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05000331/LER-2007-003, Re Linear Indications Found During UT Examination of Safe-End to Nozzle Welds
MNS-17-012, Relief Request 17-MN-001, Alternative for Repair of Class 1 Piping
BSEP 17-0033, Proposed In-service Inspection Alternative for Application of Dissimilar Metal Weld Full Structural Overlay
BSEP 17-0064, Application of Dissimilar Metal Weld Full Structural Overlay on Reactor Pressure Vessel Nozzle N9
DCL-17-083, Request for Approval of Alternative for Application of Full Structural Weld Overlay, REP-RHR-SWOL
NOC-AE-16003345, LTR-PAFM-16-11-NP, Revision 0, Technical Justification to Support Extended Volumetric Examination Interval for South Texas, Unit 2 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds.
PLA-3060, Responds to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. Staff Position on Matls, Water Chemistry,Crack Evaluation & Repair Criteria & Insp Schedules Among Topics Addressed.Flaw Evaluations Encl
PNP 2015-089, Inservice Inspection Master Program Fifth 10-Year Interval
L-2015-272, 1301103.401, Revision 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L, May 2015
NRC 2015-0040, Steam Generator Nozzle to Safe-End Dissimilar Metal (DM) Weld Inspection
NLS2105025, 10 CFR 50.55a Requests for Fifth Ten-Year Inservice Inspection Interval
NOC-AE-15003250, LTR-PAFM- 15-27-NP, Technical Justification to Support Extended Volumetric Examination Interval for South Texas, Unit 1, Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds (Non-Proprietary)
HNP-15-039, Relief Request I3R-15 Revision 2, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Third Ten-Year Interval
CP-201500402, Relief Request 1B3-3 Inservice Inspection for Application of an Alternative to ASME Boiler & Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Cold Leg Weld Inspection Frequency
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
MNS-15-014, LTR-PAFM-14-114-NP, Rev. 0, Technical Justification to Support Extended Volumetric Examination Interval for McGuire, Unit 1, Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds (Non-Proprietary)
PLA-7178, Inservice Inspection Program Plan for the Fourth Ten-Year Interval
RS-14-168, Responses to NRC Requests for Additional Information, Set 26, Dated May 21, 2014, Related to License Renewal Application
RS-14-084, Responses to NRC Requests for Additional Information, Set 10, Dated February 26, 2014 Related to the License Renewal Application
L-2014-005, Response to Request for Additional Information and Supplemental Information for Relief Request No. 13
NL-14-005, Submittal of Relief Request IP3-1SI-RR-07 for Code Case N-770-1 Weld Inspection Frequency Extension
RS-14-002, Response to NRC Requests for Additional Information, Set 4, Dated December 12, 2013, Related to the License Renewal Application
CP-201301361, Relief Request No. B-14 for Reactor Pressure Vessel Hot Leg Nozzle Weld Examinations (Second ISI Interval End Date: August 2, 2014)
HNP-13-119, Relief Request I3R-13, Reactor Vessel Closure Head Nozzle 37, Inservice Inspection Program - Third Ten-Year Interval
CNL-13-104, Response to NRC Request for Additional Information Regarding the Review of License Renewal Application, Sets 11 (B.1.40-4a, B.1.25.1a), 13 (B.1.41-4a),14 (3.5.1-57, 3.5.1-87)
L-2013-112, ASME Section XI, Inservice Inspection, Relief Requests No. 11 Alternative Through-Wall Sizing Requirements for Implementation of Appendix Viii, Supplement 10
TMI-13-038, Relief Request RR-12-02 Concerning the Installation of a Full Structural Weld Overlay on the Lower Cold Leg Letdown Nozzle Dissimilar Metal Welds and Alloy 600 Safe-End
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)
RC-12-0173, Technical Basis for Westinghouse Embedded Flaw Repair for V. C. Summer Unit 1 Reactor Vessel Head Penetration Nozzles
RC-12-0165, Relief Request RR-III-09 Alternative Weld Repair for Reactor Vessel Head Penetration
GNRO-2012/00109, Stress Analysis Summary Demonstrating That the Nozzle to Safe-End DMW, N06B-KB, Will Perform Its Intended Design Function After Weld Overlay Installation
