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| Issue date | Title | Topic | |
|---|---|---|---|
| ML23278A129 | 14 December 2023 | Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines | |
| ML21299A003 | 28 October 2021 | and Waterford Steam Electric Station, Unit 3 - Approval of Request for Alternative EN-20-RR-003 from Certain Requirements of the ASME Code | |
| 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 |
| 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 |
| 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 |
| ML19269C534 | 27 September 2019 | Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques | Incorporated by reference |
| ML19135A444 | 21 June 2019 | Issuance of Relief Request I4R-22 Relief from the Requirements of the ASME Code | Weld Overlay VT-2 Incorporated by reference Liquid penetrant Dissimilar Metal Weld |
| ML19161A257 | 4 June 2019 | BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 | Incorporated by reference |
| ML19098A034 | 30 April 2019 | Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins | |
| 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 |
| JAFP-18-0076, End of Interval Relief Request Associated with the Fourth Ten-Year Lnservice Inspection (ISI) Interval | 26 July 2018 | End of Interval Relief Request Associated with the Fourth Ten-Year Lnservice Inspection (ISI) Interval | Non-Destructive Examination VT-2 |
| ML18039A854 | 30 May 2018 | Relief Requests I5R-02, I5R-03, I5R-04 from ASME Code Requirements for Reactor Vessel Internals, Ferretic Piping Repair/Replacement, and RPV Flange Welds, 5th 10-Year Inservice Inspection Interval (MG0116-MG0118; L-2017-LLR-0083 to 0085) | Hydrostatic Nondestructive Examination Incorporated by reference EVT-1 Dissimilar Metal Weld |
| 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 |
| ML18044A993 | 13 April 2018 | Request for Alternatives PRR-01, PRR-02, PRR-04, VRR-02, VRR-03, and VRR-04 from ASME OM Code Requirements for Various Pumps and Valves, Fifth 10-Year Inservice Testing Interval (CAC MG0052-MG0061; EPID L-2017-LLR-0067 to L-2017-LLR-0074) | Stroke time Incorporated by reference Grace period |
| ML17289A075 | 12 December 2017 | Issuance of Relief Request for Proposed Alternative to Use ASME Code Case N-789-1 (CAC No. MF9692; EPID L-2017-LLR-0027) Note Correction Safety Evaluation See ML18003B382 | Incorporated by reference Liquid penetrant |
| ML17219A428 | 11 December 2017 | Issuance of Relief Request-Alternative to Certain Requirements of the ASME Code Regarding Use of ASME Code Case N-513-4 (CAC No. MF9641; EPID L-2017-LLR-0023) | Through-Wall Leak |
| ML17223A280 | 10 August 2017 | Submittal of Relief Requests Associated with the Fifth Lnservice Inspection (ISI) Interval | Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Finite Element Analysis Earthquake EVT-1 Liquid penetrant Dissimilar Metal Weld DM weld Weak link |
| ML17090A168 | 12 April 2017 | Alternative to ASME Code Requirements for Weld Overlay Repair | Weld Overlay Hydrostatic Nondestructive Examination Finite Element Analysis Liquid penetrant Dissimilar Metal Weld |
| ML16355A429 | 6 January 2017 | Relief Request for Proposed Alternative for the Implementation of BWRVIP-05 | Incorporated by reference |
| ML16334A440 | 6 December 2016 | Relief from the Requirements of the ASME Code Case N-702 and BWRVIP-241 for Plant Nozzle-to-Vessel Welds and Nozzle Inner Radii | |
| ML16270A046 | 3 October 2016 | Acceptance of Requested Licensing Action Relief Request for Proposed Alternative for the Implementation of BWRVIP-05 | |
| ML16253A341 | 14 September 2016 | Acceptance of Requested Licensing Action Relief Request for Plant Nozzle-to-Vessel Welds and Nozzle Inner Radii Using ASME Code Case N-702 and BWRVIP-241 | |
| ML16180A289 | 29 June 2016 | Inservice Inspection Program Alternative for Safety Relief Valves | VT-2 Pressure Boundary Leakage |
| ML16096A269 | 6 June 2016 | Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1 | Functionality Assessment Liquid penetrant |
| ML16077A352 | 22 March 2016 | Withdrawal of Relief Request No. 19 from the Fourth Inservice Inspection Interval | |
| JAFP-15-0122, Withdrawal of Application for Alternative Examination Requirements for James A. FitzPatrick Nuclear Power Plant Nozzle-to-Vessel Welds and Nozzle Inner Radii Using ASME Code Case N-702 and BWRVIP-241 | 20 November 2015 | Withdrawal of Application for Alternative Examination Requirements for James A. FitzPatrick Nuclear Power Plant Nozzle-to-Vessel Welds and Nozzle Inner Radii Using ASME Code Case N-702 and BWRVIP-241 | |
| ML15230A350 | 18 August 2015 | J.A Fitzpatrick Nuclear Power Plant - Requests Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1), Implementation of BWRVIP-05 (GL 98-05) | Hydrostatic |
| CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, D | 5 June 2015 | Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, Division | Liquid penetrant |
| ML12279A248 | 17 October 2012 | Issuance of Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code | Incorporated by reference |
| JAFP-11-0112, Relief Request (RR-8), Alternative Examination Requirements for Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Using American Society of Mechanical Engineers Code Case N-702 and BWRVIP-108NP | 3 October 2011 | Relief Request (RR-8), Alternative Examination Requirements for Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Using American Society of Mechanical Engineers Code Case N-702 and BWRVIP-108NP | |
| ML080390223 | 13 March 2008 | Relief Request No. 5, Use of Performance Demonstration Initiative in Lieu of ASME Code Section XI, Appendix Viii, Supplement 11 Requirement | Weld Overlay Incorporated by reference |
| ML080300307 | 28 February 2008 | Relief Request No. RR-6, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals Components Inspection | Incorporated by reference EVT-1 |
| ML080370080 | 25 February 2008 | Relief Request No. 2 (RR-2) from the Requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Appendix Viii, Supplement 10 | Incorporated by reference |
| ML080420427 | 22 February 2008 | Relief Request No. 3 (RR-3) Risk-Informed Inservice Inservice Inspection Program | Probabilistic Risk Assessment Nondestructive Examination Incorporated by reference Large early release frequency |
| ML052070047 | 9 August 2005 | Relief Request for Temporary Non-Code Repair of a Shutdown Cooling Pipe | Safe Shutdown Incorporated by reference Earthquake |
| JAFP-05-0105, Request for Approval of Relief Request No. RR-38, Proposed Alternative to Perform a Temporary Non-Code Repair in Accordance with 10 CFR 50.55a(a)(3)(ii) | 9 July 2005 | Request for Approval of Relief Request No. RR-38, Proposed Alternative to Perform a Temporary Non-Code Repair in Accordance with 10 CFR 50.55a(a)(3)(ii) | Safe Shutdown Temporary Modification Abnormal operational transient |
| ML042740664 | 14 October 2004 | Relief Request Nos. R-33, R-71, R 3-40(A) and R-41, James A. FitzPatrick Nuclear Power Plant, Indian Point Nuclear Generating Unit Nos. 2 and No. 3 and Pilgrim Nuclear Power Station | Incorporated by reference |
| ML042030157 | 20 July 2004 | Relief, Relief Request No. 30 for Third 10-Year Inservice Inspection (ISI) Program Interval | Incorporated by reference |
| ML041070088 | 6 July 2004 | Relief Request to Use American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Case N-600 | |
| ML041740184 | 6 July 2004 | Relief Request, Nos. RR-34 and PRR for the Third 10-Year Inservice Inspection (ISI) Interval, MC1999 and MC2006 | Incorporated by reference |
| ML040540693 | 12 April 2004 | Relief Request Review, Relief Request VRR-08 Related to the Third 10-Year Inservice Testing (IST) Ubtervak | |
| JPN-03-020, Indian Point Nuclear Generating Station, Units 2 & 3, Pilgrim Nuclear Power Station, Vermont Yankee Nuclear Power Station, Relief, Relief Request to Use ASME Code Case N-600 | 11 August 2003 | Indian Point Nuclear Generating Station, Units 2 & 3, Pilgrim Nuclear Power Station, Vermont Yankee Nuclear Power Station, Relief, Relief Request to Use ASME Code Case N-600 | |
| JAFP-03-0111, Proposed Alternatives in Accordance with 10CFR50.55a(g)(6)(ii)(A)(5) and Relief from ASME Section XI Code Regarding Inspection of RPV Vertical Shell Welds Pursuant to 10 CFR 50.55a (g)(6)(i) | 4 August 2003 | Proposed Alternatives in Accordance with 10CFR50.55a(g)(6)(ii)(A)(5) and Relief from ASME Section XI Code Regarding Inspection of RPV Vertical Shell Welds Pursuant to 10 CFR 50.55a (g)(6)(i) | |
| ML030650255 | 1 April 2003 | Relief Request Review, Third 10-Year Pump and Valve Inservice Testing Program, Revision of Relief Request VRR-04 | Incorporated by reference |
| ML023180496 | 14 November 2002 | Relief, Request for Relief No. RR-28 for the Third 10-Year Inservice Inspection Interval Program Plan for the FitzPatrick Power Plant | Non-Destructive Examination Weld Overlay Through Wall Leak |
| JAFP-02-0194, Proposed Revision of Relief Request VRR-06 for In-Service Testing Program | 30 September 2002 | Proposed Revision of Relief Request VRR-06 for In-Service Testing Program | Stroke time Power-Operated Valves |
| JPN-02-011, Request for Relief RR-29, Third 10-Year Inservice Inspection Interval Program Plan | 8 May 2002 | Request for Relief RR-29, Third 10-Year Inservice Inspection Interval Program Plan | Weld Overlay |
| JPN-02-010, Relief Request RR-28, Revision 1 for the Third 10-Year Inservice Inspection Interval Program Plan | 8 May 2002 | Relief Request RR-28, Revision 1 for the Third 10-Year Inservice Inspection Interval Program Plan | High Radiation Area Weld Overlay Hydrostatic Liquid penetrant |