ML15140A266

2015-05-Final Written Exam Outline

ML15140A266
Person / Time
Site:	Callaway
Issue date:	05/18/2015
From:	Vincent Gaddy Operations Branch IV
To:	Union Electric Co
References
50-483/15-005
Download: ML15140A266 (12)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Date of Exam:

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 2 3 5 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 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).

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 / SRO)

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 Trip - Stabilization - Recovery / 1 000008 Pressurizer Vapor Space Accident / 3 000009 Small Break LOCA / 3 X EA2.13 Ability to determine or interpret 3.6 1 the following as they apply to a small break LOCA:

Charging Pump flow indication (CFR 43.5 / 45.13) 000011 Large Break LOCA / 3 000015/17 RCP Malfunctions / 4 000022 Loss of Rx Coolant Makeup / 2 X 2.4.45 Ability to prioritize and interpret the 4.3 2 significance of each annunciator or alarm.

(CFR: 41.10 / 43.5 / 45.3 / 45.12) 000025 Loss of RHR System / 4 000026 Loss of Component Cooling Water / 8 000027 Pressurizer Pressure Control X AA2.11 Ability to determine and interpret 4.0 3 System Malfunction / 3 the following as they apply to the Pressurizer Pressure Control Malfunctions:

RCS Pressure (CFR: 43.5 / 45.13) 000029 ATWS / 1 000038 Steam Gen. Tube Rupture / 3 000040 (BW/E05; CE/E05; W/E12)

Steam Line Rupture - Excessive Heat Transfer / 4 000054 (CE/E06) Loss of Main Feedwater / 4 000055 Station Blackout / 6 000056 Loss of Off-site Power / 6 X 2.4.41 Knowledge of the emergency action 4.6 4 level thresholds and classifications.

(CFR: 41.10 / 43.5 / 45.11)

000057 Loss of Vital AC Inst. Bus / 6 X AA2.14 Ability to determine and interpret 3.6 5 the following as they apply to the Loss of Vital AC Instrument Bus:

That substitute power sources have come on line on a loss of initial ac.

(CFR: 43.5 / 45.13) 000058 Loss of DC Power / 6 000062 Loss of Nuclear Svc Water / 4 000065 Loss of Instrument Air / 8 W/E04 LOCA Outside Containment / 3 W/E11 Loss of Emergency Coolant Recirc. / 4 BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 000077 Generator Voltage and Electric X 2.2.40 Ability to apply Technical 4.7 6 Grid Disturbances / 6 Specifications for a system.

(CFR: 41.10 / 43.2 / 43.5 / 45.3)

K/A Category Totals: 3 3 Group Point Total: 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 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 Fuel Handling Accident / 8 X AA2.03 Ability to determine and 4.2 7 interpret the following as they apply to the Fuel Handling Incidents:

Magnitude of potential radioactive release.

(CFR: 43.5 / 45.13) 000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 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 000076 High Reactor Coolant Activity / 9 X 2.4.11 Knowledge of abnormal 4.2 8 condition procedures.

(CFR: 41.10 / 43.5 / 45.13)

W/E01 Rediagnosis / 3 W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 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

W/E03 LOCA Cooldown - Depress. / 4 X EA2.1 Ability to determine and 3.4 9 interpret the following as they apply to the (LOCA Cooldown and Depressurization)

Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

(CFR: 43.5 / 45.13)

W/E10 Natural Circulation with Steam Void in X 2.4.46 Ability to verify that the 4.2 10 Vessel with/without RVLIS / 4 alarms are consistent with the plant conditions.

(CFR: 41.10 / 43.5 / 45.3 / 45.12)

BW/E13&E14 EOP Rules and Enclosures CE/A11; W/E08 RCS Overcooling - PTS / 4 CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery K/A Category Point Totals: 2 2 Group Point Total: 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 4 003 Reactor Coolant Pump 004 Chemical and Volume Control 005 Residual Heat Removal 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 010 Pressurizer Pressure Control 012 Reactor Protection X 2.4.30 Knowledge of events 4.1 11 related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

(CFR: 41.10 / 43.5 / 45.11) 013 Engineered Safety Features X A2.05 Ability to (a) predict the 4.2 12 Actuation impacts of the following malfunctions or operations on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; Loss of dc control power (CFR: 41.5 / 43.5 / 45.3 / 45.13) 022 Containment Cooling X 2.1.32 Ability to explain and apply 4.0 13 system limits and precautions.

(CFR: 41.10 / 43.2 / 45.12) 025 Ice Condenser 026 Containment Spray 039 Main and Reheat Steam 059 Main Feedwater 061 Auxiliary/Emergency Feedwater 062 AC Electrical Distribution

063 DC Electrical Distribution X A2.01 Ability to (a) predict the 3.2 14 impacts of the following malfunctions or operations on the DC electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Grounds (CFR: 41.5 / 43.5 / 45.3 / 45.13) 064 Emergency Diesel Generator 073 Process Radiation Monitoring 076 Service Water 078 Instrument Air 2.4.4 Ability to recognize 103 Containment X 4.7 15 abnormal indications for system operating parameters that l are entry-level conditions for emergency and abnormal operating procedures.

