Text

CW-2011-02-Draft Outlines
	ML110660598
Person / Time
Site:	Callaway
Issue date:	02/04/2011
From:	Clyde Osterholtz; NRC Region 4
To:	;
References
	Download: ML110660598 (49)
	v • d • e

ES-401 PWR Examination Outline - RO Form ES-401-2 Facility: Callaway Date of Exam: January 2011 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 1 5 5 1 4 18 2 4 6 Emergency &

Abnormal 2 3 1 0 N/A 0 4 N/A 1 9 2 2 4 Plant Evolutions Tier Totals 5 2 5 5 5 5 27 4 6 10 1 5 3 3 3 3 3 3 0 3 2 0 28 1 4 5 2.

Plant 2 0 1 0 0 1 0 0 2 1 3 2 10 1 2 3 Systems Tier Totals 5 4 3 3 4 3 3 2 4 5 2 38 2 6 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 3 2 3 2 2 2 1 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.

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)

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

1 2 3 1 2 000007 (BW/E02&E10; CE/E02) Reactor X 007 EK3.01 Knowledge of the interrelations 4.0 1 Trip - Stabilization - Recovery / 1 between a reactor trip: Actions contained in EOP for reactor trip. (CFR 41.5/ 41.10 / 45.6 /

45.13)

X 2.2.25 Knowledge of the bases in Technical 3.2 2 000008 Pressurizer Vapor Space Accident / 3 Specifications for limiting conditions for operations and safety limits.

(CFR: 41.5 / 41.7 / 43.2) 000011 Large Break LOCA / 3 X EK3.02 Knowledge of the reasons for the 3.5 3 following responses as the apply to the Large Break LOCA: Feedwater isolation (CFR 41.5 / 41.10 / 45.6 / 45.13)

X AA2.08 Ability to determine and interpret 3.4 4 000015/17 RCP Malfunctions / 4 the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): When to secure RCPs on high bearing temperature.

(CFR 43.5 / 45.13)

X AK3.03 Knowledge of the reasons for the 3.9 5 000025 Loss of RHR System / 4 following responses as they apply to the Loss of Residual Heat Removal System:

Immediate actions contained in EOP for Loss of RHRS.

(CFR 41.5,41.10 / 45.6 / 45.13)

X AK3.02 Knowledge of the reasons for the 3.6 6 000026 Loss of Component Cooling Water / 8 following responses as they apply to the Loss of Component Cooling Water: The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS.

(CFR 41.5,41.10 / 45.6 / 45.13)

X EK1.01 Knowledge of the operational 2.8 7 000029 ATWS / 1 implications of the following concepts as they apply to the ATWS: Reactor nucleonics and thermo-hydraulics behavior.

(CFR 41.8 / 41.10 / 45.3)

X EA1.34 Ability to operate and monitor the 4.2 8 000038 Steam Gen. Tube Rupture / 3 following as they apply to a SGTR:

Obtaining shutdown with natural circulation.

(CFR 41.7 / 45.5 / 45.6)

X 040 AK1.05 Knowledge of the operational 4.1 9 000040 (BW/E05; CE/E05; W/E12)

Steam Line Rupture - Excessive Heat implications of the following concepts as Transfer / 4 they apply to Steam Line Rupture:

Reactivity effects of cooldown.

(CFR 41.8 / 41.10 / 45.3)

X 2.1.7 Ability to evaluate plant performance 4.4 10 000054 (CE/E06) Loss of Main Feedwater / 4 and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

(CFR: 41.5 / 43.5 / 45.12 / 45.13)

X EA1.02 Ability to operate and monitor the 4.3 11 000055 Station Blackout / 6 following as they apply to a Station Blackout: Manual ED/G start.

(CFR 41.7 / 45.5 / 45.6)

X 2.4.8 Knowledge of how abnormal 3.8 12 000056 Loss of Off-site Power / 6 operating procedures are used in conjunction with EOPs.

(CFR: 41.10 / 43.5 / 45.13)

X AK3.03 Knowledge of the reasons for the 4.0 13 000062 Loss of Nuclear Svc Water / 4 following responses as they apply to the Loss of Nuclear Service Water: Guidance actions contained in EOP for Loss of nuclear service water.

(CFR 41.4, 41.8 / 45.7 )

X AA1.03 Ability to operate and / or monitor 2.9 14 000065 Loss of Instrument Air / 8 the following as they apply to the Loss of Instrument Air: Restoration of systems served by instrument air when pressure is regained.

