ML13066A337
| ML13066A337 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 02/12/2013 |
| From: | D'Antonio J Operations Branch I |
| To: | Entergy Nuclear Indian Point 3 |
| Jackson D | |
| Shared Package | |
| ML12214A189 | List: |
| References | |
| ES-401, ES-401-2, TAC U01866 | |
| Download: ML13066A337 (33) | |
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 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 1 9 2 2 4
& N/A Abnormal Tier Plant 5 5 10 Totals 5 5 5 4 4 4 27 Evolutions 1 2 2 3 3 3 2 3 3 2 3 2 28 3 2 5 2.
Plant 2 1 1 0 1 1 1 1 1 1 1 1 10 0 I 2 1 3 Systems Tier 4 3 3 4 4 3 4 4 3 4 2 38 5 3 8 Totals 1 2 3 4 1 2 3 4
- 3. Generic Knowledge And 10 7 Abilities Categories 3 3 2 2 2 2 1 2 Note:
- 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only 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).
- 2. The point total for each group and tier in the proposed outline must match that speCified in the table.
The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 pOints and the SRO-only exam must total 25 pOints.
- 3. Systems/evolutions within each group are identified on the 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.
- 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5. Absent a plant-specific priority, only those 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.
- 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7.* 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.
- 8. 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.
- 9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.
PWR RO/SRO Examination Outline Facility: Indian Pont Unit 3 NRC Written Examination Outline 1
Knowledge of the interrelations between 000008 Pressurizer Vapor Space AK2.02 I the Pressurizer Vapor Space Accident I 2.7 Accident 1 3 I X I and the following: - Sensors and Detectors Knowledge of the reasons for the 000009 Small Break LOCA 1 3 I X I EK3.24 I following responses as they apply to the I 4.1 2 I
small break LOCA: - ECCS throttling or termination criteria Ability to determine and interpret the following as they apply to a Large Break 000011 Large Break LOCA 13 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 000015/000017 RCP Malfunctions 1 4 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 000022 Loss of Rx Coolant Makeup 1 2 I X I AK3.06 I following responses as they apply to the 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 000022 Loss of Rx Coolant Makeup / 2
- II AA2.04 Reactor Coolant Makeup: - How long PZR I 38 I 77 level can be maintained within limits Knowledge of the operational implications of the following concepts as they apply to 000025 Loss of RHR System /4 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 000025 Loss of RHR System /4 2.4.9 I of low power / shutdown implications in I 3.8 I 81 accident (e.g. LOCA or loss of RHR) m NUREG 1021 2
PWR RO/SRO Examination Outline Facility: Indian Pont Unit 3 1
Ability to determine and interpret the 000026 Loss of Component Cooling AA2.01 I following as they apply to the Loss of I 29 I 7 Water /8 Component Cooling Water: - Location of a .
leak in the CCWS Knowledge of the interrelations between 000029 ATWS /1 I X I EK2.06 I the ATWS and the following: - Breakers, I 2.9 I 9 and disconnects Conduct of Operations - Ability to perform 000029 ATWS /1 2.1.23 I specific system and integrated plant I 4.4 I 78 procedures during all modes of plant o~eration.
Knowledge of the operational imp 000038 Steam Gen. Tube Rupture / 3 X EK1.03 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 4.2 79 of abnormal condition ~rocedures.
000054 Loss of Main Feedwater / 4 2.1.20 I Conduct of Operations - Ability to interpret I 46 11 and execute ~rocedure ste~s. .
Equipment Control - Knowledge of the process for managing maintenance 000055 Station Blackout / 6 2.2.18 I activities during shutdown operations, I 2.6 I 12 such as risk assessments, work etc.
Ability to operate and/or monitor the I following as they apply to the Loss of I 3.6 I 000056 Loss of Off-Site Power /6 I X AA1.10 Offsite Power: - Auxiliary/emergency 4
feedwater ~ume (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 I 36 I 13 AC Instrument Bus: - Feedwater pump .
