Semantic search
Jump to navigation
Jump to search
Issue date | Title | Topic | |
---|---|---|---|
ML23235A172 | 23 August 2023 | Re. Ginna Nuclear Power Plant, Transmittal of 2023 Owner'S Activity Report | |
NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits | 30 June 2022 | Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits | Mururoa |
ML21350A114 | 16 December 2021 | Annual Commitment Change Notification | |
ML21316A051 | 12 November 2021 | Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections | EVT-1 |
RS-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections | 1 September 2021 | R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections | Finite Element Analysis Aging Management |
RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping | 4 January 2021 | Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping | Nondestructive Examination |
ML20303A175 | 23 October 2020 | Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting | |
ML20265A198 | 21 September 2020 | R. E. Ginna Nuclear Power Plant, Application to Revise Technical Specifications for Steam Generator Tube Inspection Frequency | Anticipated operational occurrence Weld Overlay Locked High Radiation Area Pandemic COVID-19 |
ML17345A990 | 21 December 2017 | R. E. Ginna Nuclear Power Plant Flood Hazard Mitigation Strategies Assessment | High winds FLEX Fukushima Dai-Ichi Spent Fuel Pool Instrumentation Flood Hazard Mitigation Strategies Assessment |
ML17214A118 | 27 July 2017 | Transmittal of 2017 Owner'S Activity Report for the Plant | |
ML15167A505 | 11 June 2015 | (Redacted Version) Response to Request for Additional Information Regarding the License Amendment Request (LAR) to Adopt NFPA 805, Attachment 3 | Hot Short Safe Shutdown Fire Barrier Coatings Hemyc Earthquake Fire Protection Program Fire Watch |
ML15153A026 | 11 June 2015 | Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insight | Safe Shutdown Earthquake Fukushima Dai-Ichi Earthquake |
RS-15-069, Enclosure 2: Areva, Inc., Rev. 1 to 51-9205719-001, R.E. Ginna Nuclear Power Plant Flood Hazard Reevaluation Report, Part 2 of 2 | 11 March 2015 | Enclosure 2: Areva, Inc., Rev. 1 to 51-9205719-001, R.E. Ginna Nuclear Power Plant Flood Hazard Reevaluation Report, Part 2 of 2 | Earthquake |
ML15072A011 | 11 March 2015 | Enclosure 2: Areva, Inc., Rev. 1 to 51-9205719-001, R.E. Ginna Nuclear Power Plant Flood Hazard Reevaluation Report, Part 1 of 2 | Safe Shutdown High winds Safe Shutdown Earthquake Hydrostatic Operating Basis Earthquake Fukushima Dai-Ichi Earthquake |
RS-15-069, Enclosure 2: Areva, Inc., Rev. 1 to 51-9205719-001, R.E. Ginna Nuclear Power Plant Flood Hazard Reevaluation Report, Part 1 of 2 | 11 March 2015 | Enclosure 2: Areva, Inc., Rev. 1 to 51-9205719-001, R.E. Ginna Nuclear Power Plant Flood Hazard Reevaluation Report, Part 1 of 2 | Safe Shutdown High winds Safe Shutdown Earthquake Hydrostatic Operating Basis Earthquake Fukushima Dai-Ichi Earthquake |
RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 | 24 September 2014 | Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 | Through-Wall Leak |
ML14170B022 | 26 June 2014 | Staff Assessment of Flooding Walkdown Reports Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Accident | Safe Shutdown Unanalyzed Condition Time of Discovery Hydrostatic Operator Manual Action Locked High Radiation Area Fukushima Dai-Ichi Earthquake |
ML14099A196 | 31 March 2014 | Constellation Energy Nuclear Group, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task. | Safe Shutdown Unanalyzed Condition Mission time Safe Shutdown Earthquake Internal Flooding Probabilistic Risk Assessment Operating Basis Earthquake Fukushima Dai-Ichi Design basis earthquake Operability Determination Earthquake Operability Assessment Seismic Walkdown Report |