(CFR 41.7 / 45.5 / 45.6)

X 2.2.12 Knowledge of surveillance 3.7 15 W/E04 LOCA Outside Containment / 3 procedures.

(CFR: 41.10 / 45.13)

X EA1.1 Ability to operate and / or monitor 3.9 16 W/E11 Loss of Emergency Coolant Recirc. / 4 the following as they apply to the (Loss of Emergency Coolant Recirculation):

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41.7 / 45.5 / 45.6)

X EA1.3 Ability to operate and / or monitor 3.8 17 BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 the following as they apply to the (Loss of Secondary Heat Sink): Desired operating results during abnormal and emergency situations.

(CFR: 41.7 / 45.5 / 45.6)

000077 Generator Voltage and Electric X AK2.05 Knowledge of the interrelations 3.1 18 Grid Disturbances / 6 between Generator Voltage and Electric Grid Disturbances and the following:

Pumps (CFR: 41.4, 41.5, 41.7, 41.10 / 45.8)

K/A Category Totals: 2 1 5 5 1 4 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)

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 X AA2.05 Ability to determine and 4.4 19 interpret the following as they apply to the Continuous Rod Withdrawal :

Uncontrolled rod withdrawal, from available indications (CFR: 43.5 / 45.13) 000032 Loss of Source Range NI / 7 X AA2.04 Ability to determine and 3.1 20 interpret the following as they apply to the Loss of Source Range Nuclear Instrumentation: Satisfactory source-range/intermediate-range overlap (CFR: 43.5 / 45.13) 000033 Loss of Intermediate Range NI / 7 X AK1.01 Knowledge of the 2.7 21 operational implications of the following concepts as they apply to Loss of Intermediate Range Nuclear Instrumentation: Effects of voltage changes on performance.

(CFR 41.8 / 41.10 / 45.3) 000051 Loss of Condenser Vacuum / 4 X AA2.02 Ability to determine and 3.9 22 interpret the following as they apply to the Loss of Condenser Vacuum:

Conditions requiring reactor and/or turbine trip (CFR: 43.5 / 45.13) 000059 Accidental Liquid RadWaste Rel. / 9 X AK2.02 Knowledge of the 2.7 23 interrelations between the Accidental Liquid Radwaste Release and the following: Radioactive-gas monitors.

(CFR 41.7 / 45.7) 000061 ARM System Alarms / 7 X AA2.06 Ability to determine and 3.2 24 interpret the following as they apply to the Area Radiation Monitoring (ARM) System Alarms: Required actions if alarm channel is out of service.

(CFR: 43.5 / 45.13)

W/E13 Steam Generator Over-pressure / 4 X EK1.1 Knowledge of the operational 3.2 25 implications of the following concepts as they apply to the (Steam Generator Overpressure):

Components, capacity, and function of emergency systems (CFR: 41.8 / 41.10, 45.3)

W/E16 High Containment Radiation / 9 X EK1.1 Knowledge of the operational 2.7 26 implications of the following concepts as they apply to the (High Containment Radiation):

Components, capacity, and function of emergency systems.

(CFR: 41.8 / 41.10, 45.3)

CE/A11; W/E08 RCS Overcooling - PTS / 4 X 2.1.30 Ability to locate and operate 4.4 27 components, including local controls.

(CFR: 41.7 / 45.7)

K/A Category Point Totals: 3 1 0 0 4 1 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)

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 K1.04 Knowledge of the physical 003 Reactor Coolant Pump X 2.6 28 connections and/or cause-effect relationships between the RCPS and the following systems: CVCS (CFR: 41.2 to 41.9 / 45.7 to 45.8)

K3.02 Knowledge of the effect 003 Reactor Coolant Pump X 3.5 29 that a loss or malfunction of the RCPS will have on the following:

S/G (CFR: 41.7 / 45.6) 004 Chemical and Volume X K6.01 Knowledge of the effect of 3.1 30 Control a loss or malfunction on the following CVCS components:

Spray/heater combination in PZR to assure uniform boron concentration (CFR: 41.7 / 45.7)

K1.11 Knowledge of the physical 005 Residual Heat Removal X 3.5 31 connections and/or causeeffect relationships between the RHRS and the following systems: RWST (CFR: 41.2 to 41.9 / 45.7 to 45.8)

K6.03 Knowledge of the effect of 005 Residual Heat Removal X 2.5 32 a loss or malfunction on the following will have on the RHRS:

RHR heat exchanger (CFR: 41.7 / 45.7)

K5.08 Knowledge of the 006 Emergency Core Cooling X 2.9 33 operational implications of the following concepts as they apply to ECCS: Operation of pumps in parallel (CFR: 41.5 / 45.7)

