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L-2018-234, Subsequent License Renewal Application Safety Review Request for Additional Information (RAI) Set 5 Response 4.3.5-2 Revision
L-2019-091, License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements
RA-21-0203, Response to Request for Additional Information Regarding License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications
NL-16-097, Fifth Ten Year Interval Inservice Inspection Program Plan
2CAN031602, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, and to Request an Alternative to the Asme
RA17-086, County Station, Units I & 2 - 10CFR50.55a Relief Request 14R-01
BYRON 2015-0152, Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 4, (B1R20)
PNP 2015-089, Inservice Inspection Master Program Fifth 10-Year Interval
LR-N15-0157, Inservice Inspection Activities - 90 Day Report Nineteenth Refueling Outage
L-2015-080, Administrative Changes to Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
BYRON 2015-0009, 90-Day Inservice Inspection Report for Interval 3, Period 3, (B2R18)
CNL-14-099, Application to Modify Technical Specifications Regarding Reactor Coolant Pump Motor Flywheel Examination Periodicity (TS-WBN-13-03)
BYRON 2013-0100, Day Inservice Inspection Report for Interval 3, Period 3, (B2R17)
SBK-L-13084, Revised Response to RAI B.2.1.3-5 and RAI 4.7.2-1 for License Renewal Application
SBK-L-12235, License Amendment Request 12-06, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process
CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications
DCL-12-081, License Amendment Request 12-02 James M. Welsch Station Director 10 CFR 50.90 Revision to Technical Specification 5.5.7. Reactor Coolant Pump Flywheel Inspection Program (TSTF-421)
NL-12-1795, Revision to License Amendment Request to Extend the Inspection Interval for Reactor Coolant Pump Flywheels
NOC-AE-12002802, Response to Requests for Additional Information for the License Renewal Application, Aging Management Program, Set 13
CNRO-2011-00006, Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Technical Specifications Regarding Staff Qualifications
LR-N11-0213, Inservice Inspection (Lsi) Program Plan, Fourth Ten-Year Interval
SBK-L-11132, Submittal of Third Ten-Year Interval Inservice Inspection and Second Ten-Year Containment Inservice Inspection Program
TMI-11-061, ISI Program Plan, Fourth Ten-Year Inspection Interval
2CAN011105, Program Section SEP-ISI-105 for ASME Section XI, Division 1, Arkansas Nuclear One, Unit 2, Inservice Inspection Program
NL-17-1713, Proposed Alternative GEN-ISI-ALT-2017-03, and HNP-ISI-ALT-05-07, Version 1.0 Service Water Evaluation for Code Case N-513-4 for Moderate Pressure, and for Higher Pressure
LR-N17-0088, Redacted - Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 3, Design of Structures, Components, Equipment and Systems, Sections 3.1 Through 3.5
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 5, Reactor Coolant System
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 1, Introduction and General Description of Plant
NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 4 Through Chapter 5
NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 3, Part 1
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3A, Pse&G Positions on Us NRC Regulatory Guides
RS-16-248, Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Requirements Manual
RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix a - Application of NRC Regulatory Guides
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 5.0 - Reactor Coolant System and Connected Systems
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report. Appendix a
NL-15-1898, Enclosure 6: Clean-Typed EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 5.0 - Reactor Coolant System
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
DCL-12-006, Diablo Canyon - Inservice Inspection Program Plan, Third 10-Year Inspection Interval, Revision 1, Cover Page Through Page 100
DCL-10-123, Response to NRC Letter Dated August 30, 2010, Request for Additional Information (Set 21) for License Renewal Application
NOC-AE-10002577, Notification of Upgrading of the Inservice Inspection Program for the Third Inspection Interval
