Text

2016-06 Final Outlines
	ML16158A469
Person / Time
Site:	Callaway
Issue date:	06/01/2016
From:	Vincent Gaddy; Operations Branch IV
To:	;
References
	Download: ML16158A469 (40)
	v • d • e

ES-401 PWR Examination Outline Form ES-401-2 Facility: Callaway Plant (RO, Rev. 2) Date of Exam: 2016 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G* A2 G* Total 1 2 3 4 5 6 1 2 3 4 Total

1. 1 2 2 4 3 4 3 18 6 Emergency &

Abnormal 2 1 1 1 N/A 2 2 N/A 2 9 4 Plant Evolutions Tier Totals 3 3 5 5 6 5 27 10 1 2 2 2 3 3 3 3 2 3 2 3 28 5 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 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). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category).

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 with justification; 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 a category 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.

G* Generic K/As

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)

E/APE # / Name / Safety Function K K K A A G* K/A Topic(s) IR #

1 2 3 1 2 EK2.02 - Knowledge of the 000007 (BW/E02&E10; CE/E02) Reactor X 2.6 1 interrelations between a reactor trip Trip - Stabilization - Recovery / 1 and the following: Breakers, relays and disconnects (CFR 41.7/45.7) 2.4.11 - Knowledge of abnormal 000008 Pressurizer Vapor Space X 4.0 2 condition procedures. (CFR:

Accident / 3 41.10/43.5/45.13)

EK1.02 - Knowledge of the operational 000009 Small Break LOCA / 3 X 3.5 3 implications of the following concepts as they apply to the small break LOCA: Use of steam tables (CFR 41.8/41.10/45.3)

EK3.02 - Knowledge of the reasons for 000011 Large Break LOCA / 3 X 3.5 4 the following responses as the apply to the Large Break LOCA: Feedwater isolation (CFR 41.5/41.10/45.6/45.13) 000015/17 RCP Malfunctions / 4 000022 Loss of Rx Coolant Makeup / 2 AK3.01 - Knowledge of the reasons for 000025 Loss of RHR System / 4 X 3.1 5 the following responses as they apply to the Loss of Residual Heat Removal System: Shift to alternate flowpath (CFR 41.5,41.10/45.6/45.13)

AA2.06 - Ability to determine and 000026 Loss of Component Cooling X 2.8 6 interpret the following as they apply Water / 8 to the Loss of Component Cooling Water: The length of time after the loss of CCW flow to a component before that component may be damaged (CFR: 43.5/45.13)

A2.10 - Ability to determine and 000027 Pressurizer Pressure Control X interpret the following as they apply 3.3 7 System Malfunction / 3 to the Pressurizer Pressure Control Malfunction: PZR Heater energized/ de energized condition (CFR 43.5/45.13)

EK3.12 - Knowledge of the reasons for 000029 ATWS / 1 X the following responses as the apply 4.4 8 to the ATWS: Actions contained in EOP for ATWS (CFR 41.5 / 41.10 /45.6 /

45.13)

EK3.01 - Knowledge of the reasons for 000038 Steam Gen. Tube Rupture / 3 X 4.1 9 the following responses as the apply to the SGTR: Equalizing pressure on primary and secondary sides of ruptured S/G (CFR 41.5/41.10/45.6/45.13)

W/E12, EA1.3 - Ability to operate and 000040 (BW/E05; CE/E05; W/E12) X 3.4 10

/ or monitor the following as they Steam Line Rupture - Excessive Heat apply to the (Uncontrolled Transfer / 4 Depressurization of all Steam Generators): Desired operating results during abnormal and emergency situations. (CFR: 41.7 / 45.5 /

45.6)

AA2.02 - Ability to determine and 000054 (CE/E06) Loss of Main X 4.1 11 interpret the following as they apply Feedwater / 4 to the Loss of Main Feedwater (MFW):

Differentiation between loss of all MFW and trip of one MFW pump (CFR:

43.5 / 45.13)

EA1.02 Ability to operate and monitor 000055 Station Blackout / 6 X the following as they apply to a 4.3 13 Station Blackout: Manual ED/G start (CFR 41.7 / 45.5 / 45.6)

AA1.08 - Ability to operate and/or 000056 Loss of Off-site Power / 6 X 2.5 12 monitor the following as they apply to the Loss of Offsite Power: HVAC chill water pump and unit (CFR 41.7/45.5/45.6) 000057 Loss of Vital AC Inst. Bus / 6 000058 Loss of DC Power / 6 000062 Loss of Nuclear Svc Water / 4 2.1.28 - Knowledge of the purpose and 000065 Loss of Instrument Air / 8 X 4.1 14 function of major system components and controls. (CFR: 41.7)

EK2.1 - Knowledge of the W/E04 LOCA Outside Containment / 3 X 3.5 15 interrelations between the (LOCA Outside Containment) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. (CFR:

41.7 / 45.7)

EK1.3 - Knowledge of the operational W/E11 Loss of Emergency Coolant X 3.6 16 implications of the following Recirc. / 4 concepts as they apply to the (Loss of Emergency Coolant Recirculation):

Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Emergency Coolant Recirculation).

(CFR: 41.8 / 41.10 / 45.3)

W/E05, EA2.1 - Ability to determine BW/E04; W/E05 Inadequate Heat X 3.4 17 and interpret the following as they Transfer - Loss of Secondary Heat Sink / 4 apply to the (Loss of Secondary Heat Sink): Facility conditions and selection of appropriate procedures during abnormal and emergency operations. (CFR: 43.5 / 45.13) 2.1.19 - Ability to use plant 000077 Generator Voltage and Electric X 3.9 18 computers to evaluate system or Grid Disturbances / 6 component status. (CFR: 41.10 /

45.12)

K/A Category Totals: 2 2 4 3 4 3 Group Point Total: 18/6

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)

E/APE # / Name / Safety Function K K K A A G* K/A Topic(s) IR #

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod / 1 AK1.03 - Knowledge of the 000005 Inoperable/Stuck Control Rod / 1 X 3.2 19 operational implications of the following concepts as they apply to Inoperable / Stuck Control Rod: Xenon transient (CFR 41.8 / 41.10 / 45.3) 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 000037 Steam Generator Tube Leak / 3 X

000051 Loss of Condenser Vacuum / 4 2.4.11 Knowledge of abnormal 4.0 20 condition procedures (CFR:

41.10 / 43.5 / 45.13) 000059 Accidental Liquid Radwaste Rel. / 9 AA1.02 - Ability to operate and 000060 Accidental Gaseous Radwaste Rel. / 9 X 2.9 21

/ or monitor the following as they apply to the Accidental Gaseous Radwaste: Ventilation System (CFR 41.7 / 45.5 / 45.6) 000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8 000068 (BW/A06) Control Room Evac. / 8 000069 (W/E14) Loss of CTMT Integrity / 5 000074 (W/E06&E07) Inad. Core Cooling / 4 AK2.01 - Knowledge of the 000076 High Reactor Coolant Activity / 9 X 2.6 22 interrelations between the High Reactor Coolant Activity and the following: Process radiation monitors (CFR 41.7 /

45.7)

W/E02, EA2.2 - Ability to W/EO1 & E02 Rediagnosis & SI Termination / 3 X 3.5 23 determine and interpret the following as they apply to the (SI Termination): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments. (CFR:

43.5 / 45.13)

W/E13 Steam Generator Over-pressure / 4 X EA1.2 - Ability to operate and 2.7 24 W/E15 Containment Flooding / 5 / or monitor the following as they apply to Containment Flooding: Operating behavior characteristics of the facility (CFR: 41.7 / 45.5 / 45.6)

W/E16 High Containment Radiation / 9 BW/A01 Plant Runback / 1 BW/A02&A03 Loss of NNI-X/Y / 7

