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| Issue date | Title | Topic | |
|---|---|---|---|
| RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator | 7 December 2022 | Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator | |
| RS-22-084, Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator . | 17 June 2022 | Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator . | Hydrostatic Incorporated by reference |
| RS-22-074, Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds . | 20 May 2022 | Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds . | Non-Destructive Examination |
| 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-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated | 23 February 2022 | Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P | Surveillance Frequency Control Program |
| ML21320A054 | 15 November 2021 | R. E. Ginna Nuclear Power Plant - Response to Request for Additional Information - Request for Exemption from the Biennial Emergency Preparedness Exercise Requirements in 10 CFR 50, Appendix E, Section IV.F.2.c | Exemption Request Coronavirus |
| JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments | 16 September 2021 | Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments | |
| ML21225A006 | 13 August 2021 | Response to Request for Additional Information Regarding License Amendment Request to Address the Issues Identified in Westinghouse Documents NSAL-09-5, Rev.1 and NSAL-15-1, Rev. 0 | Anticipated operational occurrence |
| JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments | 11 June 2021 | Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments | |
| JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting | 20 April 2021 | Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting | |
| ML21078A002 | 19 March 2021 | Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of R. E. Ginna Nuclear Power Plant, License Amendment Request to Modify the Steam Generator Tube Inspection Frequency | |
| RS-20-017, Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-885 | 1 February 2021 | Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-885 | Foreign Material Exclusion |
| ML20248H388 | 4 September 2020 | Response to Request for Additional Information - License Amendment Request for Implementation of WCAP-14333 and WCAP-15376, Reactor Trip System Instrumentation and Engineered Safety Feature Actuation System. | Safe Shutdown High winds Tornado Missile Safe Shutdown Earthquake Internal Flooding Probabilistic Risk Assessment Multiple Spurious Operation FLEX Tornado-Generated Missile Fukushima Dai-Ichi Tornado Missile Protection Flooding Focused Evaluation Earthquake Fire Protection Program |
| ML20188A264 | 6 July 2020 | Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information | Incorporated by reference |
| ML20080N889 | 20 March 2020 | R. E. Ginna Nuclear Power Plant, Supplemental Information Associated with the License Amendment Request to Add a One-Time Note for Use of Alternate Residual Heat Removal Methods | |
| JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 | 4 June 2019 | Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 | |
| NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants | 1 May 2019 | Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants | |
| JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 | 8 January 2019 | Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 | Commercial Grade Dedication Nondestructive Examination |
| ML18338A235 | 4 December 2018 | R. E. Ginna Nuclear Power Plant - Relief Request ISI-18 to Extend the Reactor Pressure Vessel Inservice Inspection Interval | |
| ML18243A167 | 29 August 2018 | R. E. Ginna Nuclear Power Plant - Response to Request for Additional Information - License Amendment Request: Revision to Technical Specifications to Adopt Technical Specifications Task Force TSTF-547, Revision 1, Clarification of Rod Posit | Shutdown Margin |
| NMP1L3221, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes. | 10 May 2018 | Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes. | High winds Earthquake Fuel cladding |
| ML17298B444 | 25 October 2017 | License Amendment Request - Revised Commitment Associated with Implementation of NFPA 805, 2001 Edition | Safe Shutdown Probabilistic Risk Assessment FLEX Fire Protection Program |
| RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography | 13 March 2017 | Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography | Hydrostatic Nondestructive Examination Incorporated by reference Dissimilar Metal Weld |
| ML16336A048 | 30 November 2016 | Response to Request for Additional Information for the Review of TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec. | |
| RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure | 26 May 2016 | Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure | Safe Shutdown High winds Loop seal Ultimate heat sink Enforcement Discretion Probabilistic Risk Assessment Operating Basis Earthquake FLEX Design basis earthquake Severe Accident Management Guideline B.5.b Mitigating Strategies Earthquake Fire Watch Downpower |
| ML16042A421 | 11 February 2016 | Response to Request for Additional Information Regarding Reactor Internals Program | Aging Management Power change |
| ML16034A139 | 3 February 2016 | Response to Request for Additional Information - Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program.. | Internal Flooding Probabilistic Risk Assessment Aging Management Surveillance Frequency Control Program Large early release frequency Pressure Boundary Leakage |
| RS-15-288, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident | 4 December 2015 | High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident | Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi |
| RS-15-255, Response to NRC Audit Review Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report | 30 September 2015 | Response to NRC Audit Review Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report | Hydrostatic Fukushima Dai-Ichi |
| ML18143A448 | 28 July 1978 | R. E. Ginna - Response to Letter of 6/21/1978. Additional Information About Standby Auxiliary Feedwater System Attached | Safe Shutdown Tornado Missile Hydrostatic Tornado Generated Missile Earthquake |
| ML18190A167 | 27 July 1978 | R. E. Ginna - Enclosed Copy of Reactor Vessel Fabrication & Inspection Information Requested by Mr. K. G. Hoge. Listed Various Inspection Reports & Dates for Documentation | Nondestructive Examination |
| ML18142A694 | 15 June 1978 | Steam Generator Water Hammer Prevention | Loop seal |
| ML18143A029 | 25 April 1978 | R. E. Ginna - Response to NRC Request Regarding Submittals of 01/16/1978 & 02/15/1978 on the ECCS Analyses for R. E. Ginna Nuclear Power Plant | |
| ML18142A706 | 6 April 1978 | Forwarding Revision to Tests Described in Applicant'S 03/27/78 Submittal Questions 6.1.E & 6.1.0 Re the Cycle 8 Fuel Reload | |
| ML18142B974 | 15 February 1978 | R. E. Ginna - 02/15/1978 Response to Request for Additional Information on Adequacy of ECCS Evaluation Model | |
| ML18142A804 | 18 January 1978 | R. E. Ginna - Enclosed Is Response to Nrc'S Questionnaire of 12/15/1977 Regarding Standby Diesel Generating Units | |
| ML18142B975 | 31 October 1977 | R. E. Ginna - 10/31/1977 Response to Request for Additional Information Inservice Pump and Valve Testing Program | Safe Shutdown Boric Acid |
| ML18142A864 | 13 September 1977 | R. E. Ginna - Response to Request of May 23, 1977 for Additional Information on the Ginna Reactor Vessel Material Surveillance Program | |
| ML18142A719 | 4 August 1977 | R. E. Ginna - 08/04/1977 Letter Response to Request for Additional Information on Inservice Pump and Valve Testing Program | Safe Shutdown Boric Acid Stroke time |
| ML18142A833 | 24 February 1977 | R. E. Ginna - Fission Gas Release Model | |
| ML18142B977 | 24 February 1977 | R. E. Ginna - 02/24/1977 Response to Request for Additional Information Reactor Vessel Overpressurization | Stroke time Hydrostatic |
| ML18142A837 | 19 January 1977 | Forwards Response Letter of 12/17/1976 Requesting Additional Information Regarding Appendix I Evaluation | |
| ML18143A967 | 23 March 1976 | R. E. Ginna - Plans for Demonstrating Compliance with 10 CFR 50.34a |