ML13114A774
| ML13114A774 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 04/29/2013 |
| From: | Mcneil D NRC/RGN-III/DRS/OLB |
| To: | Exelon Generation Co |
| References | |
| ES-401-2, 50-454/13-301, 50-455/13-301 | |
| Download: ML13114A774 (6) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: Byron Nuclear Station Date of Exam: 04/29/2013 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G* Total A2 G* Total 1 2 3 4 5 6 1 2 3 4
- 1. 1 3 3 3 3 3 3 18 3 3 6 Emergency
& Abnormal 2 1 2 1 N/A 1 2 N/A 2 9 2 2 4 Plant Evolutions Tier 4 5 4 4 5 5 27 5 5 10 Totals 1 3 2 3 3 2 2 3 3 2 2 3 28 3 2 5 2.
Plant 2 1 1 1 1 1 1 1 1 1 1 0 10 0 2 1 3 Systems Tier 4 3 4 4 3 3 4 4 3 3 3 38 5 3 8 Totals 1 2 3 4 1 2 3 4
- 3. Generic Knowledge and Abilities 10 7 Categories 2 3 3 2 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 ATier 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 that are not included on the outline should be added. Refer to ES-401, Attachment 2, 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.
- 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. 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 G K/A Topic(s) IR #
1 2 3 1 2 000007 (CE/E02) Reactor Trip - 0 Actions contained in EOP for reactor trip 4.0 29 Stabilization - Recovery / 1 1 000008 Pressurizer Vapor Space Accident 0 Sensors and detectors 2.7 30
/3 2 2.01.31 Ability to locate control room switches, controls, and 4.6 31 indications, and to determine that they correctly reflect the 000009 Small Break LOCA / 3 S R desired plant lineup.
3.4 79 A2.15 RCS parameters 0
000011 Large Break LOCA / 3 Natural circulation and cooling, including reflux boiling 4.1 32 1
0 000015/17 RCP Malfunctions / 4 RCP indicators and controls 2.8 33 1
0 000022 Loss of Rx Coolant Makeup / 2 CVCS Charging pump ammeters and running indicators 2.9 34 6
1 000025 Loss of RHR System / 4 RCS Temperature indicators 3.6 35 2
000026 Loss of Component Cooling Water 0 The normal values and upper limits for the temperatures of the 2.5 36
/8 4 components cooled by CCW 000027 Pressurizer Pressure Control S A2.04 Tech-Spec limits for RCS pressure 4.3 76 System Malfunction / 3 0
000029 ATWS / 1 Reactor nuclear instrumentation 4.4 37 1
2.2.22 Knowledge of limiting conditions for operations and 000038 Steam Gen. Tube Rupture / 3 S 4.7 77 safety limits 000040 (CE/E05) Steam Line Rupture -
S A2.03 Difference between steam line rupture and LOCA 4.7 78 Excessive Heat Transfer / 4 Annunciators and conditions indicating signals, and remedial WE12 Uncontrolled Depressurization of all 0 actions associated with the Uncontrolled Depressurization of 3.4 38 Steam Generators / 4 3 all Steam Generators 000054 (CE/E06) Loss of Main Feedwater 0 HPI/PORV cycling upon total feedwater loss 4.6 39
/4 5 000055 Station Blackout / 6 2.4.02 Knowledge of system setpoints, interlocks, and 000056 Loss of Off-site Power / 6 x 4.5 40 automatic actions associated with EOP entry conditions 1 The plant automatic actions that will occur on the loss of a vital 000057 Loss of Vital AC Inst. Bus / 6 4.0 41 9 ac electrical instrument bus 2.4.32 Knowledge of operator response to loss of all 000058 Loss of DC Power / 6 S 4.0 80 annunciators 2.4.23 Knowledge of the bases for prioritizing emergency 000062 Loss of Nuclear Svc Water / 4 S 4.4 81 procedure implementation during emergency operations 0 Restoration of systems served by instrument air when 000065 Loss of Instrument Air / 8 2.9 42 3 pressure is regained W/E04 LOCA Outside Containment / 0 Normal, abnormal, and emergency operating procedures 3.5 43 3 2 associated with LOCA Outside Containment W/E11 Loss of Emergency Coolant 2.4.13 Knowledge of crew roles and responsibilities during x 4.0 44 Recirc. / 4 EOP usage.