A3.02 Ability to monitor 006 Emergency Core Cooling X 4.1 34 automatic operation of the ECCS, including: Pumps (CFR: 41.7 / 45.5)

K5.02 Knowledge of the 007 Pressurizer Relief/Quench X 3.1 35 Tank operational implications of the following concepts as the apply to PRTS: Method of forming a steam bubble in the PZR (CFR: 41.5 / 45.7)

A1.02 Ability to predict and/or 007 Pressurizer Relief/Quench X 2.7 36 Tank monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS controls including:

Maintaining quench tank pressure (CFR: 41.5 / 45.5)

K3.02 Knowledge of the effect 008 Component Cooling Water X 2.9 37 that a loss or malfunction of the CCWS will have on the following:

CRDS K4.03 Knowledge of PZR PCS 010 Pressurizer Pressure Control X 3.8 38 design feature(s) and/or interlock(s) which provide for the following: Over pressure control (CFR: 41.7)

K2.01 Knowledge of bus power 012 Reactor Protection X 3.3 39 supplies to the following: RPS channels, components, and interconnections.

(CFR: 41.7)

K6.10 Knowledge of the effect of 012 Reactor Protection X 3.3 40 a loss or malfunction of the following will have on the RPS:

Permissive circuits (CFR: 41.7 / 45/7)

K6.01 Knowledge of the effect of 013 Engineered Safety Features X 2.7 41 Actuation a loss or malfunction on the following will have on the ESFAS: Sensors and detectors (CFR: 41.7 / 45.5 to 45.8)

A4.02 Ability to manually operate 013 Engineered Safety Features X 4.3 42 Actuation and/or monitor in the control room: Reset of ESFAS channels (CFR: 41.7 / 45.5 to 45.8)

A1.03 Ability to predict and/or 022 Containment Cooling X 3.1 43 monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls including:

Containment humidity (CFR: 41.5 / 45.5)

K2.01 Knowledge of bus power 026 Containment Spray X 3.4 44 supplies to the following:

Containment spray pumps (CFR: 41.7)

K1.02 Knowledge of the physical 039 Main and Reheat Steam X 3.3 45 connections and/or cause-effect relationships between the MRSS and the following systems:

Atmospheric relief dump valves (CFR: 41.2 to 41.9 / 45.7 to 45.8)

K4.13 Knowledge of MFW design 059 Main Feedwater X 2.9 46 feature(s) and/or interlock(s) which provide for the following:

Feedwater fill for S/G upon loss of RCPs (CFR: 41.7)

A3.01 Ability to monitor 061 Auxiliary/Emergency X 4.2 47 Feedwater automatic operation of the AFW, including: AFW startup and flows (CFR: 41.7 / 45.5)

K2.01 Knowledge of bus power 062 AC Electrical Distribution X 3.3 48 supplies to the following: Major system loads (CFR: 41.7)

A4.01 Ability to manually operate 063 DC Electrical Distribution X 2.8 49 and/or monitor in the control room: Major breakers and control power fuses (CFR: 41.7 / 45.5 to 45.8)

K1.03 Knowledge of the physical 064 Emergency Diesel Generator X 3.6 50 connections and/or cause effect relationships between the ED/G system and the following systems:

Diesel fuel oil supply system (CFR: 41.2 to 41.9 / 45.7 to 45.8)

K3.01 Knowledge of the effect 073 Process Radiation X 3.6 51 Monitoring that a loss or malfunction of the PRM system will have on the following: Radioactive effluent releases.

(CFR: 41.7 / 45.6)

K4.06 Knowledge of SWS design 076 Service Water X 2.8 52 feature(s) and/or interlock(s) which provide for the following:

Service water train separation (CFR: 41/7)

K1.03 Knowledge of the physical 078 Instrument Air X 3.3 53 connections and/or cause-effect relationships between the IAS and the following systems:

Containment air (CFR: 41.2 to 41.9 / 45.7 to 45.8)

A1.01 Ability to predict and/or 103 Containment X 3.7 54 monitor changes in parameters (to prevent exceeding design limits) associated with operating the containment system controls including: Containment pressure, temperature, and humidity (CFR: 41.5 / 45.5)

A3.01 Ability to monitor 103 Containment X 3.9 55 automatic operation of the containment system, including:

Containment isolation (CFR: 41.7 / 45.5)

K/A Category Point Totals: 5 3 3 3 3 3 3 0 3 2 0 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)

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 A4.13 Ability to manually operate 001 Control Rod Drive X 2.7 56 and/or monitor in the control room:

Stopping other changes in plant, e.g.,

turbine, S/G,SDBCS, boration, before adjusting rods.

