ML100850399
| ML100850399 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/25/2010 |
| From: | Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML100850379 | List: |
| References | |
| RIS-02-003 | |
| Download: ML100850399 (12) | |
Text
ATTACHMENT 4 NRC Regulatory Issue Summary 2002-03 Cross-Reference
ATTACHMENT 4 NRC Regulatory Issue Summary 2002-03 Cross-Reference NRC RIS 2002-03 LAR DOCUMENT Item No. DESCRIPTION ATTACHMENT SECTION and TITLE I. Feedwater Flow Measurement Technique and Power Measurement Uncertainty I.1. Detailed description of plant-specific Attachment 1 3.1 Background and General Approach implementation of feedwater flow measurement 3.2 LEFM Ultrasonic Flow Measurement and Core Thermal technique and power increase gained as a result Power Uncertainty of implementing technique I.1.A. NRC approval of topical report on flow Attachment 1 3.2.1 LEFM Flow Measurement measurement technique I.1.B. Reference to NRCs approval of proposed Attachment 1 3.2.1 LEFM Flow Measurement measurement technique I.1.C. Plant Implementation Attachment 1 3.2.2 Plant Implementation I.1.D. Disposition of NRC criteria Attachment 1 3.2.4 Disposition of NRC Criteria for Use of Topical Reports I.1.E. Total power measurement uncertainty calculation Attachment 1 3.2.3 LEFM and Core Thermal Power Measurement Uncertainty for the plant and Methodology Attachment 11 Core Thermal Power Uncertainty Calculation I.1.F. Calibration and maintenance Attachment 1 3.2.4 Disposition of NRC Criteria for Use of Topical Reports 3.2.5 Deficiencies and Corrective Actions I.1.G. Proposed outage time for LEFM and basis for Attachment 1 3.2.4 Disposition of NRC Criteria for Use of Topical Reports selected time I.1.H Proposed actions if outage time is exceeded, and Attachment 1 3.2.4 Disposition of NRC Criteria for Use of Topical Reports basis for actions II. Accidents and Transients for which the Existing Analyses of Record Bound Plant Operation at the Proposed Uprated Power Level II.1 Matrix for bounded accidents and transients Attachment 6 9.0 Reactor Safety Performance Evaluations Page 1 of 11
ATTACHMENT 4 NRC Regulatory Issue Summary 2002-03 Cross-Reference NRC RIS 2002-03 LAR DOCUMENT Item No. DESCRIPTION ATTACHMENT SECTION and TITLE III. Accidents and Transients for which the Existing Analyses of Record Do Not Bound Plant Operation At the Proposed Uprated Power Level III.1,2, 3 Matrix for unbounded accidents and transients Attachment 6 9.0 Reactor Safety Performance Evaluations IV. Mechanical/Structural/Material Component Integrity and Design IV.1.A.i Reactor vessel, nozzles, supports Attachment 6 3.2 Reactor Vessel 3.2.1 Fracture Toughness 3.2.2 Reactor Vessel Structural Evaluation IV.1.A.ii Reactor core support structures and vessel Attachment 6 3.3 Reactor Internals internals 3.3.1 Reactor Internal Pressure Difference 3.3.2 Reactor Internals Structural Evaluation 3.3.3 Steam Separator and Dryer Performance 3.4 Flow-Induced Vibration Attachment 1 3.4.2 Adverse Flow Effects IV.1.A.iii Control rod drive mechanisms Attachment 6 2.5 Reactivity Control Page 2 of 11