e to control eressure and level in S/G Ability to determine and interpret the 000058 Loss of DC Power / 6 I following as they apply to the Loss of DC I 3.9 I 80 AA2.03 Power: - DC loads lost; impact on to and monitor 000062 Loss of Nuclear Svc Water /4 _2.1.20 I Conduct of Operati~ **" - '.'...... "y and execute LV .. m ........ v L I 4.6 I 14 NUREG 1021 3
PWR RO/SRO Examination Outline Facility: Indian Pont Unit 3 ES-401 1 Knowledge of the reasons for the following responses as they apply to 000077 Generator Voltage and Electric AK3.02 I Generator Voltage and Electrical Grid I 3.6 I 15 Grid Disturbances I 6 I X I Disturbances: - Actions contained in abnormal operating procedure for voltage and grid disturbances Ability to determine and interpret the following as they apply to the LOCA W/E04 LOCA Outside Containment / 3 EA2.2 I Outside Containment: - Adherence to I 3.6 I 16 appropriate procedures and operation within the limitations in the facility's license and amendments Knowledge of the interrelations between the Loss of Secondary Heat Sink and the following: - Facility's heat removal W/E05 Inadequate Heat Transfer - Loss EK2.2 I systems, including primary coolant, I 3.9 I 17 of Secondary Heat Sink / 4 I X I emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the o~eration of the y Ability to operate and/or monitor the following as they apply to the Loss of W/E11 Loss of Emergency Coolant Recirc./4 Ix EA1.3 I Emergency Coolant Recirculation: -
Desired operating results during abnormal I 3.7 I 18 and emergency situations Knowledge of the operational implications of the following concepts as they apply to the Uncontrolled Depressurization of all W/E12 Steam Line Rupture - Excessive IX I EK1.03 I Steam Generators: - Annunciators and I 3.4 I 8 Heat Transfer I 4 conditions indicating Signals, and remedial actions associated with the Uncontrolled Depressurization of all Steam Generators NUREG 1021 4
PWR RO/SRO Examination Outline Facility: Indian Pont Unit 3 2
Equipment Control - Ability to interpret control room indications to verify the 000003 Dropped Control Rod 11 2.2.44 I status and operation of a system, and 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 Malfunctions and the following: - Sensors I 2.6 124 and detectors Knowledge of the reasons for the following responses as they apply to the 000033 Loss of Intermediate Range NI /7 I IX I AK3.02 I Loss of Intermediate Range Nuclear I 3.6 I 19 Instrumentation: - Guidance contained in EOP for loss of intermediate-range instrumentation Ability to operate and/or monitor the 000036 Fuel Handling Accident / 8 IX AA1.04 I following as they apply to the Fuel I 3.1 120 U~~...I"ng Incidents: - Fuel handling 9 ~ ent during an incident Ability to determine and interpret the 000037 Steam Generator Tube Leak 1 3 AA2.16 I following as they apply to the Steam 4 Generator Tube Leak: - Pressure at which I .3 183 to maintain RCS during S/G cooldown Emergency Procedures/Plan - Knowledge 000068 Control Room Evac. I 8 2.4.34 I of RO tasks performed outside the main 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 o~erations NUREG 1021 5
PWR RO/SRO Examination Outline Facility: Pont Unit 3 NRC Written Examination Outline I -- .u En;terge~cy a~d A~norm.!!!l!R!!}yolutions - Tier 1/ Group 2 For~ ES-~OI-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 13.4 127 conditions, 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
PWR RO/SRO Examination Outline Facility: Indian Pont Unit 3 NRC Written Examination Outline ES-401 I'lant . m s - Tier 21 Group 1 m n u n Form ES-401-2
.... ""'TPm #lName ~§JAlmn~4-n. Number I KIA Topic Q#
Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS and (b) based on those 003 Reactor Coolant predictions, use procedures to correct, 12.5 128 Pump control, or mitigate the consequences of those malfunctions or operations: - Effects of VCT pressure on RCP seal leakoff flows Knowledge of the effect of a loss or 004 Chemical and malfunction on the following CVCS I 2 7 I 29 Volume Control IX components: - Reason for excess letdown .
and its relationshie to CCWS Knowledge of the physical connections 005 Residual Heat IX and/or cause-effect relationships between I 3 2 I 30 Removal the RHRS and the following systems: - .
CCWS Knowledge of bus power supplies to the 005 Residual Heat Removal IX following: - RCS pressure boundary 12.7 I 31 motor-operated valves Knowledge of the effect of a loss or 006 Emergency Core Cooling IX malfunction of the following will have on 13.0 132 ECCS: - HPIfLPI cooling water Knowledge of the operational implications 006 Emergency Core of the following concepts as they apply to Cooling IX the ECCS: - Operation of pumps in 12.9 133 parallel Conduct of Operations - Ability to explain 007 Pressurizer Relief/Quench Tank and apply all system limits and I 2.9 134 tions.
