EVT-2D1
type: Ontology
creation date: 2025-12-08T15:20:50-05:00
imports: http://semantic-mediawiki.org/swivt/1.0

EVT-1
type: Subject
type: Category:Topic
page: https://kanterella.com/EVT-2D1
wiki namespace: 0
wiki page content language: en
wiki page modification date: 2020-09-29T12:55:42Z
modification date#aux: 2459122.0386806
wiki page sort key: EVT-1

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http://kanterella.com/Special:URIResolver/EVT-2D1-23_QUERY57c1f3fb69162fa96d2e0446c36d30a7
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http://kanterella.com/Special:URIResolver/EVT-2D1-23_QUERYb7370dd5a3f5ded59ed937d234c09779
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IR 05000220/2009003
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IR 05000331/2009010
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IR 05000220/2009007
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IR 05000219/2009006
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ML091620163
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IR 05000335/2015010
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IR 05000259/2005009
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IR 05000416/2005004
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IR 05000387/2004002
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NUREG-1927
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ML17047A708
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NL-17-020, License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan
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ML103050402
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GNRO-2017/00009, Proposed Alternative with 10 CFR 50.55a(z)(1), Use of Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines
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ML17157B692
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RS-17-072, Fourth 10-Year Interval Inservice Inspection Program Relief Requests
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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)
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2CAN091701, Response to Request for Additional Information Reactor Vessel Internals Aging Management Program Plan
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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)
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SVP-16-044, Deviation from BWR Vessel and Internals Project (Swavip) Guidelines Inspection Core Shroud Welds
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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
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RS-16-052, Response to NRC Requests for Additional Information, Set 15, Dated February 16, 2016 Related to the License Renewal Application
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NG-16-0035, Notification of Deviation from Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines
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ML12167A008
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IR 05000271/2012008
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IR 05000331/2013009
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L-2017-216, License Renewal Commitments: Reactor Vessel Internals Aging Management Plan, Clarification of Responses to RAI 1 and RAI 6
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RA17-086, County Station, Units I & 2 - 10CFR50.55a Relief Request 14R-01
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NOC-AE-15003320, Response to Request for Additional Information Set 34 for the Review of the License Renewal Application
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NRC-15-0104, Notification of Revision to BWRVIP Core Plate Deviation Disposition
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PNP 2015-089, Inservice Inspection Master Program Fifth 10-Year Interval
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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
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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
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L-2015-229, License Renewal Commitments, Reactor Vessel Internals Aging Management Plan
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GO2-15-139, Deviation from BWRVIP-25 Guidance for Inspection Requirements
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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
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U-604237, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
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RA15-028, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
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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
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NLS2015075, Deviation from BWRVIP-18 and BWRVIP-41 Inspection Requirements Cooper Nuclear Station
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NL-15-1032, E. I. Hatch, Unit 2 - Inservice Inspection Program Owners Activity Report for Outage 2R23
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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)
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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
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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
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RC-14-0145, Twenty-First Refueling Inservice Inspection (ISI) Reports
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PNP 2014-081, Response to Fourth Request for Additional Information - Reactor Vessel Internals (ME9569)
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NL-14-093, Reply to Request for Additional Information Regarding License Renewal Application
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SVP-14-049, Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines - Inspection of RB-2 Welds
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SBK-L-14089, Response to Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application- Set 21 (Tag ME4028)
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L-14-206, License Renewal Application Amendment No. 50 - Annual Update
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RS-14-002, Response to NRC Requests for Additional Information, Set 4, Dated December 12, 2013, Related to the License Renewal Application
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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
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W3F1-2013-0070, Submittal of Reactor Vessel Internals Aging Management Program Consistent with MRP-227-A
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L-2013-287, License Renewal (Lr) Reactor Vessel Internals (Rvi) Inspection Program Response to Request for Additional Information (RAI)
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L-13-328, Response to Request for Additional Information on 10 CFR 50.55a Request RR-A36
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RS-13-258, Submittal of Additional Information Supporting Relief Request I5R-11 Associated with Reactor Pressure Vessel Penetration N-11B Repair
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L-PI-13-089, Supplement to Aging Management Program Submittals
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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
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SVP-13-044, Day Post Outage ISI Letter
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L-MT-13-040, Supplemental Information Regarding Cycle 25 Inservice Inspection Summary Report-Core Shroud Support Flaw Evaluation
