Category:Letter type:NL
Jump to navigation
Jump to search
(previous page) (next page)
Pages in category "Letter type:NL"
The following 200 pages are in this category, out of 3,601 total.
(previous page) (next page)N
- NL-00-139, Secy-00-0238-Attachment 2 - Indian Points Emergency Planning Interface with State and County Authorities
- NL-02-006, Response to Request for Additional Information Indian Point 2 License Amendment Request for Reactor Coolant System Heatup and Cooldown Limitation Curves
- NL-02-010, Entergy Response to Significance Determination Re Yellow Finding for Operator Annual Requalification Exam Failures at Indian Point, Unit 2
- NL-02-013, Response to Request for Additional Information Regarding Spent Fuel Storage Pit Analysis with Soluble Boron Credit
- NL-02-014, Entergy Response to NRC Regulatory Issue Summary 2001-21, Licensing Action Estimates for Operating Reactors, Dated 11/16/2001
- NL-02-015, Ltr Dtd 01/25/02 from F. Dacimo 2002 Fundamentals Improvement Plan with Attachment
- NL-02-020, Letter from Fred Dacimo to NRC, Providing Revision to Emergency Plan Procedures
- NL-02-024, Submittal of Technical Specifications Bases Changes for Indian Point Unit 2
- NL-02-028, Withdrawal of License Amendment Request for Revision of Technical Specifications
- NL-02-030, Response to Request for Additional Information Regarding One-time Extension of Containment Integrated Leak Rate Test Frequency
- NL-02-031, Proposed New Administration Building for Indian Point Energy Center - Identification of Permitting Agency
- NL-02-032, Revised Pages - 2000 Annual Effluent & Waste Disposal Report
- NL-02-037, Technical Specification Bases Changes
- NL-02-041, Response to Issuance of Order for Interim Safeguards and Security Compensatory Measures
- NL-02-042, License Amendment Request (LAR-02-007),, Changes to Effectively Coordinate Indian Point Units 1 & 2 Programs
- NL-02-044, Revision to Emergency Plan Procedures
- NL-02-045, Supplemental Response to Issuance of Order for Interim Safeguards and Security Compensatory Measures from Entergy Nuclear Northeast
- NL-02-047, Response to Request for Additional Information Regarding One-Time Extension of Containment Integrated Leak Rate Test Frequency
- NL-02-048, Annual Exposure Monitoring and Statistical Summary Report for 2001 for Indian Point Units 1 & 2
- NL-02-049, Notification of Emergency Response Data System Unavailability
- NL-02-050, Submittal of 15 Day Response to NRC Bulletin 2002-01.
- NL-02-052, Response to Request for Additional Information Indian Point 2 License Amendment Request for Power Limits with Inoperable Steam Line Safety Valves
- NL-02-057, Annual 10 CFR 50.46 Report
- NL-02-060, Annual Report of Individual Monitoring for Cy 2001
- NL-02-062, Annual Environmental Protection Plan Report
- NL-02-063, Updated Replacement of Technical Specifications for License Amendment Request (LAR 01-010) Regarding Spent Fuel Storage Pit Rack Criticality Analysis with Soluble Boron Credit
- NL-02-065, Annual Effluent and Waste Disposal Report
- NL-02-067, Indian Points Annual Radiological Environmental Operating Report for 2001
- NL-02-068, Transmittal of Revised Emergency Plan Implementing Procedures TOC (Revised 04/11/2002), IP-1023 (Revision 18), IP-1027 (Revision 16) & IP-1050 (Revision 3) for Indian Point Nuclear Generating Station
- NL-02-069, April 2002 Monthly Operating Report for Indian Point Unit 2
- NL-02-071, License Amendment Request (LAR-02-009), Changes to Facility Operating License No. DPR-26 to Reflect Enn/Ipec Reorganizations
- NL-02-072, Entergy Revision to Emergency Plan Implementing Procedures
- NL-02-074, Submittal of 60-Day Response to NRC Bulletin 2002-01
- NL-02-075, Entergy Nuclear Northeast, Indian Point Nuclear Generating Unit 2, - Response to Request for Additional Information Regarding One-time Extension of Containment Integrated Leak Rate Test Frequency
- NL-02-076, Licensee Amendment Request (LAR No. 02-008) - Revision to the Steam Generator Tube Surveillance Requirements for Eddy Current Inspection Probe Diameter in Technical Specifications
- NL-02-081, Response to Issuance of Order for Interim Safeguards and Security Compensatory Measures