Equipment Control- Knowledge of 007 Pressurizer Relief/Quench Tank conditions and limitations in the facility I 4.5 I 87 license.
Knowledge of the physical connections 008 Component IX and/or cause-effect relationships between I 3 1 135 Cooling Water the CCWS and the following systems: .
PWR RO/SRO Examination Outline Facility: Indian Pont 3 Knowledge of PZR PCS design 010 Pressurizer Ix K4.03 I and/or interlock(s) which provide for the 13.8 136 Pressure Control I following: - Over ~ressure control Ability to predict and/or monitor changes in parameters (to prevent exceeding 010 Pressurizer Ix A1.07 I design limits) associated with operating 13.7 137 Pressure Control the PZR PCS controls including: - RCS
~ressure I I Ability to monitor automatic operation of 012 Reactor Protection X I A3.07 the RPS. including: - Tri~ breakers 14.0 138 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 13.9 139 RPS setpoints are exceeded for each RPS function; basis for each Knowledge of ESFAS design feature(s) 013 Engineered Safety K4.10 I and/or interlock(s) which provide for the I 33 I 40 Features Actuation Ix I following: - Safeguards equipment control .
reset Ability to (a) predict the impacts of the following malfunctions or operations on 013 Engineered Safety Features Actuation A2.01 I the ESFAS and (b) based on those predictions, use procedures to correct, I 4.8 I 88 control, or mitigate the consequences of those malfunctions or o~erations: - LOCA Ability to predict and/or monitor changes in parameters (to prevent exceeding 022 Containment Ix A1.04 I design limits) associated with operating 13.2 '42 Cooling the CCS controls including: - Cooling waterflow Knowledge of the effect that a loss or 026 Containment Spray Ix I K3.01 I malfunction of the CSS will have on the 13.9 143 following: - CCS Knowledge of the operational implications 039 Main and Reheat Steam Ix I K5.08 I of the following concepts as they apply to the MRSS: - Effect of steam removal on 13.6 144 NUREG l02l 8
PWR RO/SRO Examination Outline Facility: Indian Pont Unit 3 ES~401 Form ES-401~2
""",HP'" #lName Ability to predict and/or monitor changes in parameters (to prevent exceeding I design limits) associated with operating 059 Main Feedwater IX A1.03 12.7 145 the MFW System controls including:
Power level restrictions for operation of MFW ~uml2s 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 ~ower increase and decrease Knowledge of the operational implications 061 of the following concepts as they apply to Auxiliary/Emergency Feedwater II II Ix I
II K5.03 the AFW System: - Pump head effects 12.6 147 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 X malfunction of the A.C. Distribution 14.1 148 Distribution S~stem 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 Electrical A2.16 I based on those predictions, use I 2.9 I 89 Distribution 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 1021 9
PWR RO/SRO Examination Outline Facility: Indian Pont Unit 3 ES-401 SyS!t::II1 K5 064 Emergency Diesel to 3.7 50 Generator Ability to manually operate and/or monitor 073 Process Radiation in the control room: - Radiation monitoring 3.7 51 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 073 Process Radiation predictions, use procedures to correct, 3.2 90 Monitoring 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 076 Service Water predictions, use procedures to correct, 2.7 52 control, or mitigate the consequences of those malfunctions or operations:
Service water header oressure bus power supplies to the 076 Service Water x SOI"\/;" water 2.7 53 078 Instrument Air 3.1 154 103 Containment x 3.3 155 NUREG 1021 10
PWR RO/SRO Examination Outline Facility: Indian Pont Unit 3 Form ES-401-2 001 Control Rod Drive I IX I K2.05 I '" 'V"'::l of bus power supplies to the 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:
Incorrect 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 Ix I
- K5.15 I of the following concepts as they apply to I 3 6 I 58 Control the PZR LCS: - PZR level indication when .
