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

04/28/2016 Printed:

ES-401 Facility:

Cook Nuclear Plant PWR Examination Outline Form ES-401-2 3

3 3

3 3

3 2

2 1

2 1

1 5

5 4

5 4

4 3

2 3

3 2

2 3

3 2

2 3

1 1

1 1

0 1

1 1

1 1

1 4

3 4

4 2

3 4

4 3

3 4

3 2

3 2

RO K/A Category Points Tier Group Total K1 K2 K3 K4 K5 A1 A2 A3 A4 K6 G*

1.

Emergency Abnormal Plant Evolutions 1

1 2

2 Tier Totals Tier Totals

2.

Plant Systems 1

2 3

4

3. Generic Knowledge And Abilities Categories
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.

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.

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.

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.

Note:

Date Of Exam:

07/11/2016 28 18 9

27 10 38 10

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).

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.

SRO-Only Points A2 G*

3 3

2 2

5 5

3 2

2 1

3 1

2 2

2 1

2 3

4 10 4

6 5

3 8

7

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.

6.

Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

N/A N/A Total 0

5 1

04/28/2016 12:00:04 pm

04/28/2016 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

ES - 401 Facility:

Cook Nuclear Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 EK2.02 - Breakers, relays and disconnects 2.6 1

X 000007 Reactor Trip - Stabilization - Recovery

/ 1 EK2.02 - Pumps 2.6*

1 X

000011 Large Break LOCA / 3 AK2.07 - RCP seals 2.9 1

X 000015/000017 RCP Malfunctions / 4 AA1.02 - CVCS charging low flow alarm, sensor, and indicator 3.0 1

X 000022 Loss of Rx Coolant Makeup / 2 AK1.01 - Loss of RHRS during all modes of operation 3.9 1

X 000025 Loss of RHR System / 4 AK3.03 - Guidance actions contained in EOP for Loss of CCW 4.0 1

X 000026 Loss of Component Cooling Water / 8 AK3.01 - Isolation of PZR spray following loss of PZR heaters 3.5*

1 X

000027 Pressurizer Pressure Control System Malfunction / 3 EK3.02 - Prevention of secondary PORV cycling 4.4 1

X 000038 Steam Gen. Tube Rupture / 3 AK1.01 - MFW line break depressurizes the S/G (similar to a steam line break) 4.1 1

X 000054 Loss of Main Feedwater / 4 EA2.03 - Actions necessary to restore power 3.9 1

X 000055 Station Blackout / 6 AA2.01 - That a loss of dc power has occurred; verification that substitute power sources have come on line 3.7 1

X 000058 Loss of DC Power / 6 AA2.02 - The cause of possible SWS loss 2.9 1

X 000062 Loss of Nuclear Svc Water / 4 2.4.8 - Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

3.8 1

X 000065 Loss of Instrument Air / 8 2.2.44 - Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

4.2 1

X 000077 Generator Voltage and Electric Grid Disturbances / 6 EA1.2 - Operating behavior characteristics of the facility 3.6 1

X W/E04 LOCA Outside Containment / 3 EK1.1 - Components, capacity, and function of emergency systems 3.8 1

X W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 2.1.20 - Ability to interpret and execute procedure steps.

4.6 1

X W/E11 Loss of Emergency Coolant Recirc. / 4 1

04/28/2016 11:57:46 am

04/28/2016 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

ES - 401 Facility:

Cook Nuclear Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 EA1.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 3.8 1

X W/E12 - Steam Line Rupture - Excessive Heat Transfer / 4 18 3

3 3

3 3

3 K/A Category Totals:

Group Point Total:

04/28/2016 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

ES - 401 Facility:

Cook Nuclear Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR RO Examination Outline Form ES-401-2 AA1.02 - Rod selection switches 3.7 1

X 000005 Inoperable/Stuck Control Rod / 1 2.4.9 - Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

3.8 1

X 000059 Accidental Liquid RadWaste Rel. / 9 AK2.01 - Detectors at each ARM system location 2.5*

1 X

000061 ARM System Alarms / 7 AK3.02 - Steps called out in the site fire protection plan, FPS manual, and fire zone manual 2.5 1

X 000067 Plant Fire On-site / 9 AA2.01 - S/G level 4.0 1

X 000068 Control Room Evac. / 8 EA1.3 - Desired operating results during abnormal and emergency situations 3.8 1

X W/E02 SI Termination / 3 EK1.2 - Normal, abnormal and emergency operating procedures associated with Degraded Core Cooling 3.5 1

X W/E06 Inad. Core Cooling / 4 EK2.2 - 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 3.6 1

X W/E10 Natural Circ. / 4 EK1.3 - Annunciators and conditions indicating signals, and remedial actions associated with the High Containment Radiation 3.0 1