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SVP-13-037, Regulatory Commitment Change Summary Report
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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)
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RA13-023, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
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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
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L-13-160, Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 40
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PNP 2013-022, Response to Request for Additional Information - Revised Program Plan for Aging Management of Reactor Vessel Internals
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L-PI-13-024, Materials Reliability Program (MRP) 227-A Applicant/Licensee Action Items One and Two
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ML13064A410
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L-13-076, 10 CFR 50.55a Notification of Impracticality and Requests for Alternatives Supporting the Third and Fourth to-Year Inservice Inspection Intervals
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L-2012-438, License Renewal (Lr) Reactor Vessel Internals (Rvi) Commitment Implementation Report and Inspection Plan
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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
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BVY 12-067, Technical Specifications Proposed Change 300, Supplement 1, Response to Request for Additional Information
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ML12326A467
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ML12292A015
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NL-12-140, Reply to Request for Additional Information Regarding the License Renewal Application
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ML12297A069
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NL-12-134, Reply to Request for Additional Information Regarding the License Renewal Application
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AEP-NRC-2012-82, Transmittal of Reactor Vessel Internals Aging Management Program
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ML12278A100
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ML12277A164
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L-PI-12-078, PWR (Pressurized Water Reactor) Vessel Internals Program for Fulfillment of License Renewal Commitment 25
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RS-12-150, Fifth Interval Inservice Inspection Program Plan and Relief Requests
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ML11294A349
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PNP 2012-080, Revised Program Plan for Aging Management of Reactor Vessel Internals
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RA-12-097, Submittal of Relief Requests for the Fifth Ten-Year Inservice Inspection (Lsi) Interval
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ML12233A738
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ML12233A672
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NRC 2012-0052, Reactor Vessel Internals Inspection Plan, Response to Request for Additional Information
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ML12228A651
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ML12139A061
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ML081070060
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NUREG-2123 Volume 2, Safety Evaluation Report Related to the License Renewal of Columbia Generating Station
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ML11312A247
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ML12139A050
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ML12107A149
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GNRO-2012/00032, Response to Request for Additional Information (RAI) Dated April 11, 2012
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ML12128A438
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ML121170481
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ML12108A217
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TMI-12-069, Submittal of Inspection Plan for Reactor Internals
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ML12101A231
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ML12101A061
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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
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ML12095A220
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ML12093A503
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ML12091A062
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ML12061A063
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ML12067A349
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ML12072A316
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U-604060, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
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ML12080A191
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NL-12-037, License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A
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ML12043A009
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ML12045A559
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ML12047A000
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BVY 12-008, Response to Request for Additional Information Regarding Core Plate Hold-down Bolt Inspection Plan and Analysis
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ML12019A408
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ML12021A016
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ML082480573
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NRC-12-0003, Additional Information Regarding Relief Request for Use of the BWRVIP Guidelines in Lieu of ASME Code Requirements
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ML11355A156
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ML12009A117
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ML11356A340
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ML11356A307
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ML11356A291
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NRC 2011-0106, License Renewal Commitment Reactor Vessel Lnternals Program Submittal
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wiki page sort key: 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
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page: https://kanterella.com/L-2D11-2D354-2C_Reply_to_Requests_for_Additional_Information_for_the_Review-2C_License_Renewal_Application_Amendment_No._22_-26_Revised_License_Renewal_Application_Boundary_Draw…
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NOC-AE-11002742, Response to Requests for Additional Information for the License Renewal Application
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page: https://kanterella.com/NOC-2DAE-2D11002742-2C_Response_to_Requests_for_Additional_Information_for_the_License_Renewal_Application
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ML11234A381
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ML11234A386
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ML11293A381
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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
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page: https://kanterella.com/NRC-2D11-2D0048-2C_Response_to_Request_for_Additional_Information_Regarding_Relief_Request_RR-2DA39_for_Use_of_the_BWRVIP_Guidelines_in_Lieu_of_Specific_ASME_Code_Requirements
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wiki page sort key: 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
