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 Issue dateTitleTopic
LR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies23 June 2023License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test FrequenciesHot Short
Safe Shutdown
Boric Acid
High winds
Weld Overlay
Internal Flooding
Probabilistic Risk Assessment
Coatings
Emergency Lighting
Incorporated by reference
FLEX
Aging Management
Test box
Thermoset
Local Leak Rate Testing
Foreign Material Exclusion
Large early release frequency
Integrated leak rate test
Moisture barrier
License Renewal
Fuel cladding
Power Uprate
LR-N21-0048, One-Time License Amendment Request to Revise Unit 2 Technical Specification Action for Rod Position Indicators18 June 2021One-Time License Amendment Request to Revise Unit 2 Technical Specification Action for Rod Position IndicatorsSafe Shutdown
High winds
Shutdown Margin
Anticipated operational occurrence
FLEX
Power change
LR-N21-0006, Application to Revise Technical Specifications to Adopt TSTF-569 Revision of Response Time Testing Definitions16 February 2021Application to Revise Technical Specifications to Adopt TSTF-569 Revision of Response Time Testing DefinitionsShutdown Margin
Packing leak
LR-N20-0072, License Amendment Request to Amend Tech Specs to Revise and Relocate the Reactor Coolant System Pressure & Temperature Limits & Pressurizer Overpressure Protection System Limits to a Pressure & Temperature Limits Report6 December 2020License Amendment Request to Amend Tech Specs to Revise and Relocate the Reactor Coolant System Pressure & Temperature Limits & Pressurizer Overpressure Protection System Limits to a Pressure & Temperature Limits ReportAnticipated operational occurrence
Hydrostatic
Incorporated by reference
B.5.b
Pressure and Temperature Limits Report
License Renewal
Exemption Request
Pressure Boundary Leakage
LR-N15-0020, License Amendment Request to Revise Technical Specification 3/4.3.1, Reactor Trip System Instrumentation27 March 2015License Amendment Request to Revise Technical Specification 3/4.3.1, Reactor Trip System InstrumentationSafe Shutdown Earthquake
Operating Basis Earthquake
Surveillance Frequency Control Program
Earthquake
Affidavit
ML11186156028 July 2011and Salem Nuclear Generating Station, Unit Nos. 1 and 2, License Amendment, Issuance of Amendments Approval of Cyber Security PlanCyber Security
Excess Flow Check Valve
Safeguards Contingency Plan
License Renewal
Cyber attack
LR-N09-0034, License Amendment Request to Relocate Communications, Manipulator Crane, and Crane Travel Requirements from Technical Specifications9 April 2009License Amendment Request to Relocate Communications, Manipulator Crane, and Crane Travel Requirements from Technical SpecificationsUnanalyzed Condition
Shutdown Margin
Probabilistic Risk Assessment
Control of Heavy Loads
LR-N08-0046, Request for Changes to Technical Specifications Refueling Operations - Decay Time, License Amendment Request (LAR) S08-0111 March 2008Request for Changes to Technical Specifications Refueling Operations - Decay Time, License Amendment Request (LAR) S08-01Shutdown Margin
Ultimate heat sink
Probabilistic Risk Assessment
Design basis earthquake
Power Uprate
ML0715901856 June 2007Units, 1 and 2, Tech Spec Pages for Amendment 265 Relocation of Technical Specification Requirements for the Movable Incore Detectors and Radioactive Gaseous Effluent Oxygen Monitoring InstrumentationGrab sample
LR-N07-0030, License Change Request S06-010, Steam Generator Feedwater Pump Trip, Feedwater Isolation Valve Response Time Testing and Containment Cooling System16 March 2007License Change Request S06-010, Steam Generator Feedwater Pump Trip, Feedwater Isolation Valve Response Time Testing and Containment Cooling SystemUltimate heat sink
Stroke time
High Energy Line Break
Coast down
ML07019009411 January 2007License Amendment Request 07-01, Revision to Technical Specifications to Support Steam Generator ReplacementShutdown Margin
High Radiation Area
Offsite Dose Calculation Manual