BW/E04, W/E05 Inadequate Heat Components, and functions of control and safety systems, 0
Transfer - Loss of Secondary Heat 1 including instrumentation, signals, interlocks, failure modes, 3.6 45 Sink / 4 and automatic and manual features 000077 Generator Voltage and 0 Actions contained in abnormal operating procedure for voltage 3.6 46 Electric Grid Disturbances / 6 2 and grid disturbances 3 3 K/A Category Totals: 3 3 3 3 / / Group Point Total: 18/6 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 Proper actions to be taken if automatic safety functions 000001 Continuous Rod Withdrawal / 1 4.5 47 3 have not taken place 000003 Dropped Control Rod / 1 2.1.37 Knowledge of procedures, guidelines, or 000005 Inoperable/Stuck Control Rod / 1 R 4.3 48 limitations associated with reactivity management 000024 Emergency Boration / 1 0
000028 Pressurizer Level Malfunctions / 2 Charging subsystem flow indicator and controller 2.8 53 3
000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 0 Radiation monitoring equipment (portable and 000036 Fuel Handling Accident / 8 3.4 49 2 installed) 000037 Steam Generator Tube Leak / 3 S A2.10 Tech-Spec limits for RCS leakage 4.1 82 000051 Loss of Condenser Vacuum / 4 0
000059 Accidental Liquid RadWaste Rel. / 9 Radioactive-liquid monitor 3.5 50 1
000060 Accidental Gaseous Radwaste Rel. / 9 0 Guidance contained in alarm responses for ARM 000061 APRM System Alarms / 7 3.4 51 2 system 2.4.49 Ability to perform without reference to 000068 (BW/A06) Control Room Evac / 8 S procedures those actions that require immediate 4.4 83 operation of system 000069 (W/E14) Loss of CTMT Integrity / 5 0
000074 Inad. Core Cooling / 4 Definition of superheated steam 3.0 52 6
000076 High Reactor Coolant Activity / 9 S A2.03 RCS radioactivity level meter 3.0 85 2.4.46 Ability to verify that the alarms are consistent W/E02 SI Termination / 3 R 4.2 55 with the plant conditions 2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity W/E07 Saturated Core Cooling / 4 S control, core cooling and heat removal, reactor coolant 4.6 84 system integrity, containment conditions, radioactivity release control, etc.
Components, and functions of control and safety 0
W/E16 High Containment Radiation / 9 systems, including instrumentation, signals, interlocks, 3.0 54 1
failure modes, and automatic and manual features 2 2 K/A Category Point Totals: 1 2 1 1 / / Group Point Total: 9/4 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 RCPs; Problems associated with RCP motors; 3.1 1 0 0 003 Reactor Coolant Pump including faulty motors and current, and winding 1 3 and bearing temperature problems 2.7 5 1 K5.15 Boron and control rod reactivity effects as 004 Chemical and Volume Control 3.3 2 5 they relate to MTC RHR valve malfunction; 2.1.7 Ability to evaluate 2.9 3 0 plant performance and make operational 005 Residual Heat Removal R 4 judgments based on operating characteristics, 4.4 4 reactor behavior, and instrument interpretation.
4.1 6 0
006 Emergency Core Cooling S Pumps; A2.11 Rupture of ECCS header 1
4.4 86 007 Pressurizer Relief/Quench 0 Overpressurization of the PZR 3.6 7 Tank 3 0
008 Component Cooling Water CCW flow rate 2.8 8 1
3.6 9 0 0 010 Pressurizer Pressure Control RCS; PZR spray valve 3 1 3.7 10 2.8 11 0 Bistables and bistable test equipment 012 Reactor Protection S 1 G. 2.2.14 4.3 87 013 Engineered Safety Features 0 RCS 4.3 12 Actuation 2 2.9 13 0
022 Containment Cooling S Chilled Water A202: Fan motor vibration 4
2.6 88 Containment Spray Pumps; G 2.2.22, 3.4 14 0
026 Containment Spray x Knowledge of limiting conditions for operations 1
and safety limits 4.0 15 0
039 Main and Reheat Steam Effect of steam removal on reactivity 3.6 16 8
3.6 17 0 0 059 Main Feedwater AFW System; Turbine driven feed pump 2 4 2.5 18 061 Auxiliary/Emergency 0 Controllers and positioners 2.5 19 Feedwater 1 Uninterruptable ac power sources 3.1 20 1 G 2.2.42: Ability to recognize system parameters 062 AC Electrical Distribution S 0 that are entry-level conditions for Technical Specifications 4.6 89 2.7 21 Manual/automatic transfers of control; 0 0 063 DC Electrical Distribution Meters, annunciators, dials, recorders, and 1 1 indicating lights 2.7 22 0 Maintaining minimum load on ED/G (to prevent 064 Emergency Diesel Generator 3.1 23 8 reverse power) 0 073 Process Radiation Monitoring Radioactive effluent releases 3.6 24 1
G 2.2.15 Service water train separation; Ability to 2.8 25 0 determine the expected plant configuration using 076 Service Water R 6 design and configuration control documentation, 3.9 26 such as drawings, line-ups, tag-outs, etc.
