Category:Letter type:LR
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Pages in category "Letter type:LR"
The following 200 pages are in this category, out of 1,544 total.
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- LR-N02-0003, Request for Amendment, Change to TS to Deactivate Reactor Vessel Head Spray Portion of Residual Heat Removal (RHR) System
- LR-N02-0032, 10 CFR 50.46 Report, Change in Application of Emergency Core Cooling System Evaluation
- LR-N02-0039, Request for Change to Technical Specifications, Extended Use of Pressure - Temperature Limit Curves
- LR-N02-0055, Stations Technical Specification 6.9.1.5 Annual Reports
- LR-N02-0069, Request for License Amendment A.C. Sources - Operating
- LR-N02-0072, Stations, Guaranteed Retrospective Premiums, Following Nuclear Accident
- LR-N02-0080, Request for Change to Technical Specifications Requirements Supplemental Request One-Time Extension to Increase the Interval of the Integrated Leak Rate Test from Ten to Fifteen Years
- LR-N02-0083, Supplement to Request for Change to Technical Specification 3.9.1, Boron Concentration
- LR-N02-0084, Change to Commitments Re Cable Raceway Fire Wrap Resolution Plan & 4160 Volt Switchgear Room Suppression for Salem Generating Station Unit Nos. 1 & 2
- LR-N02-0099, Response to the Issuance of Order for Interim Safeguards and Security Compensatory Measures
- LR-N02-0106, Request for Change to Technical Specifications Requirements, Supplemental Request One-Time Extension to Increase the Interval of the Integrated Leak Rate Test from Ten to Fifteen Years
- LR-N02-0108, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
- LR-N02-0142, Request for Exemption from 10 CFR 50, Appendix R, for Fire Areas 1(2)-FA-AB-64B, 1(2)-FA-AB-84C, and 1(2)-FA-AB-84B
- LR-N02-0177, Steam Generator Tube Plugging Report, Technical Specification 4.4.6.5.a
- LR-N02-0178, Response to NRC Bulletin 2002-01 Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
- LR-N02-0180, Response to NRC Bulletin 2001-01, Circumferential Cracking of Reactor Vessel Head Penetration Nozzles and Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity, Salem Generating Statio
- LR-N02-0187, April 2002 Monthly Operating Report for Hope Creek
- LR-N02-0188, April 2002 Monthly Operating Report for Salem Unit 1
- LR-N02-0189, April 2002 Monthly Operating Report for Salem Unit 2
- LR-N02-0192, Correction of Technical Specification Page Issued with Amendment 245
- LR-N02-0196, Supplemental Response to the Issuance of Order for Interim Safeguards and Security Compensatory Measures
- LR-N02-0215, Reactor and Senior Reactor Operator Initial Examination Report No. 50-354/02-301 Dtd 6/13/02
- LR-N02-0222, Core Operating Limits Report - Cycle 13
- LR-N02-0229, Request for License Amendment Increased Snubber Surveillance Test Interval
- LR-N02-0244, Request for Changes to Technical Specifications Refueling Operations - Relaxation of Requirements Applicable During Movement of Irradiated Fuel
- LR-N02-0283, Reply to Request for Additional Information Regarding Request for Exemption from 10CFR50, Appendix R, for Fire Areas 1(2)-FA-AB-64B, 1(2)-FA-AB-84C & 1(2)-FA-AB-84B, Salem Generating Station, Units 1 & 2
- LR-N02-0297, Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head & Vessel Head Penetration Nozzle Inspection Programs for Salem Units 1 & 2
- LR-N02-0300, PSEG Nuclear, LLC Additional Information Request for License Amendment LCR-S02-03 Refueling Operations -- Fuel Decay Time Prior to Commencing Core Alterations or Movement of Irradiated Fuel for Salem Plant
- LR-N02-0303, Additional Information Request for License Amendment LCR S02-03 Refueling Operations - Fuel Decay Time Prior to Commencing Core Alterations or Movement of Irradiated Fuel
- LR-N02-0313, Update of Emergency Response Data System (ERDS) Data Point Library
- LR-N02-0315, Request for Change to Technical Specifications to Reflect New Setpoints and Allowable Values for Steam Generator Low-Low Level Trip
- LR-N02-0319, Response to Request for Change to TS One Time Extension to Increase Interval of Integrated Leak Rate Test from Ten to Twenty Years
- LR-N02-0333, Supplement to License Change Request H02-03 Regarding Missed Surveillance Requirements & Adoption of TS Bases Control Program Using Clip
- LR-N02-0334, Supplement to License to Change Request S02-02 Regarding Missed Surveillance Requirements and Adoption of TS Bases Control Program Using Clip
- LR-N02-0343, Request for Change to Technical Specifications Revise Section 6.12, High Radiation Area.