HNP-12-060, Relief Request I3R-09 Reactor Vessel Closure Head Nozzle Repairs Inservice Inspection Program - Third Interval, Request for Additional Information Response
ULNRC-05860, Amendment to Application for Renewed Operating License
RS-12-040, Response to Request for Additional Information Related to Braidwood Station Relief Request 13R-08
NOC-AE-11002742, Response to Requests for Additional Information for the License Renewal Application
ULNRC-05822, CFR 50.55a Request: Proposed Alternative to ASME Section XI Requirements Regarding Performance of Second Successive Examination for Indication on C Cold Leg Safe-End to Elbow Weld
NG-11-0320, Fourth 10-Year Inservice Inspection Plan
NL-11-1081, Reactor Pressure Vessel 2N2G Recirculation Inlet Nozzle-To-Safe End Weld Full Structural Weld Overlay, Crack Growth Calculations and Stress Analysis - Spring 2011 Outage (2R21)
TMI-11-078, Response to Request for Additional Information - Submittal of Relief Request RR-10-02 Concerning the Weld Overlay of the Pressurizer Spray Nozzle to Safe-End and Safe-End to Elbow Dissimilar Metal Welds
TMI-11-061, ISI Program Plan, Fourth Ten-Year Inspection Interval
TMI-11-062, Response to Request for Additional Information - Submittal of Relief Request RR-10-02 Concerning the Weld Overlay of the Pressurizer Spray Nozzle to Safe-End and Safe-End to Elbow Dissimilar Metal Welds
DCL-11-003, Response to Telephone Conference Call Held on December 14, 2010, Between the NRC and Pacific Gas & Electric Co. Concerning Responses to Requests for Additional Information Related to the License Renewal Application
2CAN011105, Program Section SEP-ISI-105 for ASME Section XI, Division 1, Arkansas Nuclear One, Unit 2, Inservice Inspection Program
RBG-47110, Inservice Inspection Plan for the Third 10-Year Interval
BSEP 18-0039, Proposed In-Service Inspection Alternative for Application of Dissimilar Metal Weld Full Structural Overlay - Nozzles N4A and N4D
NL-18-0193, Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-03, Version 1.0
LR-N17-0088, Redacted - Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 3, Design of Structures, Components, Equipment and Systems, Sections 3.1 Through 3.5
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 5, Reactor Coolant System and Connected Systems
DCL-15-131, Diablo Canyon, Unit 1, Pressurizer Spray Line Pipe Weld Flaw Evaluation, Calculation Package, Part 1
RA-18-0073, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D
RA-10-096, Submittal of Analytical Evaluation for a Reactor Recirculation Line Weld
NG-10-0567, Revision to Relief Request for Alternative to ASME Section XI Requirements to Use Structural Weld Overlay Repairs as an Alternative Repair Technique
DCL-10-120, Response to NRC Letter Dated August 26, 2010, Request for Additional Information (Set 17) for License Renewal Application
TMI-10-100, Submittal of Relief Request RR-10-02 Re Weld Overlay of the Pressurizer Spray Nozzle to Safe-End & Safe-End to Elbow Dissimilar Metal Welds
LIC-10-0065, LTR-PAFM-10-123-NP, Rev. 0, Technical Justification to Support Alternative Visual Examination Intervals for Fort Calhoun Reactor Vessel Outlet Nozzle to Safe End Dissimilar Metal Welds, Enclosure 2
LR-N10-0243, Response to NRC Request for Additional Information Dated June 14, 2010, Related to Sections 4.3 and 4.4 License Renewal Application
LR-N10-0192, Response to NRC Request for Additional Information Dated May 14, 2010 Related to Aging Management Program B.2.1.6, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel
NL-10-0967, Pressurizer Nozzle Full Structural Weld Overlays, Nondestructive Examination Results -Spring 2010 Outage (2R20)
NL-10-0918, Submittal of Report LTR-PAFM-10-54-NP, Revision 0, Pressurizer Spray and Safety/Relief Nozzles Full Structural Weld Overlay Evaluation
NRC 2010-0035, Response to Request for Additional Information on License Amendment 261 Extended Power Uprate
SBK-L-10027, Inservice Inspection Examination Report for Inspections Conducted Prior to and During the Thirteenth Refueling Outage That Concluded on November 12, 2009
