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NL-17-020, License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan
GNRO-2017/00009, Proposed Alternative with 10 CFR 50.55a(z)(1), Use of Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines
RS-17-072, Fourth 10-Year Interval Inservice Inspection Program Relief Requests
L-17-183, 10 CFR 50.55a Request to Apply Alternative Examination Requirements to Certain ASME Section Xl Class 1 Components (Request IR-056. Revision 2)
2CAN091701, Response to Request for Additional Information Reactor Vessel Internals Aging Management Program Plan
NMP2L2620, Submittal of Post Extended Power Uprate Steam Dryer Inspection Results and Long-term Steam Dryer Inspection Plan in Accordance with Operating License Conditions 2.C.(20)(f), 2.C.(20)(g) and 2.C.(20)(h)
SVP-16-044, Deviation from BWR Vessel and Internals Project (Swavip) Guidelines Inspection Core Shroud Welds
L-MT-16-026, Response to Request for Additional Information for Approval of Alternative to Apply the BWRVIP Guidelines in Lieu of Specific ASME Section XI Code Requirements for Reactor Pressure Vessel Internals and Components Inspection
RS-16-052, Response to NRC Requests for Additional Information, Set 15, Dated February 16, 2016 Related to the License Renewal Application
NG-16-0035, Notification of Deviation from Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines
L-2017-216, License Renewal Commitments: Reactor Vessel Internals Aging Management Plan, Clarification of Responses to RAI 1 and RAI 6
RA17-086, County Station, Units I & 2 - 10CFR50.55a Relief Request 14R-01
NOC-AE-15003320, Response to Request for Additional Information Set 34 for the Review of the License Renewal Application
NRC-15-0104, Notification of Revision to BWRVIP Core Plate Deviation Disposition
PNP 2015-089, Inservice Inspection Master Program Fifth 10-Year Interval
RS-15-318, Stations - Submittal of Relief Requests I3R-10, 1ISI-004, and 2ISI-013 Concerning Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements
L-MT-15-083, 10 CFR 50.55a Request No. RR-010: Request for Approval of an Alternative to Apply the BWRVIP Guidelines in Lieu of Specific ASME Section XI Code Requirements for Reactor Pressure Vessel Internals and Components Inspection
L-2015-229, License Renewal Commitments, Reactor Vessel Internals Aging Management Plan
GO2-15-139, Deviation from BWRVIP-25 Guidance for Inspection Requirements
GO2-15-110, Enclosure 2, Revision 2 to 001N6043.5-NP, Energy Northwest Columbia Generating Station Jet Pump 17/18 Riser Evaluation at 106% Rated Core Flow (115 Mlbs/Hr), Non-Proprietary
U-604237, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
RA15-028, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
NOC-AE-15003270, Response to Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2, License Renewal Application - Set 28
NLS2015075, Deviation from BWRVIP-18 and BWRVIP-41 Inspection Requirements Cooper Nuclear Station
NLS2105025, 10 CFR 50.55a Requests for Fifth Ten-Year Inservice Inspection Interval
NL-15-1032, E. I. Hatch, Unit 2 - Inservice Inspection Program Owners Activity Report for Outage 2R23
CNL-14-221, Response to NRC Request for Additional Information Regarding Review of License Renewal Application, Set 23, B.1.34-9.d (Follow Up)
CNL-14-181, Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application, Set 22, B.1.34-9c
RNP-RA/14-0097, Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals
RC-14-0145, Twenty-First Refueling Inservice Inspection (ISI) Reports
PNP 2014-081, Response to Fourth Request for Additional Information - Reactor Vessel Internals (ME9569)
NL-14-093, Reply to Request for Additional Information Regarding License Renewal Application
SVP-14-049, Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines - Inspection of RB-2 Welds
SBK-L-14089, Response to Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application- Set 21 (Tag ME4028)
L-14-206, License Renewal Application Amendment No. 50 - Annual Update
RS-14-002, Response to NRC Requests for Additional Information, Set 4, Dated December 12, 2013, Related to the License Renewal Application
RBG-47417, Supplement to Request for Alternative in Accordance with 10 CFR 50.55a(a)(3)(i), Use of Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements