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page: https://kanterella.com/L-2D11-2D317-2C_Reply_to_Request_for_Additional_Information_for_the_Review_of_License_Renewal_Application_-28TAC_No._ME4640-29_and_Amendment_No._20
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L-11-252, Reply to Request for Additional Information for the Review of License Renewal Application and License Renewal Application No. 15
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page: https://kanterella.com/L-2D11-2D252-2C_Reply_to_Request_for_Additional_Information_for_the_Review_of_License_Renewal_Application_and_License_Renewal_Application_No._15
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SVP-11-069, Post Outage Inservice Inspection (ISI) Summary Report
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ML112580356
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ML11250A043
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ML11147A034
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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
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page: https://kanterella.com/L-2D11-2D237-2C_Reply_to_Request_for_Additional_Information_for_the_Review_of_the_Davis-2DBesse_Nuclear_Power_Station-2C_Unit_No._1-2C_License_Renewal_Application_-28TAC_No._ME4…
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wiki page sort key: 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
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wiki page sort key: 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
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LR-N11-0213, Inservice Inspection (Lsi) Program Plan, Fourth Ten-Year Interval
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wiki page sort key: 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
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ML11154A083
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RA11-024, Unit 2 - Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
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ML11145A113
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GO2-11-093, Deviation from BWRVIP-25 Inspection Requirements
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NRC-11-0022, Notification of Deviation from BWRVIP-25 Guidelines
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ML11116A197
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PLA-6712, Deviation from BWRVIP-25 Inspection Requirements
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NLS2011035, Deviation from BWRVIP-25 Inspection Requirements
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LR-N11-0105, Deviation from BWRVIP-25 Inspection Requirements
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BSEP 11-0039, Notification of Deviation from BWRVIP-25 Guidance
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TMI-11-061, ISI Program Plan, Fourth Ten-Year Inspection Interval
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RS-11-053, Deviation from BWR Vessel and Internals Project Guideline - Inspection of the Core Plate Bolts
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JAFP-11-0043, Deviation from BWRVIP-25 Inspection Requirements
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ML110871250
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BVY 11-024, Deviation from BWRVIP-25 Inspection Requirements
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ML083090046
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L-10-246, 10 CFR 50.55a Requests in Support of the Third 10-Year In-Service Inspection Interval
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ML110270220
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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)
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ML17157B242
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NL-18-0193, Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-03, Version 1.0
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IR 05000331/2018003
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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
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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
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NL-15-1507, J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals
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NL-16-135, Preservice Inspection Program Plan, Watts Bar Nuclear Plant, Unit 2, Program No: WBN-2 PSI Rev. 11
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ML12093A484
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GO2-10-179, Response to Request for Additional Information License Renewal Application
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BVY 10-050, License Renewal Application Supplemental Information
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ML101950430
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NL-10-063, Amendment 9 to License Renewal Application, Reactor Vessel Internals Program
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ML100760099
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NG-10-0091, Responses to Requests for Additional Information Regarding the Center License Renewal Application - Batch 4
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NG-10-0043, Response to Request for Additional Information for the Review of License Renewal Application - Batch 3
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NG-10-0009, Supplemental Information Regarding License Renewal Application
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NG-09-0663, Time Limited Aging Analysis Evaluations for the Duane Arnold License Renewal Project
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ML093000502
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ML092580547
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NRC 2009-0095, License Renewal Commitment Reactor Vessel Lnternals Program Submittal
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L-MT-09-078, Submittal of Cycle No. 24 Inservice Inspection Summary Report for Inservice Inspection and ASME Section Xl Repairs and Replacements
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NRC-09-0038, Fermi 2 - Summary Report of the 2009 Inservice Inspection Activities
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ML091900645
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L-PI-09-044, Supplemental Information Regarding Application for Renewed Operating Licenses
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ML091420578
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RA09-041, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
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NL-09-056, Reply to Request for Additional Information - Open Items
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NL-09-018, Reply to Request for Additional Information - Miscellaneous Items
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ML090260075
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PLA-6469, Submittal of Amendment to Table A-1 of the SSES License Renewal Application to Previously Submitted Information
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LR-N09-0001, License Amendment Request to Eliminate Unnecessary Reporting Requirements in the Operating License and the Administrative Controls Section of the Technical Specifications
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PLA-6457, License Renewal Application (LRA) Amendments to LRS and RAI Responses
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NLS2008065, Inservice Inspection Summary Report for the Spring 2008 Refueling Outage
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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