X W/E16 High Containment Radiation / 9 9

2 2

1 2

1 1

K/A Category Totals:

Group Point Total:

1 04/28/2016 11:58:15 am

04/28/2016 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility: Cook Nuclear Plant PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 K1.10 - RCS 3.0 1

X 003 Reactor Coolant Pump K5.07 - Relationship between SUR and reactivity 2.8 1

X 004 Chemical and Volume Control K6.03 - RHR heat exchanger 2.5 1

X 005 Residual Heat Removal 2.4.2 - Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

4.5 1

X 005 Residual Heat Removal K2.04 - ESFAS-operated valves 3.6 1

X 006 Emergency Core Cooling 2.2.37 - Ability to determine operability and/or availability of safety related equipment.

3.6 1

X 006 Emergency Core Cooling A2.04 - Overpressurization of the waste gas vent header 2.5 1

X 007 Pressurizer Relief/Quench Tank A4.07 - Control of minimum level in the CCWS surge tank 2.9*

1 X

008 Component Cooling Water A2.07 - Consequences of high or low CCW flow rate and temperature; the flow rate at which the CCW standby pump will start 2.5*

1 X

008 Component Cooling Water K4.03 - Over pressure control 3.8 1

X 010 Pressurizer Pressure Control A1.01 - Trip setpoint adjustment 2.9*

1 X

012 Reactor Protection A4.07 - M/G set breakers 3.9*

1 X

012 Reactor Protection K6.01 - Sensors and detectors 2.7*

1 X

013 Engineered Safety Features Actuation K1.01 - SWS/cooling system 3.5 1

X 022 Containment Cooling K3.01 - Containment 3.8*

1 X

025 Ice Condenser 2.4.18 - Knowledge of the specific bases for EOPs.

3.3 1

X 026 Containment Spray K3.02 - Recirculation spray system 4.2*

1 X

026 Containment Spray A2.04 - Malfunctioning steam dump 3.4 1

X 039 Main and Reheat Steam A3.02 - Programmed levels of the S/G 2.9 1

X 059 Main Feedwater A1.03 - Power level restrictions for operation of MFW pumps and valves 2.7*

1 X

059 Main Feedwater 1

04/28/2016 11:58:47 am

04/28/2016 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility: Cook Nuclear Plant PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 K4.04 - Prevention of AFW runout by limiting AFW flow 3.1 1

X 061 Auxiliary/Emergency Feedwater A3.01 - Vital ac bus amperage 3.0 1

X 062 AC Electrical Distribution K4.04 - Trips 2.6?

1 X

063 DC Electrical Distribution K3.01 - Systems controlled by automatic loader 3.8*

1 X

064 Emergency Diesel Generator K5.01 - Radiation theory, including sources, types, units, and effects 2.5 1

X 073 Process Radiation Monitoring A1.02 - Reactor and turbine building closed cooling water temperatures 2.6*

1 X

076 Service Water K2.01 - Instrument air compressor 2.7 1

X 078 Instrument Air K1.01 - CCS 3.6 1

X 103 Containment 28 3

2 3

3 3

3 K/A Category Totals:

3 2

2 2

2 Group Point Total:

2 04/28/2016 11:58:47 am

04/28/2016 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility: Cook Nuclear Plant PWR RO Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 K3.02 - RCS 3.4*

1 X

001 Control Rod Drive A4.07 - Flow path linking the RWST through the RHR system to the RCS hot legs for gravity refilling of the refueling cavity 2.8 1

X 002 Reactor Coolant 2.1.7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

4.4 1

X 011 Pressurizer Level Control A2.06 - Loss of LVDT 2.6*

1 X

014 Rod Position Indication A1.01 - NIS calibration by heat balance 3.5 1

X 015 Nuclear Instrumentation A3.01 - Indications of normal, natural, and interrupted circulation of RCS 3.6*

1 X

017 In-core Temperature Monitor K2.01 - Hydrogen recombiners 2.5*

1 X

028 Hydrogen Recombiner and Purge Control K6.02 - Secondary PORV 3.1 1

X 035 Steam Generator K1.06 - PRM system 2.6 1

X 055 Condenser Air Removal K4.01 - Cross-connect with IAS 2.9 1

X 079 Station Air 10 1

1 1

1 1

1 K/A Category Totals:

1 0

1 1

1 Group Point Total:

1 04/28/2016 11:59:17 am

Facility:

Cook Nuclear Plant Generic Category KA KA Topic Imp.

Points Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 04/28/2016 Printed:

PWR RO Examination Outline 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

3.9 1

Conduct of Operations 2.1.42 Knowledge of new and spent fuel movement procedures.

