ML14328A749

2015 Point Beach Nuclear Power Plant Initial License Examination Forms ES-401-2 and ES-401-3

ML14328A749
Person / Time
Site:	Point Beach
Issue date:	03/06/2015
From:	Mcneil D NRC/RGN-III/DRS/OLB
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ML14328A659	List: ML14328A667 ML14328A684 ML14328A687 ML14328A722 ML14328A725 ML14328A730 ML14328A749 ML14328A763
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Download: ML14328A749 (8)

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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 3 3 3 3 3 3 18 3 3 6 Emergency &

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

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

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

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 K/A Topic(s)

G IR #

1 2 3 1 2 000007 Reactor Trip - Stabilization -

Recovery / 1 000008 Pressurizer Vapor Space 0 Controllers and positioners 2.5 1 Accident / 3 3 000009 Small Break LOCA / 3 000011 Large Break LOCA / 3 R: Verifying Main Steam Isolation Valve position 0 3.4 2 S S: A2.01Actions to be taken, based on RCS 1 4.7 76 temperature and pressure saturated and superheated 000022 Loss of Rx Coolant Makeup / 0 PZR level trend 3.2 3 2 3 000026 Loss of Component Cooling R: The length of time after the loss of CCW Water / 8 flow to a component before that component 0 2.8 4 S may be damaged 6 4.5 77 S: 2.2.38: Knowledge of conditions and limitations in the facility license 000029 ATWS / 1 2.1.20: Ability to interpret and execute R 4.6 5 procedure steps 000038 Steam Gen. Tube Rupture / 0 Use of steam tables 3.1 6 3 1 000040 (W/E12) Steam Line Components, capacity, and function of Rupture - Uncontrolled 0 emergency systems 3.4 7 Depressurization of all Steam S 1 S: A2.04: Conditions requiring ESFAS 4.7 78 Generators / 4 initiation 000054 (CE/E06) Loss of Main 2.2.36: Ability to analyze the effect of Feedwater / 4 maintenance activities, such as degraded R 3.1 8 power sources on the status of limiting conditions for operations.

000055 Station Blackout / 6 2.2.4: Ability to explain the variations in control R board layouts, systems, instrumentation, and 3.6 9 procedural actions between units at a facility.

000056 Loss of Off-site Power / 6 Order and time to initiation of power for the load sequencer S: 2.4.21: Knowledge of the parameters and 3.5 10 0 logic used to assess the status of safety S

1 functions, such as reactivity control, core 4.6 79 cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

000057 Loss of Vital AC Inst. Bus / 6 0 Actions contained in EOP for loss of vital AC 4.1 11 1 electrical instrument bus 000058 Loss of DC Power / 6 0 Cross-tie of the affected dc bus with the 3.4 12 1 alternate supply

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 K/A Topic(s)

G IR #

1 2 3 1 2 000062 Loss of Nuclear Svc Water / Flow rates to the components and systems 0

4 that are serviced by the SWS: interactions 3.8 13 7

among the components 000065 Loss of Instrument Air / 8 0 Whether backup nitrogen supply is controlling 2.8 14 7 valve position 000065 Loss of Instrument Air / 8 S: A2.04: Typical conditions which could S cause a compressor trip (e.g. high 2.7 80 temperature)

W/E04 LOCA Outside Containment / Adherence to appropriate procedures and 0

3 operation within the limitations in the facilitys 3.6 15 2

license and amendments.

W/E11 Loss of Emergency Coolant Components, and functions of control and Recirc. / 4 0 safety systems, including instrumentation, 3.6 16 1 signals, interlocks, failure modes, and automatic and manual features BW/E04; W/E05 Inadequate Heat Facilitys heat removal systems, including Transfer - Loss of Secondary Heat primary coolant, emergency coolant, the 0

Sink / 4 decay heat removal systems, and relations 3.9 17 2

between the proper operation of these systems to the operation of the facility.