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RA08-035, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
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U-603857, 90-Day Post-Outage Inservice Inspection (ISI) Summary Report
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L-08-066, Inservice Inspection Program Relief Requests IR-043, Revision 1, IR-055, IR-056, and IR-057
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NL-08-0132, Unit 1, Response to NRC Questions Regarding Modification of the Core Shroud Stabilizer Assemblies
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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)
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BVY 07-079, Update of Aging Management Program Audit Q&A Database
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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
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NL-07-1155, Proposed Modification of Core Shroud Stabilizer Assemblies During the Upcoming 2008 Refueling Outage
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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
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BVY 07-047, License Renewal Application, Amendment 27, Submitted on January 25, 2006
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PLA-6225, Proposed License Amendment Nos. 285 and 253, Extended Power Uprate Application Supplement to Request for Additional Information Responses
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RA07-045, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
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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
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JAFP-07-0019, License Renewal Application, Amendment 9
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BVY 07-018, License Renewal Application, Amendment 26
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JAFP-07-0021, License Renewal Application, Amendment 6
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BVY 07-003, Email: (PA-LR) Vermont Yankee Nuclear Power Station License Renewal Commitment List, Rev. 5
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BVY 06-096, License Renewal Application, Amendment No. 17
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L-MT-06-060, License Renewal Application Update
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LR-N06-0337, Inservice Inspection Activities - 90 Day Report, Thirteenth Refueling Outage
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NRC-06-0052, Notification of Deviation from Boiling Water Reactor Vessel and Internals Project Guidelines
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BSEP-06-0048, Notification of Deviation from Boiling Water Reactor Vessel and Internals Project Guidelines
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BVY 06-058, License Renewal Application, Amendment 3
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RA06-038, Post-Outage 90-Day Inservice Inspection Summary Report
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GO2-06-082, Notification of Deviation from Boiling Water Reactor Vessel Internals Project (BWRVIP) Program Element
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U-603774, 90-Day Post-Outage Inservice Inspection (SI) Summary Report
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L-MT-06-019, Supplemental Information and Response to Requests for Additional Information Regarding Monticello Nuclear Generating Plant License Renewal Application
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L-MT-06-018, License Renewal Application Annual Update
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LR-N18-0087, Submittal of Relief Request Associated with the Third Inservice Inspection (ISI) Interval
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NL-18-1480, Response to NRC Request for Additional Information on Alternative Request (HNP-ISI-ALT-05-04)
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L-2018-193, Set 6 Responses to Request for Additional Information (RAI) on Subsequent License Renewal Application Safety Review
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ML18310A013
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ML19011A010
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JAFP-18-0113, Fifth Ten-Year Inservice Inspection Interval Program Plan
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IR 05000250/2018004
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ML18334A150
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NRC-19-0016, Submittal of the Inservice Inspection / Nondestructive Examination Program Relief Requests for the Fourth Ten-year Interval
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LR-N19-0013, Supplement to Submittal of Relief Request Associated with the Third Inservice Inspection (ISI) Interval
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ML072120484
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IR 05000315/2019004
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ML052930161
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ML19095A600
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ML19092A417
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ML19081A001
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ML19134A186
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ML19163A018
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ML19128A079
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ML19168A028
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ML19164A333
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NRC-19-0042, Responses to Requests for Additional Information Regarding Relief Requests for the Inservice Inspection Program Fourth Ten-year Interval
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SVP-19-053, Regulatory Commitment Change Summary Report
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ML19136A026
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IR 05000387/2019002
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ML19204A253
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ML19269B734
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ML19308B926
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ML19295G582
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NL-19-1336, Implementation of BWRVIP-38 and -76 in Lieu of B-N-2 Examinations for Core Support Structures
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ML11349A076
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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
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NG-05-0420, Inservice Inspection Report
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BVY 05-071, Clarifications to Relief Request RI-01 Table
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ML051800441
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ML050050476
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BVY 05-059, Revised Response to Request for Additional Information Regarding Relief Request RI-01
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NLS2005049, Inservice Inspection Summary Report
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BSEP 05-0042, Response to Request for Additional Information Regarding Core Flow Operating Range Expansion
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ML050740404
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LR-N05-0005, Response to Request for Additional Information Regarding Approval to Extend the Risk-Informed Inservice Inspection Program
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ML040570650