BW/A04 Turbine Trip / 4 BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 BW/E03 Inadequate Subcooling Margin / 4 EK3.2 - Knowledge of the BW/E08; W/E03 LOCA Cooldown - Depress. / 4 X 3.4 25 reasons for the following responses as they apply to the (LOCA Cooldown and Depressurization): Normal, abnormal and emergency operating procedures associated with (LOCA Cooldown and Depressurization). (CFR: 41.5 /

41.10, 45.6 / 45.13) 2.4.45 - Ability to prioritize BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 X 4.1 26 and interpret the significance of each annunciator or alarm.

(CFR: 41.10 / 43.5 / 45.3 /

45.12)

BW/E13&E14 EOP Rules and Enclosures EA2.1 - Ability to determine CE/A11; W/E08 RCS Overcooling - PTS / 4 X 3.1 27 and interpret the following as they apply to the (Pressurized Thermal Shock): Facility conditions and selection of appropriate procedures during abnormal and emergency operations. (CFR: 43.5 / 45.13)

CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery K/A Category Point Totals: 1 1 1 2 2 2 Group Point Total: 9/4

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G* K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 K6.04 - Knowledge of the 003 Reactor Coolant Pump X effect of a loss or 2.8 28 malfunction on the following will have on the RCPS:

Containment isolation valves affecting RCP operation (CFR: 41.7 / 45/5)

K3.04 - Knowledge of the 004 Chemical and Volume X effect that a loss or 3.7 29 Control malfunction of the CVCS will have on the following: RCPS (CFR: 41.7/45/6)

K3.01 - Knowledge of the 005 Residual Heat Removal X effect that a loss or 3.9 30 malfunction of the RHRS will have on the following: RCS (CFR: 41.7 / 45.6)

A4.03 - Ability to manually 005 Residual Heat Removal X operate and/or monitor in 2.8 31 the control room: RHR temperature, PZR heaters and flow, and nitrogen (CFR:

41.7 / 45.5 to 45.8)

K5.08 - Knowledge of the 006 Emergency Core Cooling X operational implications of 2.9 32 the following concepts as they apply to ECCS:

Operation of pumps in parallel (CFR: 41.5 / 45.7)

A1.03 - Ability to predict 007 Pressurizer Relief/Quench X and/or monitor changes in 2.6 33 Tank parameters (to prevent exceeding design limits) associated with operating the PRTS controls including:

Monitoring quench tank temperature (CFR: 41.5 /

45.5)

A3.04 - Ability to monitor 008 Component Cooling Water X automatic operation of the 2.9 34 CCWS, including:

Requirements on and for the CCWS for different conditions of the power plant (CFR: 41.7 / 45.5)

A2.02 - Ability to (a) 010 Pressurizer Pressure Control X predict the impacts of the 3.9 36 following malfunctions or operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Spray valve failures (CFR: 41.5 / 43.5 /

45.3 / 45.13)

G2.2.22 Knowledge of 012 Reactor Protection X limiting conditions for 4.0 37 operations and safety limits. (CFR: 41.5 / 43.2 /

45.2)

K2.01 - Knowledge of bus 013 Engineered Safety Features X power supplies to the 3.6 38 Actuation following: ESFAS/safeguards equipment control (CFR:

41.7)

K6.01 - Knowledge of the 013 Engineered Safety Features X effect of a loss or 2.7 39 Actuation malfunction on the following will have on the ESFAS:

Sensors and detectors (CFR:

41.7 / 45.5 to 45.8)

K4.04 - Knowledge of CCS 022 Containment Cooling X design feature(s) and/or 2.8 40 interlock(s) which provide for the following: Cooling of control rod drive motors (CFR: 41.7) 025 Ice Condenser Not part of the plant design K1.01 - Knowledge of the 026 Containment Spray X physical connections and/or 4.2 41 cause/effect relationships between the CSS and the following systems: ECCS (CFR: 41.2 to 41.9 / 45.7 to 45.8)

