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| Issue date | Title | Topic | |
|---|---|---|---|
| RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. | 10 August 2022 | R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. | Safe Shutdown Non-Destructive Examination Post Accident Monitoring Internal Flooding Probabilistic Risk Assessment Nondestructive Examination Cyber Security Pressure and Temperature Limits Report Surveillance Frequency Control Program Fire Protection Program |
| ML22145A586 | 3 June 2022 | R. E. Ginna Correction to Pages Issued for Amendments Nos. 225, 225, 227, 227, & 148, Respectively, Regarding Issues Identified in Westinghouse Documents | |
| ML22118B143 | 28 April 2022 | Supplemental Information No. 2 for R.E. Ginna Nuclear Power Plant to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b | Reactor Vessel Water Level Surveillance Frequency Control Program Power change |
| RS-22-008, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin | 24 January 2022 | Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin | Shutdown Margin Anticipated operational occurrence Post Accident Monitoring Hydrostatic Coatings Pressure and Temperature Limits Report Process Control Program Power change |
| RS-21-082, Attachment 2 - Technical Basis for NSAL-09-5 Revision 1 and Applicability to Byron, Braidwood, and R.E. Ginna Non-Proprietary Version for NRC | 13 August 2021 | Attachment 2 - Technical Basis for NSAL-09-5 Revision 1 and Applicability to Byron, Braidwood, and R.E. Ginna Non-Proprietary Version for NRC | |
| ML20339A221 | 20 November 2020 | Technical Specifications Bases, Rev 101 | Safe Shutdown Unanalyzed Condition Boric Acid Shutdown Margin Reactor Vessel Water Level High Radiation Area Non-Destructive Examination Grab sample Fire Barrier Stroke time Anticipated operational occurrence Tornado Missile Post Accident Monitoring Internal Flooding Hydrostatic Coatings Qualified Offsite Circuit Missed surveillance Surveillance Frequency Control Program Foreign Material Exclusion Battery sizing Earthquake Power Operated Valves Turbine Missile Fuel cladding Pressure Boundary Leakage Offsite Circuit Power change Unidentified leakage Power Uprate |
| JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability | 22 June 2020 | Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability | Time of Discovery |
| JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability | 27 June 2019 | Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability | Fire Barrier Tornado Missile Internal Flooding Incorporated by reference Turbine Missile |
| RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls | 26 June 2019 | Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls | High Radiation Area Locked High Radiation Area Process Control Program Deep Dose Equivalent |
| ML19150A511 | 10 May 2019 | Revision 90 to Technical Specification Bases | Safe Shutdown Unanalyzed Condition Boric Acid Shutdown Margin Reactor Vessel Water Level High Radiation Area Non-Destructive Examination Grab sample Stroke time Anticipated operational occurrence Tornado Missile Post Accident Monitoring Hydrostatic Qualified Offsite Circuit Missed surveillance Surveillance Frequency Control Program Foreign Material Exclusion Battery sizing Earthquake Power Operated Valves Fuel cladding Pressure Boundary Leakage Offsite Circuit Power change Unidentified leakage Power Uprate |
| ML18176A327 | 25 June 2018 | R. E. Ginna Nuclear Power Plant - License Amendment Request: Revision to Technical Specifications to Adopt Technical Specifications Task Force TSTF-547, Revision 1, Clarification of Rod Position Requirements | Boric Acid Shutdown Margin Anticipated operational occurrence Surveillance Frequency Control Program Fuel cladding |
| ML16209A218 | 26 July 2016 | Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. | Shutdown Margin Reactor Vessel Water Level Packing leak High Radiation Area Stroke time Hydrostatic Squib Incorporated by reference Missed surveillance Surveillance Frequency Control Program Excess Flow Check Valve Power Operated Valves Pressure Boundary Leakage Recently irradiated fuel Power change Unidentified leakage |
| ML16168A261 | 16 June 2016 | Supplement No. 2 to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Rev. 3).... | |
| ML15166A075 | 4 June 2015 | Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) | Safe Shutdown Boric Acid High winds Shutdown Margin Reactor Vessel Water Level High Radiation Area Ultimate heat sink Stroke time Post Accident Monitoring Internal Flooding Hydrostatic Probabilistic Risk Assessment Multiple Spurious Operation Incorporated by reference Surveillance Frequency Control Program Battery sizing Power Operated Valves Pressure Boundary Leakage Offsite Circuit Power change Unidentified leakage |
| ML14191A255 | 10 July 2014 | Nine Mile Point and Ginna, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process | Unanalyzed Condition Boric Acid Reactor Vessel Water Level Ultimate heat sink Stroke time Time to boil Fuel cladding |
| ML121290485 | 20 April 2012 | LAR File for Rod Indication/Attachment 1 Mrpi LAR | Shutdown Margin |
