loss of Intermediate Range NI /7 I IX I AK3.02 I 3.6 I 19 Instrumentation:

-Guidance contained in EOP for loss of intermediate-range instrumentation Ability to operate and/or monitor the I following as they apply to the Fuel 000036 Fuel Handling Accident / 8 IX AA1.04 I 3.1 120 Incidents:

-Fuel handling 9 ent during an incident Ability to determine and interpret the I following as they apply to the Steam 4 000037 Steam Generator Tube Leak 1 3 AA2.16 183 Generator Tube Leak: -Pressure at which I .3 to maintain RCS during S/G cooldown Emergency Procedures/Plan

-Knowledge I of RO tasks performed outside the main 000068 Control Room Evac. I 8 2.4.34 I 4.2 I 21 control room during an emergency and the resultant oeerational effects. Knowledge of the interrelations between 000076 High Reactor Coolant Activity 19 I IX I AK2.01 I the High Reactor Coolant Activity and the I 2.6 122 following:

-Process radiation monitors Ability to determine and interpret the following as they apply to the Sl I Termination:

-Facility conditions and W/E02 SI Termination 13 EA2.1 I 3.8 123 selection of appropriate procedures during abnormal and emergency III I NUREG 1021 PWR RO/SRO Examination Outline Facility:

Pont Unit 3 NRC Written Examination Outline I --.u

-Tier 1/ Group 2 Equipment Control -Ability to determine W/E03 LOCA Cooldown -Depress. 14 2.2.37 I operability andlor availability of safety I 4.6 184 related Knowledge of the operational implications of the following concepts as they apply to I the Degraded Core Cooling: -Normal, W/E06 Inad. Core Cooling I 4 IX I EK1.2 I 3.5 125 abnormal and emergency operating procedures associated with Degraded Core Cooli Ability to determine and interpret the following as they apply to the Natural Circulation with Steam Void in Vessel W/E10 Natural Circ./4 EA2.1 I with/without RVLlS: -Facility conditions I 3.9 185 and selection of appropriate procedures during abnormal and emergency Knowledge of the reasons for the following responses as they apply to the Natural Circulation with Steam Void in Vessel with/without RVLlS: -Facility I operating characteristics during transient W/E10 Natural Circ. 14 IX I EK3.1 13.4 127conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these rating characteristics Knowledge of the operational im plications of the following concepts as they apply to the High Containment Pressure: W/E14 Loss of CTMT Integrity 15 IX I EK1.3 I 3.3 126 I Annunciators and conditions indicating signals, and remedial actions associated with the Hiah Containment Pressure NUREG 1021 6 Facility:

Indian Pont Unit 3 PWR RO/SRO Examination Outline NRC Written Examination Outline ES-401 .... ""'TPm #lName I'lant .ms-Tier 21 Group 1m nun Number I KIA Topic Form ES-401-2 Q# Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS and (b) based on those 003 Reactor Coolant Pump predictions, use procedures to correct, control, or mitigate the consequences of 12.5 128 those malfunctions or operations:

-Effects of VCT pressure on RCP seal leakoff flows Knowledge of the effect of a loss or 004 Chemical and Volume Control IX malfunction on the following CVCS components:

-Reason for excess letdown I 2 7 . I 29 and its relationshie to CCWS Knowledge of the physical connections 005 Residual Heat Removal IX and/or cause-effect relationships between the RHRS and the following systems: -I 3 2 . I 30 CCWS 005 Residual Heat Removal IX Knowledge of bus power supplies to the following:

-RCS pressure boundary motor-operated valves 12.7 I 31 006 Emergency Core Cooling IX Knowledge of the effect of a loss or malfunction of the following will have on ECCS: -HPIfLPI cooling water 13.0 132 Knowledge of the operational implications 006 Emergency Core Cooling IX of the following concepts as they apply to the ECCS: -Operation of pumps in 12.9 133 parallel 007 Pressurizer Relief/Quench Tank Conduct of Operations