(CFR: 41.7/45.5 to 45.8 A3.02 Ability to monitor automatic 002 Reactor Coolant X 2.6 57 operation of the RCS, including:

Containment sound-monitoring system.

(CFR: 41.7 / 45.5)

K5.02 Knowledge of the operational 014 Rod Position Indication X 2.8 58 implications of the following concepts as they apply to the RPIS:

RPIS independent of demand position.

(CFR: 41.5 / 45.7)

A4.04 Ability to manually operate 027 Containment Iodine Removal X 2.8 59 and/or monitor in the control room:

Filter temperature (CFR: 41.7 / 45.5 to 45.8)

A2.03 Ability to (a) predict the 029 Containment Purge X 2.7 60 impacts of the following malfunctions or operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Startup operations and the associated required valve lineups (CFR: 41.5 / 43.5 / 45.3 / 45.13)

A4.02 Ability to manually operate 045 Main Turbine Generator X 2.7 61 and/or monitor in the control room:

T/G controls, including breakers (CFR: 41.7 / 45.5 to 45.8) 2.2.42 Ability to recognize system 055 Condenser Air Removal X 3.9 62 parameters that are entry-level conditions for Technical Specifications.

(CFR: 41.7 / 41.10 / 43.2 / 43.3 / 45.3)

A2.02 Ability to (a) predict the 068 Liquid Radwaste X 2.7 63 impacts of the following malfunctions or operations on the Liquid Radwaste System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Lack of tank recirculation prior to release.

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

K2.03 Knowledge of bus power 075 Circulating Water X 2.6 64 supplies to the following:

Emergency/essential SWS pumps (CFR: 41.7) 2.4.20 Knowledge of the operational 079 Station Air X 3.8 65 implications of EOP warnings, cautions, and notes.

(CFR: 41.10 / 43.5 / 45.13)

K/A Category Point Totals: 0 1 0 0 1 0 0 2 1 3 2 Group Point Total: 10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) - RO Form ES-401-3 Facility: Callaway Date of Exam: January 2011 Category K/A # Topic RO SRO-Only IR # IR #

2.1.4 Knowledge of individual licensed operator 3.3 66 responsibilities related to shift staffing, such as

1. medical requirements, no-solo operation, Conduct maintenance of active license status, 10CFR55, etc.

of Operations (CFR: 41.10 / 43.2) 2.1.34 Knowledge of primary and secondary plant chemistry 2.7 67 limits.

(CFR: 41.10 / 43.5 / 45.12)

Subtotal 2 2.2.17 Knowledge of the process for managing maintenance 2.6 68 activities during power operations, such as risk assessments, work prioritization, and coordination

2. with the transmission system operator.

Equipment (CFR: 41.10 / 43.5 / 45.13)

Control 2.2.21 Knowledge of pre- and post-maintenance operability 2.9 69 requirements.

(CFR: 41.10 / 43.2) 2.2.37 Ability to determine operability and/or availability of 3.6 70 safety related equipment.

(CFR: 41.7 / 43.5 / 45.12)

Subtotal 3 2.3.13 Knowledge of radiological safety procedures 3.4 71 pertaining to licensed operator duties, such as response to radiation monitor alarms, containment

3. entry requirements, fuel handling responsibilities, Radiation access to locked high-radiation areas, aligning filters, Control etc.

(CFR: 41.12 / 43.4 / 45.9 / 45.10) 2.3.15 Knowledge of radiation monitoring systems, such as 2.9 72 fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

(CFR: 41.12 / 43.4 / 45.9)

Subtotal 2 2.4.2 Knowledge of system set points, interlocks and 4.5 73 automatic actions associated with EOP entry

4. conditions.

Emergency (CFR: 41.7 / 45.7 / 45.8)

Procedures /

Plan 2.4.25 Knowledge of fire protection procedures. 3.3 74 (CFR: 41.10 / 43.5 / 45.13)

2.4.47 Ability to diagnose and recognize trends in an 4.2 75 accurate and timely manner utilizing the appropriate control room reference material.

(CFR: 41.10 / 43.5 / 45.12)

Subtotal 3 Tier 3 Point Total 10

ES-401 PWR Examination Outline - SRO Form ES-401-2 Facility: Callaway Date of Exam: January 2011 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 3 3 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 10 1 2 3 4 7 Categories 2 2 1 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).