ATTACHMENT 4 NRC Regulatory Issue Summary 2002-03 Cross-Reference NRC RIS 2002-03 LAR DOCUMENT Item No. DESCRIPTION ATTACHMENT SECTION and TITLE IV.1.A.iv Nuclear Steam Supply System (NSSS) piping, Attachment 6 3.4 Flow-Induced Vibration pipe supports, branch nozzles 3.5 Piping Evaluation 3.5.1 Reactor Coolant Pressure Boundary Piping 3.6 Reactor Recirculation System 3.7 Main Steam Line Flow Restrictors 3.8 Main Steam Isolation Valves 3.9 Reactor Core Isolation Cooling 3.10 Residual Heat Removal System 3.11 Reactor Water Cleanup System IV.1.A.v Balance of plant (BOP) piping (NSSS interface Attachment 6 3.5 Piping Evaluation systems, safety-related cooling water systems, 3.5.2 Balance-of-Plant Piping Evaluation and containment systems) 6.4.1 Service Water Systems 6.4.3 Reactor Enclosure Cooling Water System IV.1.A.vi Steam generator tubes, secondary side internal NA NA support structures, shell and nozzles IV.1.A.vii Reactor coolant pumps NA NA IV.1A.viii Pressurizer shell, nozzles, and surge lines NA NA Page 3 of 11
ATTACHMENT 4 NRC Regulatory Issue Summary 2002-03 Cross-Reference NRC RIS 2002-03 LAR DOCUMENT Item No. DESCRIPTION ATTACHMENT SECTION and TITLE IV.1.A.ix Safety-related valves Attachment 6 3.1 Nuclear System Pressure Relief/Overpressure Protection 3.8 Main Steam Isolation Valves 4.1 Containment System Performance 4.1.1 Generic Letter 89-10 Program 4.1.2 Generic Letter 95-07 Program 6.5 Standby Liquid Control System IV.1.B.i Stresses Attachment 6 3.2 Reactor Vessel 3.2.2 Reactor Vessel Structural Evaluation 3.4 Flow-Induced Vibration 3.5 Piping Evaluation 3.5.1 Reactor Coolant Pressure Boundary Piping 3.5.2 Balance-of-Plant Piping Evaluation IV.1.B.ii Cumulative usage factors Attachment 6 3.2.2 Reactor Vessel Structural Evaluation IV.1.B.iii Flow induced vibration Attachment 6 3.4 Flow-Induced Vibration Attachment 1 3.4.2 Adverse Flow Effects IV.1.B.iv Changes in temperature (pre- and post- uprate) Attachment 6 1.3 TPO Plant Operating Conditions 1.3.1 Reactor Heat Balance 1.3.2 Reactor Performance Improvement Features Table 1-2 Thermal-Hydraulic Parameters at TPO Uprate Conditions Page 4 of 11
ATTACHMENT 4 NRC Regulatory Issue Summary 2002-03 Cross-Reference NRC RIS 2002-03 LAR DOCUMENT Item No. DESCRIPTION ATTACHMENT SECTION and TITLE IV.1.B.v Changes in pressure (pre- and post- uprate) Attachment 6 1.3 TPO Plant Operating Conditions 1.3.1 Reactor Heat Balance 1.3.2 Reactor Performance Improvement Features Table 1-2 Thermal-Hydraulic Parameters at TPO Uprate Conditions IV.1.B.vi Changes in flow rate (pre- and post-uprate) Attachment 6 1.3 TPO Plant Operating Conditions 1.3.1 Reactor Heat Balance 1.3.2 Reactor Performance Improvement Features Table 1-2 Thermal-Hydraulic Parameters at TPO Uprate Conditions IV.1.B.vii High-energy line break locations Attachment 6 10.1 High Energy Line Break 10.1.1 Steam Line Breaks 10.1.2 Liquid Line Breaks IV.1.B.viii Jet impingement and thrust forces Attachment 6 10.1 High Energy Line Break 10.1.1 Steam Line Breaks 10.1.2 Liquid Line Breaks 10.1.2.6 Pipe Whip and Jet Impingement IV.1.C.i Reactor vessel pressurized thermal shock Attachment 6 3.1 Nuclear System Pressure Relief/Overpressure Protection calculations IV.1.C.ii Reactor vessel fluence evaluation Attachment 6 3.2 Reactor Vessel 3.2.1 Fracture Toughness Page 5 of 11