- LR-N02-0344, Request for Change to Technical Specifications Revise Section 6.12, High Radiation Area.
- LR-N02-0364, Hope Creek Security Plan
- LR-N02-0369, Response to NRC Bulletin 2002-02 Reactor Pressure Vessel Head & Vessel Head Penetration Nozzle Inspection Programs
- LR-N02-0374, Change to Commitment Regarding Cable Raceway Fire Wrap Resolution Plan
- LR-N02-0375, Request for Exemption 10CFR 55.59 Requalification Program Schedule
- LR-N02-0393, Additional Information for License Change Request H02-013 Regarding One-Time Extension to Increase Interval of Integrated Leak Rate Test from Ten to Fifteen Years
- LR-N02-0400, Change to Commitment Regarding 4166 Volt Switchgear Room Suppression
- LR-N02-0406, Request for Change to Reactor Material Surveillance Program Hope Creek Generating Station
- LR-N02-0409, Core Operating Limits Report - Cycle 16, Revision 0
- LR-N02-0413, Response to Request for Additional Information Regarding Integrated Leak Rate Test Interval Extension
- LR-N02-0415, Withdrawal of Request for License Amendment Increased Snubber Surveillance Test Interval
- LR-N02-0416, Request for Additional Information Regarding Relaxation of Secondary Containment Operability Requirements & Elimination of FRVS Recirculation Charcoal Filters
- LR-N02-0417, Request for Additional Information Regarding Relaxation of Secondary Containment Operability Requirements & Elimination of FRVS Recirculation Charcoal Filters - Revision to Request for Change to TS Dated 06/28/2002
- LR-N02-0420, November 2002 Monthly Operating Report for Salem Generating Station Unit 2
- LR-N02-0436, Request for Authorization to Use a Risk-Informed Inservice Inspection Alternative to the ASME Boiler and Pressure Vessel Code Section XI Requirements for Class 1 and 2 Piping
- LR-N02-0437, Cable Raceway Fire Wrap Resolution Plan
- LR-N02-0440, Response to Request for Additional Information Regarding a Change to TS Mechanical Vacuum Pump Trip Instrumentation
- LR-N02-0453, Supplemental Information Inservice Inspection Program Relief Requests S2-RR-03-V01 and V02
- LR-N03-0014, Request for Change to Technical Specifications Administrative and Editorial Changes
- LR-N03-0018, TS Bases Change
- LR-N03-0022, Revision to Request for Change to Technical Specifications
- LR-N03-0023, Response to NRC Bulletin 2002-01- Request for Additional Information Regarding Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity
- LR-N03-0036, Deferral on Inservice Inspection Program Examinations
- LR-N03-0037, Response to the Issuance of Order for Compensatory Measures Related to Access Authorization
- LR-N03-0050, Request for Change to TS Post Accident Sampling
- LR-N03-0060, January 2003 Monthly Operating Report for Hope Creek Generating Station
- LR-N03-0061, January 2003 Monthly Operating Report for Salem Generating Station Unit 1
- LR-N03-0077, Technical Specification 6.9.1.5 Annual Reports
- LR-N03-0079, Response to Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactor, Salem Generating Station Units 1 & 2
- LR-N03-0083, Information Regarding a Change to TS for Mechanical Vacuum Pump Trip Instrumentation
- LR-N03-0085, Information Regarding Relaxation of Containment Operability Requirements
- LR-N03-0086, Correction of Information Provided in Request for License Amendment
- LR-N03-0092, Request for Change to TSs Explosive Gas Mixture
- LR-N03-0095, Request for Change to Technical Specifications Depressurization Systems - Suppression Chamber Surveillance Requirement
- LR-N03-0099, Response to Request for Additional Information Regarding Change to TS to Reflect New Setpoints & Allowable Values for Steam Generator Low Level Trip
- LR-N03-0107, TS Bases Change
- LR-N03-0126, Correction of Bases Pages Issued with Amendments 251 & 232
- LR-N03-0130, Volt Switchgear Room Suppression
- LR-N03-0135, Stations Submittal of Statements & Supporting to Satisfy Guarantee Requirements
- LR-N03-0136, Response to Request for Additional Information Re Change to Technical Specification Related to Containment Closure and Fuel Handling Ventilation
- LR-N03-0140, NRC Decommissioning Funding Status Report
- LR-N03-0142, Request for Change to Technical Specifications Pressure Sensor Response Time Testing, Salem Station
- LR-N03-0165, Hope Creek Security Plan
