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1CAN020803, Request for Alternative ANO1-R&R-011 Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs
JAFP-08-0099, Request for Relief (RR-7) - Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs
JAFP-08-0102, Request for Relief (RR-7 Revision 1) - Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs
0CAN102002, Reduction of Commitment to the Entergy Operations Quality Assurance Program Manual Description
RA-19-0067, License Amendment Request to Revise Technical Specifications for the Adoption of 10 CFR 50, Appendix J, Option B for Type B and C Testing and for Permanent Extension of Type a, B and C Leak Rate Test Frequencies
L-MT-04-050, Fourth Interval Inservice Inspection Examination Plan, Revision 2
NG-99-0491, Requests Relief from Noted Requirements,For Relief Requests MC-R002 Through MC-R006,MC-P001 & NDE-R015,rev 1.Approval Is Requested Prior to Refueling Outage 16,scheduled to Begin on 991008
NMP1L3513, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)
NMP1L3516, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)
1CAN031103, Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05, Relief Request ANO1-R&R-015
1CAN041105, Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05 Relief Request ANO1-R&R-016
RA-20-0312, Relief Request, Service Water Pinhole Leak in a Socket Weld, Inservice Inspection Program, Fourth Ten-Year Interval
L-2022-035, Fifth Ten-Year Inservice Inspection Interval Relief Request No. 10 Part-II
L-2020-056, Fifth Ten-Year Inservice Inspection Interval Relief Request No. 6
L-2020-074, Response to Request for Additional Information for Relief Request No. 6
L-2020-073, Fifth Ten-Year Inservice Inspection Interval Revised Relief Request No. 6 and Supplemental Information for Train B CCW Return Piping
L-2020-104, Fifth Ten-Year Inservice Inspection Interval Relief Request No. 7 for Train a and B Component Cooling Water (CCW) Supply and Return Piping
L-2021-183, Fifth Ten-Year Inservice Inspection Interval Relief Request No. 10
NMP1L3519, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)
NMP1L3485, Proposed Alternative Associated with a Weld Overlay Repair to the Torus
RA-20-0036, Request for Alternative to Defect Removal Prior to Performing Repair/Replacement Activities on Low Pressure Service Water (LPSW) System Piping
HNP-18-035, Relief Request I3R-18, Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Inservice Inspection Program for Containment, Third Ten-Year Interval
BSEP 18-0039, Proposed In-Service Inspection Alternative for Application of Dissimilar Metal Weld Full Structural Overlay - Nozzles N4A and N4D
W3F1-2019-0052, CFR 50.55a Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 in Accordance with 10 CFR 50.55a(z)(2)
W3F1-2019-0056, Revision to Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-1
BSEP 17-0033, Proposed In-service Inspection Alternative for Application of Dissimilar Metal Weld Full Structural Overlay
RS-18-125, Proposed Alternative Requirements for the Repair and Examination of Reactor Pressure Vessel Head Penetration Nozzles for the Fourth Inservice Inspection Interval in Accordance with 10 CFR 50.55a(z)(1)
RS-21-042, Relief Request I4R-12 Relief from Code Examinations for 2B33-F060A and 2B33-F060B Repairs, Revision 2
RS-22-032, Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs
RS-21-034, Relief Request I4R-12 Relief from Code Surface Examinations for 2B33-F060B Valve Repair
JAFP-17-0010, Proposed Alternative to ASME Code Requirements for Weld Overlay Repair, RR-21
RS-16-259, Response to Request for Additional Information for Relief Request I4R-10: Proposed Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval
RS-16-163, Relief Request for Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval
CNRO-2016-00016, Entergy - Response to RAI Questions and Submittal of Relief Request EN-ISI-15-1 (Updated)
CNRO-2015-00002, Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 1
NL-15-2270, Response to Request for Additional Information for Alternative HNP-ISI-ALT-5-01
CNRO-2015-00018, Entergy - Relief Request Number RR EN-15-2 - Proposed Alternative to Use ASME Code Case N-786-1, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, Section XI, Division 1
HNP-15-039, Relief Request I3R-15 Revision 2, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Third Ten-Year Interval
NL-17-1769, Proposed ISI Alternative FNP-ISI-ALT-22 Implementation of Code Case N-786-1
NL-17-0910, Proposed Alternatives GEN-ISI-ALT-2017-01 Implementation of Code Case N-786-1 and GEN-ISI-ALT-2017-02 Implementation of Code Case N-789-1