NLS2010013, Request Relief from Certain Inservice Inspection (ISI) Code Requirements
RS-09-165, Request for Approval of Updated Pipe Flaw Evaluation Report
NL-09-1510, Vogtle Electric Generating Plant, Units 1 and 2 - Inservice Inspection Plan Third Inspection Interval Volume 1, Version 3.0
AEP-NRC-2009-70, Revised Technical Justification for Deviation from EPRI MRP-139 Inspection Requirements for Reactor Vessel Alloy 600/82/182 Welds at DC Cook Nuclear Plant
AEP-NRC-2009-58, Notification of MRP-139 Deviation
L-PI-09-086, NSPM Comments on NRC Safety Evaluation Report with Open Items Related to Renewal of Operating Licenses
L-09-179, Response to Requests for Additional Information Related to Alternative Dissimilar Metal Weld Repair Methods
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
NLS2009040, Response to Request for Additional Information for License Renewal Application - Aging Management Programs
LR-N09-0018, Relief Request RR-HC-I3R-04 Proposed Alternate Repair Method
L-09-020, 10 CFR 50.55a Requests for Alternative Dissimilar Metal Weld Repair Methods for Reactor Vessel Nozzles, Reactor Coolant Pump Nozzles, and Reactor Coolant Piping
L-PI-09-006, Responses to NRC Requests for Additional Information Dated December 18, 2008 Regarding Application for Renewed Operating Licenses
NL-08-0877, Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i) Application of Dissimilar Weld Full-Structural Weld Overlays Alternative Lsi ALT-08-02 Version 1
L-PI-08-106, Responses to NRC Requests for Additional Information Dated November 20, 2008 Regarding Application for Renewed Operating Licenses
JAFP-08-0131, James A. FitzPatrick Nuclear Power Plant - Submittal of the Stress Analysis Summary for the N2C-SE Weld Overlay
PLA-6449, Request for Additional Information for the Review of License Renewal Application, Section B.2.1 - Questions and Responses
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
JAFP-08-0102, Request for Relief (RR-7 Revision 1) - 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
L-2008-210, In-Service Inspection Plans, RAI Reply for Fourth Ten-Year Interval Unit 1 Relief Request 2
L-08-207, Proposed Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Inspection Period Extension Requirement
PLA-6383, Response to Request for Additional Information for the Review of the Units 1 & 2, License Renewal Application (LRA) Sections B.2.1, B.2.5, B.2.7, B.2.9, and B.2.10
L-08-147, Reply to Request for Additional Information for Renewal License Application
L-PI-08-003, Prairie Lsland Nuclear Generating Plant, Unit 2 - Response to RAI Regarding 10 CFR 50.55a, Request for Relief from ASME Section XI Repair and Replacement Requirements: Proposed Alternatives for Application of Structural Weld Overlay to t
LIC-08-0067, Response to Request for Additional Information Relief Request for Valve Replacement and Supplemental Information
W3F1-2008-0037, Summary of Design and Analyses of Weld Overlays for Pressurizer and Hot Leg Nozzle Dissimilar Metal Welds for Alloy 600 Mitigation
NL-08-0667, Unit 1 Pressurizer Nozzle Full Structural Weld Overlay Evaluation and Nondestructive Examination Results, Spring 2008 Outage (1R14)
L-2008-098, In-Service Inspection Plans, Submittal for the Use of Structural Weld Overlays as an Alternative Repair Technique, Fourth Ten-Year Interval Unit 1 Relief Request 2
NL-08-0611, Pressurizer Nozzle Full Structural Weld Overlay Evaluation and Nondestructive Examination Results, Spring 2008 Outage (1R14)
2CAN040801, Summary of Design and Analyses of Weld Overlays for Hot Leg Nozzle Dissimilar Metal Welds for Alloy 600 Mitigation at ANO-2
NLS2008031, Response to Request for Additional Information Regarding 10 CFR 50.55a Request RI-35, Revision 0, and Submittal of RI-35, Revision 1
NL-08-0311, Response to NRC Request for Additional Information Regarding Application of a Dissimilar Metal Weld Full-Structural Weld Overlay
1CAN020803, Request for Alternative ANO1-R&R-011 Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs
NL-08-0280, Application of a Dissimilar Metal Weld Full-Structural Weld Overlay
W3F1-2008-0010, Revised Request for Alternative W3-R&R-006 - Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs
2CAN020801, Supplemental to Request for Alternative ANO2-R&R-005, Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs
SBK-L-08022, Supplement to Request for Use of Structural Weld Overlays as an Alternative Repair Technique
L-08-034, Summary of Design and Analyses of the Weld Overlays for Pressurizer and Hot Leg Nozzle Large Bore Dissimilar Metal Welds for Alloy 600 Mitigation
NLS2008012, 10 CFR 50.55a Request Number RI-35, Revision 0
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 15 - Aging Management Programs and Time Limited Aging Analysis
NL-07-2116, Pressurizer Nozzle Full Structural Weld Overlays Nondestructive Examination Results - Fall 2007 Outage (1R21)
LR-N07-0282, Response to Request for Additional Information, Relief Request HC-RR-I2-W02
NL-07-2065, Pressurizer Nozzle Structural Weld Overlay Evaluation Report
DCL-07-099, ASME Section XI Inservice Inspection Program Relief Request REP-1 U2, Revision 1, and Response to Request for Additional Information
LR-N07-0276, Relief Request HC-RR-I2-W03 Proposed Alternative Repair Method
LR-N07-0273, Relief Request HC-RR-I2-W02, Proposed Alternative Repair Method
HNP-07-143, Inservice Inspection Relief Request 1 Re Weld Overlay Repair Stress Analysis Summary
1CAN100702, Request for Alternative ANO1-R&R-011, Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs
L-2007-148, In-Service Inspection Plans, Resubmittal for the Use of Structural Weld Overlays as an Alternative Repair Technique Third Ten-Year Interval Unit 2 Relief Request 10
CPSES-200701302, Relief Request B-4 to the Unit 2 Inservice Inspection (ISI) Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date - August 03, 2004, Second Interval)
NL-07-1320, Proposed Alternative or Application of Pressurizer Nozzle Full-Structural Weld Overlays
L-PI-07-054, CFR 50.55a Request: Proposed Alternatives for Application of Structural Weld Overlay to the Pressurize Surge Nozzle Weld (2-RR-4-81)
RC-07-0085, Virgil Summer - Request to Use Alternatives to ASME Code Section XI Requirements for Application of Weld Overlay Repairs (RR-III-05)
L-07-073, Supplement to Proposed Alternative to American Society of Mechanical Engineers Code Section XI Repair Requirements (Request No. BV1-PZR-01, Revision 1)
HNP-07-041, Inservice Inspection Relief Request 1, Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs
BYRON 2007-0059, Pressurizer Weld Overlay Examination Results Related to Byron Station Relief Request 13R-08
NL-07-0961, Pressurizer Nozzle Full Structural Weld Overlay Evaluation
CNRO-2007-00021, Request for Alternative W3-R&R-006 Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs
JAFP-06-0109, License Renewal Application, Amendment 10, RAI Responses
JAFP-07-0019, License Renewal Application, Amendment 9
NL-07-0837, Pressurizer Nozzle Full Structural Weld Overlay Evaluation
CPSES-200700708, Evaluation of Pressurizer Weld Overlay Confirmatory Analyses
L-2007-045, In-Service Inspection Plans, Use of Structural Weld Overlays as an Alternative Repair Technique Third Ten-Year Interval Unit 2 Relief Request 10
DCL-07-038, ASME Section XI Inservice Inspection Program Relief Request REP-1 U2
CNRO-2007-00014, Request for Alternative ANO1-R&R-010 Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs
CNRO-2007-00012, Request for Alternative ANO2-R&R-005, Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs
CNRO-2007-00010, Request for Alternative ANO1-R&R-010 Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs
L-07-039, Proposed Alternative to American Society of Mechanical Engineers Code Section XI Repair Requirements (Request No. BV1-PZR-01)
NG-07-0176, Alternative to ASME Section XI Requirements to Use Code Cases N-504-2 and N-638-1 for Weld Overlay Repairs at the Duane Arnold Energy Center
NL-07-0366, Proposed Alternative for Application of Pressurizer Nozzle Full-Structural Weld Overlays - Revision 2.0
