ML13039A465
| ML13039A465 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/17/2012 |
| From: | NRC/RGN-III |
| To: | Florida Power & Light Energy Point Beach |
| Zoia, Charles | |
| Shared Package | |
| ML11354A218 | List: |
| References | |
| Download: ML13039A465 (10) | |
Text
ES-401PWR Examination OutlineFORM ES-401-2Facility Name:Point Beach Nuclear Plant Date of Exam:December 3, 2012 K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G *TotalTotal 1 3 2 3 4 3 3 18 6 2 2 2 2 1 1 1 9 4Tier Totals 5 4 5 5 4 4 27 10 1 3 3 3 3 2 2 3 3 2 2 2 28 5 2 1 1 1 1 1 0 1 1 1 1 1 10 0 1 3Tier Totals 4 4 4 4 3 2 4 4 3 3 3 38 8 1 2 3 4 1 2 2 2Note: 1.Note: 2.Note: 3.Note: 4.Note: 5.Note: 6.Note: 7.*Note: 8.Note: 9.ES-401, 22 of 34 2 3 3 5 3The 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.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 Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.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).
3 2 4 2 3Select 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.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.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.Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.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.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.TierGroupSRO-Only PointsRO K/A Category Points A 2 G *3. Generic Knowledge and Abilities Categories 1 7 10 2 3 2 5 2 2 32. Plant Systems1. Emergency
& Abnormal Plant Evolutions 5N/AN/A ES-401 2Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)
IR#1000007 Reactor Trip - Stabilization - Recovery / 1 0 2Breakers, relays and disconnects2.6 1 2000008 Pressurizer Vapor Space Accident / 3 0 6Control of PZR level3.6 1000009 Small Break LOCA / 3 0000011 Large Break LOCA / 3 0000015 RCP Malfunctions / 4000017 RCP Malfunctions (Loss of RC Flow) / 4 000022 Loss of Rx Coolant Makeup / 2 0000025 Loss of RHR System / 4 0 3000026 Loss of Component Cooling Water / 8 0 3Guidance actions contained in EOP for Loss of CCW 4 1 4000027 Pressurizer Pressure Control System Malfunction / 3 0 4Pressure recovery, using emergency-only heaters3.9 1 5000029 ATWS / 1 0
1Reactor nuclear instrumentation4.4 1 6000038 Steam Gen. Tube Rupture / 302.38Knowledge of conditions and limitations in the facility license.3.6 1000040 Steam Line Rupture - Excessive Heat Transfer
/ 4 7WE12 Uncontrolled Depressurization of all Steam Generators / 4 0 1Components:, capacity, and function of emergency systems3.4 8000054 (CE/E06) Loss of Main Feedwater / 4 0
2Matching of feedwater and steam flows3.4 1 9000055 Station Blackout / 6 0
7Restoration of power from offsite4.3 110000056 Loss of Off-site Power / 6 0
5Operational status of HVAC chill water pump2.6 111000057 Loss of Vital AC Inst. Bus / 604.04Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.4.5 112000058 Loss of DC Power / 6 0
1Battery charger equipment and instrumentation2.8 113000062 Loss of Nuclear Svc Water / 4 0
2The automatic actions (alignments) within the nuclear service water resulting from the actuation of the ESFAS3.6 114000065 Loss of Instrument Air / 8 0 3Restoration of systems served by instrument air when pressure is regained2.9 115W/E04 LOCA Outside Containment / 3 0 1Facility conditions and selection of appropriate procedures during abnormal and emergency operations3.4 116W/E11 Loss of Emergency Coolant Recirc. / 402.37Ability to determine operability and/or availability of safety related equipment.3.6 117BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 0 1Components, capacity, and function of emergency systems3.8 118000077 Generator Voltage and ElectricGrid Disturbances / 6 0 3Sensors, detectors, indicators3.0 1K/A Category Totals:
3 2 3 4 3 318ES-401, 23 of 34Group Point Total:
0 1 ES-401 3Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)
Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)
IR#000001 Continuous Rod Withdrawal / 1 0 19000003 Dropped Control Rod / 1 07Tech-Spec limits for T-ave3.8 1000005 Inoperable/Stuck Control Rod / 1 0000024 Emergency Boration / 1 0 20000028 Pressurizer Level Malfunction / 2 03RCP and seal water system2.9 1 21000032 Loss of Source Range NI / 7 05Nature of abnormality, from rapid survey of control room data2.9 1 22000033 Loss of Intermediate Range NI / 7 04.45Ability to prioritize and interpret the significance of each annunciator or alarm.4.1 1000036 Fuel Handling Accident / 8 0 23000037 Steam Generator Tube Leak / 3 01Use of steam tables2.9 1000051 Loss of Condenser Vacuum / 4 0000059 Accidental Liquid RadWaste Rel. / 9 0000060 Accidental Gaseous Radwaste Rel. / 9 0 24000061 ARM System Alarms / 7 01Detectors at each ARM system location2.5 1000067 Plant Fire On-site / 8 0000068 Control Room Evac. / 8 0000069 Loss of CTMT Integrity / 5 25W/E14 High Containment Pressure / 5 04RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated3.3000074 Inad. Core Cooling / 4W/E06 Degraded Core Cooling / 4 W/E07 Saturated Core Cooling / 4 000076 High Reactor Coolant Activity / 9 0W/E01 Rediagnosis / 3 W/E02 SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 0 26W/E15 Containment Flooding / 5 01Components, capacity, and function of emergency systems2.8 1 27W/E16 High Containment Radiation / 9 02Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility2.6 1W/E03 LOCA Cooldown - Depress. / 4 0W/E09 Natural Circulation Operations / 4W/E10 Natural Circulation with Steam Voide in Vessel with/without RVLIS. / 4W/E08 RCS Overcooling - PTS / 4 0K/A Category Totals:
2 2 2 1 1 1 9ES-401, 24 of 34Group Point Total:
0 0 1 0 ES-401 4Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2/Group 1 (RO)
Q#System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)
IR#28003 Reactor Coolant Pump 04Effects of RCP shutdown on secondary parameters, such as steam pressure, steam flow, and feed flow3.2 1 29004 Chemical and Volume Control 2 0Function of demineralizer, including boron loading and temperature limits2.5 1 30005 Residual Heat Removal 0 2RHR flow rate3.3 1 31006 Emergency Core Cooling 0
8Effect of electric power loss on valve position 3 1 32007 Pressurizer Relief/Quench Tank 0
1Components which discharge to the PRT2.7 1 33008 Component Cooling Water 0 2Filling and draining operations of the CCWS including the proper venting of the components2.5 1 34010 Pressurizer Pressure Control 01.23Ability to perform specific system and integrated plant procedures during all modes of plant operation.4.3 1 35012 Reactor Protection 0 8MFW2.9 1 36013 Engineered Safety Features Actuation 0 1ESFAS/safeguards equipment control3.6 1 37022 Containment Cooling 0
2Containment instrumentation readings 3 1025 Ice Condenser 0 38026 Containment Spray 0 1Source of water for CSS, including recirculation phase after LOCA4.2 139,40039 Main and Reheat Steam 0 1 0 5S/G; Bases for RCS cooldown limits3.1; 2.7 241,42059 Main Feedwater 0
4 0 3RCS; Power level restrictions for operation of MFW pumps and valves3.6; 2.7 243,44061 Auxiliary/Emergency Feedwater 0 9 0 7Cross-ties between multi-unit station; Air or MOV failure3.7; 3.4 245,46062 AC Electrical Distribution 0
1 0 5Significance of D/G load limits; Safety-related indicators and controls3.4; 3.5 247,48063 DC Electrical Distribution 0 1 0 3Major DC loads; Battery discharge rate2.9; 3 249,50064 Emergency Diesel Generator 0 8 04.30Fuel oil storage tanks; Knowledge of events 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.3.2; 2.7 251,52073 Process Radiation Monitoring 0 1 0 2Those systems served by PRMs; Detector failure3.6; 2.7 2 53076 Service Water 0