- NL-02-082, License Amendment Request (LAR No. 02-010) - Regarding Indian Point Energy Center, Unit No. 2 Technical Specifications Requirements for Control Rod Misalignment & Rod Position Indication
- NL-02-084, Response to Request for Additional Information Regarding One-Time Extension of Containment Integrated Leak Rate Test Frequency
- NL-02-096, Response to Regulatory Issue Summary 2002-09, Preparation and Scheduling of Operator Licensing Examinations
- NL-02-099, Submittal of Supplement to 15-day Response for NRC Bulletin 2002-01 from Entergy Nuclear Northeast
- NL-02-101, Letter Providing Additional Details Re Reactor Vessel Head Inspections to Be Performed at Indian Point Unit No. 2 During Next Refueling Outage (2R15)
- NL-02-104, ASME Code Relief Requests to Use Alternative to Temper Bead Welding for Contingency Repairs on Reactor Vessel Head Penetration Nozzles
- NL-02-105, Response to Request for Additional Information Regarding NRC Generic Letter 96-06: Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions
- NL-02-107, ASME Section XI, Inservice Inspection (ISI) Program Relief Request No. 60
- NL-02-112, Proposed Steam Generator Examination Program - 2002 Refueling Outage (2R15)
- NL-02-113, Gas Turbine Generator Fuel Oil Storage Requirements
- NL-02-114, ASME Code Relief Requests to Use Alternative Repair Methods and NDE Techniques for Reactor Vessel Head Penetration Nozzles
- NL-02-119, Letter from John Herron Re 30 Day Response to NRC Bulletin 2002-02
- NL-02-124, Combined Emergency Plan. Changes Integrated & Upgraded Units 1 & 2 Plan with Unit 3 Plan in Combined Site Emergency Plan for Indian Point Energy Center
- NL-02-125, Response to Questions Regarding Relief Requests to Use an Alternative to Temper Bead Welding Requirements for Contingency Repairs on Reactor Vessel Head Penetration Nozzles
- NL-02-130, Response to Request for Additional Information Regarding Section 3.6 (Containment Systems) of the Improved Technical Specifications (ITS)
- NL-02-133, Response to Request for Additional Information Regarding Section 5.5.14 of the Improved Technical Specifications (ITS)
- NL-02-143, Cycle 16 Core Operating Limit Report (COLR)
- NL-02-144, October 2002 Monthly Operating Report for Indian Point Unit No.2
- NL-02-145, Final Response to Issuance of Orders for Interim Safeguards and Security Compensatory Measures
- NL-02-148, Response to Request for Additional Information Regarding Sections 3.3.1, 3.5.3, 3.7.8, 3.6.3, 3.8.4, & 3.8.6 of Improved TS
- NL-02-153, Submittal of Integrated Security Force Training & Qualification Plan, Rev. 0
- NL-02-1582, Withdrawal of Emergency Technical Specification Revision Request for 3.8.1 AC Sources - Operating
- NL-02-160, Response to Request for Additional Information Regarding Sections 1.0, 2.0, 3.0, 3.1, 3.2, 3.3, 3.4, 3.5, 3.6, 3.7, 3.9, 4.0, & 5.0 of Improved TS
- NL-02-161, Steam Generator Inservice Examination Program Results 2002 Refueling Outage(2R15)
- NL-02-162, Reactor Vessel Head Inspection Results; Indian Point 2, Fall 2002 Refueling Outage
- NL-03-002, Response to Request for Additional Information Regarding Section 3.8.1, AC Sources Operating, of Improved TS
- NL-03-003, Reply to Request for Additional Information Regarding Relief Request RR 3-28 for Risk Informed Inservice Inspection
- NL-03-004, CFR 50.55a Inservice Testing Program Relief Request Regarding Relief Valve Testing; Elapsed Time Between Successive Openings
- NL-03-005, Reply to Request for Additional Information Regarding Proposed Amendment for Selective Adoption of Alternate Source Term
- NL-03-0086, December 2002 Monthly Operating Report for Edwin I. Hatch Nuclear Plant
- NL-03-0088, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity, 60-Day Response, Request for Additional Information
- NL-03-0108, Response to Request for Additional Information Technical Specification Revision Request Integrated Leakage Rate Testing Interval Extension
- NL-03-0120, Inservice Inspection Summary Report
- NL-03-0134, Request for Technical Specification Change, Steam Generator Inspection Frequency Revision for Spring 2004 Refueling Outage
- NL-03-014, Additional Information on 10 CFR 50.12 Exemption Request for Post Accident Containment Ventilation System