W3F1-2013-0070, Submittal of Reactor Vessel Internals Aging Management Program Consistent with MRP-227-A
L-2013-287, License Renewal (Lr) Reactor Vessel Internals (Rvi) Inspection Program Response to Request for Additional Information (RAI)
L-13-328, Response to Request for Additional Information on 10 CFR 50.55a Request RR-A36
RS-13-258, Submittal of Additional Information Supporting Relief Request I5R-11 Associated with Reactor Pressure Vessel Penetration N-11B Repair
L-PI-13-089, Supplement to Aging Management Program Submittals
RNP-RA/13-0073, Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals
L-MT-13-040, Supplemental Information Regarding Cycle 25 Inservice Inspection Summary Report-Core Shroud Support Flaw Evaluation
SVP-13-037, Regulatory Commitment Change Summary Report
GNRO-2013/00044, Request for Alternative in Accordance with 10 CFR 50.55a(a)(3)(i) Use of Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements (GG-ISI-017)
RA13-023, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
RBG-47362, Request for Alternative in Accordance with 10 CFR 50.55a(a)(3)(i) Use of Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements
L-13-160, Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 40
PNP 2013-022, Response to Request for Additional Information - Revised Program Plan for Aging Management of Reactor Vessel Internals
L-PI-13-024, Materials Reliability Program (MRP) 227-A Applicant/Licensee Action Items One and Two
L-13-076, 10 CFR 50.55a Notification of Impracticality and Requests for Alternatives Supporting the Third and Fourth to-Year Inservice Inspection Intervals
L-2012-438, License Renewal (Lr) Reactor Vessel Internals (Rvi) Commitment Implementation Report and Inspection Plan
NL-12-089, Official Exhibit - ENT000554-00-BD01 - NL-12-089, Letter from F. Dacimo, Entergy, to NRC, Reply to Request for Additional Information Regarding the License Renewal Application Indian Point Nuclear Generating Unit Nos. 2 & 3
BVY 12-067, Technical Specifications Proposed Change 300, Supplement 1, Response to Request for Additional Information
NL-12-140, Reply to Request for Additional Information Regarding the License Renewal Application
NL-12-134, Reply to Request for Additional Information Regarding the License Renewal Application
AEP-NRC-2012-82, Transmittal of Reactor Vessel Internals Aging Management Program
L-PI-12-078, PWR (Pressurized Water Reactor) Vessel Internals Program for Fulfillment of License Renewal Commitment 25
RS-12-150, Fifth Interval Inservice Inspection Program Plan and Relief Requests
PNP 2012-080, Revised Program Plan for Aging Management of Reactor Vessel Internals
RA-12-097, Submittal of Relief Requests for the Fifth Ten-Year Inservice Inspection (Lsi) Interval
NRC 2012-0052, Reactor Vessel Internals Inspection Plan, Response to Request for Additional Information
NUREG-2123 Volume 2, Safety Evaluation Report Related to the License Renewal of Columbia Generating Station
GNRO-2012/00032, Response to Request for Additional Information (RAI) Dated April 11, 2012
TMI-12-069, Submittal of Inspection Plan for Reactor Internals
NOC-AE-12002816, Supplement to the Response to Requests for Additional Information for the South Texas Project License Renewal Application, Aging Management Program, Set 12
U-604060, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
NL-12-037, License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A
BVY 12-008, Response to Request for Additional Information Regarding Core Plate Hold-down Bolt Inspection Plan and Analysis
NRC-12-0003, Additional Information Regarding Relief Request for Use of the BWRVIP Guidelines in Lieu of ASME Code Requirements
NRC 2011-0106, License Renewal Commitment Reactor Vessel Lnternals Program Submittal
L-11-354, Reply to Requests for Additional Information for the Review, License Renewal Application Amendment No. 22 & Revised License Renewal Application Boundary Drawings
NOC-AE-11002742, Response to Requests for Additional Information for the License Renewal Application
NRC-11-0048, Response to Request for Additional Information Regarding Relief Request RR-A39 for Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements
L-11-317, Reply to Request for Additional Information for the Review of License Renewal Application (TAC No. ME4640) and Amendment No. 20
L-11-252, Reply to Request for Additional Information for the Review of License Renewal Application and License Renewal Application No. 15
SVP-11-069, Post Outage Inservice Inspection (ISI) Summary Report
L-11-237, Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application (TAC No. ME4640), & License Renewal Application Amendment No. 14
L-MT-11-046, Cycle 25 Inservice Inspection Summary Report
L-11-238, Reply to Request for Additional Information for the Review of License Renewal Application and License Renewal Application Amendment No. 13
LR-N11-0213, Inservice Inspection (Lsi) Program Plan, Fourth Ten-Year Interval
NRC-11-0039, Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements
RA11-024, Unit 2 - Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
GO2-11-093, Deviation from BWRVIP-25 Inspection Requirements
NRC-11-0022, Notification of Deviation from BWRVIP-25 Guidelines
PLA-6712, Deviation from BWRVIP-25 Inspection Requirements
NLS2011035, Deviation from BWRVIP-25 Inspection Requirements
LR-N11-0105, Deviation from BWRVIP-25 Inspection Requirements
BSEP 11-0039, Notification of Deviation from BWRVIP-25 Guidance
TMI-11-061, ISI Program Plan, Fourth Ten-Year Inspection Interval
RS-11-053, Deviation from BWR Vessel and Internals Project Guideline - Inspection of the Core Plate Bolts
JAFP-11-0043, Deviation from BWRVIP-25 Inspection Requirements
BVY 11-024, Deviation from BWRVIP-25 Inspection Requirements
L-10-246, 10 CFR 50.55a Requests in Support of the Third 10-Year In-Service Inspection Interval
RBG-47827, Request for Alternative in Accordance with 10 CFR 50.55a(z)(1) Use of Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements (RR- RBS-ISI-019)
NL-18-0193, Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-03, Version 1.0
NL-18-0863, CFR 50.55a Request for Alternative HNP-ISI-ALT-05-04 Implementation of BWRVIP Documents in Lieu of Certain 8-N-1 and 8-N-2 Examinations
NL-17-0534, Joseph M. Farley Nuclear Plant - Submittal of Updated Final Safety Analysis Report, 10 CFR 50.59 Report, Fire Hazard Analysis Changes, Technical Specifications Bases Changes, Technical Requirements Manual Changes, and Revised NRC Commitme
NL-15-1507, J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals
NL-16-135, Preservice Inspection Program Plan, Watts Bar Nuclear Plant, Unit 2, Program No: WBN-2 PSI Rev. 11
GO2-10-179, Response to Request for Additional Information License Renewal Application
BVY 10-050, License Renewal Application Supplemental Information
NL-10-063, Amendment 9 to License Renewal Application, Reactor Vessel Internals Program
NG-10-0091, Responses to Requests for Additional Information Regarding the Center License Renewal Application - Batch 4
NG-10-0043, Response to Request for Additional Information for the Review of License Renewal Application - Batch 3
NG-10-0009, Supplemental Information Regarding License Renewal Application
NG-09-0663, Time Limited Aging Analysis Evaluations for the Duane Arnold License Renewal Project
NRC 2009-0095, License Renewal Commitment Reactor Vessel Lnternals Program Submittal
L-MT-09-078, Submittal of Cycle No. 24 Inservice Inspection Summary Report for Inservice Inspection and ASME Section Xl Repairs and Replacements
NRC-09-0038, Fermi 2 - Summary Report of the 2009 Inservice Inspection Activities
L-PI-09-044, Supplemental Information Regarding Application for Renewed Operating Licenses
RA09-041, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
NL-09-056, Reply to Request for Additional Information - Open Items
NL-09-018, Reply to Request for Additional Information - Miscellaneous Items
PLA-6469, Submittal of Amendment to Table A-1 of the SSES License Renewal Application to Previously Submitted Information
LR-N09-0001, License Amendment Request to Eliminate Unnecessary Reporting Requirements in the Operating License and the Administrative Controls Section of the Technical Specifications
PLA-6457, License Renewal Application (LRA) Amendments to LRS and RAI Responses
NLS2008065, Inservice Inspection Summary Report for the Spring 2008 Refueling Outage
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
RA08-035, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
