ML16340B595

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DC Cook 2016 ES-401-2 & 3 Combined SRO & RO
ML16340B595
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 12/02/2016
From:
NRC/RGN-III
To:
Indiana Michigan Power Co, American Electric Power
Shared Package
ML15274A374 List:
References
ES-401-2
Download: ML16340B595 (13)


Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Cook Nuclear Plant Printed: 04/28/2016 Date Of Exam: 07/11/2016 RO K/A 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 1 2 1 1 9 2 2 4

& N/A N/A Abnormal Tier Plant Totals 5 5 4 5 4 4 27 5 5 10 Evolutions 1 3 2 3 3 2 2 3 3 2 2 3 28 3 2 5 2.

2 1 1 1 1 0 1 1 1 1 1 1 10 0 2 1 3 Plant Systems Tier 5 3 8 4 3 4 4 2 3 4 4 3 3 4 38 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge And 10 7 Abilities Categories 3 2 3 2 1 2 2 2 Note:
1. Ensure that at least two topics from every applicable K/A 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 K/A 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 K/A 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 K/As 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 K/A categories.

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A 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 K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

04/28/2016 12:00:04 pm 1

PWR RO Examination Outline Printed: 04/28/2016 Facility: Cook Nuclear Plant ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000007 Reactor Trip - Stabilization - Recovery X EK2.02 - Breakers, relays and disconnects 2.6 1

/1 000011 Large Break LOCA / 3 X EK2.02 - Pumps 2.6* 1 000015/000017 RCP Malfunctions / 4 X AK2.07 - RCP seals 2.9 1 000022 Loss of Rx Coolant Makeup / 2 X AA1.02 - CVCS charging low flow alarm, 3.0 1 sensor, and indicator 000025 Loss of RHR System / 4 X AK1.01 - Loss of RHRS during all modes 3.9 1 of operation 000026 Loss of Component Cooling Water / 8 X AK3.03 - Guidance actions contained in 4.0 1 EOP for Loss of CCW 000027 Pressurizer Pressure Control System X AK3.01 - Isolation of PZR spray 3.5* 1 Malfunction / 3 following loss of PZR heaters 000038 Steam Gen. Tube Rupture / 3 X EK3.02 - Prevention of secondary PORV 4.4 1 cycling 000054 Loss of Main Feedwater / 4 X AK1.01 - MFW line break depressurizes 4.1 1 the S/G (similar to a steam line break) 000055 Station Blackout / 6 X EA2.03 - Actions necessary to restore 3.9 1 power 000058 Loss of DC Power / 6 X AA2.01 - That a loss of dc power has 3.7 1 occurred; verification that substitute power sources have come on line 000062 Loss of Nuclear Svc Water / 4 X AA2.02 - The cause of possible SWS loss 2.9 1 000065 Loss of Instrument Air / 8 X 2.4.8 - Knowledge of how abnormal 3.8 1 operating procedures are used in conjunction with EOPs.

000077 Generator Voltage and Electric Grid X 2.2.44 - Ability to interpret control room 4.2 1 Disturbances / 6 indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

W/E04 LOCA Outside Containment / 3 X EA1.2 - Operating behavior 3.6 1 characteristics of the facility W/E05 Inadequate Heat Transfer - Loss of X EK1.1 - Components, capacity, and 3.8 1 Secondary Heat Sink / 4 function of emergency systems W/E11 Loss of Emergency Coolant Recirc. / 4 X 2.1.20 - Ability to interpret and execute 4.6 1 procedure steps.

04/28/2016 11:57:46 am 1

PWR RO Examination Outline Printed: 04/28/2016 Facility: Cook Nuclear Plant ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points W/E12 - Steam Line Rupture - Excessive Heat X EA1.1 - Components, and functions of 3.8 1 Transfer / 4 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18

PWR RO Examination Outline Printed: 04/28/2016 Facility: Cook Nuclear Plant ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000005 Inoperable/Stuck Control Rod / 1 X AA1.02 - Rod selection switches 3.7 1 000059 Accidental Liquid RadWaste Rel. / 9 X 2.4.9 - Knowledge of low 3.8 1 power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

000061 ARM System Alarms / 7 X AK2.01 - Detectors at each ARM system 2.5* 1 location 000067 Plant Fire On-site / 9 X AK3.02 - Steps called out in the site fire 2.5 1 protection plan, FPS manual, and fire zone manual 000068 Control Room Evac. / 8 X AA2.01 - S/G level 4.0 1 W/E02 SI Termination / 3 X EA1.3 - Desired operating results during 3.8 1 abnormal and emergency situations W/E06 Inad. Core Cooling / 4 X EK1.2 - Normal, abnormal and 3.5 1 emergency operating procedures associated with Degraded Core Cooling W/E10 Natural Circ. / 4 X EK2.2 - Facility's heat removal systems, 3.6 1 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 W/E16 High Containment Radiation / 9 X EK1.3 - Annunciators and conditions 3.0 1 indicating signals, and remedial actions associated with the High Containment Radiation K/A Category Totals: 2 2 1 2 1 1 Group Point Total: 9 04/28/2016 11:58:15 am 1