ML14071A478 | 21 February 2014 | Response to Nrc'S Request for Cashflow Statements Regarding Application for Order Approving Transfer of Operating Authority and Conforming License Amendments | |
ML14007A704 | 19 February 2014 | R. E. Ginna Nuclear Power Plant - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) | Safe Shutdown Boric Acid High winds Shutdown Margin Ultimate heat sink Safe Shutdown Earthquake Internal Flooding Emergency Lighting FLEX Tornado Generated Missile Fukushima Dai-Ichi Frazil ice Earthquake Fire Protection Program |
ML14037A277 | 9 February 2014 | Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for R.E. Ginna Nuclear Power Plant, TAC No.: MF1152 | Safe Shutdown Boric Acid High winds Shutdown Margin Ultimate heat sink Tornado Missile Safe Shutdown Earthquake Internal Flooding Emergency Lighting FLEX Fukushima Dai-Ichi Frazil ice Earthquake Fire Protection Program |
ML13294A023 | 16 October 2013 | Snubber Program Plan | High Radiation Area Nondestructive Examination |
ML13210A034 | 25 July 2013 | Supplemental Response to 10 CFR 50.54(f) Request for Recommendation 2.3, Seismic Information | Safe Shutdown Unanalyzed Condition Fukushima Dai-Ichi Earthquake |
ML13093A065 | 29 March 2013 | Transition Report to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition - Transition Report, Redacted Version. Enclosure 2 | Hot Short Safe Shutdown Boric Acid Shutdown Margin Ultimate heat sink Mission time Fire Barrier Time to boil Internal Flooding Enforcement Discretion Probabilistic Risk Assessment Fire impairment Operator Manual Action Multiple Spurious Operation Emergency Lighting Large early release frequency Hemyc Exemption Request Earthquake Maintenance Rule Program Fire Protection Program Fire Watch |
ML13066A171 | 28 February 2013 | R.E. Gina, Overall Integrated Plan for Mitigation Strategies for Beyond-Design-Basis External Events | Safe Shutdown Boric Acid High winds Shutdown Margin Ultimate heat sink Tornado Missile Time to boil Safe Shutdown Earthquake Internal Flooding Probabilistic Risk Assessment Operating Basis Earthquake Emergency Lighting FLEX Tornado Generated Missile Fukushima Dai-Ichi Design basis earthquake Spent Fuel Pool Instrumentation B.5.b Mitigating Strategies Earthquake Pressure Boundary Leakage Fire Protection Program |
ML12362A451 | 21 December 2012 | Supplemental Response to 10 CFR 50.54(f) Request for Information, Recommendation 2.3. Seismic, Attachment (1) Supplemental Seismic Walkdown Report, Table of Contents Through Attachment (2) Seismic Walkdown Checklists, Page B-90 | Safe Shutdown Unanalyzed Condition Boric Acid Locked High Radiation Area Fukushima Dai-Ichi Seismically rugged License Renewal Earthquake Seismic Walkdown Report |
ML12362A452 | 21 December 2012 | Supplemental Response to 10 CFR 50.54(f) Request for Information, Recommendation 2.3. Seismic, Attachment (3) Area Walk-By Checklists Through End | Boric Acid Aging Management Scaffolding |
ML12277A090 | 12 October 2012 | Technical Letter Report on Aging Management Program Audits at Ginna and Nine Mile Point 1 | Safe Shutdown Boric Acid Ultimate heat sink Non-Destructive Examination Fire Barrier Weld Overlay Coatings VT-2 Aging Management Foreign Material Exclusion Moisture barrier Earthquake Biofouling EVT-1 Through-Wall Leak Through-Wall Leakage Preliminary White Finding Fire Protection Program Dissimilar Metal Weld |