Anticipated operational occurrence
Post Accident Monitoring
Hydrostatic
Probabilistic Risk Assessment
Nondestructive Examination
Pressure and Temperature Limits Report
Annual Radiological Environmental Operating Report
Process Control Program
Stress corrosion cracking
Eddy Current Testing
Affidavit
Operational leakage
LR-N06-0201, Request for Change to Technical Specifications to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Analyzers Using the Consolidated Line Item Improvement Process7 June 2006Request for Change to Technical Specifications to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Analyzers Using the Consolidated Line Item Improvement ProcessIncorporated by reference
LR-N06-0055, Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program and Steam Generator Tube Inspection Report and to Revise Reactor Coolant System Operational Leakage Requiremen6 April 2006Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program and Steam Generator Tube Inspection Report and to Revise Reactor Coolant System Operational Leakage RequirementsSafe Shutdown
Offsite Dose Calculation Manual
Hydrostatic
Nondestructive Examination
Annual Radioactive Effluent Release Report
Process Control Program
Stress corrosion cracking
Earthquake
Pressure Boundary Leakage
Fire Protection Program
Unidentified leakage
Operational leakage
ML06013002511 January 2006Technical Specifications Deletion of Reactor Coolant System Volume
ML0525600409 September 2005Units, 1 and 2 - Tech Spec Pages for Amendments 265 and 247 to Extend the Inspection Interval for Reactor Coolant Pump Flywheels
LR-N05-0377, Revision to Request for Changes to Technical Specifications Containment Systems - Containment Cooling System11 August 2005Revision to Request for Changes to Technical Specifications Containment Systems - Containment Cooling SystemHigh Radiation Area
LR-N05-0018, Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program, & Steam Generator Tube Inspection Report & to Revise Reactor Coolant System Operational.23 February 2005Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program, & Steam Generator Tube Inspection Report & to Revise Reactor Coolant System Operational.Safe Shutdown
Offsite Dose Calculation Manual
Hydrostatic
Operating Basis Earthquake
Nondestructive Examination
Annual Radioactive Effluent Release Report
Process Control Program
Stress corrosion cracking
Earthquake
Pressure Boundary Leakage
Fire Protection Program
Unidentified leakage
Overspeed trip
Operational leakage
LR-N04-0021, Units I and 2 - Implementation of Alternative Source Term (AST) Request for Changes to Technical Specifications and Updated Final Safety Analysis Report26 April 2004Units I and 2 - Implementation of Alternative Source Term (AST) Request for Changes to Technical Specifications and Updated Final Safety Analysis ReportPacking leak
Probabilistic Risk Assessment
Deep Dose Equivalent
Fuel cladding
Power Uprate
Operational leakage
Potassium iodide
ML0400804437 January 2004Tech Spec Pages for License Amendment, Request for Changes to License Condition 2.C.(10)Safe Shutdown
Fire Protection Program
LR-N03-0092, Request for Change to TSs Explosive Gas Mixture6 June 2003Request for Change to TSs Explosive Gas MixtureAnticipated operational occurrence
LR-N03-0022, Revision to Request for Change to Technical Specifications14 February 2003Revision to Request for Change to Technical SpecificationsBoric Acid
Shutdown Margin
LR-N03-0014, Request for Change to Technical Specifications Administrative and Editorial Changes29 January 2003Request for Change to Technical Specifications Administrative and Editorial Changes
LR-N02-0344, Request for Change to Technical Specifications Revise Section 6.12, High Radiation Area.23 October 2002Request for Change to Technical Specifications Revise Section 6.12, High Radiation Area.High Radiation Area
Offsite Dose Calculation Manual
Process Control Program
ML0200702424 January 2002TS Pages to Amendment 249 & 229 Change to Technical Specifications 28 Volt D.C. Distribution