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| Issue date | Title | Topic | |
|---|---|---|---|
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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-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 |
| 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 |
| 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 |
| 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 |
| 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 | |
| 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 |
| 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 |
| ML082190013 | 7 August 2008 | Monthly Operating Reports Second Quarter 2008 | Reserve Station Service Transformer Power change |
| 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 |
| ML051930019 | 1 July 2005 | R. E. Ginna Nuclear Power Plant, Transmittal of RCS Pressure and Temperature Limits Report (PTLR) | Pressure and Temperature Limits Report |
| ML041140323 | 15 April 2004 | R. E. Ginna, Report of Facility Changes, Tests, and Experiments Conducted Without Prior Commission Approval | Fitness for Duty Nondestructive Examination Overspeed trip |
| ML032681130 | 25 September 2003 | Summary of the U.S. Nuclear Regulatory Commission (NRC) Staff'S Review of the R.R. Ginna Nuclear Power Plant (Ginna) Steam Generator Tube Inspection Report Dated July 2002 | |
| ML031070329 | 11 April 2003 | R. E. Ginna Nuclear Power Plant - Response to LRA RAIs 4.2.1-1 & 4.2.2-1 | |
| ML030410599 | 31 January 2003 | Response to December 26, 2002 Request for Additional Information Regarding Severe Accident Mitigation Alternatives | Safe Shutdown High winds Fire Barrier Time to boil Internal Flooding Large early release frequency |
| ML022960389 | 17 October 2002 | Supplementary Information Associated with the 2002 Steam Generator Inservice Inspection | Nondestructive Examination Liquid penetrant |
| ML023120172 | 7 October 2002 | Response to Request for Additional Information Related to Creats Actuation Instrumentation License Amendment Request, Attachment 12 | Commercial Grade Dedication |
| ML022910417 | 7 October 2002 | Response to Request for Additional Information Related to Creats Actuation Instrumentation License Amendment Request, Attachments 17 -19 | Grace period |
| ML022890518 | 7 October 2002 | Response to Request for Additional Information Related to Creats Actuation Instrumentation License Amendment Request, Attachments 10 and 11 | Offsite Dose Calculation Manual Stroke time Pressure and Temperature Limits Report Maintenance Rule Program Fire Protection Program |
| ML022890157 | 7 October 2002 | Response to Request for Additional Information Related to Creats Actuation Instrumentation License Amendment Request, Attachments 1 - 4 | Hot Short |
| ML023040268 | 19 September 2002 | Part 4 of 4 - Westinghouse Technology Manual, Course Outline for R-104P and Course Manual | Safe Shutdown Boric Acid Shutdown Margin Ultimate heat sink Power-Operated Valves |
| ML081280096 | 31 July 2002 | WCAP-15885, Rev. 0, R.E. Ginna Heatup and Cooldown Limit Curves for Normal Operation. | Hydrostatic |
| NRC Generic Letter 1979-45 | 25 September 1979 | NRC Generic Letter 1979-045: Transmittal of Reports Regarding Foreign Reactor Operation Experiences | Boric Acid |
| ML18143A451 | 24 July 1978 | Amendments to Prior Design Modifications on the Undervoltages Protection Systems | |
| ML18192A130 | 31 January 1978 | R. E. Ginna - Safety Analysis of Proposed Modification of Pressurizer Instrument Terminal Blocks Presented to PORC and Nsarb on Jan. 31, 1978 | |
| ML18142B235 | 16 May 1977 | LER 1977-003-00 for R.E. Ginna, Abnormal Degradation of Steam Generator Tubes | |
| ML18143A104 | 5 October 1971 | R.E Ginna Unit 1, Amendment No. 2 to Technical Supplement Accompanying Application to Increase Power | Safe Shutdown Boric Acid High Radiation Area Post Accident Monitoring Design basis earthquake Earthquake |