RCS is saturated 015 Nuclear I Ability to monitor automatic operation of 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 Temperature Monitor Ix A4.02 I used to determine RCS/RCP operation during inadequate core cooling (i.e., if I 3.8 I 60 g of five highest val Knowledge of Containment Purge System 029 Containment Purge Ix I K4.03 I design feature(s) and/or interlock(s) which provide for the following: - Automatic I 32 I 62 isolation NUREG 102l 11
PWR RO/SRO Examination Outline Facility: Indian Pont Unit 3 ES-401 SYl3tem #/Name Knowledge of the effect of a loss or 034 Fuel Handling malfunction of the following will have on Equipment x the Fuel Handling System: - Radiation 2.6 163 Ability to (a) predict the impacts of the following malfunctions or operations on the Fuel Handling System and (b) based 034 Fuel Handling on those predictions, use procedures to 4.4 93 Equipment correct, control, or mitigate the consequences of those malfunctions or element Knowledge of the physical connections 041 Steam Dump and/or cause-effect relationships between System and Turbine x the SDS and the following systems:
2.6 61 Bypass Control Condenser 045 Main Turbine Conduct of Operations - Knowledge of 3.9 64 Generator and or function.
Ability to predict and/or monitor changes in parameters (to prevent exceeding 086 Fire Protection x design limits) associated with operating 2.9 65 the Fire Protection System controls includina: - FPS Ii NUREG 1021 12
Generic Knowledge and Abilities Outline (Tier 3)
PWR RO/SRO Examination Outline Facility: Indian Pont Unit 3 Form ES-401-3 Facility I Indian Point Unit 3 I Date of Exam 2111/2013 RO SRO-Only Category KIA # Topic IR Q# IR Q#
Ability to use procedures related to shift staffing, such as minimum crew 2.1.5 2.9 66 complement, overtime limitations, etc.
Ability to perform specific system and integrated plant procedures during all 2.1.23 4.3 67 modes of plant operation.
1 . Conduct of Knowledge of procedures, guidelines, Operations or limitations associated with reactivity 2.1.37 4.3 68 management.
Knowledge of refueling administrative 2.1.40 3.9 94 requirements Ability to identify and interpret diverse 2.1.45 indications to validate the response of 4.3 95 another indication Subtotal 3 3 2 2 Equipment Control - Ability to perform pre-startup procedures for the facility, 2.2.1 including operating those controls 4.5 69 associated with plant equipment that could affect reactivity.
Ability to manipulate the console controls as required to operate the 2.2.2 4.0 70 facility between shutdown and designated power levels.
- 2. Equipment Ability to analyze the effect of Control maintenance activities, such as 2.2.36 3.1 71 degraded power sources, on the status of limiting conditions for operations.
Knowledge of limiting conditions for 2.2.22 4.7 96 operations and safety limits Knowledge of bases in technical 2.2.25 specifications for limiting conditions for 4.2 97 operations and safety limits.
Subtotal 3 3 2 2 NUREG 1021 13
Generic Knowledge and Abilities Outline (Tier 3)
PWR ROISRO Examination Outline Facility: Indian Pont Unit 3 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 2.3.12 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
- 3. operator duties, such as response to Radiological 2.3.13 radiation monitor alarms, containment 3.4 73 Controls entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc Ability to use radiation monitoring systems, such as fixed radiation 2.3.5 monitors and alarms, portable survey 2.9 98 instruments, personal monitoring equipment, etc Subtotal 2 2 1 1 Knowledge of the organization of the operating procedures network for 2.4.5 3.7 74 normal, abnormal, and emergency evolutions.
Knowledge of abnormal condition 2.4.11 4.0 75 procedures.
- 4. Emergency Knowledge of the bases for prioritizing Proced ures/pla n 2.4.22 safety functions during 4.4 99 abnormallemergency operations.
Knowledge of the bases for prioritizing 2.4.23 emergency procedure implementation 4.4 100 during emergency operations Subtotal 2 2 2 2 Tier 3 Point Totals 10 10 7 7 NUREG 1021 14
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 15
ES*401 Record of Rejected KIAs Form ES*401*4 Tier /
Randomly Selected KJA Reason for Rejection Group 0000112113 Conduct of Operations - Knowledge of facility REJECTED Generic KA is not applicable to R 1/1 Large Break requirements for controlling vitali controlled access. Large Break LOCA.