000077 Generator Voltage and R: Over-excitation Electric Grid Disturbances / 6 0 S: 2.4.47: Ability to diagnose and recognize 3.3 18 S trends in an accurate and timely manner 2 4.2 81 utilizing the appropriate control room reference material K/A Category Totals: 3 3 Group Point Total: 18/

3 3 3 3 / / 6 3 3

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

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

1 2 3 1 2 0

000001 Continuous Rod Withdrawal / 1 Rod bank step counters 2.9 19 1

0 Actions contained in EOP for 000005 Inoperable/Stuck Control Rod / 1 3.9 20 6 inoperable/stuck control rod 000024 Emergency Boration / 1 S S: A2.06 3.7 82 0

000028 Pressurizer Level Malfunction / 2 Checking of RCS leaks 3.3 21 6

1 Maximum allowable channel 000033 Loss of Intermediate Range NI / 7 2.5 22 2 disagreement S: 2.1.23: Ability to perform specific 000036 Fuel Handling Accident / 8 S system and integrated plant procedures 4.4 83 during all modes of plant operation 2.4.1: Knowledge of EOP entry 000037 Steam Generator Tube Leak / 3 R 4.6 23 conditions and immediate action steps Types of radiation, their units of 0

000059 Accidental Liquid RadWaste Rel. / 9 intensity and the location of the sources 2.7 24 1

of radiation in a nuclear power plant Adherence to appropriate procedures 0

W/E13 Steam Generator Over-pressure / 4 and operation within the limitations in 3.0 25 2

the facility license and amendments S: A2.01: Facility conditions and 0 selection of appropriate procedures W?E15 Containment Flooding / 5 3.2 84 1 during abnormal and emergency operations 2.1.30: Ability to locate and operate W/E16 High Containment Radiation / 9 R 4.4 26 components, including local controls Annunciators and conditions indicating 0 signals, and remedial actions BW/A02&A03 Loss of NNI-X/Y / 7 3.3 27 3 associated with the Natural Circulation Operations S; 2.2.25: Knowledge of the bases in Technical Specifications for limiting W/E08 RCS Overcooling - PTS / 4 S 4.2 85 conditions for operations and safety limits 2 2 Group Point Total: 9/4 K/A Category Point Totals: 2 1 1 1 / /

2 2

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

K K K K K K A A A A K/A Topic(s)

System # / Name G IR #

1 2 3 4 5 6 1 2 3 4 Starting requirements 1 2.6 28 003 Reactor Coolant Pump S S: 2.4.45: Ability to prioritize and 4 interpret the significance of each 4.3 86 annunciator or alarm 004 Chemical and Volume 3 Boron loading of demineralizer resin 2.9 29 Control 7 Detection of and response to 0

005 Residual Heat Removal presence of water in RHR 3.3 30 5

emergency sump 0 Boron concentration in accumulator, 006 Emergency Core Cooling 3.0 31 2 boron storage tanks 007 Pressurizer Relief/Quench 0 Exceeding PRT high-pressure limits 3.2 32 Tank 5 007 Pressurizer Relief/Quench A2.01: Stuck-open PORV or code S 4.2 87 Tank safety 008 Component Cooling 0 Loss of CCW pump 3.3 33 Water 1 010 Pressurizer Pressure 0 PZR pressure 3.6 34 Control 2 0 0 Trip logic 3.7 35 012 Reactor Protection 6 5 Channel defeat controls 3.6 36 Reset of ESFAS channels 013 Engineered Safety 0 S: 2.4.35: Knowledge of local 4.3 37 S auxiliary operator tasks during an Features Actuation 2 4.0 88 emergency and the resultant operational effects Valves in the CCS 0 3.1 38 022 Containment Cooling x 2.2.22: Knowledge of limiting 4 conditions for operations and safety 4.0 39 limits 2.2.39: Knowledge of less than or 026 Containment Spray x equal to one hour Tech Specs 3.9 40 action statements for systems T/G 0 2.5 41 039 Main and Reheat Steam x Ability to verify that the alarms are 5 4.2 42 consistent with the plant conditions S/Gs 0 3.1 43 059 Main Feedwater S S: A2.05: Rupture in MFW suction 3 3.4 89 or discharge line

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

K K K K K K A A A A K/A Topic(s)

System # / Name G IR #

1 2 3 4 5 6 1 2 3 4 AFW electric driven pumps 061 Auxiliary/Emergency 0 0 3.7 44 Feedwater 2 5 Feed line voiding and water 2.7 45 hammer 0