PWR RO Examination Outline Printed: 04/28/2016 Facility: Cook Nuclear Plant ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump X K1.10 - RCS 3.0 1 004 Chemical and Volume Control X K5.07 - Relationship between 2.8 1 SUR and reactivity 005 Residual Heat Removal X K6.03 - RHR heat exchanger 2.5 1 005 Residual Heat Removal X 2.4.2 - Knowledge of system 4.5 1 set points, interlocks and automatic actions associated with EOP entry conditions.

006 Emergency Core Cooling X K2.04 - ESFAS-operated 3.6 1 valves 006 Emergency Core Cooling X 2.2.37 - Ability to determine 3.6 1 operability and/or availability of safety related equipment.

007 Pressurizer Relief/Quench Tank X A2.04 - Overpressurization of 2.5 1 the waste gas vent header 008 Component Cooling Water X A4.07 - Control of minimum 2.9* 1 level in the CCWS surge tank 008 Component Cooling Water X A2.07 - Consequences of high 2.5* 1 or low CCW flow rate and temperature; the flow rate at which the CCW standby pump will start 010 Pressurizer Pressure Control X K4.03 - Over pressure control 3.8 1 012 Reactor Protection X A1.01 - Trip setpoint 2.9* 1 adjustment 012 Reactor Protection X A4.07 - M/G set breakers 3.9* 1 013 Engineered Safety Features X K6.01 - Sensors and detectors 2.7* 1 Actuation 022 Containment Cooling X K1.01 - SWS/cooling system 3.5 1 025 Ice Condenser X K3.01 - Containment 3.8* 1 026 Containment Spray X 2.4.18 - Knowledge of the 3.3 1 specific bases for EOPs.

026 Containment Spray X K3.02 - Recirculation spray 4.2* 1 system 039 Main and Reheat Steam X A2.04 - Malfunctioning steam 3.4 1 dump 059 Main Feedwater X A3.02 - Programmed levels of 2.9 1 the S/G 059 Main Feedwater X A1.03 - Power level 2.7* 1 restrictions for operation of MFW pumps and valves 04/28/2016 11:58:47 am 1

PWR RO Examination Outline Printed: 04/28/2016 Facility: Cook Nuclear Plant ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 061 Auxiliary/Emergency Feedwater X K4.04 - Prevention of AFW 3.1 1 runout by limiting AFW flow 062 AC Electrical Distribution X A3.01 - Vital ac bus 3.0 1 amperage 063 DC Electrical Distribution X K4.04 - Trips 2.6? 1 064 Emergency Diesel Generator X K3.01 - Systems controlled 3.8* 1 by automatic loader 073 Process Radiation Monitoring X K5.01 - Radiation theory, 2.5 1 including sources, types, units, and effects 076 Service Water X A1.02 - Reactor and turbine 2.6* 1 building closed cooling water temperatures 078 Instrument Air X K2.01 - Instrument air 2.7 1 compressor 103 Containment X K1.01 - CCS 3.6 1 K/A Category Totals: 3 2 3 3 2 2 3 3 2 2 3 Group Point Total: 28 04/28/2016 11:58:47 am 2

PWR RO Examination Outline Printed: 04/28/2016 Facility: Cook Nuclear Plant ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 001 Control Rod Drive X K3.02 - RCS 3.4* 1 002 Reactor Coolant X A4.07 - Flow path linking the 2.8 1 RWST through the RHR system to the RCS hot legs for gravity refilling of the refueling cavity 011 Pressurizer Level Control X 2.1.7 - Ability to evaluate 4.4 1 plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

014 Rod Position Indication X A2.06 - Loss of LVDT 2.6* 1 015 Nuclear Instrumentation X A1.01 - NIS calibration by 3.5 1 heat balance 017 In-core Temperature Monitor X A3.01 - Indications of 3.6* 1 normal, natural, and interrupted circulation of RCS 028 Hydrogen Recombiner and X K2.01 - Hydrogen 2.5* 1 Purge Control recombiners 035 Steam Generator X K6.02 - Secondary PORV 3.1 1 055 Condenser Air Removal X K1.06 - PRM system 2.6 1 079 Station Air X K4.01 - Cross-connect with 2.9 1 IAS K/A Category Totals: 1 1 1 1 0 1 1 1 1 1 1 Group Point Total: 10 04/28/2016 11:59:17 am 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 04/28/2016 Facility: Cook Nuclear Plant Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.25 Ability to interpret reference materials, such as 3.9 1 graphs, curves, tables, etc.