2.5 1

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

4.3 1

3 Category Total:

2.2.21 Knowledge of pre-and post-maintenance operability requirements.

2.9 1

Equipment Control 2.2.23 Ability to track Technical Specification limiting conditions for operations.

3.1 1

2 Category Total:

2.3.11 Ability to control radiation releases.

3.8 1

Radiation Control 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

3.2 1

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

2.9 1

3 Category Total:

2.4.29 Knowledge of the emergency plan.

3.1 1

Emergency Procedures/Plan 2.4.31 Knowledge of annunciator alarms, indications, or response procedures.

4.2 1

2 Category Total:

10 Generic Total:

1 04/28/2016 11:59:47 am

04/28/2016 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

ES - 401 Facility:

Cook Nuclear Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR SRO Examination Outline Form ES-401-2 AA2.27 - Effects on indicated PZR pressure and/or level of sensing line leakage 3.2 1

X 000008 Pressurizer Vapor Space Accident / 3 EA2.04 - PZR level 4.0 1

X 000009 Small Break LOCA / 3 2.1.7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

4.7 1

X 000029 ATWS / 1 2.4.6 - Knowledge of EOP mitigation strategies.

4.7 1

X 000040 Steam Line Rupture - Excessive Heat Transfer / 4 AA2.39 - Safety injection pump ammeter and flowmeter 3.6 1

X 000056 Loss of Off-site Power / 6 2.2.40 - Ability to apply Technical Specifications for a system.

4.7 1

X 000057 Loss of Vital AC Inst. Bus / 6 6

0 0

0 0

3 3

K/A Category Totals:

Group Point Total:

1 04/28/2016 9:43:08 am

04/28/2016 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

ES - 401 Facility:

Cook Nuclear Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR SRO Examination Outline Form ES-401-2 2.4.31 - Knowledge of annunciator alarms, indications, or response procedures.

4.1 1

X 000001 Continuous Rod Withdrawal / 1 2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc.

4.2 1

X 000037 Steam Generator Tube Leak / 3 EA2.1 - Facility conditions and selection of appropriate procedures during abnormal and emergency operations 4.2 1

X W/E03 LOCA Cooldown - Depress. / 4 EA2.1 - Facility conditions and selection of appropriate procedures during abnormal and emergency operations 4.2 1

X W/E08 RCS Overcooling - PTS / 4 4

0 0

0 0

2 2

K/A Category Totals:

Group Point Total:

1 04/28/2016 9:43:32 am

04/28/2016 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility: Cook Nuclear Plant PWR SRO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 A2.27 - Improper RWST boron concentration 4.2 1

X 004 Chemical and Volume Control 2.1.27 - Knowledge of system purpose and/or function.

4.0 1

X 007 Pressurizer Relief/Quench Tank 2.4.9 - Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

4.2 1

X 061 Auxiliary/Emergency Feedwater A2.02 - Detector failure 3.2 1

X 073 Process Radiation Monitoring A2.01 - Air dryer and filter malfunctions 2.9 1

X 078 Instrument Air 5

0 0

0 0

3 2

K/A Category Totals:

0 0

0 0

0 Group Point Total:

1 04/28/2016 9:43:58 am

04/28/2016 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points Printed:

K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility: Cook Nuclear Plant PWR SRO Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 A2.01 - Loss of offsite power 3.3 1

X 014 Rod Position Indication 2.4.35 - Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

4.0 1

X 034 Fuel Handling Equipment A2.11 - Control problems in primary, e.g., axial flux imbalance; need to reduce load on secondary 2.9*

1 X

045 Main Turbine Generator 3

0 0

0 0

2 1

K/A Category Totals:

0 0

0 0

0 Group Point Total:

1 04/28/2016 9:44:27 am

Facility:

Cook Nuclear Plant Generic Category KA KA Topic Imp.

Points Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 04/28/2016 Printed:

PWR SRO Examination Outline 2.1.6 Ability to manage the control room crew during plant transients.

4.8 1

Conduct of Operations 1

Category Total:

2.2.14 Knowledge of the process for controlling equipment configuration or status.

4.3 1

Equipment Control 2.2.43 Knowledge of the process used to track inoperable alarms.

3.3 1

2 Category Total:

2.3.5 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personal monitoring equipment, etc.

2.9 1

Radiation Control 2.3.6 Ability to approve release permits.

3.8 1

2 Category Total:

2.4.11 Knowledge of abnormal condition procedures.

4.2 1

Emergency Procedures/Plan 2.4.25 Knowledge of fire protection procedures.

3.7 1

2 Category Total:

7 Generic Total:

1 04/28/2016 9:44:48 am