LOCA Ability to operate and/or monitor the following as 0OO015A111 REJECTED This KA is evaluated during R 1/1 they apply to the Reactor Coolant Pump RCP Malfunction Malfunctions: - RCP on/off and run indicators Simulator Operational Examination. I 000027K1.02 Knowledge of the operational implications of the Pressurizer following concepts as they apply to Pressurizer REJECTED This KA was rejected due to R-1/1 Pressure Control Pressure Control Malfunctions: - Expansion of overlap with Question 37.
System liquids as temperature increases Malfunction Ability to determine and interpret the following as 000058A201 they apply to the Loss of DC Power: - That a loss of REJECTED Not applicable to Indian Point 3.
R 1/1 dc power has occurred; verification that substitute Unit 3 does not have any automatic swap to Loss of DC Power alternate DC source functions.
power sources have come on line Conduct of Operations - Knowledge of non-nuclear 00WE042126 safety procedures (e.g. rotating equipment, REJECTED Generic KA is not applicable to R111 LOCA Outside electrical, high temperature, high pressure, caustic, LOCA Outside Containment Containment chlorine, oxygen and hydrogen.
Ability to operate and/or monitor the following as they 000015A120 RREJECTED This KA was rejected due to R 1/1 apply to the Reactor Coolant Pump Malfunctions: - RCP RCP Malfunctions bearing temperature indicators overlap with SRO Only Question 76.
000024K302 Knowledge of the reasons for the following responses as they apply to the Emergency Boration: REJECTED This KA overlaps with a currently R 1/2 Emergency
- Actions contained in EOP for emergency boration selected JPM.
Boration 0000362140 Conduct of Operations - Knowledge of refueling REJECTED Over sample, This Generic KA R 1/2 Fuel Handling administrative requirements. selected for SRO Only Question 94 Accident
ES-401 Record of Rejected K/As Form ES-401-4 Knowledge of the interrelations between the LOCA 00WE03K202 Cooldown and Depressurization and the following:
Facility's heat removal systems, including primary REJECTED. This KA was rejected due to R 1/2 LOCA Cooldown coolant, emergency coolant, the decay heat removal overlap with question 2.
- systems, and relations between the proper operation Depressurization of these systems to the operation of the facility Knowledge of the operational implications of the REJECTED This is a Yellow Path Functional 00WE13K103 following concepts as they apply to the Steam Restoration Procedure. The condition is R 1/2 Generator Overpressure: - Annunciators and generally corrected without entering the Steam Generator conditions indicating signals, and remedial actions procedure. Not able to write a discriminatory Over-Pressure associated with the Steam Generator Overpressure RO Question that is not too trivial.
Knowledge of the reasons for the following 00WE15K3.2 responses as they apply to the Containment REJECTED This KA was rejected because it F!ooding: - Norma!, abnormal and emergency yields a question with a Level of Difficulty of R-1 12 Containment operating procedures associated with Containment 1.0. Unable to write a discriminatory RO Flooding Question.
Flooding 0030002314 Radiological Controls - Knowledge of radiation or R 2/1 contamination hazards that may arise during normal, REJECTED Generic KA not applicable to the Reactor Coolant Reactor Coolant Pump System.
abnormal, or emergency conditions or activities.
Pump Knowledge of the physical connections and/or 004000K134 cause-effect relationships between the CVCS and REJECTED Plant configuration NA at IPEC.
R-2/1 Chemical and the following systems: - Interface between CVCS KA is Not Applicable Volume Control and reactor coolant drain tank; and PZR PCS 007000K1.03 REJECTED This KA was rejected because it Knowledge of the physical connections and/or Pressurizer cause-effect relationships between the PRTS and yields a question with a Level of Difficulty of R-2/1 Relief/Quench the following systems: - RCS 1.0. Unable to write a discriminatory RO Tank Question.
Radiological Controls - Ability to use radiation 0220002305 monitoring systems, such as fixed radiation monitors REJECTED Over sample Radiation Monitors R-2/1 Containment and alarms, portable survey instruments, personnel (Questions 22, 51, 63, 90, 98)
Cooling monitoring equipment, etc.
ES-401 Record of Rejected KlAs Form ES-401-4 Conduct of Operations - Ability to locate control 0390002131 room switches, controls and indications and to REJECTED This Generic KA is evaluated R 2/1 Main and Reheat determine that they are correctly reflecting the during Simulator Operational Examination.
Steam System <!esired plant lineup.