-Ability to explain and apply all system limits and tions. I 2.9 134 007 Pressurizer Relief/Quench Tank Equipment Control-Knowledge of conditions and limitations in the facility license. I 4.5 I 87 Knowledge of the physical connections 008 Component Cooling Water IX and/or cause-effect relationships between the CCWS and the following systems: I 3 1 . 135 NUREG 1021 PWR RO/SRO Examination Outline Facility:

Indian Pont 3 010 Pressurizer Pressure Control Ix I K4.03 Knowledge of PZR PCS design I and/or interlock(s) which provide for the following:

-Over control Ability to predict and/or monitor changes 010 Pressurizer Pressure Control Ix A1.07 in parameters (to prevent exceeding I design limits) associated with operating the PZR PCS controls including:

-RCS 012 Reactor Protection I X I A3.07 I Ability to monitor automatic operation of the RPS. including:

-

breakers Knowledge of RPS design feature(s) and/or interlock(s) which provide for the 012 Reactor Protection I Ix I K4.02 I following:

-Automatic reactor trip when RPS setpoints are exceeded for each RPS function; basis for each Knowledge of ESFAS design feature(s) 013 Engineered Safety Features Actuation Ix I K4.10 I and/or interlock(s) which provide for the following:

-Safeguards equipment control reset Ability to (a) predict the impacts of the 013 Engineered Safety Features Actuation A2.01 following malfunctions or operations on I the ESFAS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or

-LOCA Ability to predict and/or monitor changes 022 Containment Cooling Ix A1.04 in parameters (to prevent exceeding I design limits) associated with operating the CCS controls including:

-Cooling waterflow 026 Containment Spray Ix I K3.01 Knowledge of the effect that a loss or I malfunction of the CSS will have on the following:

-CCS 039 Main and Reheat Steam Ix I K5.08 Knowledge of the operational implications I of the following concepts as they apply to the MRSS: -Effect of steam removal on 13.8 13.7 14.0 13.9 I 33 . I 4.8 13.2 13.9 13.6 136 137 138 139 I 40 I 88 '42 143 144 NUREG l02l 8 PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 Form

""",HP'" #lName Ability to predict and/or monitor changes in parameters (to prevent exceeding I design limits) associated with operating 059 Main Feedwater IX 12.7 145 the MFW System controls including: Power level restrictions for operation of MFW and valves Ability to manually operate and/or monitor 059 Main Feedwater Ix A4.03 I in the control room: -Feedwater control 12.9 146 during increase and decrease Knowledge of the operational implications 061 of the following concepts as they apply to K5.03 12.6 147I I Ix the AFW System: -Pump head effects Feedwater I I I I when control valve is shut Ability to (a) predict the impacts of the following malfunctions or operations on 061 the AFW System and (b) based on those Auxiliary/Emergency A2.02 predictions, use procedures to correct, I 3.2 141 Feedwater control, or mitigate the consequences of those malfunctions or operations:

-Loss of air to steam su I valve 061 Conduct of Operations

-Ability to explain Auxiliary/Emergency and apply all system limits and 14.0 I 86 Feedwater recautions.

Knowledge of the effect that a loss or 062 AC Electrical malfunction of the A.C. Distribution 14.1 148 Distribution will have on the following:

-ED/G Ability to (a) predict the impacts of the following malfunctions or operations on the A.C. Distribution System and (b) 062 AC I based on those predictions, use I 2.9 I 89 procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

-Degraded system 063 DC Electrical 13.0 149 Distribution I I I I I NUREG 9 PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 ES-401 SyS!t::II1 K5 064 Emergency Diesel Generator 073 Process Radiation Monitoring 073 Process Radiation Monitoring 076 Service Water 076 Service Water x to Ability to manually operate and/or monitor in the control room: -Radiation monitoring c"d""m control Ability to (a) predict the impacts of the following malfunctions or operations on the PRM System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure Ability to (a) predict the impacts of the following malfunctions or operations on the SWS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Service water header oressure bus power supplies to the SOI"\/;"

water 3.7 3.7 3.2 2.7 2.7 50 51 90 52 53 078 Instrument Air 3.1 154 1 03 Containment x 3.3 155 NUREG 1021 PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 Form ES-401-2 I '" 'V"'::l

of bus power supplies to the 001 Control Rod Drive I IX I K2.05 I 3.1 156 following:

-M/G sets Ability to (a) predict the impacts of the following malfunctions or operations on the CRDS and (b) based on those 001 Control Rod Drive I A2.18 I predictions, use procedures to correct, 13.8 191 control, or mitigate the consequences of those malfunctions or operations: I ncorrect rod Ability to (a) predict the impacts of the following malfunctions or operations on the RCS and (b) based on those 002 Reactor Coolant A2.04 I predictions, use procedures to correct, 14.3 157 control, or mitigate the consequences of those malfunctions or operations:

-Loss of heat sinks Conduct of Operations

-Knowledge of 002 Reactor Coolant 2.1.42 I new and spent fuel movement I 3.4 I 92 s. Knowledge of the operational implications 011 Pressurizer Level I of the following concepts as they apply to I 3 6 I 58

  • K5.15 Ix I .Control the PZR LCS: -PZR level indication when RCS is saturated I Ability to monitor automatic operation of 015 Nuclear X A3.02 the NIS, including:

-Annunciator and 13.7 159 Instrumentation I alarm signals Ability to manually operate and/or monitor in the control room: -Temperature values 017 In-core A4.02 I used to determine RCS/RCP operation I 3.8 I 60 Temperature Monitor Ix during inadequate core cooling (i.e., if g of five highest val Knowledge of Containment Purge System 029 Containment I design feature(s) and/or interlock(s) which I 32 I 62 K4.03 Ix I Purge provide for the following:

-Automatic . isolation NUREG 102l 11 PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 ES-401 SYl3tem #/Name 034 Fuel Handling x Equipment 034 Fuel Handling Equipment 041 Steam Dump System and Turbine x Bypass Control 045 Main Turbine Generator 086 Fire Protection x Knowledge of the effect of a loss or malfunction of the following will have on the Fuel Handling System: -Radiation Ability to (a) predict the impacts of the following malfunctions or operations on the Fuel Handling System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or element Knowledge of the physical connections and/or cause-effect relationships between the SDS and the following systems: Condenser Conduct of Operations

-Knowledge of and or function.

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the Fire Protection System controls includina:

-FPS Ii 2.6 163 4.4 93 2.6 61 3.9 64 2.9 65 NUREG 1021 12 Generic Knowledge and Abilities Outline (Tier 3) PWR RO/SRO Examination Outline Facility:

Indian Pont Unit 3 Facility I Indian Point Unit 3 I Date of Exam Category KIA # 2.1.5 2.1.23 1 . Conduct of Operations 2.1.37 2.1.40 2.1.45 Subtotal 2.2.1 2.2.2 2. Equipment Control 2.2.36 2.2.22 2.2.25 Subtotal Topic Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Knowledge of procedures, guidelines, or limitations associated with reactivity management.

Knowledge of refueling administrative requirements Ability to identify and interpret diverse indications to validate the response of another indication Equipment Control -Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels. Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

Knowledge of limiting conditions for operations and safety limits Knowledge of bases in technical specifications for limiting conditions for operations and safety limits. Form ES-401-3 2111/2013 RO SRO-Only IR Q# IR Q# 2.9 66 4.3 67 4.3 68 3.9 94 4.3 95 3 3 2 2 4.5 69 4.0 70 3.1 71 4.7 96 4.2 97 3 3 2 2 NUREG 1021 Generic Knowledge and Abilities Outline (Tier PWR ROISRO Examination Facility:

Indian Pont Unit Form ES-401-3 Facility I Indian Point Unit 3 I Date of Exam 211112013 Category KIA # Topic RO SRO-Only IR Q# IR Q# Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment 3.2 72 entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to 2.3.13 radiation monitor alarms, containment 3.4 73 entry requirements, fuel handling Controls responsibilities, access to locked high-radiation areas, aligning filters, etc Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey 2.9 98 instruments, personal monitoring equipment, etc 2 2 1 1 Knowledge of the organization of the operating procedures network for 3.7 74 normal, abnormal, and emergency evolutions.