CNRO-2007-00001, Request for Alternative ANO1-R&R-010, Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs
NL-06-2768, Proposed Alternative for Application of Pressurizer Nozzle Full-Structural Weld Overlays and Response to Request for Additional Information
BYRON 2006-0119, Pressurizer Weld Overlay Examination Results Related to Relief Request I3R-08
NL-06-2434, Response to Request for Additional Information Regarding Proposed Alternative for Application of Full Structural Weld Overlays on Pressurizer Nozzles
CPSES-200601983, Relief Request B-6 to Unit 1 Inservice Inspection Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date - August 13, 2000, Second Interval)
NL-06-1713, Proposed Alternative for Application of Pressurizer Nozzle Full-Structural Weld Overlays
DCL-06-069, Residual Heat Removal Weld RB-119-11 - Flaw Analytical Evaluation Results
NOC-AE-06002000, Proposed Alternative to ASME Section XI Requirements for Application of a Weld Overlay (RR-ENG-2-43)
L-06-038, Proposed Alternative to American Society of Mechanical Engineers Code Section XI Repair Requirements
L-2018-174, Structural Integrity Associates Engineering Report No. 0901350.401, Revision 4, Leak-Before-Break Evaluation - Accumulator, Pressurizer Surge, and Residual Heat Removal Lines
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
NL-18-1565, Inservice Inspection Program Owners Activity Report for Outage 1R21
JAFP-18-0113, Fifth Ten-Year Inservice Inspection Interval Program Plan
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
NRC Generic Letter 84-11, Inspections of BWR Stainless Steel Piping
NRC Generic Letter 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping
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
NLS2005003, Response to Request for Additional Information Regarding Relief Request RI-35 Cooper Nuclear Station
ET 06-0021, Operating Corporations Response to Request for Additional Information Regarding 10 CFR 50.55a Request 13R-05 and Submittal of Revision 1 to 10 CFR 50.55a Request 13R-05
ULNRC-05100, Transmittal of Inservice Inspection, Summary Report for Refuel 13 and WCAP-16280-P, Flaw Evaluation Handbook for Plant Reactor Vessel Inlet Nozzle Safe-End Weld Region, May 2004
SBK-L-04065, ASME Section III and Section XI Relief Request Pr 04-01 for the Repair of CRDM Canopy Seal Welds
NLS2004125, Inservice Inspection Relief Request RI-35 Cooper Nuclear Station
PLA-5744, Proposed Relief Request No. 31 to the Second 10-Year Inservice Inspection Program for Susquehanna Ses Unit 1, PLA-5744
PLA-5743, Supplemental Information for Proposed Relief Requests No. 29 and 30 to the Second 10-Year Inservice Inspection Program for Susquehanna Ses Unit 1
PLA-5740, Proposed Relief Request No. 29 to the Second 10-Year Inservice Inspection Program
RS-03-206, Request for Approval of Pipe Flaw Evaluation
RNP-RA/03-0075, Technical Basis for RPV Head CRDM Nozzle Inspection Interval H.B. Robinson Steam Electric Plant, Unit No. 2, References 9-1 Through E-6
ULNRC-05423, Responses to Requests for Additional Information Regarding Requests for Relief from ASME Section XI Code Examination Requirements, RRs ISI-34, ISI-37, ISI-38, and ISI-40
CPSES-200300265, Relief Request B-10 for Second 10 Year ISI Interval from 10 CFR 50.55a Requirements for Class I Repair/Replacement of CRDM Canopy Seal Weld (Second Interval Start Date: August 2003)
CPSES-200203940, Relief Request B-3 for Second 10 Year ISI Interval from 10 CFR 50.55a Requirements for Class 1 the Repair/Replacement of CRDM Canopy Seal Weld (Interval Start Date: August 13, 2000, Second Interval)
SVP-02-102, Supplemental Request for Approval of Pipe Flaw Evaluation and Response to Request for Additional Information
NOC-AE-02001427, Second Revised Request for Relief from ASME Section XI Requirements for Repair/Replacement Activity of Control Rod Drive Mechanism Canopy Seal Welds in Accordance with IWA 4000, for the Second Ten-Year Inservice Inspection Interval
NOC-AE-02001424, Revised Request for Relief from ASME Section XI Requirements for Repair/Replacement Activity of Control Rod Drive Mechanism Canopy Seal Welds in Accordance with IWA 4000, for the Second Ten-Year Inservice Inspection Interval