L-2010-122, Proposed License Amendment, Application to Delete Structural Integrity Technical Specifications, Update Accident Monitoring Instrumentation Requirements, and Minor Corrections
LR-N10-0243, Response to NRC Request for Additional Information Dated June 14, 2010, Related to Sections 4.3 and 4.4 License Renewal Application
LR-N10-0111, Response to Request for Additional Information March 22, 2010, Related to Section 4 of License Renewal Application
W3F1-2010-0014, Response to NRC Request for Additional Information Dated January 6, 2010 Waterford 3 Steam Electric Station, Unit 3 - Requests for Relief from ASME Section XI Volumetric Examination Requirements - Second 10-Year Inservice Inspection I
L-2009-262, Proposed License Amendment Application to Delete Structural Integrity Technical Specifications, Update Accident Monitoring Instrumentation Requirements, and Minor Corrections
LR-N09-0218, Unit 2 - License Amendment Request (LAR) S09-06 Revision to Technical Specification 4.0.5, Surveillance Requirements for Inservice Inspection and Testing of ASME Code Components
LR-N09-0164, License Amendment Request to Correct Technical Specification and Facility Operating License Editorial Items
NL-09-097, Submittal of Fourth Ten-Year Interval Inservice Inspection and Containment Inservice Inspection Program Plan
BW090069, Submittal of Inservice Inspection Summary Report, Fourteenth Refueling Outage (A1R14)
L-09-078, 10 CFR 50.55a Request Numbers 1-TYP-4-B3.120-1 and 2-TYP-3-C6.10-1, and Beaver Valley Power Station Inservice Inspection Plans
1CAN050807, Inservice Inspection Plan for the Fourth 10 - Year Interval
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
L-2008-043, Fourth Ten-Year Inservice Inspection Interval ISI Program Plan - Revision 0
NL-08-016, Reply to Request for Additional Information Regarding License Renewal Application - (Reactor Coolant Pump Flywheel and Leak Before Break Analyses)
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 5.0, Reactor Coolant System
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment and Systems
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 4 - Reactor Coolant System - Design Basis
HNP-07-119, License Renewal Application, Amendment 2: Changes Resulting from Responses to Site Audit Questions Regarding Time-Limited Aging Analyses
L-PI-07-048, License Amendment Request (LAR) Incorporating Technical Specification Task Force (TSTF) Industry Travelers TSTF-479, TSTF-485, and TSTF-497
RC-07-0025, License Amendment Request - LAR 05-3594 Steam Generator Tube Integrity
LR-N07-0016, Inservice Inspection Activities - 90-Day Report
DCL-06-143, License Amendment Request 06-10 Revision to Technical Specification 5.5.8, Inservice Testing Program
BYRON 2006-0027, Transmittal of Inservice Inspection Program Plan for Third Ten Year Inspection Interval
RC-06-0084, License Amendment Request - LAR 05-3594, Steam Generator Tube Integrity
LR-N06-0120, Request for Change to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process (CLIIP) Salem Units 1 & 2
LR-N06-0023, Inservice Inspection Activities - 90 Day Report and Reactor Vessel Head Inspection, Seventeenth Refueling Outage (1R17)
L-2018-175, Subsequent License Renewal Application, Safety Review Requests for Additional Information (RAI) Set 5 Responses
JAFP-18-0113, Fifth Ten-Year Inservice Inspection Interval Program Plan
RS-20-011, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
LR-N05-0380, Inservice Inspection Activities - 90 Day Report Fourteenth Refueling Outage Salem Generating Station Unit 2
BW050065, Inservice Inspection Summary Report
LR-N05-0386, Unit 1 and Unit 2, Supplement to Request for Change to Technical Specification to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process
2CAN121901, License Amendment Request Technical Specification Deletions, Additions, and Relocations
3F0508-06, Inservice Inspection Program Plan, Ten Year Update Response to Request for Additional Information
ET 06-0001, Revision to Technical Specification 5.5.8, Inservice Testing Program to Adopt Technical Specification Task Force Standard Technical Specification Change Traveler, TSTF-479, Revision 0
2CAN120401, License Amendment Request Proposed Technical Specification Changes Revising Containment Building Structural Integrity Requirements