- LR-N03-0173, Technical Specification Bases Change Re Reactor Coolant System Pressure and Temperature Limits
- LR-N03-0220, Notification of Intent to Apply the 10 CFR 50 Appendix B Quality Assurance Program to Independent Spent Fuel Storage Installation Activities
- LR-N03-0223, April 2003 Monthly Operating Report for Salem Generating Station Unit 1
- LR-N03-0224, April 2003 Monthly Operating Report for Salem Generating Station Unit 2
- LR-N03-0225, April 2003 Monthly Operating Report for Hope Creek Generating Station
- LR-N03-0243, Fuel Related Analyses for Extended Power Uprate and Fuel Vendor Change
- LR-N03-0249, Request for Approval of Changes to Post-Fire Safe Shutdown Strategy for Fire Areas 2-FA-AB-64B, 2-FA-AB-84C and 2-FA-AB-84B
- LR-N03-0250, Core Operating Limits Report - Cycle 12
- LR-N03-0259, May 2003 Monthly Operating Report for Salem Generating Station Unit 2
- LR-N03-0277, Response to RAI Re Risk-Informed Inservice Inspection Submittal
- LR-N03-0293, Steam Generator Tubesheet Inspection Information
- LR-N03-0305, Response to 06/17/03 Request for Additional Information Relief Request S1-RR-F01 for Salem Unit 1
- LR-N03-0308, June 2003 Monthly Operating Report for Hope Creek Generating Station
- LR-N03-0310, June 2003 Monthly Operating Report for Salem Unit 2
- LR-N03-0359, July 2003 Monthly Operating Report for Salem Generating Station Unit 2
- LR-N03-0386, Transmittal of Information Relating to SVEA-96+ Modeling Dimensions in Support of the Nrc'S Review of GNF-A Proprietary Report, NEDC-33107P, GEXL80 Correlation for SVEA96+ Fuel, Dated September 2003
- LR-N03-0388, GE14 and SVEA-96+ Thermal-Hydraulic Compatibility Report
- LR-N03-0392, August 2003 Monthly Operating Report for Hope Creek
- LR-N03-0393, August 2003 Monthly Operating Report for Salem Unit 1
- LR-N03-0394, August 2003 Monthly Operating Report for Salem Unit 2
- LR-N03-0405, Request for Change to Technical Specifications Regarding Reactor Protection System Instrumentation, Control Rod Block Instrumentation, Source Range Monitors, and Power Distribution Limits Surveillance Requirements
- LR-N03-0406, GNF-A Proprietary Report, NEDC-33107P, GEXL80 Correlation for SVEA96+ Fuel. (Non-Proprietary Version)
- LR-N03-0434, September 2003 Monthly Operating Report for Hope Creek Generating Station
- LR-N03-0435, September 2003 Monthly Operating Report for Salem, Unit 1
- LR-N03-0436, September 2003 Monthly Operating Report for Salem Generating Station, Unit 2
- LR-N03-0448, Core Operating Limits Report - Cycle 14
- LR-N03-0450, Inservice Inspection Program Relief Requests SC-RR-03-V01 and V02
- LR-N03-0451, Inservice Inspection Program Relief Requests S2-RR-03-V01 and V02
- LR-N03-0457, Stations - Closeout of Order for Compensatory Measures Related to Fitness-for-Duty Enhancements Applicable to Nuclear Facility Security Force Personnel
- LR-N03-0466, Steam Generator Tube Plugging Report Per Technical Specification 4.4.6.5.A
- LR-N03-0468, October 2003 Monthly Operating Report for Hope Creek Generating Station
- LR-N03-0469, October 2003 Monthly Operating Report for Salem, Unit 1
- LR-N03-0470, October 2003 Monthly Operating Report for Salem, Unit 2
- LR-N03-0471, 180-Day Response to Generic Letter 2003-01, Control Room Habitability
- LR-N03-0476, Withdrawal of Request for One-Time Only Change to Technical Specifications, Control Room Emergency Filtration System
- LR-N03-0517, November 2003 Monthly Operating Report for Hope Creek Generating Station
- LR-N03-0518, November 2003 Monthly Operating Report for Salem Unit 1
- LR-N03-0519, November 2003 Monthly Operating Report for Salem Unit 2
- LR-N03-0524, Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity
- LR-N03-0526, Letter Informing NRC Regarding Plans to Enable the Oscillation Power Range Monitor (OPRM) Trip Function for the Hope Creek
- LR-N03-0529, 60-day Response to Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel-Heads at Pressurized Water Reactors
- LR-N03-0533, Revised Core Operating Limits Report, Cycle 12
- LR-N04-0002, Request for Additional Information Response - Hope Creek Generating Station Relief Request HC-RR-B12
- LR-N04-0004, Response to NRC Request for Additional Information (RAI) Steam Generator Tube Inspections Annual Report