K2.01 - Knowledge of the bus 026 Containment Spray X power supplies to the 3.4 42 following: Containment Spray Pumps (CFR: 41.7)

K5.08 - Knowledge of the 039 Main and Reheat Steam X operational implications of 3.6 43 the following concepts as the apply to the MRSS:

Effect of steam removal on reactivity (CFR: 41.5 /

45.7)

A1.07 - Ability to predict 059 Main Feedwater X and/or monitor changes in 2.5 44 parameters (to prevent exceeding design limits) associated with operating the MFW controls including:

Feed Pump speed, including normal control speed for ICS (CFR: 41.5 / 45.5)

A3.06 - Ability to monitor 059 Main Feedwater X automatic operation of the 3.2 45 MFW, including: Feedwater isolation (CFR: 41.7 / 45.5)

K5.02 - Knowledge of the 061 Auxiliary/Emergency X operational implications of 3.2 46 Feedwater the following concept as the apply to the AFW: Decay Heat Sources and Magnitude.

(CFR: 41.5 / 45.7)

A1.01 - Ability to predict 061 Auxiliary/Emergency X and/or monitor changes in 3.9 47 Feedwater parameters (to prevent exceeding design limits) associated with operating the AFW controls including:

S/G level (CFR: 41.5 / 45.5)

K4.10 - Knowledge of ac 062 AC Electrical Distribution X distribution system design 3.1 48 feature(s) and/or interlock(s) which provide for the following:

Uninterruptable ac power sources (CFR: 41.7)

A3.01 - Ability to monitor 063 DC Electrical Distribution X automatic operation of the 2.7 49 DC electrical system, including: Meters, annunciators, dials, recorders, and indicating lights (CFR: 41.7 / 45.5)

A4.03 Ability to manually 063 DC Electrical Distribution X operate and / or monitor in 3.0 35 the control room: Battery Discharge Rate (CFR: 41.7 /

45.5 to 45.8)

K6.08 - Knowledge of the 064 Emergency Diesel Generator X effect of a loss or 3.2 50 malfunction of the following will have on the ED/G system: Fuel oil storage tanks (CFR: 41.7 / 45.7) 2.4.31 - Knowledge of 073 Process Radiation Monitoring X annunciator alarms, 4.2 51 indications, or response procedures. (CFR: 41.10 /

45.3)

K1.21 - Knowledge of the 076 Service Water X physical connections and/or 2.7 52 cause- effect relationships between the SWS and the following systems: Auxiliary backup SWS (CFR: 41.2 to 41.9 / 45.7 to 45.8)

K4.02 - Knowledge of SWS 076 Service Water X design feature(s) and/or 2.9 53 interlock(s) which provide for the following:

Automatic start features associated with SWS pump controls (CFR: 41/7) 2.4.18 - Knowledge of the 078 Instrument Air X specific bases for EOPs. 3.3 54 (CFR: 41.10 / 43.1 / 45.13)

A2.03 - Ability to (a) 103 Containment X predict the impacts of the 3.5 55 following malfunctions or operations on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Phase A and B isolation (CFR: 41.5 / 43.5 / 45.3 /

45.13)

K/A Category Point Totals: 2 2 2 3 3 3 3 2 3 2 3 Group Point Total: 28/5

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A A A G* K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 A2.14 Ability to (a) predict 001 Control Rod Drive X the impacts of the following 3.7 56 malfunction or operations on the CRDS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Urgent failure alarm, including rod-out-of-sequence and motion-inhibit alarms.