4Reactor building closed cooling water2.5 1 54078 Instrument Air 0
2Systems having pneumatic valves and controls3.4 1 55103 Containment 0
6Containment isolation system3.1 1 0K/A Category Totals:
3 3 3 3 2 2 3 3 2 2 2 28ES-401, Page 25 of 34Group Point Total:
ES-401 5Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2/Group 2 (RO)
Q#System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)
IR#56001 Control Rod Drive 0 1One-line diagram of power supply to M/G sets3.5 1002 Reactor Coolant 0011 Pressurizer Level Control 0 57014 Rod Position Indication 0
2NIS 3 1015 Nuclear Instrumentation 0 58016 Non-nuclear Instrumentation 0
3Input to control systems2.8 1017 In-core Temperature Monitor 0027 Containment Iodine Removal 0028 Hydrogen Recombiner and Purge Control 0 59029 Containment Purge 0 3Containment pressure, temperature, and humidity 3 1033 Spent Fuel Pool Cooling 0034 Fuel Handling Equipment 0 60035 Steam Generator 0
3Shrink and swell concept2.8 1041 Steam Dump/Turbine Bypass Control 0045 Main Turbine Generator 0 61055 Condenser Air Removal 0
1Main condenser2.5 1056 Condensate 0 62068 Liquid Radwaste 0
2Lack of tank recirculation prior to release2.7 1071 Waste Gas Disposal 0 63072 Area Radiation Monitoring 0
1Changes in ventilation alignment2.9 1075 Circulating Water 0 64079 Station Air 0
1Cross-tie valves with IAS2.7 1 65086 Fire Protection04.35Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.3.8 1K/A Category Totals:
1 1 1 1 1 0 1 1 1 1 110ES-401, Page 26 of 34Group Point Total:
ES-401 2Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)
Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)
IR#000007 Reactor Trip - Stabilization - Recovery / 1 0000008 Pressurizer Vapor Space Accident / 3 0000009 Small Break LOCA / 3 0000011 Large Break LOCA / 3 0000015 RCP Malfunctions / 4000017 RCP Malfunctions (Loss of RC Flow) / 4000022 Loss of Rx Coolant Makeup / 2 0000025 Loss of RHR System / 4 076000026 Loss of Component Cooling Water / 8 0 2The cause of possible CCW loss3.6 1000027 Pressurizer Pressure Control System Malfunction / 3 077000029 ATWS / 104.09Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.4.2 178000038 Steam Gen. Tube Rupture / 3 0 7Plant conditions, from survey of control room indications4.8 1000040 Steam Line Rupture - Excessive Heat Transfer
/ 4WE12 Uncontrolled Depressurization of all Steam Generators / 479000054 (CE/E06) Loss of Main Feedwater / 402.40Ability to apply Technical Specifications for a system.4.7 1000055 Station Blackout / 6 080000056 Loss of Off-site Power / 6 2 1ED/G frequency and voltage indicators3.8 1000057 Loss of Vital AC Inst. Bus / 6 081000058 Loss of DC Power / 601.32Ability to explain and apply system limits and precautions.
4 1000062 Loss of Nuclear Svc Water / 4 0000065 Loss of Instrument Air / 8 0W/E04 LOCA Outside Containment / 3 0W/E11 Loss of Emergency Coolant Recirc. / 4 0BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 0000077 Generator Voltage and Electric Grid Disturbances / 6 0K/A Category Totals:
0 0 0 0 3 3 6ES-401, 23 of 34Group Point Total:
0 0 ES-401 3Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)
Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)
IR#000001 Continuous Rod Withdrawal / 1 0000003 Dropped Control Rod / 1 082000005 Inoperable/Stuck Control Rod / 103Required actions if more than one rod is stuck or inoperable4.4 1000024 Emergency Boration / 1 0000028 Pressurizer Level Malfunction / 2 0000032 Loss of Source Range NI / 7 0000033 Loss of Intermediate Range NI / 7 0000036 Fuel Handling Accident / 8 0000037 Steam Generator Tube Leak / 3 0000051 Loss of Condenser Vacuum / 4 0000059 Accidental Liquid RadWaste Rel. / 9 083000060 Accidental Gaseous Radwaste Rel. / 904.18Knowledge of the specific bases for EOPs.