- LR-N04-0010, Stations - Closeout of Order for Compensatory Measures Related to Access Authorization
- LR-N04-0011, December 2003 Monthly Operating Report for Hope Creek Generating Station
- LR-N04-0013, December 2003 Monthly Operating Report Salem Generating Station Unit 2
- LR-N04-0021, Units I and 2 - Implementation of Alternative Source Term (AST) Request for Changes to Technical Specifications and Updated Final Safety Analysis Report
- LR-N04-0022, Technical Specification Bases Change S03-09B
- LR-N04-0034, Relief Request S1-RR-W02, Proposed Alternative Repair Method for Reactor Vessel Head Penetrations
- LR-N04-0036, Correction PSEG Letter LR-N04-0036, Risk-Informed Inservice Inspection Submittal
- LR-N04-0040, Response to RAI Regarding Relief Request S1-RR-13-B21, NRC Order EA-03-009 on Reactor Pressure Vessel Head Inspections Salem, Unit I
- LR-N04-0042, Stations - Semi-Annual Report of Fitness-for-Duty Performance Data for Period Ending December 31, 2003
- LR-N04-0055, Submittal of the 90-Day Report for Inservice Inspection Activities Conducted During the Thirteenth Refueling Outage
- LR-N04-0059, January 2004 Monthly Operating Report for Hope Creek Generating Station
- LR-N04-0060, January 2004 Monthly Operating Report for Salem, Unit 1
- LR-N04-0061, January 2004 Monthly Operating Report for Salem, Unit 2
- LR-N04-0062, Request for License Amendment Arts/Mellla Implementation
- LR-N04-0066, Transmittal of Technical Specification 6.9.1.5 Annual Reports
- LR-N04-0077, Revision 1 to 180-Day Response to Generic Letter 2003-01, Control Room Habitability
- LR-N04-0089, Request for Changes to Technical Specifications, Containment Systems - Containment Cooling System
- LR-N04-0096, Relaxation Request to First Revised NRC Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors (Relief Request S1-RR-13-B22)
- LR-N04-0098, Response to Issuance of First Revised NRC Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors
- LR-N04-0108, Steam Generator Condition Monitoring Report
- LR-N04-0109, February 2004 Monthly Operating Report for Hope Creek Generating Station
- LR-N04-0110, February 2004 Monthly Operating Report for Salem, Unit 1
- LR-N04-0111, February 2004 Monthly Operating Report for Salem, Unit 2
- LR-N04-0113, Risk-Informed Technical Specifications Pilot Plant Request for Fee Waiver
- LR-N04-0116, Stations, 2003 Annual Radiological Environmental Operating Report
- LR-N04-0117, Stations, Radioactive Effluent Release Report
- LR-N04-0120, Summary of Revised Regulatory Commitments
- LR-N04-0130, Update ASME XI Code of Record, Request That Relief Request S1-I3-RR-A13 Be Withdrawn
- LR-N04-0136, Request for Change to Technical Specifications Pressure/Temperature Limits
- LR-N04-0137, Request for Additional Information Inservice Inspection Program Relief Request HC-RR-12-023
- LR-N04-0146, February 2005 Monthly Operating Report for Salem Generating Station Unit 2
- LR-N04-0156, Response to Request for Additional Information Regarding Relief Request S1-RR-13-B21 NRC Order EA-03-009 on Reactor Pressure Vessel Head Inspections
- LR-N04-0158, Guaranteed Retrospective Premiums Following a Nuclear Accident
- LR-N04-0161, Update ASME XI Code of Record
- LR-N04-0166, Core Operating Limits Report - Cycle 16, Revision 1
- LR-N04-0167, Core Operating Limits Report - Cycle 14, Revision 1
- LR-N04-0169, March 2004 Monthly Operating Report for Hope Creek Generating Station
- LR-N04-0170, March 2004 Monthly Operating Report for Salem Generating Station Unit 1
- LR-N04-0171, March 2004 Monthly Operating Report for Salem Generating Station Unit 2
- LR-N04-0175, Response to Request for Additional Information Regarding Relaxation Request S1-RR-I3-B21, First Revised NRC Order (EA-03-009) on Reactor Pressure Vessel Head Inspections Salem Generating Station Unit 1
- LR-N04-0183, Request for Change to Technical Specifications Safety Limit Minimum Critical Power Ratio
- LR-N04-0184, Supplemental Response to the April 29, 2003, Orders
- LR-N04-0185, Steam Generator Tube Plugging Report as Required by Technical Specification 4.4.5.5.a
- LR-N04-0199, Response to Request for Additional Information Regarding Relief Request S1-RR-13-B21 NRC Order EA-03-009 on Reactor Pressure Vessel Head Inspections
