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| Issue date | Title | Topic | |
|---|---|---|---|
| ML23073A368 | 16 March 2023 | Authorization and Safety Evaluation for Proposed Alternative I6R-10, Revision 0 Related to the Steam Generators, | |
| RS-22-110, Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request. | 20 September 2022 | Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request. | Non-Destructive Examination Scaffolding |
| ML21250A382 | 29 September 2021 | R. E. Ginna Nuclear Power Plant - Issuance of Relief Request I6R-06 Alternate Inspection for Reactor Vessel Internals | Safe Shutdown Earthquake Operating Basis Earthquake Incorporated by reference Earthquake Flow Induced Vibration |
| ML21246A106 | 22 September 2021 | R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Alternative Request GR-03, Valve Position Verification Testing Extension Sixth 10-Year Inservice Testing Program Interval | Incorporated by reference Grace period |
| ML21230A206 | 3 September 2021 | Proposed Alternative to Use ASME OM Code Case OMN-28 | Incorporated by reference |
| ML21216A220 | 5 August 2021 | Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting | Coatings Nondestructive Examination Incorporated by reference |
| ML21117A031 | 26 April 2021 | Verbal Authorization by the NRC NRR for 10 CFR 50.55a Alternative Request Position Verification Testing Extension - Exelon Generation, R. E. Ginna Nuclear Power Plant | Incorporated by reference |
| ML20269A200 | 30 September 2020 | Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 | Incorporated by reference |
| 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 |
| ML20090D291 | 2 June 2020 | R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternative I6R-02 for the Sixth 10-Year Inservice Inspection Interval (EPID L-2019-LLR-0071). Supersedes ML20056D559 | |
| ML20113F041 | 30 April 2020 | Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) | Incorporated by reference Pandemic Coronavirus COVID-19 |
| ML20099D955 | 17 April 2020 | Request to Use Provisions in the 2013 Edition of the ASME Boiler and Pressure Vessel Code for Performing Non-Destructive Examinations | Non-Destructive Examination Incorporated by reference |
| ML20055F886 | 13 March 2020 | R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternative I6R-01 for the Sixth 10-Year Inservice Inspection Interval | Boric Acid |
| RS-20-020, Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi) | 28 February 2020 | Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi) | Power-Operated Valves |
| ML19269C534 | 27 September 2019 | Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques | Incorporated by reference |
| ML19205A453 | 5 August 2019 | R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternatives PR-01 and PR-02 for Sixth 10-Year Inservice Testing Program | Incorporated by reference |
| ML19205A353 | 5 August 2019 | R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternatives GR-01, VR-01, and VR-02 for the Sixth 10-Year Inservice Testing Program (EPID L-2018-LLR-0382; EPID L-2018-LLR-0383) | Stroke time Incorporated by reference Surveillance Frequency Control Program |
| ML19177A218 | 26 June 2019 | R. E. Ginna Nuclear Power Plant - Relief Request Associated with Snubber Inservice Testing Program for the Sixth Ten-Year Interval | |
| ML19161A257 | 4 June 2019 | BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 | Incorporated by reference |
| ML19100A004 | 22 April 2019 | R. E. Ginna Nuclear Power Plant - Issuance of Relief Request ISI-18 Regarding Fifth 10-Year Inservice Inspection Program Interval | Probabilistic Risk Assessment |
| JAFP-19-0023, Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds | 15 February 2019 | Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds | Dissimilar Metal Weld |
| ML18347B036 | 13 December 2018 | Relief Requests Associated with Sixth Ten-Year Lnservice Testing Interval | Stroke time Surveillance Frequency Control Program |