(CFR: 41.5 / 43.5 / 45.3 /

45.13)

K5.07 Knowledge of the 002 Reactor Coolant X operational implications of 3.3 65 the following concepts as they apply to the RCS: Reactivity effects of RCS boron, pressure and temperature (CFR: 41.5 /

45.7) 011 Pressurizer Level Control A1.02 - Ability to predict 014 Rod Position Indication X and/or monitor changes in 3.2 57 parameters (to prevent exceeding design limits) associated with operating the RPIS controls, including:

Control rod position indication on control room panels. (CFR: 41.5 / 45.5)

K1.01 - Knowledge of the 015 Nuclear Instrumentation X physical connections and/or 4.1 58 cause/effect relationships between the NIS and the following systems: RPS (CFR:

41.2 to 41.9 / 45.7 to 45.8) 016 Non-Nuclear Instrumentation 017 In-Core Temperature Monitor K2.01 - Knowledge of bus power 027 Containment Iodine Removal X supplies to the following: 3.1 59 Fans (CFR: 41.7) 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment K6.01 - Knowledge of the 035 Steam Generator X effect of a loss or 3.2 62 malfunction on the following will have on the S/GS: MSIVs (CFR: 41.7 / 45.7)

A4.05 Ability to manually 041 Steam Dump/Turbine Bypass X operate and/or monitor in the 3.1 63 Control control room: Main steam header pressure (CFR: 41.7 / 45.5 to 45.8)

K4.02 Knowledge of MT/G system 045 Main Turbine Generator X design feature(s) and/or 2.5 60 interlock( s) which provide for the following: Automatic shut of reheat stop valves as well as main control valves when tripping turbine (CFR:

41.7) 055 Condenser Air Removal X G2.1.28 Knowledge of the 4.1 61 purpose and function of major system components and controls. (CFR 41.7) 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air A3.01 Ability to monitor 086 Fire Protection X automatic operation of the 2.9 64 Fire Protection System including: Starting mechanisms of the fire water pumps (CFR 41.7 / 45.5)

K/A Category Point Totals: 1 1 0 1 1 1 1 1 1 1 1 Group Point Total: 10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Callaway Plant (RO, Rev. 2) Date of Exam: 2016 Category K/A # Topic RO SRO-Only IR # IR #

(CFR: 41.10 / 43.5 / 45.9 / 45.10 )

2.1.13 2.5 66 Knowledge of procedures and limitations involved in core

1. 2.1.36 3.0 67 alterations. (CFR: 41.10 / 43.6 / 45.7)

Conduct of Knowledge of shift or short-term relief turnover practices Operations 2.1.3 3.7 68 (CFR: 41.10 / 45.13)

Subtotal 3 Knowledge of the process for controlling equipment 2.2.14 3.9 69

2. configuration or status. (CFR: 41.10 / 43.3 / 45.13)

Equipment Ability to track Technical Specification limiting conditions 2.2.23 3.1 70 Control for operations. (CFR: 41.10 / 43.2 / 45.13)

Subtotal 2 Ability to control radiation releases. (CFR: 41.11 / 43.4 /

2.3.11 3.8 71 45.10)

3. Knowledge of radiation or contamination hazards that Radiation 2.3.14 3.4 72 may arise during normal, abnormal, or emergency Control conditions or activities. (CFR: 41.12 / 43.4 / 45.10)

Subtotal 2 Knowledge of how abnormal operating procedures are 2.4.8 3.8 73 used in conjunction with EOPs. (CFR: 41.10 / 43.5 /

4. 45.13)

Emergency Knowledge of the emergency plan. (CFR: 41.10 / 43.5 /

2.4.29 3.1 74 Procedures / 45.11)

Plan Knowledge of emergency response facilities. (CFR: 41.10 2.4.42 2.6 75

/ 45.11)

Subtotal 3 Tier 3 Point Total 10 7

ES-401 PWR Examination Outline Form ES-401-2 Facility: Callaway Plant (SRO, Rev. 2) Date of Exam: 2016 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G* A2 G* Total 1 2 3 4 5 6 1 2 3 4 Total

1. 1 18 2 4 6 Emergency &

Abnormal 2 N/A N/A 9 2 2 4 Plant Evolutions Tier Totals 27 5 5 10 1 28 3 2 5 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 Categories 1 2 2 2 7 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). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category).