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RS-19-116, Relief Requests Associated with the Fourth Inservice Inspection Interval
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ML17059B511
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ML19361A056
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IR 05000354/2019004
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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
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ML20034E617
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JAFP-04-0190, In-Vessel Visual Inspection Summary Report 2004 Refuel Outage (Reload 16/Cycle 17)
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L-19-145, 10 CFR 50.55a Request in Support of the Fourth 10-Year Inservice Inspection (ISI) Interval
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ML043220627
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ML041420129
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LR-N17-0079, Supplemental Information for Response to Request for Additional Information, Aging Management Program Plan for Reactor Vessel Internals
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ML040410417
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ML040090048
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NL-03-2158, Updated Analysis of Core Shroud Vertical Welds
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ML032530391
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ML032410065
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ML032120667
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NG-03-0509, Inservice Inspection Report
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ML031920426
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ML031490018
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ML031420481
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ML031400574
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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
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ML031120339
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ML030930470
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NLS2003028, BWRVIP-25 Rim Hold Down Bolt Inspection Deferral
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ML030770448
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ML030700021
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ML051890464
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ML030290523
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ML030290090
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JAFP-02-0251, In-Vessel Visual Inspection Summary Report 2002 Refuel Outage (Reload 15/Cycle 16)
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wiki page sort key: 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
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U-603571, Day Post-Outage Inservice Inspection (ISI) Summary Report
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BSEP 02-0103, Feedwater Sparger and Safe End Examinations
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ML021330743
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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
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NLS2002040, Inservice Inspection Summary Report for Cooper Nuclear Station
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ML020860693
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BECO-LTR-95-048, Responds to Request for Addl Info Re Planned Mod to Core Shroud
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ML20078B073
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ML20117P487
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ML20140A239
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ML20137C526
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RS-20-095, Response to Request for Additional Information Related to Relief Request I4R-06 for the Fourth Inservice Inspection Interval
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IR 05000387/2020002
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ML20309B020
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SVPLTR 20-0053, Deviation from BWR Vessel and Internals Project (BWRVIP) Guideline - Inspection of Unit 3 Top Guide Rim Weld
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ML20212J914
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CNRO-2020-00021, Response to Request for Additional Information Regarding Relief Requests GG-ISI-020 and RBS-ISI-019
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ML20248L739
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ML20350B806
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IR 05000369/2020004
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NRC-20-0054, Submittal of Revised Relief Request RR-A39 for the Fourth Ten-Year Inservice Inspection Interval
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RS-21-035, Relief Request I4R-12 Relief from Code Examinations for 2B33-F060A and 2B33-F060B Repairs
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RS-21-034, Relief Request I4R-12 Relief from Code Surface Examinations for 2B33-F060B Valve Repair
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ML20181A434
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RS-21-043, Supplemental Information Regarding Relief Request I4R-12 Relief from Code Examinations for 2B33-F060A and 2B33-F060B Repairs, Revision 2
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RS-21-042, Relief Request I4R-12 Relief from Code Examinations for 2B33-F060A and 2B33-F060B Repairs, Revision 2
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IR 05000373/2021001
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NOC-AE-21003806, Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval
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L-2020-123, Amendment 26 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Time-Limited Aging Analyses Activities
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A Tracking Sys & Were Found Acceptable
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label: 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
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L-2020-043, Amendment 30 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Time-Limited Aging Analyses Activities
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ML22024A014
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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
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ML22066A762
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RS-22-032, Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs
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ML21055A075
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ML20189A113
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ML22133A003
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SVPLTR 22-0016, Unit 3, Deviation from BWR Vessel and Internals Project (BWRVIP) Guideline - Inspection of Unit 2 and Unit 3 Shroud Vertical Welds
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ML22013A668
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ML22194A915
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ML20142A529
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ML22111A114
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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
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ML23060A478
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L-MT-22-021, 0 to Updated Safety Analysis Report, Appendix K, Revision 37, Renewed Operating License-USAR Supplement
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ML22292A124