064000K301 Knowledge of the effect that a loss or malfunction of the EDIG System will have on the following: REJECTED Indian Point 3 does not have an R 2/1 Emergency Diesel Systems controlled by automatic loader automatic loader. KA is Not Applicable.
Generator 073000A403 Ability to manually operate and/or monitor in the R 2/1 Process Radiation control room: - Check source for operability REJECTED Overlap with SRO question 90 Monitoring demonstration System Emergency Procedures/Plan - Knowledge of EOP 0150002416 implementation hierarchy and coordination with other support procedures or guidelines such as, REJECTED Generic KA only applicable to R2/2 Nuclear ATWS condition at Indian Point. This would operating procedures, abnormal operating Instrumentation be overlap with SRO question 78 procedures, severe accident management System guidelines.
033000A301 Ability to monitor automatic operation of the Spent Fuel Pool Cooling System, including: - Temperature REJECTED Indian Point 3 does not have R2/2 Spent Fuel Pool control valves automatic temperature control valves.
Cooling 027000K101 Knowledge of the physical connections and/or REJECTED Indian Point no longer adds cause-effect relationships between the CIRS and sodium hydroxide to the containment spray R2/2 Containment the following systems: - CSS flow. Unable to write a discriminatory RO level Iodine Removal question for this KA.
Conduct of Operations - Knowledge of RO duties in the CR during fuel handling, such as responding to REJECTED At Indian Point 3 the ROs in the 1940012144 control room respond to plant alarms as alarms from the fuel handling area, communication R3 Conduct or with the fuel storage facility, systems operated from necessary. All other activities are performed Operations the CR in support of fueling operations, and by refueling team members not necessarily supporting instrumentation. 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 and alarms, portable survey instruments, personnel REJECTED Overlap with SRO Question 98.
monitorinQ equipment, etc.
000029A206 Ability to determine and interpret the following as Anticipated they apply to a A TWS: - Main turbine trip switch REJECTED Equipment (Main Turbine Trip S 1/1 Transient Without position indication Switch) does not exist at IPEC.
Scram (ATWS) 0000402137 Conduct of Operations - Knowledge of procedures, REJECTED Low level KA. Not able to write a Steam Line S 1/1 guidelines, or limitations associated with reactivity discriminatory SRO level question. Discussed Rupture management. with Joe D.
Excessive Heat Transfer /4 0000652105 Conduct of Operations - Ability to use procedures REJECTED Generic KA is not applicable to S 1/1 Loss of related to shift staffing such as minimum crew Loss of Instrument Air Instrument Air compliment, overtime limitations, etc.
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 staffing, such as medical requirements, "no solo" REJECTED Generic KA is not applicable to S 1/1 Large Break operation, maintenance of active license status, Large Break LOCA LOCA 10CFR55, etc.
00WE112450 Emergency Procedures/Plan - Ability to verify REJECTED. This Generic KA is best Loss of S 1/1 system alarm setpoints and operate controls evaluated during Simulator Scenarios. Not Emergency identified in the alarm response manual. able to write a discriminatory SRO question.
Coolant Recirculation -------- ------ -- ------- -
ES-401 Record of Rejected K/As Form ES-401-4 00WE062142 Conduct of Operations - Knowledge of new and REJECTED Generic KA is not applicable to S 1/2 Degraded Core spent fuel movement procedures. Degraded Core Cooling CoolinQ REJECTED Generic KA refers to subsequent 003000221 Equipment Control - Ability to perform pre-~tartup step information in an SOP that requires procedures for the facility, including operating those S 2/1 Reactor Coolant contacting Reactor Engineering for guidance.
controls associated with plant equipment that could Pump Unable to write a discriminatory SRO affect reactivity.
question.
0060002141 Conduct of Operations - Knowledge of the refueling REJECTED Generic KA is not applicable to S 2/1 Emergency Core process. Emergency Core Cooling System CoolinQ System 0110002314 Radiological Controls - Knowledge of radiation or S 2/2 contamination hazards that may arise during normal, REJECTED Generic KA is not applicable to Pressurizer Level Pressurizer Level Control System abnormal, or emergency conditions or activities.
