NL-17-013, Response to Request for Additional Information Regarding Relief Request IP3-ISl-RR-09, Alternative to the Depth Sizing Qualification Requirement
LR-N17-0053, Request for Use of American Society of Mechanical Engineers (ASME) Code Cases N-695-1 and N-696-1
LR-N17-0102, Response to Request for Additional Information Regarding Relief Request SC-14R-171, Use of Code Cases N-695-1 and N-696-1
NL-16-132, Request for Relief Request IP3-ISI-RR-09 Alternative to the Depth Sizing Qualification Requirements
1CAN071601, Request for Relief from ASME Section XI Table IWB-2500-1 Requirements
1CAN041603, Request for Relief from ASME Section XI, Table IWB-2500-1 Requirements
PNP 2015-075, Submittal of Relief Request Number RR 4-23, Proposed Alternative Concerning ASME Code Depth Sizing Requirement
CNS-14-133, Relief Request Serial Number 14-CN-003, Relief Request to Use Alternative Depth Sizing Criteria
TMI-14-118, Submittal of Relief Request RR-14-01 Concerning Alternative Root Mean Square (RMS) Depth Sizing Requirements
MNS-14-058, Inservice Inspection Report, End of Cycle 22 Refueling Outage
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
DCL-13-038, ASME Section XI Inservice Inspection Program Relief Request NDE-RCS-SE-1R18 to Allow Use of Alternative Depth Sizing Criteria
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)
NRC 2012-0088, 10 CFR 50.55a Request, Relief Request 1 -RR-4 Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Lnlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval
L-12-183, Supplemental Information Regarding 10 CFR 50.55a Request for Alternative Examination Requirements for Reactor Vessel Safe-End Welds
RS-12-040, Response to Request for Additional Information Related to Braidwood Station Relief Request 13R-08
L-11-321, CFR 50.55a Request for Alternative Examination Requirements for Reactor Vessel Safe-End Welds
RS-11-173, Response to Request for Additional Information Related to Relief Request I3R-08
CP-201101031, Transmittal of Unit 1 Inservice Inspection Program Plan, Revision 0 (Unit 1: ASME Code XI 1998 Edition, 1999 and 2000 Addenda, Interval Start - August 13, 2010, Third Interval)
SBK-L-11132, Submittal of Third Ten-Year Interval Inservice Inspection and Second Ten-Year Containment Inservice Inspection Program
NL-11-0463, Proposed Relief Request for the Fourth ISI Interval (FNP-ISI-RR-01)
RBG-47110, Inservice Inspection Plan for the Third 10-Year Interval
SBK-L-10148, Response to Draft Request for Additional Information Re Request for Alternate Depth Sizing Qualification
NL-10-1663, VEGP-ISI-ALT-03, Version 3, Proposed Alternative for the Third ISI Interval
HNP-10-059, Request for Approval of Proposed Alternative I3R-07 in Accordance with 10 CFR 50.55a(a)(3)(i) for the Third Ten-Year Interval Inservice Interval
DCL-10-051, ASME Section XI Inservice Inspection Program Relief Request NDE-RCS-SE-1R16 to Allow Use of Alternate Sizing Qualification Criteria
NL-10-0706, VEGP-ISI-ALT-03, Version 2, Proposed Alternative for the Third ISI Interval
GNRO-2008/00071, Inservice Inspection (ISI) Program Third 10-Year Interval, Rev. 0
SBK-L-10056, Request for Use of an Alternate Depth Sizing Qualification
NL-10-0266, Proposed Alternative FNP-ISI-ALT-08
LIC-10-0004, Response to Request for Additional Information Re Use of Alternate Depth Sizing Qualification
LIC-09-0088, Request for Use of an Alternate Depth Sizing Qualification
AEP-NRC-2009-42, Response to Request for Additional Information Regarding Relief Request (ISIR-28) for Use of Weld Inlays as an Alternate Repair Technique for Alloy 82/182 Dissimilar Metal Welds in Reactor Vessel Safe End-to-Primary Nozzles
NL-09-0410, Proposed Alternatives for the Fourth ISI Interval
SBK-L-08190, Supplement to a Request for Use of an Alternate Depth Sizing Qualification
AEP-NRC-2008-25, Use of Weld Inlays as an Alternative Repair Technique for Reactor Vessel Safe End-to-Primary Nozzle Alloy 82/182 Welds
SBK-L-08174, Request for Relief to Use of an Alternate Depth Sizing Qualification Requirement for Coordinated Implementation of ASME Section XI, Supplements 2 and 10 for Piping Examinations Performed from Inside Surface
RNP-RA/08-0048, Request for Relief from ASME Boiler and Pressure Vessel Code, Section XI, Appendix Viii (Supplements 2 and 10) for the Fourth Ten-Year Inservice Inspection Program Interval
CP-200800927, (Cpnpp), Relief Request B-8 for Unit 1 Second 10 Year ISI Interval & B-6 for Unit 2 Second 10 Year ISI Interval from 10 CFR 50.55a Requirements for Reactor Vessel Hot & Cold Leg Nozzle Weld Examinations (Unit 1 Second Interval Start
1CAN050807, Inservice Inspection Plan for the Fourth 10 - Year Interval
L-2008-043, Fourth Ten-Year Inservice Inspection Interval ISI Program Plan - Revision 0
NRC 2008-0017, CFR 50.55a Request, Relief Request RR-21, Examination of the Reactor Pressure Vessels, Fourth Ten-Year Inservice Inspection Program Interval
1CAN010801, Request for Relief from ASME Section XI, Table IWB-2500-1 Requirements
DCL-16-102, ASME Section XI Inservice Inspection Program Relief Request NDE-RCS-SE-1R20 to Allow Use of Alternative Depth Sizing Criteria
NL-06-2088, Unit 1, Vogtle Electric Generating Plant - Units 1 & 2, Revised Page to Enclosure 2 in Response to NRC Request for Additional Information Re Inservice Inspection Alternatives for Reactor Pressure Vessel Examinations
NL-06-1832, Units 1 & 2, Response to NRC Request for Additional Information Regarding Inservice Inspection Alternatives for Reactor Pressure Vessel Examinations
RC-06-0117, Relief, Request to Use Alternatives to ASME Code Requirements in VCSNS Third Inservice Inspection Interval (RR-III-03, RR-III-04)
RA-18-0180, Supplement to Relief Request for an Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2
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)
ET 08-0044, 10 CFR 50.55a Request 13R-06, Alternative to the Examination Requirements of ASME Section Xl for Class 1 Piping Welds Examined from the Inside of the Reactor Vessel
GO2-03-185, Implementation of the Performance Demonstration Methods Supplement Ten (10) Qualification Requirements for Dissimilar Metal Welds
ET 09-0014, Response to Request for Additional Information Regarding 10 CFR 50.55a Request I3R-06
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
DCL-14-111, American Society of Mechanical Engineers Section Xl Inservice Inspection Program Relief Request NDE-RCS-SE-2R19 - Use of Alternate Sizing Qualification Criteria Through a Protective Clad Layer
NRC 2013-0012, Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Inlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval Response to Request for Additional Information
RS-11-050, Third 10-Year Inservice Inspection Interval Relief Request I3R-08, Alternative Requirements to ASME Section XI Appendix VII (Supplements 2 and 10), Examinations of Class 1 Pressure Retaining Welds Conducted from the Inside
BW070052, Inservice Inspection Program Relief Request I2R-49
TMI-14-136, Response to Request for Additional Information - Submittal of Relief Request RR-14-01 Concerning Alternative Root Mean Square (RMS) Depth Sizing Requirements