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ML23159A230
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ML22325A136
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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
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ML23096A033
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ML22140A076
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RA-22-0192, Subsequent License Renewal Application Response to ONS SLRA Second Round RAI B2.1.7-4a
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ML21172A238
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ML23324A422
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ML23332A004
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ML24155A004
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ML24109A108
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JAFP-12-0122, Core Plate Rim Hold Down Bolting, Plant Specific Analysis and Inspection Plan, License Renewal Commitment 23
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IR 05000387/2024002
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ML24130A078
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IR 05000277/2023004
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ML23254A173
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NLS2021066, Response to Nuclear Regulatory Commissions Request for Additional Information Regarding Alternative Request RI5-02, Revision 3
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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
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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
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ML21312A007
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ML21312A008
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ML19294A044
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ML22293A244
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IR 05000352/2019002
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IR 05000259/2019001
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NMP1L3226, Submittal of Relief Requests Associated with the Fifth and Fourth Inservice Inspection Intervals
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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
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L-MT-17-075, 5 to Updated Safety Analysis Report, Appendix K, Introduction
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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 .
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ML17191B354
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ML17059C597
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NL-16-0795, Inservice Inspection Program - Owners Activity Report for Outage IR27
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ML16054A442
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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)
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BW090029, Submittal of Third Inservice Inspection (ISI) Interval Program Plan
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BVY 08-008, July 2008 Evidentiary Hearing - Applicant Exhibit E2-09-VY, VY LRA Amendment 35
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BW080002, Inservice Inspection Summary Report
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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
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RNP-RA/09-0081, WCAP-17077-NP, Revision 0, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant
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BVY 06-097, License Renewal Application, Amendment 19
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BVY 06-088, License Renewal Application, Amendment 14 - Response to Requests for Additional Information Dated August 15 and 16, 2006
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BVY 06-079, License Renewal Application, Amendment 11
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BVY 05-103, Technical Specification Proposed Change No. 263 - Supplement No. 42 Extended Power Uprate - Steam Dryer Inspection Results
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BSEP 05-0071, Response to Request for Additional Information - License Renewal
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L-MT-05-052, Monticello. Response to Request for Additional Information and Submittal of Additional Information in Support of the Plant License Renewal Application
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ML051380587
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BSEP 05-0041, Response to Audit Questions License Renewal NUREG-1801 Consistency Audit
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ML050610059
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RS-03-223, Additional Information for the Review of the License Renewal Applications for Dresden, Units 2 & 3 and Quad Cities, Units 1 & 2
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RS-12-151, Fifth Interval Inservice Inspection Program Plan and Relief Requests
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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
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RS-03-181, Stations - Additional Information for the Review of the License Renewal Application
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SVPLTR 14-0023, Deviation from BWR Vessel and Internals Project Guidelines -Unit 3 Jet Pump 11 Holddown Beam Inspection
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ML15238A898
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NL-25-0013, License Renewal Commitment Item 20
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ML22003A002
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ULNRC-06332, Results of Steam Generator Tube In-Service Inspection
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ML051470354
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ML18283A941
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PLA-6210, Extended Power Uprate Application Vessels and Internals Integrity Technical Review Request for Additional Information Responses
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ML25059A186
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L-2021-144, Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 2 Responses
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ML21214A035
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ML21145A274
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page: https://kanterella.com/ML21145A274
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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
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page: https://kanterella.com/RA-2D20-2D0317-2C_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-2D2…
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wiki page sort key: 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
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page: https://kanterella.com/RS-2D25-2D043-2C_Enclosure_2-3A_Dresden_Nuclear_Power_Station-2C_Units_2_and_3-2C_Subsequent_License_Renewal_Application_Commitment_List_Update
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wiki page sort key: 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
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page: https://kanterella.com/DCL-2D25-2D023-2C_Supplement_and_Annual_Update_-2D_Diablo_Canyon_Power_Plant_License_Renewal_Application-2C_Amendment_4
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wiki page sort key: DCL-25-023, Supplement and Annual Update - Diablo Canyon Power Plant License Renewal Application, Amendment 4