NRC 2004-0103, License Amendment Request 243 Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process
L-PI-04-112, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process
CPSES-200401311, License Amendment Request (LAR) 04-01 Revision to Technical Specification (TS) 5.5.7 Extension of the Reactor Coolant Pump Flywheel Inspection Interval
LR-N04-0345, Request for Change to Technical Specifications to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process
W3F1-2004-0052, Supplement to Amendment Request NPF-38-249, Extended Power Uprate
RC-04-0075, License Amendment Request - LAR 04-0931 Extension of Reactor Coolant Pump Motor Flywheel Examination
ULNRC-04975, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process
LR-N04-0055, Submittal of the 90-Day Report for Inservice Inspection Activities Conducted During the Thirteenth Refueling Outage
BW040018, Inservice Inspection Summary Report
W3F1-2004-0010, Submittal of Owners Activity Report Forms for Inservice Inspection Performed During Refueling Outages 11 and 12
WO 04-0001, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process
L-03-217, Tenth Refueling Outage Inservice Inspection Report
ULNRC-04923, License Application for Revision to Technical Specification 5.5.6, Containment Tendon Surveillance Program, and Technical Specification 5.5.16, Containment Leakage Rate Testing Program
W3F1-2003-0015, License Amendment Request NPF-38-247 Relocation & Modification of Technical Specifications 4.0.5 & 3/4.4.9 & Extension of Reactor Coolant Pump Flywheel Volumetric Examination Interval
3F0204-04, 90-Day Inservice Inspection (ISI) Summary Report
2CAN020202, Response to NRC Request for Additional Information on ANO-2 Reactor Coolant Pump Flywheel Inspection Interval
3F0102-04, 90 Day Inservice Inspection (ISI) Summary Report
TSTF-20-04, Technical Specifications Task Force - Transmittal of TSTF-577, Revision 0, Revised Frequencies for Steam Generator Tube Inspections
2CAN092002, Response to Second Request for Additional Information Related to License Amendment Request Associated with Technical Specification Deletions, Additions, and Relocations
LR-N21-0036, LR-N21-0036 LAR to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
NOC-AE-21003806, Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval
B13295, Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements & RCS Operational Leakage
B13231, Rev 2 to First 10-Yr Interval Inservice Insp Plan Summary
3F0498-06, LAR 232,Rev 0 to License DPR-72,changing Scope & Frequency of Volumetric & Surface Insps for CR-3 Reactor Coolant Pump Motor Flywheels
3F0398-07, Rev 0 to LAR 227 to License DPR-72,requesting Editorial Change to Improved Tech Specs 5.6.2.8.c Re Reactor Coolant Pump Motor Flywheel Insp
0CAN109704, Informs That Final Publication Date of TR SIR-94-080 Has Been Delayed Until 971014,due to Miscommunication Between CEOG & Ano.Portion of TS Change Request Submitted on 950404, Re Elimination of Rc Flywheel Isis,Withdrawn
CP-202100694, (CPNPP) - NRC Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections
1CAN129801, Forwards Response to NRC 971202 RAI Re ANO-1 Third 10-yr ISI Program.Rev 1 to Third 10-Yr Interval ISI Program for ANO-1, Encl
2CAN049702, Application for Amend to License NPF-6,permitting Delay of Scheduled three-yr Inspections of Flywheels on All Four RCPs Until Completion of 2R13 Refueling Outage,Scheduled for Winter of 1998-99
B16290, Responds to NRC Re Violation Noted in Combined Insp Rept 50-245/96-13,50-336/96-13 & 50-423/96-13 on 961112-22.CA:test Procedure Developed for 2 Main Exhaust Sys HEPA Filter Units,Pm Mgt Sys Updated
L-96-028, TER on Third 10-Yr Interval Inservice Insp Program Plan: Consumers Power Co for Palisades Nuclear Plant
CP-202200035, Second Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections
ST-HL-AE-2093, Forwards Revised FSAR Section 3.12, Conformance W/Nrc Reg Guides. Section Updated to Reflect Util Position on All Applicable Reg Guides
NOC-AE-000241, Application for Amends to Licenses NPF-76 & NPF-80,proposing Rev to TS 4.4.10 for Alternate ISI of RCP Flywheels.Se,Nshc Determination & TS Page 3/4 4-39,included
ST-HL-AE-1440, Forwards Responses to Draft SER Open Items 14.2-1,14.2-5, 14.2-6,14.2-7,14.2-9,14.2-12 & 14.2-15.Changes to FSAR Section 14.2 Also Encl