HNP-15-034, Relief Request I3R-15 Revision and Supplement, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program - Third Ten-Year Interval
HNP-15-010, Relief Request I3R-15, Reactor Vessel Closure Head Nozzle Repair Technique Inservice Inspection Program - Third Ten-Year Interval
RS-14-251, Revision to the Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations
RS-21-035, Relief Request I4R-12 Relief from Code Examinations for 2B33-F060A and 2B33-F060B Repairs
HNP-13-119, Relief Request I3R-13, Reactor Vessel Closure Head Nozzle 37, Inservice Inspection Program - Third Ten-Year Interval
HNP-13-057, Relief Request I3R-11 Reactor Vessel Closure Head Nozzles Inservice Inspection Program - Third Interval
L-13-101, 10 CFR 50.55a Request RR-E 1, Proposed Alternative Regarding Post-Repair Pressure Testing Requirements
L-12-316, Request for Exemption for Post-Repair Testing Requirements of Containment Vessel Opening
HNP-12-054, Relief Request I3R-09 Reactor Vessel Closure Head Nozzles Inservice Inspection Program - Third Interval
GNRO-2012/00040, Relief Request ISI-17 Repair Plan for Lsi Weld N06B-KB
RS-16-224, Relief Request for Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval
RS-11-069, Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations
RS-11-094, Units 1 and 2 - Supplement to the Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations
L-10-175, Supplement to 10 CFR 50.55a Request for Alternative Weld Repair Method for Reactor Vessel Head Penetration J-Groove Welds
1CAN041002, Fourth 10-Year Inservice Inspection Interval, Request for Alternative ANO1-R&R-013, Repairs to the Pressurizer Instrumentation Penetrations
L-09-309, Request for Alternative Weld Repair Method for Reactor Vessel Head Penetration J-Groove Welds for 10 CFR 50.55a
L-08-291, CFR 50.55a Request for Alternative Repair Methods for Reactor Vessel Head Penetrations and J-Groove Welds
1CAN100702, Request for Alternative ANO1-R&R-011, Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs
NL-07-103, Supplement to Response to RAI Regarding Relief Request RR-07, Reactor Vessel Head Alternative Weld Repair Methods
RS-11-045, Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations
RS-24-088, Relief Requests Associated with the Fifth Inservice Inspection Interval
W3F1-2010-0002, Request for NRC Alternative to ASME IWE-5521 Regarding Post Repair Testing of Waterford 3s Steel Containment Vessel-Opening
W3F1-2019-0009, Proposed Inservice Inspection Program Alternative WF3-RR-19-1 for Application of Dissimilar Metal Weld Full Structural Weld Overlay - Reactor Coolant System Cold Leg Drain Nozzles
RS-18-124, Relief Request Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval
PNP 2014-024, Response to Request for Additional Information Dated February 28, 2014 for Relief Request Number RR 4-19, Proposed Alternative to Requirements of ASME Code Case N-638-4
W3F1-2011-0041, Request for Alternative to ASME IWE-5221 Re Post Repair Testing of Steel Containment Vessel Opening
W3F1-2019-0011, Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding Relief Request WF3-RR-19-1 for Application of Dissimilar Metal Weld Full Structural Weld Overlay
L-25-024, 10 CFR 50.55a Request BV-ISI-2025-01, Quench Spray Pinhole Leak
W3F1-2019-0054, Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-1
NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)
NL-21-0767, Proposed Alternative Requirements for the Repair of Reactor Vessel Head Penetrations for the 4th 10-Year Inservice Inspection Internal (VEGP-ISI-ALT-04-05, Version 1.0)
RA-21-0145, Revision to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method
RA-21-0133, Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method
RA-24-0264, Proposed In-service Inspection Alternative for Application of Dissimilar Metal Weld Full Structural Overlay - Nozzle N4D
M200212, Relief Request Number ISI No. 7, Use of 2001 Addenda for Repair/Replacement Program
RA-21-0144, Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant
NMP1L3526, Submittal of Emergency Relief Request I5R-14 Concerning a Proposed Alternative Associated with N2E Safe End-to-Nozzle Dissimilar Metal Weld Repair with Laminar Indication
L-15-297, Submittal of 10 CFR 50.55a Request for Alternative Repair Methods for Reactor Vessel Head Penetrations and J-Groove Welds (Request 2-TYP-3-RV-04)
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
PNP 2025-059, Relief Request Number RR 5-12, Proposed Alternative to ASME Section XI Code for Full Structural Weld Overlays of Primary Coolant System Hot Leg, Cold Leg, and Pressurizer Nozzle Dissimilar Metal Welds