Regulatory Guide 1.35.1, (Task Sc 807-4), Determining Prestressing Forces for Inspection of Prestressed Concrete Containments
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L-2024-196, Subsequent License Renewal Application - Fourth Annual Update
L-2025-054, Subsequent License Renewal Application - Fourth Annual Update Revision 1
RS-17-072, Fourth 10-Year Interval Inservice Inspection Program Relief Requests
NOC-AE-16003403, Supplemental Information for the Review of the South Texas Project, Units 1 and 2, License Renewal - (TAC Nos. ME4936 and ME4937)
RA17-086, County Station, Units I & 2 - 10CFR50.55a Relief Request 14R-01
NRC 2015-0010, Filing of Owners Inservice Inspection Summary Report for Tendon Surveillance and Concrete Containment Examinations
NL-15-0217, Response to Request for Additional Information Regarding Multiple Technical Specifications Changes
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
1CAN121302, License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years
LIC-13-0092, Omaha Public Power District, Special Report on the Containment Tendon Prestressing System; Grease Voids Found in Helical Tendons and Lower Seal Failure on Tendon H-2067
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
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 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
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
LIC-07-0037, Special Report on the Containment Tendon Prestressing System, Free Water Found in Dome Tendon D230P
0CAN070801, Responses to Request for Additional Information, Proposed Alternative for Containment Inspection Interval
TSTF-08-10, Transmittal of TSTF-507, Revision 0, CLIIP Traveler to Increase Standardization
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
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
TSTF-04-09, TSTF-426, Revision 0, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c
0CAN090702, Request ANO-CISI-001, Proposed Alternative for Containment Inspection Interval
RA07-036, Submittal of Relief Requests Associated with the Third Inservice Inspection (ISI) Interval and the Second Containment Inservice Inspection (Cisi) Interval
NRC 2006-0061, LAR Public Version, License Amendment Request 248; Technical Specification 5.5.8, Steam Generator Program
NL-06-0266, Request for Technical Specification Amendment Re Containment Tendon Surveillance Program
L-2018-176, Subsequent License Renewal Application, Responses to the August 2018 NRC On-Site Regulatory Audit Follow-Up Items
NL-18-1571, Proposed ISI Alternative VEGP-ISI-ALT-19-01 for Tendon Inservice Inspection Extension
L-2020-003, License Amendment Request 268, Request to Extend Containment Leakage Rate Test Frequency
1CAN039401, Forwards Vols 1-3 to Rev 0 to Twentieth Yr Physical Surveillance of ANO Unit 1 Containment Bldg
CP-201900467, (CPNPP) - Biennial Review of Procedures and Station Operations Review Committee Meetings
L-77-306, Transmittal of Request to Amend Appendix a of Facility Operating License
NL-05-0328, Request for Technical Specification Amendment Containment Tendon Surveillance Program
NL-05-0285, ASME Section XI Request for Alternative Numbers RR-57, Proposed Alternative to IWL-2421(a) Requirements, and RR-58, Proposed Alternative to IWL-2421 (B) Requirements
2CAN120401, License Amendment Request Proposed Technical Specification Changes Revising Containment Building Structural Integrity Requirements
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
LIC-03-0077, License Amendment Request, Addition of Diesel Generator Fuel Oil, Diesel Generating Lubrication Oil, and Diesel Generator Starting Air Requirements
NL-03-1499, Response to Request for Additional Information Regarding Technical Specification Revision Request Integrated Leakage Rate Testing Interval Extension
LIC-03-0068, Annual Update to Application for Renewed Operating License
LIC-02-0103, License Amendment Request, Relocation of Prestressed Containment Tendon Surveillances to the USAR
ET 02-0015, Changes to Technical Specification Bases - Revisions 6 Through 8
NRC 2002-0019, License Amendment Request 224 Control Room Habitability
NOC-AE-21003806, Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval
1CAN058409, Forwards Arkansas Nuclear One Unit 1 Reactor Containment Bldg 10-Yr Surveillance. No Abnormal Degradation of Containment Structure Indicated
B17102, Proposed Tech Specs Changing TSs 3.4.4, RCS - Pressurizer, 3.6.1.5, Containment Sys - Air Temp & 3.7.1.5, Plant Sys - Msli Valves