Control System
"lit
'l'""
~
CI) w E
~
u.
o
'l'""
o "lit CI)*
w
ES*301 Administrative Topics Outline Form ES-301-1 Facility: I~EC Unit 3 Date of Examination: 21:1:1l20:13 Examination Level: RO [Xl SRO Operating Test Number: :1 Administrative Topic Type Describe activity to be performed (see Note) Code*
Perform a QPTR Calculation by Hand Conduct of Operations 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 Perform Deborating Demineralizer In-Service Time Calculation Conduct of Operations N 2.1.25 - Conduct of Operations - Ability to interpret reference materials such as graphs, curves, tables etc.
RO-3.9 i
Prepare a Tagout Equipment ContrOl N 2.2.13 - Equipment Control - Knowledge of tagging and clearance procedures.
RO -4.1 Prepare a VC Pressure Relief Release Permit Radiation Control M 2.3.11 - Radiological Controls - Ability to control radiation releases.
RO-3.8 Emergency Procedures/Plan NA for ROs NOTE: 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)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: IPEC UNIT 3 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
- b. Respond to Pressurizer Low Pressure Alarm A, N 3 000027A1.01 R0-4.0 SRO-3.9
- d. Place Main Feed Reg Valves Controllers in Automatic N,L 4S OS9000A4.03 RO-2.9 SRO-2.9
- ystems\\!l (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
@ 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 I Criteria for RO I SRO-II SRO-U
(A)lternate path 4-6/ 4-6 12-3 (C}ontrol room (D)irect from bank : : ; 9/s 8 1::;;4 (E)mergency or abnormal in-plant 2:1/2:1/2:1 (EN)gineered safety feature 1 2:1 (control room system)
(L)ow-Power / Shutdown 2:1/2:1/;;:1 (N)ew or (M)odified from bank including 1(A) 2:2/;;:2/2:1 (P)revious 2 exams :s; 31 s 31 s 2 (randomly selected)
(R)CA 2:1/2:1/2:1 (S)imulator
ES-301 Administrative Topics Outline Form ES-301-1 Facility: IEEe Unit 3 Date of Examination: 2l:l :ll2013 Examination Level: ROO SRO ~ Operating Test Number: j Administrative Topic Type Describe activity to be performed (see Note) Code*
Review a QPTR Calculation by hand Conduct of Operations 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 Conduct of Operations N 2.1.25 - Conduct of Operations - Ability to interpret reference materials such as graphs, curves, tables etc.
SRO-4.2 Review a Tagout Equipment Control N 2.2.13 - Equipment Control - Knowledge of tagging and clearance procedures.
SR04.3 Review a VC Pressure Relief Release Permit Radiation Control M 2.3.11 - Radiological Controls - Ability to control radiation releases.
SRO-4.3 Classify Emergency Events requiring Emergency Plan Implementation Emergency Procedures/Plan M 2.4.41 - Emergency Procedures/Plan - Knowledge of the emergency action level thresholds and classifications.
SRO-4.6 NOTE: 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)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 I 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 Type Code* Safety Function
- b. Respond to Respond to Pressurizer Low Pressure Alarm A,N 3 000027A1.01 RO-4.0 SRO-3.9
- d. Place Main Feed Reg Valves Controllers in Automatic N, L 4S
- 059000A4.03 RO-2.9 SRO-2.9
- h. NASROI lant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
@ 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 I Criteria for RO I SRO-II SRO-U
(A)ltemate path 4-6/4-6/2-3 (C)ontrol room (D)irect from bank :=9/:=81:=4 (E)mergency or abnormal in-plant ;::1/;::1/;::1 (EN)gineered safety feature - 1 1;::1 (control room system)
(l)ow-Power / Shutdown ;::1/;0:1/;0:1 (N)ew or (M)odified from bank including 1(A) ;o:2/~2/;O:1 (P)revious 2 exams := 3 1:= 3 I := 2 (randomly selected)
(R}CA ;0:1/;0:1/;::1 (S)imulator
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: IPEC UNIT 3 # L Date of Examination: 2-7-2013 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
- b. Respond to Respond to Pressurizer Low Pressure Alarm A,N 3 000027A1.01 R0-4.0 SRO-3.9
- d. Transfer Main Feed to Bypass Feed During Power Reduction N,L 4S 059000A4.03 RO-2.9 SRO-2.9
- h. NASROI In-Plant Systemsf.l!l (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
@ 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 Criteria for RO / SRO-II SRO-U I
(A)lternate path 4-6/4-6/2-3 (C)ontrol room (D)irect from bank s9/s8/s4 (E)mergency or abnormal in-plant ;::1/;::1/~1 (EN)gineered safety feature 1 ;::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 3 I s 3 I s 2 (randomly selected)
(R)CA ;::1/;::1/;::1 (S)imulator
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 MAL 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 MAL C (ALL) NRHX Tube Leak.