062 AC Electrical Distribution Major system loads 3.3 46 1

0 0 Major DC loads 2.9 47 063 DC Electrical Distribution 1 1 EDG 3.7 48 064 Emergency Diesel 0 ESFAS controlled or actuated 4.2 49 Generator 2 systems Release termination when radiation exceeds setpoint 4.0 50 073 Process Radiation 0 0 S Radiation theory, including sources, 2.5 51 Monitoring 1 1 types, units, and effects 2.9 90 S: A2.03: Calibration drift 0 ESFAS controlled or actuated 076 Service Water 4.2 52 2 systems MSIV air 0 0 3.4 53 078 Instrument Air Manual/automatic transfers of 5 1 2.7 54 control 0 Loss of containment integrity under 103 Containment 3.3 55 1 shutdown conditions K/A Category Point Totals: Group Point Total: 28 2 3 3 3 3 3 2 2 2 / 2 3 / /

3 2 5

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

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

1 2 3 4 5 6 1 2 3 4 0 Reactor trip breakers, including 001 Control Rod Drive 3.7 56 5 controls 002 Reactor Coolant S: 2.1.32: Ability to explain and apply 011 Pressurizer Level Control S 4.0 91 system limits and precautions 0

014 Rod Position Indication VCT level 2.8 57 3

016 Non-nuclear Subcritical multiplication and NIS 3.4 58 Instrumentation indications 017 In-core Temperature S S: A2.02: Core damage 4.1 92 Monitor 0

029 Containment Purge CPS isolation 3.8 59 1

033 Spent Fuel Pool Cooling R: 2.1.28: Knowledge of the purpose and function of major system 4.1 60 034 Fuel Handling Equipment S R components and controls 3.9 93 S: A2.02: Dropped cask 035 Steam Generator 041 Steam Dump/Turbine 0 RCS 3.5 61 Bypass Control 5 045 Main Turbine Generator 0

055 Condenser Air Removal Main condenser 2.5 62 1

056 Condensate 0

068 Liquid Radwaste Automatic isolation 3.8 63 4

071 Waste Gas Disposal 0

072 Area Radiation Monitoring Plant ventilation systems 3.2 64 3

075 Circulating Water 0

079 Station Air Cross-connection with IAS 2.9 65 1

086 Fire Protection K/A Category Point Totals: Group Point Total: 10 1 1 1 0 1 1 1 1 1 / 1 1 / /

2 1 3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Point Beach U1/U2 Date of Exam: 02/23/2015 RO SRO-Only Category K/A # Topic IR # IR #

Ability to use procedures related to shift staffing, such as 2.1.5 2.9 66 minimum crew complement, overtime limitations, etc Knowledge of procedures and limitations involved in core 2.1.36 3.0 67 alterations 1.

Ability to identify and interpret diverse indications to validate Conduct of 2.1.45 4.3 68 the response of another indicator.

Operations Knowledge of operator responsibilities during all modes of 2.1.2 4.4 94 plant operation 2.1.35 Knowledge of the fuel-handling responsibilities of SROs 3.9 95 Subtotal 3 2 Ability to perform pre-startup procedures for the facility, 2.2.1 including operating those controls associated with plant 4.5 69 equipment that could affect reactivity

2. Ability to manipulate the console controls as required to Equipment 2.2.2 operate the facility between shutdown and designated power 4.6 70 Control levels 2.2.35 Ability to determine Technical Specification Mode of Ops 3.6 71 2.2.19 Knowledge of maintenance work order requirements 3.4 96 Subtotal 3 1 Ability to comply with radiation work permit requirements 2.3.7 3.5 72 during normal or abnormal conditions Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry 2.3.12 3.2 73 requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.

3. Knowledge of radiological safety procedures pertaining to Radiation licensed operator duties, such as response to radiation Control 2.3.13 monitor alarms, containment entry requirements, fuel handling 3.8 97 responsibilities, access to locked high radiation areas, aligning filters, etc.

Knowledge of radiation or contamination hazards that may 2.3.14 arise during normal, abnormal, or emergency conditions or 3.8 98 activities.

Subtotal 2 2 Knowledge of the operational implications of EOP warnings, 2.4.20 3.8 74 cautions, and notes Knowledge of RO responsibilities in emergency plan

4. 2.4.39 3.9 75 implementation Emergency Procedures Ability to take actions called for in the facility emergency plan, 2.4.38 4.4 99

/ Plan including acting as emergency coordinator If required.

Knowledge of SRO responsibilities in emergency plan 2.4.40 4.5 100 implementation Subtotal 2 2 Tier 3 Point Total 10 7