- NL-03-015, Code of Federal Regulations 10 CFR 50.59, Annual Report of Changes, Tests & Experiments
- NL-03-0157, Response to Request for Additional Information
- NL-03-016, Request for Review of WCAP-14936, Code Qualification Document for Best Estimate Small Break LOCA Analysis
- NL-03-0168, Southern Nuclear Operating Company, Inc., Answer to the Order for Compensatory Measures Related to Access Authorization
- NL-03-0169, Licensee Response to Order for Compensatory Measures Related to Access Authorization
- NL-03-019, Reply to Request for Additional Information Regarding Proposed License Amendment for Relaxation of Pressurizer Water Level Requirement
- NL-03-020, Response to Request for Additional Information Regarding 60-Day Response to NRC Bulletin 2002-01
- NL-03-0200, Response to Request for Additional Information, Steam Generator Tube Inspections
- NL-03-023, Supplemental Response to Request for Additional Information Regarding NRC Generic Letter 96-06: Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions
- NL-03-024, Response to Questions Regarding Relief Request RR 3-16, Rev.2, Third 10-Year Inservice Inspection Program Plan
- NL-03-0257, Technical Specification Revision Request, Integrated Leakage Rate Testing Interval Extension
- NL-03-026, Refueling Outage Inservice Inspection (ISI) Program Summary Report - Third Outage, Second Period, Third Interval
- NL-03-028, January 2003 Monthly Operating Report for Indian Point 3
- NL-03-0301, Revisions to Emergency Implementing Procedures
- NL-03-0322, Emergency Implementing Procedure Revisions
- NL-03-0346, National Pollutant Discharge Elimination System Permit Renewal
- NL-03-035, to Indian Point 2 License Amendment Request for Conversion to Improved Standard TS
- NL-03-0369, Occupational Radiation Exposure Reports
- NL-03-037, 20 Day Response to Order EA-03-009, Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors
- NL-03-0372, Technical Specifications Revision Request Removal of Reference to Plant Operations Review Committee
- NL-03-039, Reply to Request for Additional Information Proposed Amendment for Selective Adoption of Alternate Source Term
- NL-03-0390, Licensees Answer to February 11, 2003 Commission Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors at Joseph M. Farley Nuclear Plant & Vogtle Electric Generating Plant
- NL-03-041, Additional Information on 10 CFR 50.12 Exemption Request for Post Accident Containment Ventilation System
- NL-03-042, ASME Section XI, Inservice (IST) Program Relief Request No. 46
- NL-03-0438, Property Insurance Coverage as of 04/01/2003
- NL-03-044, Request for Plant Specific Approval of Best Estimate Large Break LOCA Analysis & Proposed Changes to Technical Specifications to Utilize for Indian Point 3 - Clarification from February 4, 2003, Telephone Call
- NL-03-0455, Inservice Inspection Program, Additional Information for Request for Relief No. RR-48
- NL-03-0457, Transmittal of Edwin I. Hatch Nuclear Plant Physical Security Plan Revision
- NL-03-0472, Edwin I Hatch - Nuclear Security Training & Qualification Plan
- NL-03-0488, 10 CFR 50.59 Changes to the Technical Specification Bases
- NL-03-051, Reply to Request for Additional Information Regarding ASME Code Relief Request RR-62 & RR 3-32
- NL-03-052, Response to Request for Additional Information Regarding Section 3.3, Instrumentation, of the Improved Technical Specification (ITS)
- NL-03-0538, February 2003 Monthly Operating Report for Edwin I. Hatch Nuclear Plant
- NL-03-054, NRC Order EA-03-009 Relaxation Request Regarding Inspection of Reactor Pressure Vessel Head Nozzles
- NL-03-055, Withdrawal of Relief Request RR3-29 for Inservice Inspection Program
- NL-03-058, Reply to Request for Additional Information Regarding Proposed License Amendment for 1.4% Measurement Uncertainty Recapture Power Uprate
- NL-03-0584, February 2003 Monthly Operating Report for Vogtle
- NL-03-0596, Vogtle Electric Generating Plant, Response to RIS 2003-01 and Request for Technical Alternative to ASME Section Xl, Appendix Viii, Supplement 10
- NL-03-0605, Request for Technical Specification Changes Unit Two Pressurizer Power Operated Relief Valve Block Valve Surveillance Testing
- NL-03-0620, Additional Information Concerning GL 96-06, Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions
- NL-03-0621, Emergency Implementing Procedure
- NL-03-0636, Physical Security & Contingency Plan Revision
- NL-03-0656, And Vogtle Electric Generating Plant - Request for Technical Alternative to ASME Section XI, IWA-4120(a) and IWA-4310
- NL-03-068, Annual Effluent and Waste Disposal Report
- NL-03-0684, ASME Section XI Requests for Relief Number RR-51 and RR-52 Alternative Repair Technique and Inspection Requirement - Reactor Vessel Head
- NL-03-069, Steam Generator Tube Inspection - Technical Specification 5.6.8 Report on Tubes Plugged
- NL-03-0692, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors
- NL-03-0693, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1))
- NL-03-0694, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1))
- NL-03-0696, Technical Specifications Revision to DC Electrical System Requirements
- NL-03-070, 2002 Annual Radiation Exposure Monitoring & Statistical Summary Report
- NL-03-0704, Measurement Uncertainty Recapture Power Uprate Request for Additional Information Response
- NL-03-0723, Response to Request for Additional Information Regarding Risk Informed Inservice Inspection Program Submittal
- NL-03-074, Annual Radioactive Effluent Release Report - for Period January 1, 2002 Through December 31, 2002
- NL-03-0750, Response to Request for Additional Information
- NL-03-0753, Request to Revise Technical Specifications Reactor Trip System Instrumentation Over Temperature Delta
- NL-03-0757, Cycle 18 Core Operating Limits Report (COLR)
- NL-03-0759, March 2003 Monthly Operating Report for Edwin I. Hatch, Units 1 & 2
- NL-03-076, Reply to Request for Additional Information Regarding Proposed License Amendment for 1.4% Measurement Uncertainty Recapture Power Uprate
- NL-03-0761, March 2003 Monthly Operating Report for Farley Nuclear Plant
- NL-03-0779, Request for Revise TS Control Room Emergency Filtration/Pressurization System & Penetration Room Filtration System - Revision 1
- NL-03-078, Relief Request RR 63, Risk-Informed Inservice Inspection (RI-ISI) Program
- NL-03-079, ASME Section IX, Inservice Testing (SIT) Program Relief Request Nos. 47 & 48
- NL-03-080, Core Operating Limits Report for Cycle 13
- NL-03-081, To the Indian Point 2 License Amendment Request for Conversion to Improved Standard Technical Specifications
- NL-03-0815, Responses to NRC Questions on Relaxation Request to Order EA-03-009
- NL-03-082, April 2003 Monthly Operating Report for Indian Point Unit 2
- NL-03-083, April 2003 Monthly Operating Report for Indian Point 3
- NL-03-084, CFR50.59 Report
- NL-03-0865, Supplemental Information for Relaxation Request to Order EA-03-009
- NL-03-0889, Unit 1 Cycle 19 Core Operating Limits Report
- NL-03-0894, Annual Non-Radiological Environmental Operating Reports for 2002
- NL-03-090, Submittal of Changes to the Entergy Nuclear Northeast, Inc. Quality Assurance Program Description
- NL-03-093, Proposed Changes to Technical Specifications: Pressure-Temperature and Overpressure Protection System Limits for Up to 20 Effective Full Power Years
- NL-03-0938, Southern Nuclear Operating Co. Inc, Annual Radiological Environmental Operating Reports for 2002
- NL-03-0939, Revised Epips, Including 73EP-EIP-004-0, Version 9.0, 73EP-EIP-005-0, Version 8.0, 73EP-EIP-018-0, Version 7.0, 73EP-EIP-023-0S, Version 0.4 & 73EP-EIP-073-0. Version 15.1
- NL-03-094, Proposed Exemption Request from Requirements of 10 CFR Part 50, Section 50.60 & Appendix G
- NL-03-0941, Additional Information Re Request for Technical Specification Changes Unit Two Pressurizer Power Operated Relief Valve Block Valve Surveillance
- NL-03-098, Reactor Vessel Head Inspection Results, Spring 2003 Refueling Outage
- NL-03-099, Revision to Proposed Technical Specification Amendment for Laboratory Testing of Nuclear-Grade Activated Charcoal Per NRC
- NL-03-0999, 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2002
- NL-03-103, Response to Request for Additional Information Regarding Section 3.7, Plant Systems, of the Improved Technical Specifications (ITS)
- NL-03-104, City Water Tank Surveillance Requirement
- NL-03-1047, Report of Facility Changes, Tests & Experiments