U-603857, 90-Day Post-Outage Inservice Inspection (ISI) Summary Report
L-08-066, Inservice Inspection Program Relief Requests IR-043, Revision 1, IR-055, IR-056, and IR-057
NL-08-0132, Unit 1, Response to NRC Questions Regarding Modification of the Core Shroud Stabilizer Assemblies
LR-N18-0080, Notification of Deviation from Electric Power Research Institute (Epri), Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A)
BVY 07-079, Update of Aging Management Program Audit Q&A Database
RS-07-134, Co. and Amergen Energy Co., LLC, Response to Request for Additional Information Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements
NL-07-1155, Proposed Modification of Core Shroud Stabilizer Assemblies During the Upcoming 2008 Refueling Outage
BSEP 07-0070, Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements
BVY 07-047, License Renewal Application, Amendment 27, Submitted on January 25, 2006
PLA-6225, Proposed License Amendment Nos. 285 and 253, Extended Power Uprate Application Supplement to Request for Additional Information Responses
RA07-045, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
RS-07-058, Amergen/Exelon Nuclear - Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements
JAFP-07-0019, License Renewal Application, Amendment 9
BVY 07-018, License Renewal Application, Amendment 26
JAFP-07-0021, License Renewal Application, Amendment 6
BVY 07-003, Email: (PA-LR) Vermont Yankee Nuclear Power Station License Renewal Commitment List, Rev. 5
BVY 06-096, License Renewal Application, Amendment No. 17
L-MT-06-060, License Renewal Application Update
LR-N06-0337, Inservice Inspection Activities - 90 Day Report, Thirteenth Refueling Outage
NRC-06-0052, Notification of Deviation from Boiling Water Reactor Vessel and Internals Project Guidelines
BSEP-06-0048, Notification of Deviation from Boiling Water Reactor Vessel and Internals Project Guidelines
BVY 06-058, License Renewal Application, Amendment 3
RA06-038, Post-Outage 90-Day Inservice Inspection Summary Report
GO2-06-082, Notification of Deviation from Boiling Water Reactor Vessel Internals Project (BWRVIP) Program Element
U-603774, 90-Day Post-Outage Inservice Inspection (SI) Summary Report
L-MT-06-019, Supplemental Information and Response to Requests for Additional Information Regarding Monticello Nuclear Generating Plant License Renewal Application
L-MT-06-018, License Renewal Application Annual Update
LR-N18-0087, Submittal of Relief Request Associated with the Third Inservice Inspection (ISI) Interval
NL-18-1480, Response to NRC Request for Additional Information on Alternative Request (HNP-ISI-ALT-05-04)
L-2018-193, Set 6 Responses to Request for Additional Information (RAI) on Subsequent License Renewal Application Safety Review
JAFP-18-0113, Fifth Ten-Year Inservice Inspection Interval Program Plan
NRC-19-0016, Submittal of the Inservice Inspection / Nondestructive Examination Program Relief Requests for the Fourth Ten-year Interval
LR-N19-0013, Supplement to Submittal of Relief Request Associated with the Third Inservice Inspection (ISI) Interval
NRC-19-0042, Responses to Requests for Additional Information Regarding Relief Requests for the Inservice Inspection Program Fourth Ten-year Interval
SVP-19-053, Regulatory Commitment Change Summary Report
NL-19-1336, Implementation of BWRVIP-38 and -76 in Lieu of B-N-2 Examinations for Core Support Structures
JAFP-05-0151, Request for Approval of Relief Request No. RR-39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection
BVY 05-071, Clarifications to Relief Request RI-01 Table
BVY 05-059, Revised Response to Request for Additional Information Regarding Relief Request RI-01
NLS2005049, Inservice Inspection Summary Report
BSEP 05-0042, Response to Request for Additional Information Regarding Core Flow Operating Range Expansion
LR-N05-0005, Response to Request for Additional Information Regarding Approval to Extend the Risk-Informed Inservice Inspection Program
RS-19-116, Relief Requests Associated with the Fourth Inservice Inspection Interval
CNL-20-019, American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Request for Alternative 0-ISI-47
JAFP-04-0190, In-Vessel Visual Inspection Summary Report 2004 Refuel Outage (Reload 16/Cycle 17)