NOC-AE-02001421, STP, Units 1 and 2 Request for Relief for ASME Section XI Requirements for Repair of Control Rod Drive Mechanism (CRDM) Canopy Seal Welds in Accordance with IWA 4000, for the Second Ten-Year Inservice Inspection Interval
NRC 2002-0082, Day Response to NRC Bulletin 2002-02: Reactor Pressure Vessel Head & Vessel Head Penetration Nozzle Inspection Programs
RS-02-039, Request for Approval of Pipe Flaw Evaluation
RA-20-0280, Submittal of IWB-3640 Analytical Evaluation Performed to Accept an ASME Section XI Code Rejected Sub-Surface Flaw
RA-20-0373, Submittal of IWB-3640 Analytical Evaluation of RPV Nozzle N4D Safe End to Pipe Weld Indication
NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report
BSEP-98-0118, Forwards Summary of Results of Evaluations of Cracking Found on Bsep,Unit 1,jet Pump Riser Thermal Sleeve Extension to Elbow Welds.Evaluations Justify Unrestricted Operation for 24-month Fuel Cycle
1CAN099907, Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative
B12521, Responds to NRC Comments Received on 870304 Re IGSCC Insp Plan for 1987 Refueling Outage,Per NRC 860403 Request.Igscc Plan Developed in Accordance W/Guidelines of Rev 2 to Draft NUREG-0313.Rev 1 to IGSCC Insp Plan for 1987 Outage Encl
ND-20-0907, Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1)
B17695, Forwards Response to NRC 990204 RAI Re LBB Evaluation of Pressurizer Surge Piping.Response Discusses Loads,Fatigue & Fatigue Crack Growth Analysis That Were Part of Util Original 981109 Submittal
JPN-87-018, Forwards Addl Info on Results of IGSCC During Reload 7/Cycle 8 Outage.Total of 48 Welds Inspected Including,Overlays & Cracked Welds.Util Plans to Implement Leakage Surveillance, Per Generic Ltr 84-11
SVP-98-353, Forwards Licensee Assessment of Flaw Indications Found in IGSCC Susceptible Welds in Plant Primary Sys Piping,Summary of Weld Overlay Repair Designs & Detailed Evaluations for Flaw Indications That Util Proposes to Leave as-is
JPN-88-017, Forwards Revised Pages of Rept Re Weld Overlays Installed at Plant.Pages Revised to Clarify Allowable Stress Values Used in Weld Overlay & Flaw Evaluation Studies
JPN-88-041, Responds to Generic Ltr 88-01 Re NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.Includes Insp Plans & Mitigation Plans.Separate Submittals Will Address Resistance Heat Stress Improvement & Change to Tech Specs
AECM-89-0130, Forwards Addl Info Re Response to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping, Per 890517 Request
CNL-21-081, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI, Paragraph IWB-2420(b) and the Use of Case N-526
L-2022-015, Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld - RAI
L-2022-011, Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld
L-30-100, Rev 2 to Design Rept for Recirculation Sys Weld Overlay Repairs & Flaw Analysis at Brunswick Steam Electric Plant Unit 1
NLS8400289, Forwards Weld Repair Criteria Development Summary Re Inconel Nozzle Buttering.Use of Repair Method May Be Required as Early as 841220 at Site
AECM-84-0297, Forwards Response to Generic Ltr 84-11 Re Insps of BWR Stainless Steel Piping for Igscc.Inservice Insp Program Requires IGSCC Insp on Four Welds in Each of 24 Inch & 16 Inch Pipes
RBG-35-397, Requests Permission to Operate Facility Addl 5000 Hours Until Fourth Refueling Outage W/O Reperforming Exam of N4A-2 Feedwater Nozzle to safe-end Weld & That NRC Amend Safety Evaluation Reflecting Info Contained in Encl Rept
L-17-103, Rev 0 to Statistical Evaluation of Postulated Flaws at Brunswick Steam Electric Plant,Unit 1
BSEP-83-3748, Responds to 830826 Intergranular Stress Corrosion Cracking Order Confirming Shutdown & 830304 IE Bulletin 83-02 by Providing Results of Ultrasonic Test Insp of ASME Code Class I Stainless Steel Piping.Work in Progress on Overlay Repair
L-13-104, Rev 1 to Design Rept for Weld Overlay Repairs at Brunswick Steam Electric Plant Unit 2
CNL-22-075, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,.