- LR-N04-0208, Unit I Withdrawal of Relief Request S1-RR-W02, Proposed Alternative Repair Method for Reactor Vessel Head Penetrations
- LR-N04-0211, April 2004 Monthly Operation Report for Hope Creek Generating Station
- LR-N04-0215, Transmittal of Westinghouse WCAP 16193-P Containment Response to LOCA and MSLB for Containment Fan Cooler/Service Water System Enhancement Project
- LR-N04-0222, Stations, Use of Encryption Software for Electronic Transmission of Safeguards Information
- LR-N04-0226, Correction to References in PSEG Letter LR-N04-0036, Risk-Informed Inservice Inspection Submittal
- LR-N04-0227, Ltr Dated 5/21/04: PSEG Plan for Improving the Work Environment to Encourage Identification and Resolution of Issues Salem & Hope Creek
- LR-N04-0230, Extension of Risk-Informed Inservice Inspection Applicability
- LR-N04-0238, Request for Change to Technical Specifications, to Modify Definition of Operable
- LR-N04-0239, Core Operating Limits Report - Cycle 17, Revisions 0 and 1
- LR-N04-0241, Reply to Notice of Violation EA-04-086 Issued on 05/10/2004
- LR-N04-0251, Response to Request for Additional Information Request for Change to Technical Specifications Re Fuel Vendor Change
- LR-N04-0255, May 2004 Monthly Operating Report for Hope Creek Generating Station
- LR-N04-0256, May 2004 Monthly Operating Report for Salem Generating Station Unit 1
- LR-N04-0260, Response to Request for Additional Information Request for Change to Technical Specifications Reactor Protection System Instrumentation, Control Rod Block Instrumentation, Source Range Monitors and Power Distribution Limit Surveillance.
- LR-N04-0263, Ltr from R. Anderson of PSEG to D. Vito of USNRC, Regarding Salem and Hope Creek Generating Stations Docket Nos. 50-272, 50-311 and 50-354
- LR-N04-0286, PSEG-Nuclear Organizational Update Salem and Hope Creek Generating Stations
- LR-N04-0297, NRC Bulletin 2003-02 Inspection Results Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity
- LR-N04-0299, Inservice Inspection Program Relief Requests S1-RR-04-V01 and V02
- LR-N04-0301, June 2004 Monthly Operating Report for Hope Creek Generating Station
- LR-N04-0302, June 2004 Monthly Operating Report from Salem Generating Station Unit 1
- LR-N04-0309, Inservice Inspection Program Relief Request HC-RR-A10
- LR-N04-0310, Response to Request for Additional Information Regarding Request for Change to Technical Specifications to Support Removal of the Reactor Vessel Head Spray Piping Hope Creek Generating Station
- LR-N04-0326, Response to Request for Additional Information Request for Change to Technical Specifications Pressure/Temperature Limits
- LR-N04-0328, Inservice Inspection Activities - 90 Day Report Sixteenth Refueling Outage
- LR-N04-0333, Stations, Response to Requests for Additional Information Related to the Supplemental Response to the April 29, 2003, Orders
- LR-N04-0336, Response to Request for Additional Information Regarding Request for Change to Oscillation Power Range Monitor (OPRM) Technical Specifications
- LR-N04-0337, Loss of Coolant Accident Peak Clad Temperature Annual Report
- LR-N04-0341, First Revised NRC Order EA-03-009: Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Post Outage Inspection Results
- LR-N04-0343, Revised Request for Changes to Technical Specifications Containment Systems - Containment Cooling System
- LR-N04-0345, Request for Change to Technical Specifications to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process
- LR-N04-0350, Request for Change to Technical Specifications to Eliminate Requirements for Hydrogen Recombiners and Primary Containment Hydrogen/Oxygen Concentration Analyzer and Monitor Channels Using the Consolidated Line Item.
- LR-N04-0359, Response to Request for Additional Information for LCR-S02-10, Request for Change to Technical Specifications Relaxation of Requirements Applicable During Movement of Irradiated Fuel
- LR-N04-0361, Response to Second Request for Additional Information for LCR-H03-07 Request for Change to Technical Specifications Emergency Diesel Generator (EDG) Surveillance Testing
- LR-N04-0365, Response to Request for Additional Information Regarding Request for Change to Technical Specifications to Support Removal of the Reactor Vessel Head Spray Piping