Knowledge of abnormal condition 4.0 75 procedures.

4. Emergency Knowledge of the bases for prioritizing Proced ures/pla n safety functions during 4.4 99 abnormallemergency operations.

Knowledge of the bases for prioritizing emergency procedure implementation 4.4 100 during emergency operations Subtotal 2 2 2 2 Tier 3 Point 10 10 7 7 NUREG 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 Tier / Group 0000112113 R 1/1 Large Break LOCA 0OO015A111 R 1/1 RCP Malfunction 000027K1.02 Pressurizer R-1/1 Pressure Control System Malfunction 000058A201 R 1/1 Loss of DC Power 00WE042126 R111 LOCA Outside Containment 000015A120 R 1/1 RCP Malfunctions 000024K302 R 1/2 Emergency Boration 0000362140 R 1/2 Fuel Handling Accident Record of Rejected KI As Randomly Selected KJA Conduct of Operations

-Knowledge of facility requirements for controlling vitali controlled access. Ability to operate and/or monitor the following as they apply to the Reactor Coolant Pump Malfunctions:

-RCP on/off and run indicators Knowledge of the operational implications of the following concepts as they apply to Pressurizer Pressure Control Malfunctions:

-Expansion of liquids as temperature increases Ability to determine and interpret the following as they apply to the Loss of DC Power: -That a loss of dc power has occurred; verification that substitute power sources have come on line Conduct of Operations

-Knowledge of non-nuclear safety procedures (e.g. rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen.

Ability to operate and/or monitor the following as they apply to the Reactor Coolant Pump Malfunctions:

-RCP bearing temperature indicators Knowledge of the reasons for the following responses as they apply to the Emergency Boration:

-Actions contained in EOP for emergency boration Conduct of Operations

-Knowledge of refueling administrative requirements.

Form ES*401*4 Reason for Rejection REJECTED Generic KA is not applicable to Large Break LOCA. REJECTED This KA is evaluated during Simulator Operational Examination.

REJECTED This KA was rejected due to overlap with Question 37. REJECTED Not applicable to Indian Point 3. Unit 3 does not have any automatic swap to alternate DC source functions.

REJECTED Generic KA is not applicable to LOCA Outside Containment RREJECTED This KA was rejected due to overlap with SRO Only Question 76. REJECTED This KA overlaps with a currently selected JPM. REJECTED Over sample, This Generic KA selected for SRO Only Question 94 I

00WE03K202 R 1/2 LOCA Cooldown -Depressurization 00WE13K103 R 1/2 Steam Generator Over-Pressure 00WE15K3.2 R-1 12 Containment Flooding 0030002314 R 2/1 Reactor Coolant Pump 004000K134 R-2/1 Chemical and Volume Control 007000K1.03 R-2/1 Pressurizer Relief/Quench Tank 0220002305 R-2/1 Containment Cooling Record of Rejected K/As Knowledge of the interrelations between the LOCA Cooldown and Depressurization and the following: Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility Knowledge of the operational implications of the following concepts as they apply to the Steam Generator Overpressure:

-Annunciators and conditions indicating signals, and remedial actions associated with the Steam Generator Overpressure Knowledge of the reasons for the following responses as they apply to the Containment F!ooding:

-Norma!, abnormal and emergency operating procedures associated with Containment Flooding Radiological Controls -Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

Knowledge of the physical connections and/or cause-effect relationships between the CVCS and the following systems: -Interface between CVCS and reactor coolant drain tank; and PZR PCS Knowledge of the physical connections and/or cause-effect relationships between the PRTS and the following systems: -RCS Radiological Controls -Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. Form ES-401-4 REJECTED.

This KA was rejected due to overlap with question 2. REJECTED This is a Yellow Path Functional Restoration Procedure.

The condition is generally corrected without entering the procedure.

Not able to write a discriminatory RO Question that is not too trivial. REJECTED This KA was rejected because it yields a question with a Level of Difficulty of 1.0. Unable to write a discriminatory RO Question.