2.1.42 Knowledge of new and spent fuel movement 2.5 1 procedures.

2.1.45 Ability to identify and interpret diverse indications 4.3 1 to validate the response of another indication.

Category Total: 3 Equipment Control 2.2.21 Knowledge of pre- and post-maintenance 2.9 1 operability requirements.

2.2.23 Ability to track Technical Specification limiting 3.1 1 conditions for operations.

Category Total: 2 Radiation Control 2.3.11 Ability to control radiation releases. 3.8 1 2.3.12 Knowledge of radiological safety principles 3.2 1 pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

2.3.15 Knowledge of radiation monitoring systems, such as 2.9 1 fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Category Total: 3 Emergency Procedures/Plan 2.4.29 Knowledge of the emergency plan. 3.1 1 2.4.31 Knowledge of annunciator alarms, indications, or 4.2 1 response procedures.

Category Total: 2 Generic Total: 10 04/28/2016 11:59:47 am 1

PWR SRO Examination Outline Printed: 04/28/2016 Facility: Cook Nuclear Plant ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000008 Pressurizer Vapor Space Accident / 3 X AA2.27 - Effects on indicated PZR 3.2 1 pressure and/or level of sensing line leakage 000009 Small Break LOCA / 3 X EA2.04 - PZR level 4.0 1 000029 ATWS / 1 X 2.1.7 - Ability to evaluate plant 4.7 1 performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

000040 Steam Line Rupture - Excessive Heat X 2.4.6 - Knowledge of EOP mitigation 4.7 1 Transfer / 4 strategies.

000056 Loss of Off-site Power / 6 X AA2.39 - Safety injection pump ammeter 3.6 1 and flowmeter 000057 Loss of Vital AC Inst. Bus / 6 X 2.2.40 - Ability to apply Technical 4.7 1 Specifications for a system.

K/A Category Totals: 0 0 0 0 3 3 Group Point Total: 6 04/28/2016 9:43:08 am 1

PWR SRO Examination Outline Printed: 04/28/2016 Facility: Cook Nuclear Plant ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000001 Continuous Rod Withdrawal / 1 X 2.4.31 - Knowledge of annunciator 4.1 1 alarms, indications, or response procedures.

000037 Steam Generator Tube Leak / 3 X 2.1.25 - Ability to interpret reference 4.2 1 materials, such as graphs, curves, tables, etc.

W/E03 LOCA Cooldown - Depress. / 4 X EA2.1 - Facility conditions and selection 4.2 1 of appropriate procedures during abnormal and emergency operations W/E08 RCS Overcooling - PTS / 4 X EA2.1 - Facility conditions and selection 4.2 1 of appropriate procedures during abnormal and emergency operations K/A Category Totals: 0 0 0 0 2 2 Group Point Total: 4 04/28/2016 9:43:32 am 1

PWR SRO Examination Outline Printed: 04/28/2016 Facility: Cook Nuclear Plant ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 004 Chemical and Volume Control X A2.27 - Improper RWST 4.2 1 boron concentration 007 Pressurizer Relief/Quench Tank X 2.1.27 - Knowledge of system 4.0 1 purpose and/or function.

061 Auxiliary/Emergency Feedwater X 2.4.9 - Knowledge of low 4.2 1 power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

073 Process Radiation Monitoring X A2.02 - Detector failure 3.2 1 078 Instrument Air X A2.01 - Air dryer and filter 2.9 1 malfunctions K/A Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 04/28/2016 9:43:58 am 1

PWR SRO Examination Outline Printed: 04/28/2016 Facility: Cook Nuclear Plant ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 014 Rod Position Indication X A2.01 - Loss of offsite power 3.3 1 034 Fuel Handling Equipment X 2.4.35 - Knowledge of local 4.0 1 auxiliary operator tasks during an emergency and the resultant operational effects.

045 Main Turbine Generator X A2.11 - Control problems in 2.9* 1 primary, e.g., axial flux imbalance; need to reduce load on secondary K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 04/28/2016 9:44:27 am 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Printed: 04/28/2016 Facility: Cook Nuclear Plant Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.6 Ability to manage the control room crew during 4.8 1 plant transients.

Category Total: 1 Equipment Control 2.2.14 Knowledge of the process for controlling equipment 4.3 1 configuration or status.

2.2.43 Knowledge of the process used to track inoperable 3.3 1 alarms.

Category Total: 2 Radiation Control 2.3.5 Ability to use radiation monitoring systems, such as 2.9 1 fixed radiation monitors and alarms, portable survey instruments, personal monitoring equipment, etc.

2.3.6 Ability to approve release permits. 3.8 1 Category Total: 2 Emergency Procedures/Plan 2.4.11 Knowledge of abnormal condition procedures. 4.2 1 2.4.25 Knowledge of fire protection procedures. 3.7 1 Category Total: 2 Generic Total: 7 04/28/2016 9:44:48 am 1