- NL-03-107, Supplement to the Indian Point 2 License Amendment Request for Conversion to Improved Standard Technical Specifications
- NL-03-1074, Withdrawal of ASME Section XI Request for Relief Numbers RR-51 & RR-52 Alternative Repair Technique & Inspection Requirement - Reactor Vessel Head
- NL-03-1078, Cycle 11 Core Operating Limits Report
- NL-03-108, Submittal of Physical Security Plan Revision 22
- NL-03-109, Submittal of Physical Security Plan Revision 24
- NL-03-1090, Organization and Correspondence Routine Changes
- NL-03-1091, Organization and Correspondence Routine Changes
- NL-03-110, Proposed Changes to TS: Pressure-Temperature & Overpressure Protection System Limits for Up to 20 Effective Full Power Years
- NL-03-111, Annual 10 CFR 50.46 Report for Year 2002 - Emergency Core Cooling System Evaluation Changes
- NL-03-1124, Measurement Uncertainty Recapture Power Uprate, Request for Additional Information Response
- NL-03-114, Revised Pages to the 2001 Annual Effluent & Waste Disposal Report
- NL-03-1140, Changes to Technical Specification Bases
- NL-03-116, To Indian Point 2 License Amendment Request for Conversion to Improved Standard Technical Specifications
- NL-03-1163, Version 17 of FNP Security Plan
- NL-03-117, Application for Withholding Proprietary Information from Public Disclosure
- NL-03-1178, Control Room AC System, Documentation of 05/28/2003 Teleconference Regarding Request for Enforcement Discretion
- NL-03-1180, Measurement Uncertainty Recapture Power Uprate (Murpu)
- NL-03-1185, Addition of Snubber Inspection Type
- NL-03-120, June 2003 Monthly Operating Report for Indian Point Unit 2
- NL-03-1259, Risk-Informed Inservice Inspection Program - ASME Code Category B-F, B-J, C-F-1 & C-F-2 Piping
- NL-03-126, Period Summary Report of NRC Regulatory Commitment Changes
- NL-03-1260, Measurement Uncertainty Recapture Power Uprate (Murpu) Revised Enclosure 5
- NL-03-1267, Report of Unsatisfactory Performance Testing
- NL-03-127, To the Indian Point 2 License Amendment Request for Conversion to Improved Standard Technical Specifications
- NL-03-128, 60-Day Response to NRC Bulletin 2003-01 Regarding Potential Impact of Debris Blockage of Emergency Sumps
- NL-03-1287, Response to Request for Additional Information, Technical Specification Change to Turbine Building Area High Temperature Primary Containment Isolation Setpoint
- NL-03-1299, Addendum to 2001 Annual Radioactive Effluent Release Report
- NL-03-132, July 2003 Monthly Operating Report for Indian Point, Unit 3
- NL-03-134, Steam Generator Tube Inspection - Revision to Technical Specification 5.6.8 Report on Tubes Plugged, Indian Point Unit 3
- NL-03-1347, Response to Request for Additional Information Regarding Risk Informed Inservice Inspection Program Submittal
- NL-03-1369, Application for License Renewal
- NL-03-137, To the Indian Point 2 License Amendment Request for Conversion to Improved Standard Technical Specifications
- NL-03-1380, Third 10-Year Interval Inservice Testing Program, Submittal of Relief Requests RR-V-18
- NL-03-1384, Withdrawal of Request for Relief Contained in Answer to the Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors
- NL-03-1386, Startup Test Report
- NL-03-1387, Results of Reactor Pressure Vessel Head Inspections Required by Order EA-03-009
- NL-03-139, Letter to NRC from Mccann, Entergy, Document Submission Re Indian Points Emergency Preparedness
- NL-03-1398, Submittal of Updated Fire Hazards Analysis Report (FHA) for Edwin I. Hatch Nuclear Plant, Units 1 & 2
- NL-03-140, Entergy Nuclear Northeast - Reply to Request for Additional Information Regarding NRC Order EA-03-009 Relaxation Request
- NL-03-1401, Response to Request for Additional Information
- NL-03-143, August 2003 Monthly Operating Report for Indian Point Unit 2
- NL-03-144, August 2003 Monthly Operating Report for Indian Point, Unit 3
- NL-03-1458, Revision to Annual Radioactive Effluent Release Report for 2002 for Joseph M. Farley Nuclear Plant
- NL-03-146, Special Nuclear Materials Report - October 2002 Through July 2003
- NL-03-1470, Withdrawal of Request for Technical Specification Changes Deletion of LCO 3.6.1, Condition a and Addition of LCO 3.0.8, Inoperability of Non-Technical Specification Support Systems