REJECTED Generic KA not applicable to the Reactor Coolant Pump System. REJECTED Plant configuration NA at IPEC. KA is Not Applicable REJECTED This KA was rejected because it yields a question with a Level of Difficulty of 1.0. Unable to write a discriminatory RO Question.

REJECTED Over sample Radiation Monitors (Questions 22, 51, 63, 90, 98)

ES-401 R Main and Reheat Steam System R Emergency Diesel Generator 073000A403 Process Radiation R 2/1 Monitoring System 0150002416 Nuclear R2/2 Instrumentation System Spent Fuel Pool Cooling Containment Iodine Removal Conduct or Operations Record of Rejected KlAs Conduct of Operations

-Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the <!esired plant lineup. Knowledge of the effect that a loss or malfunction of the EDIG System will have on the following: Systems controlled by automatic loader Ability to manually operate and/or monitor in the control room: -Check source for operability demonstration Emergency Procedures/Plan

-Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, severe accident management guidelines.

Ability to monitor automatic operation of the Spent Fuel Pool Cooling System, including:

-Temperature control valves Knowledge of the physical connections and/or cause-effect relationships between the CIRS and the following systems: -CSS Conduct of Operations

-Knowledge of RO duties in the CR during fuel handling, such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the CR in support of fueling operations, and supporting instrumentation.

Form ES-401-4 REJECTED This Generic KA is evaluated during Simulator Operational Examination.

REJECTED Indian Point 3 does not have an automatic loader. KA is Not Applicable.

REJECTED Overlap with SRO question 90 REJECTED Generic KA only applicable to A TWS condition at Indian Point. This would be overlap with SRO question 78 REJECTED Indian Point 3 does not have automatic temperature control valves. REJECTED Indian Point no longer adds sodium hydroxide to the containment spray flow. Unable to write a discriminatory RO level question for this KA. REJECTED At Indian Point 3 the ROs in the control room respond to plant alarms as necessary.

All other activities are performed by refueling team members not necessarily anyRO

ES-401 Record of Rejected KlAs Form ES-401-4 Radiological Controls -Ability to use radiation monitoring systems, such as fixed radiation monitors R3 1940012305 REJECTED Overlap with SRO Question 98. and alarms, portable survey instruments, personnel monitorinQ equipment, etc. 000029A206 Ability to determine and interpret the following as REJECTED Equipment (Main Turbine Trip Anticipated they apply to a A TWS: -Main turbine trip switch S 1/1 Switch) does not exist at IPEC.Transient Without position Scram Conduct of Operations

-Knowledge of REJECTED Low level KA. Not able to write a Steam Line guidelines, or limitations associated with reactivity S 1/1 discriminatory SRO level question.

Discussed Rupture management.

with Joe D.Excessive Transfer 0000652105 Conduct of Operations

-Ability to use procedures REJECTED Generic KA is not applicable to S 1/1 related to shift staffing such as minimum crew Loss of Loss of Instrument Air compliment, overtime limitations, etc. Instrument Air 00WE042220 Equipment Control -Knowledge of the process for REJECTED Generic KA is not applicable to S 1/1 LOCA Outside managing troubleshooting activities.

LOCA Outside Containment Containment Conduct of Operations

-Knowledge of individual 0000112104 licensed operator responsibilities related to shift REJECTED Generic KA is not applicable to staffing, such as medical requirements, "no solo" S 1/1 Large Break Large Break LOCA operation, maintenance of active license status, LOCA 10CFR55, etc.

Emergency Procedures/Plan

-Ability to REJECTED.

This Generic KA is best Loss of system alarm setpoints and operate controls S 1/1 evaluated during Simulator Scenarios.

Not Emergency identified in the alarm response manual. able to write a discriminatory SRO question.

00WE062142 S 1/2 Degraded Core CoolinQ 003000221 S 2/1 Reactor Coolant Pump 0060002141 S 2/1 Emergency Core CoolinQ System 0110002314 S 2/2 Pressurizer Level Control System Record of Rejected K/ As Conduct of Operations

-Knowledge of new and spent fuel movement procedures.

