(Draft Was DG-1023) Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less than 50 FT-LB
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L-2015-040, Submittal of Fifth 10 Year Interval Inservice Inspection (ISI) Program Plan
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-16-067, Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds
PNP 2014-066, Supplemental Response to NRC Request for Additional Information - Palisades Nuclear Plant 10 CFR 50 Appendix G Equivalent Margin Analysis - Mf 2962
PNP 2014-054, Response to NRC Request for Additional Information - 10 CFR 50 Appendix G Equivalent Margin Analysis - Mf 2962
L-2014-105, Inservice Inspection Plan - Fifth Inspection Interval, Unit 3 Relief Request No. 1 - Response to Follow-up Request for Additional Information
L-MT-13-059, Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests: Response to Request for Additional Information Reactor Systems Branch and Vessel & Internals Integrity Branch and Supplemental Informati
RC-12-0173, Technical Basis for Westinghouse Embedded Flaw Repair for V. C. Summer Unit 1 Reactor Vessel Head Penetration Nozzles
RS-15-236, Braidwood Station, Units 1 and 2 & Byron Station, Units 1 and 2 - Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds
RS-10-144, Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate
RS-18-124, Relief Request Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval
ND-18-0635, Response to Request for Additional Information Regarding Application of VT-1 Visual Examination Methodology for Preservice Inspection of the Reactor Vessel Nozzle Inner Radius Sections (VEGP 3&4-PSI-ALT-07S3)
L-2003-108, Inservice Inspection Plan, Unit 1 Third and Unit 2 Second Ten-Year Intervals Request for Additional Information Response Unit 1 Relief Request 23 and Unit 2 Relief Request 33
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)
BSEP-97-0060, Forwards Supplemental Info Re GL 92-01, Reactor Vessel Structural Integrity. Evaluation Rept on Reactor Vessel, Also Encl
RA-21-0144, Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant
RA-22-0180, Supplement to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant
LG-18-068, Instrumentation Nozzle N-16D As-Left J-Groove Weld Analysis, Areva Document No. 32-9281804-000 (Non-Proprietary Version)
LG-17-081, N-16D Nozzle Repair - Submittal of Analytical Flaw Evaluation, Design Analysis, and Corrosion Evaluation (Rev. 1)
RS-15-236, Areva Calculation 32-9244434-000, Revision 0, Byron and Braidwood RVCH Nozzle As-Left J-Groove Analysis
RC-13-0130, WCAP-17758-NP, Rev. 0, Technical Basis for Westinghouse Embedded Flaw Repair for V.C. Summer Unit 1 Reactor Vessel Head Penetration Nozzles and Attachment Welds
RS-07-059, Transmittal of WCAP-16401-NP, Revision 0, Technical Basis for Repair Options for Reactor Vessel Head Penetration Nozzles and Attachment Welds: Byron and Braidwood Units 1 & 2
RS-04-057, Response to License Renewal Safety Evaluation Report for the Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2
RA-25-0200, Subsequent License Renewal Application Supplement 1