BVY-96-123, Forwards Summary of Evaluation of Intention to Redesignate Several Core Spray & Residual Heat Removal Sys Containment Isolation Valves at Vermont Yankee
ET-NRC-93-3795, Forwards Responses to NRC RAIs on AP600 from Ltrs 920923, 1001 & 09.Remainder of RAIs Contained in NRC Ltrs of 920923 & 1001 Will Be Provided Prior to 930123
3F0896-12, Forwards 90-Day Inservice Inspection Summary Report IAW 1983 Edition of ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-6000 Which Includes NIS-1 Form & Summary of Exams Performed Since Preceding Summary Rept
L-95-059, Technical Evaluation Rept on Third 10-Yr Interval Inservice Insp Exam Plan:Northern State Power Co,Prairie Island Nuclear Generating Plant,Unit 2
L-95-056, Technical Evaluation Rept on Third 10-Year Interval Inservice Insp Program Plan:Northern States Power Co, Prairie Island Nuclear Generating Plant,Unit 1
0CAN049504, Application for Amends to Licenses DPR-51 & NPF-6,deleting Requirements for ISI of Reactor Coolant Pump Flywheels at Units 1 & 2.Rev 1 to SIR-94-080 Rept Encl
NRC-94-4337, Forwards Responses to NRC Requests for Addl Info on AP600 from NRC Ltrs of 940429,0714,0818 & 0902.Responses Associated W/Nrc 940429 & 0714 Ltrs Complete
3F1195-11, Application for Amend to License DPR-72,consisting of Change Request 204,proposing Delay for One Cycle Volumetric & Surface Exams of RCP Motor Flywheels Required by RG 1.14 & Regulatory Position C.4.b
B13079, Proposed Tech Specs Changes Per Generic Ltr 87-09
LD-93-011, Forwards Responses to 22 Issues Re Closure of Sys 80+ Draft SER Issues
LD-92-123, Forwards Section 17.3, Design Reliability Assurance Program Plan for Sys 80+ Standard Design, Rev 1 & Responses to 79 Issues Identified in Dser for Sys 80+
LD-95-013, Transmits Supplementary Revs for Incorporation Into DCD & Affidavit.Changes Resolve Inconsistencies Identified by NRC & by ABB-CE
W3P83-2108, Forwards Rev to FSAR Chapter 11,in Response to 830328 Request for Addl Info Re Changes to Waste Mgt Sys.Revs Will Be Included in FSAR Amend 33,scheduled for Aug 1983
RA-19-0039, License Amendment Request to Revise Technical Specifications to Adopt Two NRC-Approved Generic Technical Specification Changes
3F0913-02, License Amendment Request 313, Revision 1, Revision to Improved Technical Specifications Administrative Controls for Permanently Defueled Conditions and Response to Requests for Additional Information
3F0413-01, License Amendment Request 313, Revision 0, Revision to Improved Technical Specifications Administrative Controls for Permanently Defueled Conditions
CP-202400315, (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality
L-2024-084, Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld
05000269/LER-1987-012, :on 871203,discovered Exam Frequency of Reactor Coolant Pump Flywheels Exceeded Requirement of Tech Spec 4.2.3.Caused by QA Deficiency.Inservice Insp Plan Revised
05000302/LER-1994-005, :on 940928,failure to Perform Reactor Coolant Pump Motor Flywheel Occurred.Caused by Cognitive Personnel Error.Personnel Counselled & Regulatory Review Will Be Conducted to Determine Further Actions
05000344/LER-1990-025, :on 900523,identified That Surface Exam of Reactor Coolant Pump Flywheels Not Performed Per Tech Specs. Caused by Incorrect Interpretation of Meaning of Exposed. Surface Exam Completed
A02391, Comments on NRC Evaluation of SEP Topic III-10.B, Pump Flywheel Integrity. Util Intends to Remove Paint from Flywheels in Order to Permit Magnetic Particle Exam on Accessible Surfaces of Flywheels During Future Insps
NUREG-1432, Notification of 930422 Meeting W/Og to Discuss Improved STS & Related Matters
LD-90-008, Forwards Response to 881216 Request for Addl Info Re CESSAR-DC,Chapters 3,4,5 & 6 Re Turbine Missiles,Control Element Drive Structural Matls,Cleaning & Contamination Protection Procedures & Reactor Internals Matls
A01353, Submits Info Comparing Facility to Criteria Used for Licensing New Facilities Re SEP Topic III-10.B, Reactor Coolant Pump Flywheel Integrity, in Response to NRC 800926 ltr.In-place Ultrasonic Exam Will Be Conducted
NL-19-0832, EPRI Technical Report 3002014590, Technical Bases for Inspection Requirements for PWR Steam Generator Feedwater and Main Steam Nozzle-to-Shell Welds and Nozzle Inside Radius Sections
RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.
