NL-17-131, Relief Requests IP3-ISI-RR-11 and IP3-ISI-RR-12 Associated with Extension of Fourth Interval Reactor Vessel and Piping Weld Inspections
CP-201301361, Relief Request No. B-14 for Reactor Pressure Vessel Hot Leg Nozzle Weld Examinations (Second ISI Interval End Date: August 2, 2014)
L-2013-112, ASME Section XI, Inservice Inspection, Relief Requests No. 11 Alternative Through-Wall Sizing Requirements for Implementation of Appendix Viii, Supplement 10
CP-201300003, Submittal of Relief Request No. B-2, Third 10 Year ISI Interval from 10CFR50.55a Requirements for Reactor Vessel Hot Leg Nozzle Weld Examinations (Third ISI Interval Start Date August 13, 2010)
RS-12-040, Response to Request for Additional Information Related to Braidwood Station Relief Request 13R-08
RS-18-030, Relief Requests Associated with the Fourth Inservice Inspection Interval
RC-18-0036, (Vcsns), Unit 1 - Relief Request RR-4-13, Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds - Response to Request for Additional Information
NL-18-0193, Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-03, Version 1.0
ULNRC-06420, Request 14R-05 for Relief from Requirements of ASME Code Case N-770-2 Regarding Inspection Intervals for Reactor Vessel Nozzle Dissimilar Metal Welds
DCL-17-048, Diablo Canyon, Units 1 and 2 - Request for Approval of an Alternative to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section Xi Examination Requirements for Class 1 and 2 Piping Welds, Request for R
LR-N18-0069, Revision to Request for One-Time Relief for Reactor Vessel Cold Leg Nozzle to Safe-End Weld Examinations Inspection Interval
NL-18-053, Response to Request for Additional Information Regarding Relief Request IP3-ISI-RR-11 for Reactor Vessel Weld Inservice Inspection Frequency Extension
W3F1-2018-0060, Request for NRC Alternative to ASME Code Case N-770-2, Successive Examinations, Relief Request W3-ISI-031
W3F1-2018-0067, Response to NRC Request for Alternative to ASME Code Case N-770-2, Successive Examinations, Relief Request W3-ISI-031
RA-18-0180, Supplement to Relief Request for an Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2
CNL-19-012, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection Program, Request for Alternative, 18-ISI-1
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
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
RA-19-0026, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001)
CNL-19-057, Response to Request for Additional Information Regarding American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection Program, Request for Alternative, 18-ISl-1
RA-19-0138, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Vessel Cold Leg Dissimilar Metal Weld Inspections
NRC 2019-0026, Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure
RA-20-0048, Response to Request for Additional Information for Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Vessel Cold Leg Dissimilar Metal Weld Inspections
SBK-L-20049, Relief Request 3IIR-7, Proposed Alternative to Deter Examinations Beyond the 1 Year Code Allowable
L-20-117, 10 CFR 50.55a Request Number 2-TYP-4-RV-06, Hardship for Hot Leg Nozzle Inspections
NOC-AE-21003806, Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval
CNL-22-101, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative WBN-2-ISI-01
DCL-19-084, ASME Section XI Inservice Inspection Program Request for Alternative NDE-RCSSE-2R22 Use of Alternate Sizing Qualification Criteria Through a Protective Clad Layer
05000382/LER-2019-003, Relevant Indications Identified in Reactor Coolant Pump 1A and 2A Suction Drain Nozzle Dissimilar Metal Welds Resulting in the Condition of the Nuclear Power Plant, Including Its Principal Safety Barriers, Being
ONS-2018-023, Response to NRCs Request for Additional Information Regarding Relief Request 17-ON-001; Alternative to Extend the Code Case N-770, Inspection Item B, Examination Frequency
ONS-2017-072, Fifth Ten Year Inservice Inspection Interval, Relief Request No. 17-0N-001; Alternative to Extend the Code Case N-770, Inspection Item B Examination Frequency