3F0398-21, Special Rept:On 980302,insp Vendor Notified FPC That Grease Sample for Tendon 51H25 Had Water Content of 14.9% Volume by Weight.Caused Undeterminate.Subject Tendon Was Partially re-greased During Performance of Surveillance
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
1CAN079901, Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages
3F0399-04, Special Rept 99-01:on 990310,discovered Containment Tendons That Required Grease Addition in Excess of Prescribed Limits During Recent Insp Activites.Six Tendons Were Refilled with Appropriate Amount of Grease
1CAN049901, Application for Amend to License DPR-51,revising Requirements Associated with ANO 1 Provisions for RB Testing & Insp
3F1297-06, Special Rept 97-07:re Hoop Tendon 51H26 That Was Found to Have Normalized lift-off Force of More than 10% Below Predicted Value.Out of Tolerance Tendons Were Returned to Proper pre-stress Level.Commitment Attached
3F0298-20, Forwards Suppl to Annual 10CFR50.59 Rept That Was Provided in .Attachment a Provides Descriptions of Changes to Facility as Described in FSAR That Were Implemented Between Dec 1996 & Nov 1997.No Tests or Experiments Done
3F0198-07, Special Rept 97-09:provides Details of Conditions Found Not Meeting Acceptance Criteria During Ongoing Twentieth Year Tendon Surveillance of Containment Post Tensioning Sys. Commitments Encl
RC-97-0073, Responds to RAI Re fifteen-yr Tendon Surveillance Rept
LIC-97-0036, Special Rept:On 970321,excessive Grease Voids Were Found in Helical Wall Tendons on Containment Tendon Prestressing Sys.Insp Has Been Conducted
ST-HL-AE-2466, Lists Addl Info on Significant Hazards Evaluation for Util Proposed Change to Tech Spec 4.6.1.6.1.b.1 Re Tendon Surveillance Requirements,Per Np Kadambi 871229 Request
ST-HL-AE-2262, Forwards Revised FSAR Pages Reflecting Change in Commitment to Reg Guide 8.27 Re Conduct of General Employee Training Courses in Accordance W/Inpo Guidelines
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
NPL-99-0379, Documents Telcon with Hg Ashar of NRC Re Licensee Intentions & Basis for Reselection of Control Tendons in Pbnps Containment Structures.Plants Are Currently Completing 28th Year Tendon Surveillance During Summer of 1999
ST-HL-AE-1447, Forwards Response to Draft SER or FSAR Item F 3.8-2 Re Identification of Codes,Stds & Specs Applicable to Design. Changes Will Be Incorporated in Future FSAR Amend
B14278, Forwards Replacement Page,Reflecting Minor Word Change to TS Page 3/4 6-11,per 921019 Telcon W/Nrc & 920817 Proposed Rev to TS Re Containment Structural Integrity
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
B14216, Application for Amend to License DPR-65,changing TS to Be Consistent W/Latest Rev to Reg Guide 1.35 Re Containment Tendon Surveillance
ELV-02853, Requests Change to QA Program,Described in Encl FSAR Sections,Providing for Biennial QA Audits of Plant Procedural Development & Maint Program Utilizing Representative Sampling Process
3F1095-06, Requests Concurrence to Perform Surveillance of Eight Exempted Tendons from Fifth Tendon Surveillance W/Sixth Tendon Surveillance Scheduled for Refuel 11 Outage in Spring of 1998
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
3F1194-02, Advises That Response to Request for Addl Info Will Be Provided by 941215 Re Fifth Tendon Surveillance
3F1294-13, Requests for Addl Info Re Fifth Tendon Surveillance Rept
B16764, Informs of Change in Schedule for Commitment to Amend TS Section 4.6.1.6,made by Nene on 921030 Re Incorporation of RG 1.35,rev 3 Into Millstone Unit 2 Ts.Commitment to Be Revised,Listed
RS-23-066, Containment Post-Tensioning System Inservice Inspection Basis for Proposed Extension of Examination Interval Technical Report
3F0894-03, Forwards Crystal River Unit 3 Tendon Surveillance Program Engineering Evaluation Rept for Fifth Tendon Surveillance Insp Period
1CAN038301, Application for Amend to License DPR-51,revising Reactor Bldg Tendon Surveillance Requirement to Reduce Number of Tendons from 21 to 9 for Tenth Year & All Subsequent Tendon Surveillances
ST-HL-AE-3640, Forwards Rev 1 to Updated FSAR for South Texas Project Electric Generating Station Units 1 & 2.Changes Since Rev 0 & Unreviewed Safety Question Evaluations & Change Notices cross-reference Encl
3F0194-13, Responds to Violations Noted in Insp Rept 50-302/93-27. Corrective Actions:Procedure SP-182,Rev 10 Ref to QAP-19 Was Corrected at Time Procedure approved,QAP-19 Deleted & CP-146 Developed to Control Activity