Equipment Control -Ability to perform procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

Conduct of Operations

-Knowledge of the refueling process. Radiological Controls -Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

Form ES-401-4 REJECTED Generic KA is not applicable to Degraded Core Cooling REJECTED Generic KA refers to subsequent step information in an SOP that requires contacting Reactor Engineering for guidance.

Unable to write a discriminatory SRO question.

REJECTED Generic KA is not applicable to Emergency Core Cooling System REJECTED Generic KA is not applicable to Pressurizer Level Control System "lit*'l'"" CI) w E o u. 'l'"" o "lit*CI) w i Administrative Topics Outline Form ES-301-1 Facility:

Unit 3 Examination Level: RO [Xl Administrative Topic (see Note) Conduct of Operations Conduct of Operations Equipment ContrOl Radiation Control Emergency Procedures/Plan Date of Examination:

21:1:1l20:13 SRO Operating Test Number: :1 Type Code* Describe activity to be performed Perform a QPTR Calculation by Hand M 2.1.23 -Conduct of Operations

-Ability to perform specific system and integrated plant procedures during all modes of plant operation.

RO-4.3 N Perform Deborating Demineralizer In-Service Time Calculation 2.1.25 -Conduct of Operations

-Ability to interpret reference materials such as graphs, curves, tables etc. RO-3.9 Prepare a Tagout N 2.2.13 -Equipment Control -Knowledge of tagging and clearance procedures.

RO -4.1 Prepare a VC Pressure Relief Release Permit M 2.3.11 -Radiological Controls -Ability to control radiation releases.

RO-3.8 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 (:::i 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:

IPEC UNIT Date of Examination:

2-7-2013 Exam Level: RO SRO-I D SRO-U D Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System I .JPM Title Type Code* Safety Function a. Align Low-Head SI Flowpath for Hot Leg Recirculation A,EN 2 I 000011A.1.11 RO-4.2 SRO-4.2 b. Respond to Pressurizer Low Pressure Alarm A, N 000027A1.01 R0-4.0 c. RCP #1 RCP Seal Failure D,P 003000A2.01 RO-3.S d. Place Main Feed Reg Valves Controllers in Automatic N,L OS9000A4.03 RO-2.9 e. Start a Fan Cooler Unit N 022000A4.01 RO -3.6 SRO -f. Energize Buses Sand 6 from 13.8 kV Power D 062000A4.01 RO -3.3 SRO -g. 33 SG Steam Flow Channel Fails Low (Alt Path) A 03S000K401 RO -3.6 SRO -h. Adjust R-27 Process Rad Monitor M 9 073000A402 RO 3.7 SRO -;ystems\\!l (3 for RO); (3 for SRO-I); (3 or 2 for i. Locally Emergency Borate A, E,R 000024A 104 RO -3.6 SRO -j. Perform Actions for RHR Pump Cooling using City Water D, E, R OOSOOOK101 RO -3.2 SRO -Release a Gas Decay Tank N,R 071000A40S RO -2.6 SRO -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 (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 4-6/ 4-6 12-3 ::::; 9/s 8 1::;;4 2:1/2:1/2:1 1 2:1 (control room system) 2:1/2:1/;;:1 2:2/;;:2/2:1

s; 31 s 31 s 2 (randomly selected) 2:1/2:1/2:1 Administrative Topics Outline Form ES-301-1 Facility:

IEEe Unit 3 Examination Level: ROO Administrative Topic (see Note) Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan Date of Examination:

2l:l :ll2013 SRO Operating Test Number: j Type Code* Describe activity to be performed Review a QPTR Calculation by hand M 2.1.23 -Conduct of Operations

-Ability to perform specific system and integrated plant procedures during all modes of plant operation.

SRO-4.4 Review Deborating Demineralizer In Service Time Calculation N 2.1.25 -Conduct of Operations

-Ability to interpret reference materials such as graphs, curves, tables etc. SRO-4.2 Review a Tagout N 2.2.13 -Equipment Control -Knowledge of tagging and clearance procedures.

SR04.3 Review a VC Pressure Relief Release Permit M 2.3.11 -Radiological Controls -Ability to control radiation releases.