ATTACHMENT 4 NRC Regulatory Issue Summary 2002-03 Cross-Reference NRC RIS 2002-03 LAR DOCUMENT Item No. DESCRIPTION ATTACHMENT SECTION and TITLE IV.1.C.iii Reactor vessel heatup and cooldown pressure- Attachment 6 3.2 Reactor Vessel temperature limit curves 3.2.1 Fracture Toughness IV.1.C.iv Reactor vessel low temperature overpressure Attachment 6 3.2 Reactor Vessel protection 3.2.1 Fracture Toughness IV.1.C.v Reactor vessel upper shelf energy Attachment 6 3.2 Reactor Vessel 3.2.1 Fracture Toughness IV.1.C.vi Reactor vessel surveillance capsule withdrawal Attachment 6 3.2 Reactor Vessel schedule 3.2.1 Fracture Toughness IV.1.D Code of record Attachment 6 3.2 Reactor Vessel 3.2.2 Reactor Vessel Structural Evaluation 3.5 Piping Evaluation 3.5.1 Reactor Coolant Pressure Boundary Piping 3.5.2 Balance-of-Plant Piping Evaluation IV.1.E Component inspection/testing programs and Attachment 6 3.5 Piping Evaluation erosion/corrosion programs 3.5.1 Reactor Coolant Pressure Boundary Piping 3.5.2 Balance-of- Plant Piping Evaluation 10.6 Plant Life IV.1.F NRC Bulletin 88-02, "Rapidly Propagating NA NA Fatigue Cracks in Steam Generator Tubes" Page 6 of 11
ATTACHMENT 4 NRC Regulatory Issue Summary 2002-03 Cross-Reference NRC RIS 2002-03 LAR DOCUMENT Item No. DESCRIPTION ATTACHMENT SECTION and TITLE V. Electrical Equipment Design V.1.A Emergency diesel generators Attachment 6 6.1 AC Power 6.1.2 On-Site Power V.1.B Station blackout equipment Attachment 6 9.3.2 Station Blackout V.1.C Environmental qualification of electrical Attachment 6 10.3 Environmental Qualification equipment 10.3.1 Electrical Equipment V.1.D Grid stability Attachment 6 6.1 AC Power 6.1.1 Off-Site Power Attachment 12 All Grid Stability Study VI. System Design VI.1.A NSSS Interface Systems for BWRs (e.g., Attachment 6 3.4 Flow-Induced Vibration suppression pool cooling, as applicable) 3.5 Piping Evaluation 3.5.1 Reactor Coolant Pressure Boundary Piping 3.5.2 Balance-of-Plant Piping Evaluation 3.6 Reactor Recirculation System 3.7 Main Steam Line Flow Restrictors 3.8 Main Steam Isolation Valves 3.9 Reactor Core Isolation Cooling 3.10 Residual Heat Removal System 3.11 Reactor Water Cleanup System Page 7 of 11
ATTACHMENT 4 NRC Regulatory Issue Summary 2002-03 Cross-Reference NRC RIS 2002-03 LAR DOCUMENT Item No. DESCRIPTION ATTACHMENT SECTION and TITLE VI.1.B Containment Systems Attachment 6 4.1 Containment System Performance 4.1.1 Generic Letter 89-10 Program 4.1.2 Generic Letter 95-07 Program 4.1.3 Generic Letter 96-06 VI.1.C Safety-related cooling water systems Attachment 6 6.4 Water Systems 6.4.1 Service Water Systems 6.4.5 Ultimate Heat Sink VI.1.D Spent fuel pool storage and cooling systems Attachment 6 6.3 Fuel Pool 6.3.1 Fuel Pool Cooling 6.3.2 Crud Activity and Corrosion Products 6.3.3 Radiation Levels 6.3.4 Fuel Racks Page 8 of 11
ATTACHMENT 4 NRC Regulatory Issue Summary 2002-03 Cross-Reference NRC RIS 2002-03 LAR DOCUMENT Item No. DESCRIPTION ATTACHMENT SECTION and TITLE VI.1.E Radioactive waste systems Attachment 6 4.5 Standby Gas Treatment System 8.1 Liquid and Solid Waste Management 8.2 Gaseous Waste Management 8.3 Radiation Sources in the Reactor Core 8.4 Radiation Sources in Reactor Coolant 8.4.1 Coolant Activation Products 8.4.2 Activated Corrosion Products 8.4.3 Fission Products 8.5 Radiation Levels 8.6 Normal Operation Off-Site Doses VI.1.F Engineered safety features (ESF) heating, Attachment 6 4.4 Main Control Room Atmosphere Control System ventilation, and air conditioning systems 4.7 Post-LOCA Combustible Gas Control System 6.6 Power Dependent Heating, Ventilation and Air Conditioning VII. Other VII.1 Operator actions and effects on time available Attachment 6 4.1 Containment System Performance 6.7 Fire Protection 9.3 Special Events 9.3.2 Station Blackout 10.5 Operator Training and Human Factors VII.2.A Emergency and abnormal operating procedures Attachment 6 10.9 Emergency Operating Procedures Page 9 of 11