ND-22-0817, Enclosures 1 and 2: Proposed Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds and Alternative for Use of Code Case 648-2 for Inservice Inspection
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)
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)
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)
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
JPN-94-043, Provides Response to GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs. Plant Specific Safety Analysis Supporting Continued Operation Until 1994 Refuel Outage & Engineering Rept JAF-RPT-MISC-01788 Encl
PY-CEI-NRR-2380, Requests Approval of Attached Repair Plan for Feedwater Nozzle to safe-end Weld N4C-KB.Proposed Weld Overlay Design & Installation Plan Details Included in Attachment 1. Attachment 2 Provides Applicable Preliminary Weld Procedure
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)
3F0508-12, Relief Request 08-001-RR, Revision 1, 60-Day Response, Summary of Analysis Calculations
3F0907-05, Relief Request 07-003-RR, Revision 1, and Response to Request for Additional Information
3F0507-03, Relief Request 07-003-RR, Revision 0
3F1008-03, Relief Request 08-002-RR, Revision 0
3F0308-04, Relief Request 08-001-RR, Revision 1
L-2024-084, Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld
RA-24-0152, Duke Energy Carolinas, LLC - Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI
DCL-13-021, Areva Calculation 32-9200249-000, Diablo Canyon Power Plant Unit 2 Pzr Safety and Spray Nozzles Planar Flaw Analysis - Non Proprietary
RA-24-0229, Transmittal of Refuel 32 (O3R32) Inservice Inspection (ISI) Report, Fifth 10-Year ISI Interval
NLS2022004, Response to Nuclear Regulatory Commissions Request for Additional Information Regarding Relief Request RR5-01, Revision 1
NLS2021066, Response to Nuclear Regulatory Commissions Request for Additional Information Regarding Alternative Request RI5-02, Revision 3
NMP1L3539, Day Commitment Response - 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)
RA-22-0195, Response to Request for Additional Information (RAI) for the Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue for the Safety Injection Nozzle
SVP-99-021, Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With
05000271/LER-1986-005, :on 860426,detected Ultrasonic Indications Indicative of IGSCC in Iconel 182 Weld Butter of Both Core Spray Nozzles During Exams Performed Per IE Info Notice 84-41.Weld Overlays Will Be Applied to Nozzles
05000498/LER-1988-028, :on 880401,leakage Observed at Number of Locations in aluminum-bronze Essential Cooling Water Sys. Caused by Crevice Corrosion in Small Bore Fittings & Valves. Leaking Components Replaced
05000265/LER-1985-008-01, :on 850401 Visual Insp Revealed Recirculation Weld Area W/Water Seeping from Small Crack & Circumferential & Axial Indications in Heat Affected Zones.Caused by Igscc. Indications Repaired by Applying Weld Overlay
05000254/LER-1984-005-02, :on 840414,insps Revealed Several Welds W/ Circumferential &/Or Axial Linear Indications & Areas W/ Small Cracks.Caused by Igscc.Welds Repaired
NRC-24-0050, Inservice Inspection-Nondestructive Examination (ISI-NDE) Program for the Fourth 10-Year Inspection Interval
DCL-18-058, Flaw Evaluation of Unit 2, ASME Code Class 2 Charging Pump Discharge Lines: Welds WIC-45A and RB-46-7
GO2-91-096, Discusses Linear Indication Identified on pipe-to-valve Weld.Evaluation in Accordance W/Generic 88-01 Completed.Flaw Acceptable for Continued Operation W/O Repair.Summary Encl
GO2-91-098, Provides Response to Questions Re Water Chemistry History, Ut Characterization of 2ORRC(6)-8 Indication,Input to Flaw evaluation,poet-IHSI Exam & Location of 2ORRC(6)-8,per 910510 & s
