RNP-RA/17-0043, Relief Request (RR)-12 for Relief from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-4
LIC-15-0069, Response to NRC Request for Additional Information Regarding Relief Request RR-14
L-2015-040, Submittal of Fifth 10 Year Interval Inservice Inspection (ISI) Program Plan
CNL-13-106, Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units I and 2, License Renewal Application, Sets 13 (B.1.34-5a), 15 (4.2-1a), 16 (B.1.23-2c), 17 (B.1.23-2d), LRA Sections A.1.34 and B
NL-12-1240, Request for Additional Information Response Regarding Proposed Inservice Inspection Alternative VEGP-ISI-ALT-07
RS-11-048, Additional Information Related to Byron Station Unit 1, Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations
L-PI-18-007, CFR 50.55a Requests No. 1-RR-5-9 Associated with the Firth Ten-Year Interval for the In-service Inspection Program
2CAN061801, Notification of Revised License Renewal Commitment
AEP-NRC-2018-50, Unit 2 - Request for Alternative from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-4
WO 16-0052, Relief Request Number I4R-03, Request for Relief from Paragraph-3200(b) of ASME Code Case N-729-1 for Reactor Vessel Head Penetration Nozzle Welds and Relief Request I4R-04, Request for Relief from the Requirements of ASME Code Case N-729
1CAN111802, ANO Unit 1 SAR Amendment 28, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report
NOC-AE-19003620, Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23)
RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head
1CAN101905, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-4 Supplemental Examination Requirements ANO1-ISI-033
NL-05-0990, Response to NRC Request for Additional Information Regarding Relaxation from First Revised NRC Order EA-03-009
ET 16-0030, Relief Request Number 14R-03, Request for Relief from Paragraph-3200(b) of ASME Code Case N-729-1 for Reactor Vessel Head Penetration Nozzle Welds and Relief Request 14R-04, Request for Relief from Requirements of ASME Code Case N-729-1
ET 16-0027, Relief Request Number I4R-03, Request for Relief from Paragraph-3200(b) of ASME Code Case N-729-1 for Reactor Vessel Head Penetration Nozzle Welds and Relief Request I4R-04, Request for Relief from the Requirements of ASME Code Case N-729
NL-20-0115, Proposed Inservice Inspection Alternative FNP-ISI-AL T-05-06, Version 1.0
CP-202000431, Relief Request 1A4-1 Supplement - Reactor Vessel (Rv) Upper Head Examinations
AEP-NRC-2020-65, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-04
PMNS20201176, Pre-Application Meeting Regarding Potential N-729 Relief Request
NOC-AE-21003806, Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval
L-2020-123, Amendment 26 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Time-Limited Aging Analyses Activities
L-2020-043, Amendment 30 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Time-Limited Aging Analyses Activities
2CAN022202, Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods
2CAN102103, Response to Request for Additional Information Concerning Relief Request ANO2-R&R-012 Support the Repair of the Reactor Vessel Closure Head Penetration 46
1CAN052201, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-035
AEP-NRC-2024-29, (CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-07
L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02
AEP-NRC-2018-20, Request for Alternative from Volumetric/Surface Examination Frequency Requirement of ASME Code Case N-729-4, Request Number Isir 04-5, Revision 1
CP-201500430, Relief Request lB3-4 Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Head Penetration Weld Inspection
AEP-NRC-2014-99, Request for Alternative from Volumetric/Surface Examination Frequency Requirements of ASME Code N-729-1 Request Number Isir 04-02
L-PI-14-095, 10 CFR 50.55a Requests 1-RR-5-7 and 2-RR-5-7 Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program
AEP-NRC-2021-35, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-05
PMNS20210950, Notice of Meeting with TVA - pre-application Meeting Regarding a Sequoyah Nuclear Plant, Unit No. 2 Potential N-729-6 Relief Request
L-2021-231, Relief Request Number 10 - Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality or Safety
AEP-NRC-2022-61, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-06
PMNS20230044, Public Meeting Between U.S. Nuclear Regulatory Commission (NRC) and Electric Power Research Institute (EPRI) to Discuss Proposed Changes to Bare Metal Visual Requirements of American Society of Mechanical Engineers (ASME) Code Case N-72
PMNS20220445, Meeting for Electric Power Research Institute (EPRI) to Present Anticipated ASME Code Case N-729 Visual Exam Updates to the U.S. Nuclear Regulatory Commission (NRC)