CFW011 4 MAL 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 MAL C (CRS) Inadvertent main generator trip. Reactor will not automatically trip.
GENOO2 Manual trip will be required.
C (ATC) 7 MAL M (ALL) 33 AFW pump will not start causing a loss of heat sink. Heat sink CFWOO1 will be restored using condensate.
C 8 MAL TS (CRS) PORV 455C leaks by requiring isolation. CRS can be asked about PRS003 TS requirements at end of scenario.
D C (ATC)
- (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 Conditions:
Reset simulator to 9% Load Simulator Schedule-Scenari02 The Plant is in Mode 1 just above 9% power preparing to come on line.
Turnover:
Raise power to approximately 12% to place MTG in service. No equipment is out of service.
Event Malf. Event Event No. No. Type* Description 1 N!A R(ATC) Power ascension, maintain SG levels in manual.
N(CRS)
N(BOP) 2 MOC C(CRS) 31 CCW Pump trip with failure of 32 to auto start.
SWSOO7 C(BOP)
TS(CRS) 3 XMT I(ALL) Controlling PZR Pressure transmitter fails high.
RCS028 A TS(CRS) 4 MOV C(CRS) FCV-625 spurious closure.
CCWOO 8 C(BOP) 5 MAL M(ALL) Steam leak in the Turbine Building leading to plant trip. 33 MSIV SGNOO5 fails to close.
6 BKR C(ALL) Entered at setup, Reactor Trip Breakers will not open causing PPLOO3! team to enter FR-S.1.
4 7 MAL C(BOP) Entered at setup, AFW will not auto-start requiring manual action CFWOO1 in FR-S.1 AlC 8 RLY C(CRS) Entered at setup, SI does not automatically actuate. Manual PPL487! actuation will be required.
8 C(BOP)
- (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 0 Scenario Outline Form ES-O-1 Facility: IPEC Unit 3 Scenario No.: 3 Op-Test No.: 1 Examiners: Operators:
Initial Conditions: 50% Power IC-153 PORV 455C Leaks by seat - Block Valve 535 is closed Turnover:
Raise Power to 100%.
Event Malf. No. Event Event No. Type* Description R (ATC) 1 N/A Power Increase N (CRS)
N (BOP)
I (ALL) 2 MAL- Controlling Pressurizer Level Channel fails low TS (CRS)
PRS006 B
C (ATC) 3 MAL- PORV 456 leaks by seat. Close PORV Block Valve.
C (CRS)
PRS003 D
I (ALL) 4 MAL- PT-412B failure causing AMSAC to be inoperable and requiring TS (CRS)
TUR010 tripping of bistables B
M (ALL) 5 MAL- Loop Flow Transmitter penetration failure (SBLOCA)
RCS017 A
C (BOP) 6 MAL- 31 AFW Pump Trip C (CRS)
CFW001 A
7 MAL- SG Tube Leak to Rupture 32 SG M (ALL)
SGN005 B
8 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 0 Scenario Outline Form ES*D*1 Facility: IPEC Unit 3 Scenario No . 4 Op-Test No.: 1 Examiners: Operators:
Initial Conditions: 100% power steady state. 32 HHSI pump is OOS, expected to return to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Turnover: Maintain 100% Power Event Malf. No. Event Event No. Type* Description 1 C (ALL) VCT Level Transmitter fails Low 2 MAL- I (CRS) PT -404 failure requiring manual control of Main Boiler Feed Pumps.
MSS003 I(ATC) 3 MAL- C (ALL) Fault on 480V Bus 6A. This will require starting an ESW pump and EPSOO5D charging pump.
TS (CRS) 4 N/A R (ATC) T.S. load reduction.
N (CRS)
N (BOP) 5 MAL- C(ALL) Rod B-6 fails to move during power reduction (SD Bank Rod K-6 is CRF004AU also stuck)
TS (CRS) 6 MAL- M (ALL) SBLOCA RCSOO1A 7 MAL- C (ALL) ATWS RPSOO2A1 B
8 MAL- C(BOP No Auto SI SISOO1A1B 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