L-19-145, 10 CFR 50.55a Request in Support of the Fourth 10-Year Inservice Inspection (ISI) Interval
LR-N17-0079, Supplemental Information for Response to Request for Additional Information, Aging Management Program Plan for Reactor Vessel Internals
NL-03-2158, Updated Analysis of Core Shroud Vertical Welds
JAFP-03-0065, Summary of Plant Changes, Tests, & Experiments for 2001/2002 as Required by 10 CFR 50.59 & 10 CFR 72.48, & Summary of Commitment Changes for 2001/2002
NLS2003028, BWRVIP-25 Rim Hold Down Bolt Inspection Deferral
JAFP-02-0251, In-Vessel Visual Inspection Summary Report 2002 Refuel Outage (Reload 15/Cycle 16)
BSEP-02-0198, Response to Request for Additional Information Regarding Request for Approval of Relief Request for Reactor Pressure Vessel Nozzle Inner Radius Volumetric Examinations
U-603571, Day Post-Outage Inservice Inspection (ISI) Summary Report
BSEP 02-0103, Feedwater Sparger and Safe End Examinations
NLS2002039, Letter Providing Information Requested by NRC from Nebraska Public Power District During 03/25/2002 Telephone Conversation on Implementation of BWRVIP Program at Cooper Nuclear Station
NLS2002040, Inservice Inspection Summary Report for Cooper Nuclear Station
BECO-LTR-95-048, Responds to Request for Addl Info Re Planned Mod to Core Shroud
RS-20-095, Response to Request for Additional Information Related to Relief Request I4R-06 for the Fourth Inservice Inspection Interval
SVPLTR 20-0053, Deviation from BWR Vessel and Internals Project (BWRVIP) Guideline - Inspection of Unit 3 Top Guide Rim Weld
CNRO-2020-00021, Response to Request for Additional Information Regarding Relief Requests GG-ISI-020 and RBS-ISI-019
NRC-20-0054, Submittal of Revised Relief Request RR-A39 for the Fourth Ten-Year Inservice Inspection Interval
RS-21-035, Relief Request I4R-12 Relief from Code Examinations for 2B33-F060A and 2B33-F060B Repairs
RS-21-034, Relief Request I4R-12 Relief from Code Surface Examinations for 2B33-F060B Valve Repair
RS-21-043, Supplemental Information Regarding Relief Request I4R-12 Relief from Code Examinations for 2B33-F060A and 2B33-F060B Repairs, Revision 2
RS-21-042, Relief Request I4R-12 Relief from Code Examinations for 2B33-F060A and 2B33-F060B Repairs, Revision 2
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
JAFP-99-0085, Submits in-vessel Visual Insp Summary Rept for RFO 13 for Ja FitzPatrick Nuclear Power Plant.All Relevant Indications Recorded During Insp Were Satisfactorily Dispositioned IAW Util Internal C/A Tracking Sys & Were Found Acceptable
L-2020-043, Amendment 30 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Time-Limited Aging Analyses Activities
NRC 2022-0006, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections
RS-22-032, Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs
SVPLTR 22-0016, Unit 3, Deviation from BWR Vessel and Internals Project (BWRVIP) Guideline - Inspection of Unit 2 and Unit 3 Shroud Vertical Welds
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
L-MT-22-021, 0 to Updated Safety Analysis Report, Appendix K, Revision 37, Renewed Operating License-USAR Supplement
CNL-23-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47
RA-22-0192, Subsequent License Renewal Application Response to ONS SLRA Second Round RAI B2.1.7-4a
JAFP-12-0122, Core Plate Rim Hold Down Bolting, Plant Specific Analysis and Inspection Plan, License Renewal Commitment 23
NLS2021066, Response to Nuclear Regulatory Commissions Request for Additional Information Regarding Alternative Request RI5-02, Revision 3
RA-24-0033, Response to Request for Additional Information Regarding the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals
L-2023-036, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections
NMP1L3226, Submittal of Relief Requests Associated with the Fifth and Fourth Inservice Inspection Intervals
AEP-NRC-2018-22, WCAP-18133-NP, Revision 0, Inspection Flaw Acceptance Criteria for D.C. Cook Unit 2 Reactor Vessel Internals MRP-227-A Primary and Expansion Components
L-MT-17-075, 5 to Updated Safety Analysis Report, Appendix K, Introduction
NL-17-132, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) 227-A, Pressurized Water Reactor Internals Inspection and Evaluation Guidelines, Examination Schedule - NEI 03-08 Needed .