DCL-19-049, Owners Activity Report for Unit 1 Twenty-first Refueling Outage
HNP-99-129, Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity
L-96-300, Application for Amends to Licenses DPR-31 & DPR-41,modifying TS to Change SR for TS 4.4.10 Re Reactor Coolant Pump Flywheel Insp
L-96-200, Application for Amend to Licenses DPR-31 & DPR-41 to Modify Plants Units 3 & 4 to Revise TS Allowing Deferral for One Cycle of Reactor Coolant Pump Flywheel Ultrasonic Exams Required by Reg Guide 1.14
L-84-341, Forwards Addl Info Re Second 10-yr Inservice Insp Summary Plan,Per 840817 Request
CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1
L-16-355, Proposed Alternative to Use ASME Code Case N-513-4
BYRON 2017-0048, Day Inservice Inspection Report for Interval 3, Period 3 and Interval 4, Period 1, (BYR21)
LR-N16-0114, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing Using the Consolidated Line
CP-201600216, License Amendment Request 16-001, Application to Revise Technical Specifications to Adopt TSF-545, Revision 3, TS Inservice Testing Program Removal and Clarify SR Usage Rule Application to Section 5.5 Testing
LIC-16-0016, Ft. Calhoun, Unit 1 - Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1
RS-16-041, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1
RS-15-068, Response to RAI - Proposed Alternative to Utilize Code Case N-513-3, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Divsion 1,
RC-13-0047, License Amendment Request - LAR 12-03567, Application to Revise Tech Specs to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using Consolidated Line Item Improvement
SBK-L-18151, 1 - Additional Changes to the NextEra Energy Seabrook License Renewal Application
NL-13-2590, Units 1 and 2, ISI Program Alternative VEGP-ISI-ALT-10, Version 1
BW110084, Inservice Inspection Summary Report
BW110012, Inservice Inspection Summary Report
2CAN061001, License Amendment Request Changes to Reflect Revision to 10 CFR 50.55a Technical Change Travelers – TSTF-479-A and TSTF-497-A
BW100010, Inservice Inspection Summary Report
NL-16-2707, Units 1 and 2; Fourth 10-year Interval In-service Inspection Program ISI Program Update: Notification of Impractical ASME Code Requirements (NL-16-2707)
BW090029, Submittal of Third Inservice Inspection (ISI) Interval Program Plan
BYRON 2008-0067, Day Inservice Inspection Report for Interval 3, Period 1, Outage 2 (B1R15)
W3F1-2007-0014, Submittal of Owners Activity Report Form for Inservice Inspection Performed During Refueling Outage 14
NUREG-1916 Volume 2, Safety Evaluation Report - Related to the License Renewal of Shearon Harris Nuclear Power Plant, Unit 1
TSTF-04-15, TSTF-479, Revision 0, Changes to Reflect Revision of 10 CFR 50.55a
W3F1-2005-0060, Submittal of Owners Activity Report Form for Inservice Inspection Performed During Refueling Outage 13 Waterford Steam Electric Station, Unit 3
TSTF-05-07, Submittal and Request for Fee Waiver for Review of TSTF-343, Revision 1, Containment Structural Integrity
3F0204-05, License Amendment Request No. 279, Revision 0, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Sampling System for Babcock & Wilcox Reactors Using the Consolidated Line Item
WO 03-0051, Revision to Technical Specification (TS) 5.5.6, Containment Tendon Surveillance Program, and TS 5.5.16, Containment Leakage Rate Testing Program
BW030057, Inservice Inspection Summary Report
BW020084, Inservice Inspection Summary Report
CPSES-200201037, Augmented Inservice Inspection Program Plan, Revision 1
NLS2018025, 10 CFR 50.55a Relief Request RI5-03 Supplement
RS-08-036, License Amendment Request to Revise Containment Tendon Surveillance Program
RS-08-118, Additional Information Supporting Request to Revise Containment Tendon Surveillance Program
RS-10-052, License Amendment Request for an Extension of the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process
RA-22-0003, Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative
PLA-7052, Proposed Relief Requests for the Fourth Ten-Year Inservice Inspection Interval
L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes
RA-20-0252, License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications
B12159, Application for Amend to License DPR-61,changing Tech Specs to Upgrade Inservice Insp Surveillance Requirements for Reactor Vessel Per Rev 1 to Reg Guide 1.14.Fee Paid
CP-202100251, (CPNPP) - Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections
CP-202100575, (CPNPP) - Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections
SBK-L-21126, Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan
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
CP-202400319, (CPNPP) - Revision to CPNPP Letter to the NRC, Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality
PNP 2025-059, Relief Request Number RR 5-12, Proposed Alternative to ASME Section XI Code for Full Structural Weld Overlays of Primary Coolant System Hot Leg, Cold Leg, and Pressurizer Nozzle Dissimilar Metal Welds
TSTF-20-07, TSTF Response to NRC Questions on TSTF-577, Revision 0, Revised Frequencies for Steam Generator Tube Inspections, and Submittal of Revision 1