2CAN080304, Unit 2 License Renewal Application Table of Contents & Matrix
| ML032330250 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/15/2003 |
| From: | Ashley G Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2CAN080304 | |
| Download: ML032330250 (7) | |
Text
- 0 Entergy Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 501858 5000 2CAN080304 August 15, 2003 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 License Renewal Application Table of Contents and Matrix
Dear Sir or Madam:
In order to assist the NRC Staff in preparation for review of the Arkansas Nuclear One, Unit-2 (ANO-2), License Renewal Application (LRA), Entergy is providing a draft table of contents for the ANO-2 LRA and associated programs/systems matrix. Attachment 1 is the draft table of contents, and Attachment 2 is the matrix for the draft programs and systems/aging management reports (AMRs).
This submittal contains no commitments. Should you have any questions concerning this submittal, please contact Ms. Natalie Mosher at (479) 858-4635.
Sincerely, Glenn R. Ashley Manager, Licensing GRA/nbm attachments
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2CAN080304 Page 2 of 2 cc:
Mr. Thomas P. Gwynn Regional Administrator (Acting)
U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Thomas W. Alexion Washington, DC 20555-0001 U. S. Nuclear Regulatory Commission Attn: Mr. Steve Hoffman Washington, DC 20555-0001
Attachment I to 2CAN080304 Page 1 of 4 Table of Contents 1.0 Administrative Information 1.1 General Information 1.1.1 Name of Applicant 1.1.2 Address of Applicant 1.1.3 Description of Business of Applicant 1.1.4 Legal Status and Organization 1.1.5 Class and Period of License Sought 1.1.6 Alteration Schedule 1.1.7 Regulatory Agencies with Jurisdiction 1.1.8 Local News Publications 1.1.9 Conforming Changes to Standard Indemnity Agreement 1.1.10 Restricted Data Agreement 1.2 Plant Description 2.0 Structures and Components Subject to Aging Management Review 2.1 Scoping and Screening Methodology 2.1.1 Scoping Methodology 2.1.2 Screening Methodology 2.1.2.1 Screening of Mechanical Systems 2.1.2.2 Screening of Structures 2.1.2.3 Screening of Electrical and Instrumentation and Control Systems 2.1.3 Interim Staff Guidance Discussion 2.1.4 Generic Safety Issues 2.2 Plant Level Scoping Results 2.3 System Scoping and Screening Results - Mechanical 2.3.1 Reactor Vessel, Internals, and Reactor Coolant System 2.3.1.1 Reactor Vessel and Control Element Drive Mechanism Pressure Boundary 2.3.1.2 Reactor Vessel Internals 2.3.1.3 Class I Piping, Valves, and Reactor Coolant Pumps 2.3.1.4 Pressurizer 2.3.1.5 Steam Generators 2.3.2 Engineered Safety Features Systems 2.3.2.1 Emergency Core Cooling System 2.3.2.2 Containment Spray System to 2CAN080304 Page 2 of 4 2.3.2.3 Containment Cooling System 2.3.2.4 Containment Penetrations System 2.3.2.5 Hydrogen Control System 2.3.3 Auxiliary Systems 2.3.3.1 Spent Fuel Pool Cooling System 2.3.3.2 Water Suppression Fire Protection System 2.3.3.3 Emergency Diesel Generator System 2.3.3.4 Alternate AC Diesel Generator System 2.3.3.5 Chemical and Volume Control System 2.3.3.6 Halon and RCP Motor Oil Collection System 2.3.3.7 Fuel Oil System 2.3.3.8 Service Water System 2.3.3.9 Auxiliary Building Ventilation System 2.3.3.10 Control Room Ventilation System 2.3.3.11 Miscellaneous Systems in Scope for 10CFR54.4(a)(2) 2.3.4 Steam and Power Conversion Systems 2.3.4.1 Main Steam 2.3.4.2 Main Feedwater 2.3.4.3 Emergency Feedwater 2.4 Structures and Structural Components Scoping and Screening Results 2.4.1 Containment and Containment Internals 2.4.2 Auxiliary Building, Turbine Building, and Yard Structures 2.4.3 Intake Structure and Emergency Cooling Pond 2.4.4 Structural Commodities 2.5 Electrical and Instrumentation and Controls Systems Scoping and Screening Results 3.0 Aging Management Review Results 3.1 Reactor Vessel, Internals, and Reactor Coolant System 3.1.1 Reactor Vessel and Control Element Drive Mechanism Pressure Boundary 3.1.2 Reactor Vessel Internals 3.1.3 Class 1 Piping, Valves, and Reactor Coolant Pumps 3.1.4 Pressurizer 3.1.5 Steam Generators 3.2 Engineered Safety Features Systems 3.2.1 Emergency Core Cooling System
Attachment I to 2CAN080304 Page 3 of 4 3.2.2 Containment Spray System 3.2.3 Containment Cooling System 3.2.4 Containment Penetrations System 3.2.5 Hydrogen Control System 3.3 Auxiliary Systems 3.3.1 Spent Fuel Pool Cooling System 3.3.2 Water Suppression Fire Protection System 3.3.3 Emergency Diesel Generator System 3.3.4 Alternate AC Diesel Generator System 3.3.5 Chemical and Volume Control System 3.3.6 Halon Fire Protection and RCP Motor Oil Collection System 3.3.7 Fuel Oil System 3.3.8 Service Water System 3.3.9 Auxiliary Building Ventilation System 3.3.10 Control Room Ventilation System 3.3.11 Miscellaneous Systems in Scope for 10CFR54.4(a)(2) 3.4 Steam and Power Conversion Systems 3.4.1 Main Steam 3.4.2 Main Feedwater 3.4.3 Emergency Feedwater 3.5 Structures and Structural Components 3.5.1 Containment and Containment Internals 3.5.2 Auxiliary Building, Turbine Building and Yard Structures 3.5.3 Intake Structure and Emergency Cooling Pond 3.5.4 Structural Commodities 3.6 Electrical and Instrumentation and Controls Systems 4.0 Time-Limited Aging Analyses 4.1 Identification of Time-Limited Aging Analyses 4.2 Reactor Vessel Neutron Embrittlement 4.3 Metal Fatigue 4.4 Environmental Qualification of Electrical Components 4.5 Concrete Containment Tendon Prestress 4.6 Containment Liner Plate and Penetration Fatigue Analyses 4.7 Other Plant-Specific Time-Limited Aging Analyses to 2CAN080304 Page 4 of 4 List of Appendices Appendix A Appendix B Appendix C Appendix D Appendix E Safety Analysis Report Supplement Aging Management Programs and Activities Optional - (not used)
Technical Specifications Changes Environmental Report to 2CAN080304 Page 1 of 1
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