3F1093-15, Withdraws TS Change Request 197 Submitted on 930920 & Proposes Use of Revised Tendon Testing Requirements Provided to NRC Via Which Reflected Commitment to Reg Guide 1.35,Rev as Alternative.Supporting Proposed TS Encl
TXX-4462, Forwards Revised Method for Temporary Changes Made to Plant Procedures.All Temporary Changes to Procedures Which Do Not Change Intent of Approved Procedures Will Be Approved by Two Members of Station Mgt Staff
LD-95-013, Transmits Supplementary Revs for Incorporation Into DCD & Affidavit.Changes Resolve Inconsistencies Identified by NRC & by ABB-CE
L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program
NUREG-1432, Notification of 930422 Meeting W/Og to Discuss Improved STS & Related Matters
NUREG-1434, Forwards Changes Collected by NRC Since Publication of Rev 0 to Sts.Changes Considered Minor & Included Under One Traveler
05000285/LER-1991-001, :on 910109,determined That Containment Tendon Surveillances Performed in 1981 & 1985 Did Not Reflect Guidance in Tech Specs.Caused by Inadequate Administrative Controls.Testing Program Plan Implemented
ST-HL-AE-3212, Application for Amends to Licenses NPF-76 & NPF-80,revising Tech Spec Surveillances 4.6.1.6.1,4.6.1.6.2 & 4.6.1.6.3 Following Guidance of Reg Guide 1.35 Proposed Rev 3 & Tech Spec 3.6.1.6 Re Tendon Surveillance
0CAN112201, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)
NUREG/CR-7153, NRC071 - NUREG/CR-7153, Expanded Materials Degradation Assessment (Emda), Volume 4: Aging of Concrete and Civil Structures (Oct. 2014)
L-75-248, Letter Request to Amend Technical Specification 4.4.6 on Tendon Surveillance
05000251/LER-1992-009, :on 921117,measured Prestress Force on Containment Tendon Lower than Predicted Lower Limit.Caused by Increased Tendon Wire Steel Relaxation Loss at Higher Tendon temp.Lift-off Forces Restored
L-92-330, Special Rept:On 921106 & 12,20th Yr Tendon Insp Determined That lift-off Value for Hoop Tendon 13H54 & Dome Tendon 1D40 Below Min Design Prestress Force.Tendons Restored to Required Level.Addl Rept to Be Submitted by 930129
L-92-262, Provides Rept Summarizing Surveillance Testing of Hoops Tendons Inspected During Unit 3 Twentieth Yr Insp,Per 920805 Commitment
L-92-223, Special Rept:On 920706,hoop Tendon Group Found to Have Measured Normalized lift-off Force Below Predicted Lower Limit.Cause Under investigation.Lift-off Forces in Tendons 42H31,42H32 & 42H33 Restored to Required Level
L-92-203, Special Rept:Three Surveillance Tendons,Inspected on 920612, 19 & 29 Found W/Measured Normalized lift-off Force Below Predicted Lower limit.Lift-off Forces Restored to Required Level of Integrity.Addl Rept Will Be Sent by 920915
NRC 2010-0028, Filing of Owners Inservice Inspection Summary Report for Refueling Outage U2R30
ET 07-0014, Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application
NRC-2007-0003, To License Amendment Request 248: Technical Specification 5.5.8, Steam Generator Program
LIC-05-0098, License Amendment Request (Lar), Deletion of Shutdown Margin Surveillance Requirement and Miscellaneous Administrative Changes
TSTF-05-07, Submittal and Request for Fee Waiver for Review of TSTF-343, Revision 1, Containment Structural Integrity
2CAN070409, Unit 2, License Renewal Application Clarifications
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)
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
B18696, License Basis Document Change Request 2-17-02, Containment Systems
LIC-02-0022, Special Report on the Containment Tendon Prestressing System, Excessive Grease Voids Found in Helical Wall Tendons
NRC 2005-0020, Amendment to the Point Beach Nuclear Plant License Renewal Application
NL-25-0045, Proposed Inservice Inspection Alternative FNP-ISI-ALT-2025-10 for Containment Unbonded Post-Tensioning System Inservice Inspection Requirements in Accordance with 10 CFR 50.55a(z)(1) (NL-25-0045)
RS-21-015, Response to Request for Additional Information Related to Relief Request for Braidwood I4R-11 and Byron I4R-18
RC-96-0206, Forwards 15th Yr Physical Surveillance Rept of Facility Containment Bldg,Per NRC Request
LD-95-011, Forwards Rev Pages for Sys 80+ Design Control Document. Margin Bar Adjacent to Change & Rev Date Will Be Added to Revised DCD Page
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
05000325/LER-1984-033, :on 841119,discovered Common Chlorine Detection Sys Failed to Meet Fsar/Tech Spec Design Criteria.Caused by Inadequate Chlorine Detection Sys Signal.Plant Mod to Meet Design Criteria Implemented