(CFR: 41.10 / 43.2 / 45.6)

K/A Category Point Totals: 2 3 Group Point Total: 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 4 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control 014 Rod Position Indication 015 Nuclear Instrumentation X A2.04 Ability to (a) predict the 3.8 18 impacts of the following malfunctions or operations on the NIS; and (b based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Effects on axial flux density of control rod alignment and sequencing, xenon production and decay, and boron vs. control rod reactivity changes (CFR: 41.5 / 43.5 / 45.3 / 45.5) 016 Non-nuclear Instrumentation X A2.01 Ability to (a) predict the 3.1 16 impacts of the following malfunctions or operations on the NNIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Detector failure (CFR: 41.5 / 43.5 / 45.3 / 45.5) 017 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge X 2.1.40 Knowledge of refueling 3.9 17 administrative requirements.

(CFR: 41.10 / 43.5 / 45.13) 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator

041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air 086 Fire Protection K/A Category Point Totals: 2 1 Group Point Total: 3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date of Exam:

Category K/A # Topic RO SRO-Only IR # IR #

2.1.40 Knowledge of refueling administrative requirements. 3.9 19 (CFR: 41.10 / 43.5 / 45.13) 1.

Conduct 2.1.37 Knowledge of procedures, guidelines, or limitations 4.6 20 of Operations associated with reactivity management.

(CFR: 41.1 / 43.6 / 45.6) 2.1.

2.1.

2.1.

2.1.

Subtotal 2 2.2.6 Knowledge of the process for making changes to 3.6 21 procedures.

(CFR: 41.10 / 43.3 / 45.13) 2.

Equipment 2.2.22 Knowledge of limiting conditions for operations and 4.7 22 Control safety limits.

(CFR: 41.5 / 43.2 / 45.2) 2.2.

2.2.

2.2.

2.2.

Subtotal 2 2.3.13 Knowledge of radiological safety procedures 3.8 23 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.

2.3.

2.3.

2.3.

2.3.

Subtotal 1

2.4.21 Knowledge of the parameters and logic used to 4.6 24 assess the status of safety functions, such as

4. reactivity control, core cooling and heat removal, Emergency reactor coolant system integrity, containment Procedures / conditions, radioactivity release control, etc.

Plan (CFR: 41.7 / 43.5 / 45.12)

Ability to take actions called for in the facility 2.4.38 4.4 25 emergency plan, including supporting or acting as emergency coordinator if required.

(CFR: 41.10 / 43.5 / 45.11) 2.4.

2.4.

2.4.

2.4.

Subtotal 2 Tier 3 Point Total 7

ES-401 Record of Rejected K/As Form ES-401-4

• Random Selection method was performed for re-selecting K/As using pennies with dates ending in 0-9. The pennies were drawn in sequence to designate K-1 thru A4, then drawn to pick the number of the K/A in sequence. Pennies 1-9 were drawn from, then 0-9, then 0-9 again.

Generic K/A replacements were drawn from the generic section using the same number selection method. If a K/A could be selected from within the same System and K/A section (ie. A1, K2, etc.) then only the last two numbers were reselected. If a K/A could not be replaced within the same section, then a new section and K/A number were selected within the same system using the method listed above. If a no usable K/A could be selected within the system, then a new system, and K/A was selected from within the Same Tier and Group ensuring no resampling of systems within the Tier and Group unless all Systems were already sampled.

Tier / Randomly Reason for Rejection Group Selected K/A 1/1 000009 EA2.13 000009 EA2.26 Question #1 - Does not apply to this evolution. Random selection of new K/A with the original safety function.

1/1 000027 AA2.11 000027 AA2.12 Question #3 - Does not apply to this evolution. Random selection of new A2 K/A with the original safety function.

1/1 000077 G2.2.40 000077 G2.1.27 Question #6 - Unable to write SRO level question to meet K/A. Random selection from within Generic K/As.

1/2 000076 G2.4.11 W/E01 G2.4.11 Question #8 - Unable to write SRO level question to meet K/A. Randomly selected new safety function but maintained the same Generic K/A.

2/1 G2.4.4 G2.4.1 Question #15 - there are no immediate action steps associated with containment. Random selection from within same Generic Category 4.

2/2 G2.1.40 G2.2.39 Question #17 - One hour Technical Specification are RO knowledge. Random selection from all Generic Categories for the same system.

2/2 015 A2.04 041 A2.02 Question #18 - Previous Exam Overlap. Unable to write another question to K/A and maintain separation. Specifically this K/A was on the 2014 Audit exam. Random selection from within same Tier /

Group.

3 G2.1.40 G2.1.34 Question #19 - Previous Exam Overlap. Unable to write another question to K/A and maintain separation from 2014 NRC and AUDIT exams. Random selection from within same Generic Category 1.

3 G2.2.6 G2.2.5 Question #21 - Previous Exam Overlap. Unable to write another question to K/A and maintain separation from 2014 NRC and AUDIT exams. Random selection from within same Generic Category 2.

3 G2.4.38 G2.4.22 Question #25 - Overlap with other tier 3 Category 4 with this exam (Question #24). Random selection from within same Generic Category 4.