GO2-84-364, Responds to Generic Ltr 84-11 Re Cracks in BWR Stainless Steel Piping.Response Addresses Scope & Schedule of Planned Insp,Qualifications of Examiners,Description of Surveillance Methods & Measures Taken When Cracks Discovered
05000389/LER-1999-003, :on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With
JAFP-17-0054, Submittal of Stress Analysis Summary for the 24-10-130 Weld Overlay
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
CP-201600097, Westinghouse LTR-PAFM-16-2-NP, Technical Justification to Support Extended Volumetric Examination Interval for Comanche Peak Unit 1 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds
CP-201500999, Revision to Relief Request 1B3-3 Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Cold Leg Weld Inspection
RA-14-105, Submittal of Fifth Ten-Year Interval Inservice Inspection Program Plan
NL-14-027, LTR-PAFM-13-115-NP, Rev. 0, Technical Justification to Support Extended Volumetric Examination Interval for Indian Point Generating Station Unit 3 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds
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
HNP-13-057, Relief Request I3R-11 Reactor Vessel Closure Head Nozzles Inservice Inspection Program - Third Interval
05000219/LER-2012-003-01, Regarding Control Rod Drive Return Nozzle Weld NC-4-1A PT Indications at N9
TMI-13-009, Response to Request for Additional Information - Relief Request RR-12-02 Re Installation of Full Structural Weld Overlay on Lower Cold Leg Letdown Nozzle Dissimilar Metal Welds & Alloy 600 Safe-End
RC-12-0170, LTR-PAFM-12-137-NP, Rev. 1, Technical Basis for Westinghouse Embedded Flaw Repair for V. C. Summer, Unit 1, Reactor Vessel Head Penetration Nozzles
NL-11-123, LTR-PAFM-11-136-NP, Rev. 0, Technical Justification to Support Extended Volumetric Examination Interval for Indian Point Generating Station Unit 2 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds
L-2009-019, Report No. 0800024.407, Summary Report of the Design Analysis and Non-Destructive Examination Results for St. Lucie, Unit 1 Hot Leg Nozzle Weld Overlay Repairs
RNP-RA/08-0121, WCAP-15621-NP, Rev 1, Handbook on Flaw Evaluation for the H.B. Robinson Unit 2 Reactor Vessel
NL-08-0901, Unit 1, Inservice Inspection Program Owners Activity Report for Outage 1R23 and Structural Integrity Design Report for the N9 CRD Nozzle-to-Cap Full Structural Weld Overlay
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
BW070013, Second 10-Year Inservice Inspection Interval, Relief Request I2R-48, Structural Weld Overlays on Pressurizer Spray, Relief, Safety and Surge Nozzle Safe-Ends and Associated Alternative Repair Techniques
05000265/LER-2004-002, Regarding Axial Flaws Detected in Recirculation Piping During Inservice Inspection
SVP-02-096, Request for Approval of Pipe Flaw Evaluation & GE Report GE-NE-0000-0009-4533-01, Quad Cities Unit 1 Evaluation of Indication in Weld 02BS-F4 in 28 Inch Recirculation Piping
NRC-23-0030, Inservice Inspection-Nondestructive Examination (ISI-NDE) Program for the Fourth 10-Year Inspection Interval
RA-21-0332, Subsequent License Renewal Application Responses to NRC Request for Additional Information Set 1 and Second Round Request for Additional Information B2.1.27-1a
RA-24-0264, Proposed In-service Inspection Alternative for Application of Dissimilar Metal Weld Full Structural Overlay - Nozzle N4D
PNP 2025-047, Response to Request for Additional Information Regarding License Amendment Request to Include Leak Before Break Methodology for Primary Coolant System Hot and Cold Leg Piping in Palisades Licensing Basis
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
PNP 2025-058, Relief Request Number RR 5-11, Proposed Alternative to ASME Section XI Code Requirements for Primary Coolant System Piping Branch Connection Modifications