SRO-4.3 Classify Emergency Events requiring Emergency Plan Implementation M 2.4.41 -Emergency Procedures/Plan

-Knowledge of the emergency action level thresholds and classifications.

SRO-4.6 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 (::; 3 for ROs; ::; 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:

IPEC UNIT 3 Date of Examination:

2-7-2013 Exam Level: RO 0 SRO-I lS(l SRO-U D Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System I JPM Title a. Align Low-Head SI Flowpath for Hot Leg 000011A.1.11 R04.2 b. Respond to Respond to Pressurizer Low Pressure 000027A1.01 RO-4.0 c. RCP #1 RCP Seal 003000A2.01 RO-3.5 d. Place Main Feed Reg Valves Controllers in Automatic

  • 059000A4.03 RO-2.9 SRO-2.9 e. Start a Fan Cooler 022000A4.01 RO -3.6 SRO -f. Energize Buses 5 and 6 from 13,8 kV 062000A4.01 RO -3.3 SRO -g. 33 SG Steam Flow Channel Fails Low (Alt 035000K401 RO -3.6 SRO -NASROI lant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Locally Emergency 000024A104 RO -3.6 SRO -j. Perform Actions for RHR Pump Cooling using City 005000K101 RO -3.2 SRO -k. Release a Gas Decay 071000A405 RO -2.6 SRO -Type Code* Safety Function A,EN 2 A,N 3 D,P 4P N, L 4S N 5 D 6 A 7 A,E,R 1 D, E,R 8 N,R 9 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)ltemate 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 4-6/4-6/2-3

=9/:=81:=4
1/;
:1/;::1 -1 1;::1 (control room system) ;::1/;0:1/;0:1
= 3 1:= 3 I := 2 (randomly selected)
0
1/;0:1/;::1 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

IPEC UNIT Date of Examination:

2-7-2013#L Exam Level: RO Q SRO-I SRO-U D Operating Test No.: 1 I Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System I JPM Title Type Code* Safety Function a. Align Low-Head SI Flowpath for Hot Leg Recirculation A, EN 000011 A.1.11 R0-4.2 b. Respond to Respond to Pressurizer Low Pressure Alarm A,N 000027A1.01 R0-4.0 c. RCP #1 RCP Seal Failure D,P 003000A2.01 RO-3.5 d. Transfer Main Feed to Bypass Feed During Power Reduction N,L 059000A4.03 RO-2.9 e. Start a Fan Cooler Unit N 022000A4.01 RO -3.6 SRO -f. Energize Buses 5 and 6 from 13.8 kV Power D 062000A4.01 RO -3.3 SRO -g. 33 SG Steam Flow Channel Fails Low (Alt Path) A 035000K401 RO -3.6 SRO -h. In-Plant Systemsf.l!l (3 for RO); (3 for SRO-I); (3 or 2 for i. Locally Emergency Borate A,E,R 000024A104 RO -3.6 SRO -j. Perform Actions for RHR Pump Cooling using City Water D,E, R 005000K101 RO -3.2 SRO -k. Release a Gas Decay Tank N,R 071000A405 RO -2.6 SRO -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 / SRO-II SRO-U I (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 4-6/4-6/2-3 s9/s8/s4 1 ;::1 (control room system) ;::1/;::1/;::1
2/;
:2/;::1 s 3 I s 3 I s 2 (randomly selected)
1/;
:1/;::1 Appendix D Scenario Outline Form ES-D*1 Facility:

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

Operators:

Initial Conditions:

100% power steady state. 32 AFW Pump is out of service for bearing repair. Need to have 35 SWP in service. Turnover:

32 AFW Pump is expected back in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Team has been asked to reduce power to 90% for a Turbine StOI2 and Control Valve Test in 30 minutes. Event Malf. Event Event No. No. Type* Description 1 N/A R (ATC) Perform power reduction.

N (BOP, CRS) 2 C (CRS) 33 MFRV fails open in auto manual available.