ML12277A174 | 28 September 2012 | R. E. Ginna - License Renewal Aging Management, Submit Revised Reactor Vessel Internals Program Document in Accordance with RIS 2011-07 | Boric Acid Nondestructive Examination Functionality Assessment Aging Management EVT-1 |
ML12080A142 | 16 March 2012 | Attachments 1 & 2, Structural Integrity Evaluation of Circumferential Indication in Ginna Bmi Nozzle No. A86, and Location of Indications in A86 Bmi Penetration | |
ML11343A679 | 6 December 2011 | Report of Facility Changes. Tests, and Experiments Conducted Without Prior Commission Approval | |
ML11363A075 | 5 October 2011 | Reactor Vessel Bottom Mounted Instrumentation Paint Cracking Analysis | Pressure Boundary Leakage |
ML11363A076 | 31 August 2011 | Evaluation of Leakage and Deposit Formation in Painted Full-Scale Bmi Mockups, Final Report, Revision 2, Swri Project No. 18.16196, Ceng Purchase Order No. 6610691 | Boric Acid Finite Element Analysis |
ML102730623 | 22 September 2010 | R. E. Ginna - Transmittal of RCS Pressure and Temperature Limits Report (PTLR) | Pressure and Temperature Limits Report |
ML101270439 | 5 May 2010 | Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants | |
ML100920057 | 29 March 2010 | Report of Facility Changes, Tests, and Experiments Conducted Without Prior Commission Approval | |
ML091550271 | 31 May 2009 | WCAP-17036-NP, Rev 0, Analysis of Capsule N from the R.E. Ginna Reactor Vessel Radiation Surveillance Program. | |
ML091480261 | 19 May 2009 | Transmittal of RCS Pressure and Temperature Limits Report (PTLR) | Pressure and Temperature Limits Report |
ML090641103 | 27 February 2009 | R. E. Ginna Nuclear Power Plant - License Renewal Aging Management Reactor Vessel Internals Program | Boric Acid Non-Destructive Examination Nondestructive Examination Functionality Assessment Aging Management EVT-1 |
ML12220A101 | 24 November 2008 | Constellation Energy Group, Inc. Definitive Proxy Statement Schedule 14A | Incorporated by reference Grace period Stolen |
ML082740268 | 23 September 2008 | Transmittal of Steam Generator Examination Report for the R.E. Ginna Nuclear Power Plant Conducted in 2008 | |
ML082190013 | 7 August 2008 | Monthly Operating Reports Second Quarter 2008 | Reserve Station Service Transformer Power change |
ML080710041 | 29 February 2008 | R.E. Ginna, Supplement Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors | Safe Shutdown Boric Acid Mission time Coatings Design basis earthquake Foreign Material Exclusion Exemption Request |
ML071270307 | 1 May 2007 | Report of Facility Changes, Tests and Experiments Conducted Without Prior Commission Approval | Temporary Modification Power Uprate |
ML061210173 | 12 January 2006 | FEMA Final Exercise Report - R. E. Ginna (Dated 1/12/06) | Cyber Security |
ML053620188 | 17 November 2005 | Meeting with R. E. Ginna Nuclear Power Plant, LLC, Regarding Extended Power Uprate Amendment Application | Boric Acid Loop seal Ultimate heat sink Probabilistic Risk Assessment |
ML052920418 | 10 October 2005 | R. E. Ginna - Report of Facility Changes, Tests, and Experiments Conducted Without Prior Commission Approval | Temporary Modification |
ML051930019 | 1 July 2005 | R. E. Ginna Nuclear Power Plant, Transmittal of RCS Pressure and Temperature Limits Report (PTLR) | Pressure and Temperature Limits Report |
ML072700849 | 31 January 2005 | Caldon Experience in Nuclear Feedwater Flow Measurement | Power change |
ML041480294 | 21 May 2004 | Appendix R Summary for the Proposed Control Room Emergency Air Treatment System (Creats) Modification | Safe Shutdown Fire Barrier Emergency Lighting Exemption Request Fire Protection Program Fire Watch |