| ML11129A013 | 3 May 2011 | Update to License Amendment Request: Improvement to the Definition of Operations Involving Positive Reactivity Changes (TSTF-286) | Unanalyzed Condition Shutdown Margin |
| ML090890191 | 23 March 2009 | R. E. Ginna - License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions for TS 5.2.2 to Support Compliance with 10 CFR Part 26 | Safe Shutdown |
| ML083530806 | 23 February 2009 | R. E. Ginna Nuclear Power Plant - Amendment Re Revised Methodology for Determining Reactor Coolant System Pressure and Temperature and Low Temperature Over-Pressure Limits | Shutdown Margin Offsite Dose Calculation Manual Hydrostatic Nondestructive Examination Pressure and Temperature Limits Report Annual Radiological Environmental Operating Report |
| ML083460051 | 4 December 2008 | R. E. Ginna Nuclear Power Plant - License Amendment Request: Revision of Tech Spec. 3.9.3 to Allow Refueling Operations Inside Containment with Both Personnel Hatch Air Lock Doors Open Under Administrative Control, and Obtain Regulatory Rev | Anticipated operational occurrence Tornado Generated Missile Deep Dose Equivalent |
| ML072350432 | 16 August 2007 | R. E. Ginna - Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process | Safe Shutdown Offsite Dose Calculation Manual Tornado Missile Incorporated by reference |
| ML060480244 | 15 February 2006 | Technical Specification Pages Re Relaxed Axial Offset Control | Shutdown Margin Offsite Dose Calculation Manual Hydrostatic Pressure and Temperature Limits Report Annual Radiological Environmental Operating Report |
| ML053470201 | 8 December 2005 | R. E. Ginna Nuclear Power Plant, 5.5.1 Offsite Dose Calculation Manual (ODCM) | Offsite Dose Calculation Manual |
| ML051950123 | 7 July 2005 | License Amendment Request Regarding Extended Power Uprate | Ultimate heat sink Offsite Dose Calculation Manual Zebra Mussel Annual Radioactive Effluent Release Report License Renewal Fuel cladding Biofouling Pressure Boundary Leakage Unidentified leakage Power Uprate Affidavit |
| ML051300330 | 29 April 2005 | License Amendment Request Regarding Adoption of Relaxed Axial Offset Control (RAOC) | Unanalyzed Condition Shutdown Margin Offsite Dose Calculation Manual Anticipated operational occurrence Hydrostatic Pressure and Temperature Limits Report Annual Radiological Environmental Operating Report Fuel cladding Power change |
| ML050770204 | 14 March 2005 | R. E. Ginna, Replacement Pages Associated with the Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process | Reactor Vessel Water Level Post Accident Monitoring |
| ML050760381 | 10 March 2005 | R. E. Ginna - Application for Amendment to Facility Operating License Proposed License Amendment to Provide a One-time Integrated Leak Rate Test (ILRT) Interval Extension | Boric Acid Offsite Dose Calculation Manual Probabilistic Risk Assessment Large early release frequency Moisture barrier License Renewal Power Uprate |
| ML050620306 | 1 March 2005 | R. E. Ginna, Tech Spec Pages for Amendment 88 Regarding Increased Flexibility in Mode Restraints | Grab sample Post Accident Monitoring Offsite Circuit |
| ML042680047 | 22 September 2004 | Tech Spec for R. E. Ginna Nuclear Power Plant, Issuance of Amendment Revision to Core Safety Limits and Safety System Instrumentation Setpoints | Shutdown Margin Offsite Dose Calculation Manual Hydrostatic Pressure and Temperature Limits Report Annual Radiological Environmental Operating Report |
| ML040230729 | 22 January 2004 | R. E. Ginna Nuclear Power Plant, Revised Technical Specification Pages 3.1.3-1, 3.1.3-2, 3.3.6-1, 3.3.6-2, 3.3.6-3, Attachments 1 and 2 | |
| ML18142B948 | 22 December 1977 | R. E. Ginna - Letter Transmitting 3 Signed Originals and 19 Copies of Document Entitled, Application for Amendment to Operating License. | |
| ML18142B950 | 21 November 1977 | R. E. Ginna - Letter Transmitting 3 Signed Originals and 19 Copies of Document Entitled, Application for Amendment to Operating License. | |
| ML18143A212 | 6 January 1977 | R. E. Ginna - Forwards Copies of Application for Amendment to Operating License | |
| ML18142B988 | 21 January 1976 | R. E. Ginna - Forwards Copies of Proposed Change to Technical Specifications to Change Surveillance Requirements for Integrated Leakage Rate from Containment, and Copies of Application for Amendment to Operating License. | |
| ML18142C027 | 15 October 1974 | Transmittal of Rge Application for Amendment to Technical Specifications for Inspection Requirement for Hydraulic Snubbers | |
| ML18142C028 | 15 October 1974 | Letter Submitted Application for Amendment to Technical Specification, Consisting a Request for a Change to the License Maybe Amended to Add Inspection Requirement for Steam Generator Tubes | |
| ML18142C029 | 30 September 1974 | Letter Requesting a Proposed Change to the Technical Specification to Increase the Indicated Water Level to the Accumulators to Conform to Accident Analysis Assumptions | |
| ML18142C032 | 9 July 1974 | Submittal of Application for Amendment to Applicant'S Technical Specifications, Describing Duties and Responsibilities of the Plant Review and Audit Groups |