CFW013 E C (ATC) 33 MFRV will be placed in manual to control 33 SG level. 3 C (ALL) NRHX Tube Leak. CFW011 4 C (CRS, Loss of 480V Bus 3A. EPS05B BOP) 34 or 36 SWP will be started. TS (CRS) CRS will determine T.S. shutdown is required due to AFW. 5 N/A R (ATC) Perform power reduction with Feed Reg Valve in Manual N (BOP, CRS) 6 C (CRS) Inadvertent main generator trip. Reactor will not automatically trip. GENOO2 C (ATC) Manual trip will be required.

7 M (ALL) 33 AFW pump will not start causing a loss of heat sink. Heat sink CFWOO1 will be restored using condensate.

C 8 TS (CRS) PORV 455C leaks by requiring isolation.

CRS can be asked about PRS003 D C (ATC) TS requirements at end of scenario.

  • (N)ormal, (R}eactivity, (I)nstrument, (C)omponent, (M)ajor U3 NRC Scenano I Power ReductlOn fro 100%,33 MFRV Fads Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 1 0[20 Appendix D Scenario Outline Form ES-D-1 Facility:

Indian Point 3 Scenario No.: Op-Test No.:_1 Examiners:

Operators:

Initial Reset simulator to 9% Load Simulator The Plant is in Mode 1 just above 9% power preparing to come on Raise power to approximately 12% to place MTG in service. No equipment is out of Event Malf. No. No. 1 N!A 2 SWSOO7 3 RCS028 A 4 CCWOO 8 5 SGNOO5 6 PPLOO3! 4 7 CFWOO1 AlC 8 PPL487! 8 Event Type* R(ATC) N(CRS) N(BOP) C(CRS) C(BOP) TS(CRS) I(ALL) TS(CRS) C(CRS) C(BOP) M(ALL) C(ALL) C(BOP) C(CRS) C(BOP)

Power ascension, maintain SG levels in manual. 31 CCW Pump trip with failure of 32 to auto start. Controlling PZR Pressure transmitter fails high. FCV-625 spurious closure. Steam leak in the Turbine Building leading to plant trip. 33 MSIV fails to close. Entered at setup, Reactor Trip Breakers will not open causing team to enter FR-S.1. Entered at setup, AFW will not auto-start requiring manual action in FR-S.1 Entered at setup, SI does not automatically actuate. Manual actuation will be required.

,", .* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted so. Page 1 of 16 Appendix Scenario Outline Form ES-O-1 Facility:

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

Initial Conditions:

50% Power PORV 455C Leaks by seat -Block Valve 535 is Raise Power to Event Malf. No. Event No. Type*

R (ATC) N/A Power Increase N N I MAL-Controlling Pressurizer Level Channel fails low TS (CRS) C MAL-PORV 456 leaks by seat. Close PORV Block Valve. C (CRS) I 4 PT-412B failure causing AMSAC to be inoperable and requiring TS (CRS) TUR010 tripping of M MAL-Loop Flow Transmitter penetration failure C (BOP) MAL-31 AFW Pump Trip C (CRS) MAL-SG Tube Leak to Rupture 32 SG M (ALL) SWI-IA-PCV-1228 Instrument Air to Containment Fails to Open C (ALL) AIR002C * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 1 of33 Appendix Scenario Outline Form ES*D*1 Facility:

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

Initial Conditions:

100% power steady state. 32 HHSI pump is OOS, expected to return to service 6 Turnover:

Maintain 100% Power Event Malf. No. Event No. Type* C (ALL) VCT Level Transmitter fails Low MAL-I (CRS) PT -404 failure requiring manual control of Main Boiler Feed Pumps. MSS003 I(ATC) MAL-C (ALL) Fault on 480V Bus 6A. This will require starting an ESW pump and EPSOO5D charging pump. N/A R (ATC) T.S. load reduction.

N (CRS) N (BOP) MAL-C(ALL) Rod B-6 fails to move during power reduction (SD Bank Rod K-6 is CRF004AU also stuck) MAL-M (ALL) MAL-C (ALL) MAL-C(BOP No Auto C (CRS) * (N}ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck !Misaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 1 of37

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