IR 05000272/2024004
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page: https://kanterella.com/IR_05000272/2024004
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ML25072A155
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ML25051A255
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wiki page sort key: ML25051A255

ML20178A673
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wiki page sort key: ML20178A673

ML20288A421
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ML20294A104
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ML20308A437
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ML20329A345
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page: https://kanterella.com/ML20329A345
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wiki page sort key: ML20329A345

GO2-21-012, License Amendment Request to Remove License Condition 2.C.(34) and Revise License Condition 2.C.(35)
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page: https://kanterella.com/GO2-2D21-2D012-2C_License_Amendment_Request_to_Remove_License_Condition_2.C.-2834-29_and_Revise_License_Condition_2.C.-2835-29
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wiki page sort key: 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
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page: https://kanterella.com/NRC-2D21-2D0032-2C_Response_to_Request_for_Additional_Information_Regarding_Revised_Relief_Request_RR-2DA39_for_the_Fourth_Ten-2DYear_Inservice_Inspection_Interval
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wiki page sort key: NRC-21-0032, Response to Request for Additional Information Regarding Revised Relief Request RR-A39 for the Fourth Ten-Year Inservice Inspection Interval

IR 05000220/2021002
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page: https://kanterella.com/IR_05000220/2021002
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ML21258A408
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ML21266A011
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wiki page sort key: ML21266A011

ML21312A003
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page: https://kanterella.com/ML21312A003
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wiki page sort key: ML21312A003

ML20156A330
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page: https://kanterella.com/ML20156A330
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ML22013A334
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ML20302A313
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ML23123A088
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page: https://kanterella.com/ML23123A088
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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
type: Subject
page: https://kanterella.com/CNL-2D23-2D071-2C_Response_to_Request_for_Additional_Information_Regarding_Browns_Ferry_Nuclear_Plant-2C_Units_1-2C_2-2C_and_3-2C_Inservice_Inspection_and_Augmented_Program_Inte…
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wiki page sort key: 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

IR 05000261/2024004
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page: https://kanterella.com/IR_05000261/2024004
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RA17-055, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
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page: https://kanterella.com/RA17-2D055-2C_Post-2DOutage_90-2DDay_Inservice_Inspection_-28ISI-29_Summary_Report
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wiki page sort key: RA17-055, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report

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
type: Subject
label: 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
page: https://kanterella.com/GNRO-2D2014/00006-2C_Request_for_Information_Regarding_Request_for_Alternative_in_Accordance_with_10_CFR_50.55a-28a-29-283-29-28i-29_Use_of_Boiling_Water_Reactor_Vessel_and_Inte…
wiki namespace: 0
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wiki page sort key: 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

ML25080A136
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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
type: Subject
page: https://kanterella.com/L-2D25-2D084-2C_Notification_of_Deviation_from_MRP-2D227-2C_Revision_1-2DA-2C_Section_7.5_Regarding_the_Disposition_of_Examination_Results_for_Thermal_Shield_Flexures
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wiki page sort key: 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

IR 05000321/2025001
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page: https://kanterella.com/IR_05000321/2025001
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ML24291A204
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ML20217L203
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ML25126A252
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IR 05000272/2025002
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page: https://kanterella.com/IR_05000272/2025002
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ML24319A085
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page: https://kanterella.com/ML24319A085
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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
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page: https://kanterella.com/RA-2D25-2D0075-2C_License_Amendment_Request_to_Revise_Technical_Specification_5.5.2-2C_Containment_Leakage_Rate_Testing_Program-2C_for_Permanent_Extension_of_Type_a_and_Type_C_L…
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wiki page sort key: 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

ML24305A007
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ML24304B031
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RA-25-0200, Subsequent License Renewal Application Supplement 1
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page: https://kanterella.com/RA-2D25-2D0200-2C_Subsequent_License_Renewal_Application_Supplement_1
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wiki page sort key: RA-25-0200, Subsequent License Renewal Application Supplement 1

ML23352A243
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ML23318A402
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ML23146A014
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ML23027A098
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ML22335A513
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page: https://kanterella.com/ML22335A513
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wiki page sort key: ML22335A513

NMP1L3659, Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines – Inspection of Core Spray Welds
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page: https://kanterella.com/NMP1L3659-2C_Deviation_from_BWR_Vessel_and_Internals_Project_-28BWRVIP-29_Guidelines_–_Inspection_of_Core_Spray_Welds
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