0 078 Instrument Air Service Air 2.7 27 2
Containment pressure, temperature, and humidity 3.7 28 0
103 Containment S A2.02: Necessary plant conditions for work in 1
containment 3.2 90 3 3 K/A Category Point Totals: 3 2 3 3 2 2 3 / 2 2 / Group Point Total: 28/5 3 2
ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (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 0 3.
001 Control Rod Drive RCS 56 2 4 002 Reactor Coolant 0 2.
014 Rod Position Indication Re-zeroing of rod position prior to startup 59 4 7 015 Nuclear Instrumentation 3.
016 Non-nuclear Instrumentation S A2.01 Detector failure 91 1
0 3.
017 In-core Temperature Monitor Temperature at which cladding and fuel melt 57 1 1 0 3.
027 Containment Iodine Removal Fans 58 1 1 033 Spent Fuel Pool Cooling 0 2.
034 Fuel Handling Equipment Radiation Monitoring Systems 60 2 6 4.
035 Steam Generator S A2.06: Small Break LOCA 93 6
041 Steam Dump / Turbine Bypass 0 Relationship of low/low T-ave. setpoint in 3.
61 Control 3 SDS to primary cooldown 0 G 2.4.27: Knowledge of fire in the palnt 3.
045 Main Turbine Generator S 92 procedures 9 0 2.
056 Condensate Loss of condensate pumps 63 4 6 0 Radiation monitoring system alarm and 3.
071 Waste Gas Disposal 62 3 actuating signals 6 0 2.
075 Circulating Water SWS 064 1 5 079 Station Air 0 2.
086 Fire Protection Fire header pressure 65 1 9 K/A Category Point Totals: 1 1 1 1 1 1 1 2 1 1 0 Group Point Total: 10/3
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Palisades Nuclear Plant Date of Exam: 02/ 26/2013 RO SRO-Only Category K/A # Topic IR # IR #
Ability to use procedures related to shift staffing, such as 2.1.05 minimum crew complement, overtime limitations, etc.
3.9 94 2.1.06 Ability to manager the control room crew during plant transients 3.8 66 1.
Ability to perform specific system and integrated plant procedures Conduct 2.1.23 during all modes of plant operation.
4.4 95 of Operations 2.1.40 Knowledge of refueling administrative requirements 2.8 67 Subtotal 2 2 Ability to explain the variations in control board layouts, systems, 2.2.04 instrumentation, and procedural actions between units at a facility 3.6 68 2.2.20 Knowledge of the process for managing troubleshooting activities 3.8 96
- 2. Knowledge of the bases in Technical Specifications for limiting Equipment 2.2.25 conditions for operations and safety limits 4.2 97 Control Ability to analyze the effect of maintenance activities, such as 2.2.36 degraded power sources, on the status of limiting conditions for 3.1 69 operations Subtotal 2 2 Knowledge of radiation exposure limits under normal or 2.3.04 emergency conditions 3.7 98 Ability to comply with radiation work permit requirements during 2.3.07 normal or abnormal conditions.
3.5 71 2.3.11 Ability to control radiation releases 4 4.3 99
- 3. Knowledge of radiological safety procedures pertaining to Radiation licensed operator duties, such as response to radiation monitor Control 2.3.13 alarms, containment entry requirements, fuel handling 3.4 72 responsibilities, access to locked high-radiation areas, aligning filters, etc Knowledge of radiation or contamination hazards that may arise 2.3.14 during normal, abnormal, or emergency conditions or activities 3.4 73 Subtotal 3 2 2.4.11 Knowledge of abnormal condition procedures. 4.2 100 Knowledge of EOP implementation hierarchy and coordination
- 4. 2.4.16 with other support procedures or guidelines such as, operating 3.5 74 Emergency procedures, abnormal operating procedures, and severe accident Procedures / management guidelines.
Plan 2.4.32 Knowledge of operator response to loss of all annunciators. 3.6 75 Subtotal 2 1 Tier 3 Point Total 10 7