ATTACHMENT 4 NRC Regulatory Issue Summary 2002-03 Cross-Reference NRC RIS 2002-03 LAR DOCUMENT Item No. DESCRIPTION ATTACHMENT SECTION and TITLE VII.2.B Control room controls, displays (including the Attachment 1 3.2.4 Disposition of NRC Criteria for Use of LEFM Topical Reports safety parameter display system) and alarms 3.4.3 Plant Modifications Attachment 6 10.5 Operator Training and Human Factors VII.2.C The control room plant reference simulator Attachment 6 10.5 Operator Training and Human Factors VII.2.D The operator training program Attachment 6 10.5 Operator Training and Human Factors VII.3 Modifications completion Attachment 1 3.4.3 Plant Modifications Attachment 5 List of Regulatory Commitments VII.4 Procedure Revisions - Licensed Power Level Attachment 1 3.2.6 Reactor Power Monitoring VII.5.A 10 CFR 51.22, Exclusion of Environmental Attachment 1 5.0 Environmental Consideration Review, including discussion of effect of the Attachment 6 8.0 Radwaste and Radiation Sources power uprate on types and amounts of effluents released offsite, and whether bounded by final environmental statement and previous Environmental Assessments for the plant VII.5.B 10 CFR 51.22, Exclusion of Environmental Attachment 1 5.0 Environmental Consideration Review, including discussion of effect of the Attachment 6 8.5 Radiation Levels power uprate on individual and cumulative occupational radiation exposure VIII. Changes to Technical Specifications, Protection System Settings, Emergency System Settings VIII.1 A detailed discussion of each change to the Attachment 1 2.0 Detailed Description plants Technical Specifications, protection Attachment 2 All Markup of Proposed Operating License and Technical system settings, and/or emergency system Specifications Pages settings needed to support the power uprate Page 10 of 11
ATTACHMENT 4 NRC Regulatory Issue Summary 2002-03 Cross-Reference NRC RIS 2002-03 LAR DOCUMENT Item No. DESCRIPTION ATTACHMENT SECTION and TITLE VIII.1.A Description of the change Attachment 1 2.0 Detailed Description Attachment 2 All Markup of Proposed Operating License and Technical Specifications Pages VIII.1.B Identification of analyses affected by and/or Attachment 1 3.3 Evaluation of Changes to License and Technical supporting the change Specifications Attachment 6 All GEH Nuclear Energy Safety Analysis Report for Limerick Generating Station, Units 1 and 2 Thermal Power Optimization, NEDC-33484P VIII.1.C Justification for the change, including the type of Attachment 1 3.3 Evaluation of Changes to License and Technical information discussed in Section III, above, for Specifications any analyses that support and/or are affected by Attachment 6 All GEH Nuclear Energy Safety Analysis Report for Limerick change Generating Station, Units 1 and 2 Thermal Power Optimization, NEDC-33484P Page 11 of 11