4 1000061 ARM System Alarms / 7 084000067 Plant Fire On-site / 813Need for emergency plant shutdown4.4 1000068 Control Room Evac. / 8 0000069 Loss of CTMT Integrity / 5W/E14 High Containment Pressure / 5 000074 Inad. Core Cooling / 4 W/E06 Degraded Core Cooling / 4W/E07 Saturated Core Cooling / 4000076 High Reactor Coolant Activity / 9 0W/E01 Rediagnosis / 3 W/E02 SI Termination / 385W/E13 Steam Generator Over-pressure / 404.47Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.4.2 1W/E15 Containment Flooding / 5 0W/E16 High Containment Radiation / 9 0W/E03 LOCA Cooldown - Depress. / 4 0W/E09 Natural Circulation Operations / 4W/E10 Natural Circulation with Steam Voide in Vessel with/without RVLIS. / 4W/E08 RCS Overcooling - PTS / 4 0K/A Category Totals:
0 0 0 0 2 2 4ES-401, 24 of 34 0Group Point Total:
0 0 0 ES-401 4Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2/Group 1 (SRO)
Q#System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)
IR#003 Reactor Coolant Pump 0004 Chemical and Volume Control 0005 Residual Heat Removal 0006 Emergency Core Cooling 0 88007 Pressurizer Relief/Quench Tank 0 3Overpressurization of the PZR3.9 1008 Component Cooling Water 0010 Pressurizer Pressure Control 0012 Reactor Protection 0 86013 Engineered Safety Features Actuation 0 1LOCA4.8 1022 Containment Cooling 0025 Ice Condenser 0026 Containment Spray 0 87039 Main and Reheat Steam 02.44Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system 4.4 1059 Main Feedwater 0061 Auxiliary/Emergency Feedwater 0062 AC Electrical Distribution 0063 DC Electrical Distribution 0064 Emergency Diesel Generator 0073 Process Radiation Monitoring 0 89076 Service Water 04.46Ability to verify that the alarms are consistent with the plant conditions.4.2 1078 Instrument Air 0 90103 Containment 04.06Knowledge of EOP mitigation strategies.4.7 1 0K/A Category Totals:
0 0 0 0 0 0 0 2 0 0 3 5ES-401, Page 25 of 34Group Point Total:
ES-401 5Form ES-401-2ES-401PWR Examination OutlineForm ES-401-2Plant Systems - Tier 2/Group 2 (SRO)
Q#System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)
IR#91001 Control Rod Drive 1 4Urgent failure alarm, including rod-out-of-sequence and motion-inhibit alarms3.9 1002 Reactor Coolant 0011 Pressurizer Level Control 0014 Rod Position Indication 0015 Nuclear Instrumentation 0016 Non-nuclear Instrumentation 0017 In-core Temperature Monitor 0 92027 Containment Iodine Removal02.25Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.4.2 1028 Hydrogen Recombiner and Purge Control 0029 Containment Purge 0033 Spent Fuel Pool Cooling 0034 Fuel Handling Equipment 0035 Steam Generator 0041 Steam Dump/Turbine Bypass Control 0045 Main Turbine Generator 0055 Condenser Air Removal 0 93056 Condensate01.07Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.4.7 1068 Liquid Radwaste 0071 Waste Gas Disposal 0072 Area Radiation Monitoring 0075 Circulating Water 0079 Station Air 0086 Fire Protection 0K/A Category Totals:
0 0 0 0 0 0 0 1 0 0 2 3ES-401, Page 26 of 34Group Point Total:
ES-401Generic Knowledge and Abilities Outline (Tier 3)Form ES-401-3Facility Name:Point Beach Nuclear Plant Date of Exam:December 3, 2012 Q#IR#IR#662.1.06Ability to manage the control room crew during plant transients.3.8 1 672.1.26Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).3.4 1 942.1.35Knowledge of the fuel-handling responsibilities of SROs.3.9 12.1.2.1.
2.1.Subtotal 2 1 682.2.17Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.2.6 1 692.2.21Knowledge of pre- and post-maintenance operability requirements.2.9 1 702.2.41Ability to obtain and interpret station electrical and mechanical drawings.3.5 1 952.2.07Knowledge of the process for conducting special or infrequent tests.3.6 1 962.2.35Ability to determine Technical Specification Mode of Operation.4.5 12.2.Subtotal 3 2 712.3.12Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.3.2 1 722.3.13Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.3.4 1 732.3.14Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.3.4 1 972.3.04Knowledge of radiation exposure limits under normal or emergency conditions.3.7 1 982.3.11Ability to control radiation releases.4.3 12.3.Subtotal 3 2 742.4.34Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects.4.2 1 752.4.41Knowledge of the emergency action level thresholds and classifications.2.9 1 992.4.08Knowledge of how abnormal operating procedures are used in conjunction with EOPs.4.5 1 1002.4.22Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.4.4 12.4.2.4.Subtotal 2 210 7Tier 3 Point Total3. Radiation Control4. Emergency Procedures /
Plan2. Equipment ControlCategoryTopic1.
Conduct of OperationsK/A #ROSRO-Only