NL-16-0795, Inservice Inspection Program - Owners Activity Report for Outage IR27
GO2-15-056, Enclosure 2: GE-Hitachi Nuclear Energy 001N6043.4-NP, Rev. 1, Energy Northwest Columbia Generating Station Jet Pump 17/18 Riser Evaluation at 106% Rated Core Flow (115 Mlbs/Hr)
BW090029, Submittal of Third Inservice Inspection (ISI) Interval Program Plan
BVY 08-008, July 2008 Evidentiary Hearing - Applicant Exhibit E2-09-VY, VY LRA Amendment 35
BW080002, Inservice Inspection Summary Report
RA-08-021, Emergens Response to Request for Additional Information Re Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements
RNP-RA/09-0081, WCAP-17077-NP, Revision 0, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant
BVY 06-097, License Renewal Application, Amendment 19
BVY 06-088, License Renewal Application, Amendment 14 - Response to Requests for Additional Information Dated August 15 and 16, 2006
BVY 06-079, License Renewal Application, Amendment 11
BVY 05-103, Technical Specification Proposed Change No. 263 - Supplement No. 42 Extended Power Uprate - Steam Dryer Inspection Results
BSEP 05-0071, Response to Request for Additional Information - License Renewal
L-MT-05-052, Monticello. Response to Request for Additional Information and Submittal of Additional Information in Support of the Plant License Renewal Application
BSEP 05-0041, Response to Audit Questions License Renewal NUREG-1801 Consistency Audit
RS-03-223, Additional Information for the Review of the License Renewal Applications for Dresden, Units 2 & 3 and Quad Cities, Units 1 & 2
RS-12-151, Fifth Interval Inservice Inspection Program Plan and Relief Requests
RA-23-0218, Review Request for the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals
RS-03-181, Stations - Additional Information for the Review of the License Renewal Application
SVPLTR 14-0023, Deviation from BWR Vessel and Internals Project Guidelines -Unit 3 Jet Pump 11 Holddown Beam Inspection
NL-25-0013, License Renewal Commitment Item 20
ULNRC-06332, Results of Steam Generator Tube In-Service Inspection
PLA-6210, Extended Power Uprate Application Vessels and Internals Integrity Technical Review Request for Additional Information Responses
L-2021-144, Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 2 Responses
RA-20-0317, Review Request for the Aging Management Program and Inspection Plan for the Catawba Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227, Revision 1-A
RS-25-043, Enclosure 2: Dresden Nuclear Power Station, Units 2 and 3, Subsequent License Renewal Application Commitment List Update
DCL-25-023, Supplement and Annual Update - Diablo Canyon Power Plant License Renewal Application, Amendment 4
GO2-21-012, License Amendment Request to Remove License Condition 2.C.(34) and Revise License Condition 2.C.(35)
NRC-21-0032, Response to Request for Additional Information Regarding Revised Relief Request RR-A39 for the Fourth Ten-Year Inservice Inspection Interval
CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47
RA17-055, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
GNRO-2014/00006, Request for Information Regarding Request for Alternative in Accordance with 10 CFR 50.55a(a)(3)(i) Use of Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements
L-25-084, Notification of Deviation from MRP-227, Revision 1-A, Section 7.5 Regarding the Disposition of Examination Results for Thermal Shield Flexures
RA-25-0075, License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
RA-25-0200, Subsequent License Renewal Application Supplement 1
NMP1L3659, Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines – Inspection of Core Spray Welds