L-2017-132, Inservice Inspection Program Owners Activity Reports
Information Notice 1999-10, Degradation of Prestressing Tendon Systems in Prestresssed Concrete Containments
RS-14-183, Updated Responses to NRC Set 14 Requests for Additional Information, Related License Renewal Application
ULNRC-06125, Amendment 37 to the Callaway LRA
RS-14-149, Responses to NRC Requests for Additional Information, Set 22, Dated April 24, 2014, Related to the Byron Station, Units 1 and 2, and Braidwood Station, Units 1, and 2, License Renewal Application
RS-14-126, Response to NRC Request for Additional Information, Set 20, Dated April 7, 2014, Related to the Braidwood Station, Units 1 and 2, and Byron Station, Units 1, and 2, License Renewal Application
RS-14-097, Units 1 & 2 - Responses to NRC Requests for Additional Information, Set 14, Dated March 18, 2014, Related to License Renewal Application
NOC-AE-12002802, Response to Requests for Additional Information for the License Renewal Application, Aging Management Program, Set 13
RC-12-0032, Response to Additional NRC Questions on the Proposed License Amendment Request LAR-10-03108 and Quality Assurance Plan Changes
NOC-AE-11002732, Response to Requests for Additional Information for the License Renewal Application
RS-16-248, Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Requirements Manual
RS-12-221, Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases
RS-12-221, Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Requirements Manual
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
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 15 - Aging Management Programs and Time Limited Aging Analysis
L-2018-176, Subsequent License Renewal Application, Responses to the August 2018 NRC On-Site Regulatory Audit Follow-Up Items
L-2018-191, Supplemental Responses Requests for Additional Information (RAI) Set 7 Subsequent License Renewal Application Safety Review
L-2018-223, Subsequent License Renewal Application Safety Review - November 15, 2018 Public Meeting Action Item Responses
L-2019-033, Response to Requests for Additional Information Subsequent License Renewal Application Safety Review Revision 1, Set 8 First Submittal Responses
NL-18-1571, Proposed ISI Alternative VEGP-ISI-ALT-19-01 for Tendon Inservice Inspection Extension
NOC-AE-02001321, Request for Technical Specification Bases Changes, TS Pages B 3/4 3-1 & B 3/4 3-2b Revised to Incorporate Information Re Relaxation of Reactor Trip System & Engineered Safety Features Actuation System Allowed Outage Time
ELV-00400, Application for Amends to Licenses NPF-68 & NPF-81,revising Tech Spec 3/4.6.1.6, Containment Structural Integrity, to Eliminate Unnecessary Shutdown Requirements by Allowing Engineering Evaluation of Nonconforming Conditions
ST-HL-AE-4066, Proposed TS SR 4.6.1.1 Re Primary Containment Integrity & LCO 3.6.1.3 Re Operability of Containment Air Locks
3F0595-14, Forwards Background Section,Brief Conclusion & Two Attachments Containing Summary of follow-up Questions & Util Responses to Study Performed by Gilbert Commonwealth Re Plant Fifth Tendon Surveillance
L-2024-196, Subsequent License Renewal Application - Fourth Annual Update
NUREG/CR-7153, NRC071 - NUREG/CR-7153, Expanded Materials Degradation Assessment (Emda), Volume 4: Aging of Concrete and Civil Structures (Oct. 2014)
L-88-336, Special Rept:On 880701,one Surveillance Tendon of Horizontal Tendon Group Found to Have Measured lift-off Force Below Predicted value.Lift-off Forces in Tendons 13H49,13H50 & 13H51 Have Been Restored to Predicted Lower Values
RC-16-0034, Inservice Inspection (ISI) Owners Activity Report )OAR) for Refueling Outage 22
BW120081, Inservice Inspection Summary Report
3F0611-03, Response to Request for Additional Information for the Review of License Renewal Application
3F1210-06, Response to Request for Additional Information for the Review of the Crystal River Unit 3, Nuclear Generating Plant, License Renewal Application and Amendment 16
3F1009-08, Response to Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant License Renewal Application (TAC No. ME0274) - and Amendment 6
NRC 2004-0086, Response to Request for Additional Information Regarding Sections 3.5 and 4.5 of the Point Beach Nuclear Plant License Renewal Application (TAC Nos. MC2099 and Mc 2100)
BW020084, Inservice Inspection Summary Report
RS-08-036, License Amendment Request to Revise Containment Tendon Surveillance Program
NRC 2005-0020, Amendment to the Point Beach Nuclear Plant License Renewal Application
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
L-2025-054, Subsequent License Renewal Application - Fourth Annual Update Revision 1
RS-21-015, Response to Request for Additional Information Related to Relief Request for Braidwood I4R-11 and Byron I4R-18
ST-HL-AE-2232, Forwards Final Draft Tech Specs & Technical Changes W/ Justifications.Tech Specs Consistent W/Fsar.Ser & as-built Facility W/Exceptions,Editorial Changes & Corrections Noted on Encl marked-up Pages