| JAFP-18-0053, Proposed Alternative to Utilize Code Cases N-878 and N-880 | 30 May 2018 | Proposed Alternative to Utilize Code Cases N-878 and N-880 | Nondestructive Examination |
| JAFP-18-0052, Proposed Alternative to Utilize Code Case N-879 | 30 May 2018 | Proposed Alternative to Utilize Code Case N-879 | Nondestructive Examination |
| ML17297A524 | 6 November 2017 | R. E. Ginna - Request for Use of a Portion of a Later Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (CAC Nos. MG0079-MG0083; EPID L-2017-LLR-0061) | Incorporated by reference |
| ML17170A013 | 26 June 2017 | Proposed Alternative to Eliminate Examination of Threads in Reactor Pressure Vessel Flange (CAC Nos. MF8712-MF8729 and MF9548) | |
| ML16230A237 | 6 September 2016 | Fleet Request for Proposed Alternative to Use ASME Code Case N-513-4 (CAC Nos. MF7301-MF7322) | Incorporated by reference Through-Wall Leak |
| ML16138A021 | 19 May 2016 | Proposed Alternative to Use Code Case N-789 (CAC Nos. MF7018-MF7022) | Liquid penetrant |
| ML12264A591 | 18 September 2012 | Supplemental Information for Relief Request Number ISI-09 R. E. Ginna Nuclear Power Plant - Fifth Interval Inservice Inspection Program Proposed Alternative in Accordance with 10 CFR 50.55a (a)(3)(ii) Component Cooling Water 1 Inch Half-Cou | VT-2 |
| ML12254A378 | 6 September 2012 | Relief Request Number ISI-09 - Fifth Interval Inservice Inspection Program Proposed Alternative in Accordance with 10 CFR 50.55a (a)(3)(ii) Component Cooling Water 1 Inch Half-Coupling Weld Leak | Time to boil Hydrostatic Temporary Modification Dissimilar Metal Weld |
| ML12158A115 | 22 June 2012 | Inservice Inspections Program Relief Request Nos. ISI-02 and ISI-03 | Nondestructive Examination VT-2 Incorporated by reference Liquid penetrant Dissimilar Metal Weld DM weld |
| ML092080229 | 31 July 2009 | R. E. Ginna, Safety Evaluation for Relief Request No. 18, Reactor Vessel Weld Examination Extension | Probabilistic Risk Assessment Incorporated by reference |
| ML090900045 | 5 April 2009 | Relief Request No. 23 on End-of-Interval System Pressure Test for Class 1 Components-R.E. Ginna Nuclear Power Plant | Boric Acid Hydrostatic VT-2 Incorporated by reference |
| ML090350187 | 4 February 2009 | Acceptance Review for Ginna Relief Request No. 23 | |
| ML082880032 | 3 October 2008 | Fourth Ten-Year Interval Inservice Inspection Program, Re-submittal of Relief Request Number 18 | Probabilistic Risk Assessment |
| ML061740156 | 19 July 2006 | Relief Request No. PR-3 Regarding Testing of Auxiliary Feedwater Pumps | Incorporated by reference |
| ML061280500 | 1 May 2006 | R. E. Ginna Response to Request for Additional Information Regarding Relief Request PR-3 | |
| ML050730016 | 12 April 2005 | R. E. Ginna, Relief, Request 17 for the Fourth 10-Year Interval of the Inservice Inspection Program, MC5406 | Non-Destructive Examination Incorporated by reference Dissimilar Metal Weld |
| ML043560153 | 15 December 2004 | Fourth Ten-Year Interval in Service Inspection Program Submittal of Relief Request Number 17 Related to Appendix Viii, Supplement 10, PDI Program Alternative Requirements R. E. Ginna Nuclear Power Plant | Dissimilar Metal Weld |
| ML042450778 | 19 October 2004 | R. E. Ginna Nuclear Power Plant Relief Requests VR-1, VR-2 and VR-13 for the Fourth 10-Year Interval of the Pump and Valve Inservice Testing Program | Incorporated by reference |
| ML033040120 | 21 November 2003 | R. E. Ginna Nuclear Power Plant, Relief Request Review, Inservice Testing Program Relief Requests VR-4 and VR-8 | Incorporated by reference |
| ML032960322 | 20 October 2003 | Submittal of Relief Request VR-4 Related to the Requirements of 10CFR50.55a(f), Inservice Testing Requirements. | Incorporated by reference Cold shutdown justification |
| ML030420264 | 10 February 2003 | R. E. Ginna Nuclear Power Plant, Relief, Inservice Testing Program Relief Request PR-2, MB7232 | Incorporated by reference |
| ML031420520 | 9 January 2003 | Enclosure - R.E. Ginna, Inservice Testing Program Relief Request PR-2 | Incorporated by reference |