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 Issue dateTitleTopic
IR 05000445/200600721 December 2006IR 05000445-06-007, IR 05000446-06-007, 11/27/2006 - 11/30/2006, Comanche Peak Steam Electric Station, Units 1 and 2, Access Control - Letter OnlySignificance Determination Process
Affidavit
ML06346025821 December 2006Alternative Approach for Responding to the Nuclear Regulatory Commission Request for Additional Information Letter Regarding Generic Letter 2004-02 (Docket Nos.: See Enclosure)
CPSES-200602341, License Amendment Request (LAR) 06-006, Revision to Technical Specification (TS) 5.5.8, Inservice Testing Program19 December 2006License Amendment Request (LAR) 06-006, Revision to Technical Specification (TS) 5.5.8, Inservice Testing ProgramIncorporated by reference
Offsite Circuit
CPSES-200602340, License Amendment Request (LAR) 06-012, Revision to Technical Specification 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources - Operating, & TS 3.8.9, Distribution Systems - Operating.19 December 2006License Amendment Request (LAR) 06-012, Revision to Technical Specification 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources - Operating, & TS 3.8.9, Distribution Systems - Operating.Safe Shutdown
Offsite Circuit
CPSES-200602339, License Amendment Request (LAR) 06-010, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program.19 December 2006License Amendment Request (LAR) 06-010, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program.
ML06363015218 December 2006Update to 60-Day Response to Revision 1 of NRC Order EA-03-009, Issuance of First Revised NRC Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pwrs.
CPSES-200602475, Response to Request for Additional Information Related to License Amendment Request 05-08, Revision to Technical Specifications for Nominal Trip Setpoints and Allowable Value Setpoints for SG Water Level Low-Low and High-High14 December 2006Response to Request for Additional Information Related to License Amendment Request 05-08, Revision to Technical Specifications for Nominal Trip Setpoints and Allowable Value Setpoints for SG Water Level Low-Low and High-High
ML06347059914 December 2006Plant Service List
CPSES-200602416, Updated Response to Requested Information Part 2 of NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.13 December 2006Updated Response to Requested Information Part 2 of NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.Coatings
ML06346044013 December 2006Response Date for Request for Additional Information Regarding Resolution of Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power (TAC Nos. MD0947 Through MD1050)
ML06356002412 December 2006Comment (16) of D. Hooper on Behalf of Strategic Teaming and Resource Sharing on Implementing of Reactor Oversight Process, Stars Have Been Working with NEI and RUG IV in Development of Industry CommentsSignificance Determination Process
ML07072025012 December 200612/12-13/2006 Slides, Txu Power Comanche Peak Site, NRC Onsite Review, Site Geotechnical Investigation Activities.
ML0633803175 December 2006Enclosure 1 - Addressee List
TAC:MD09675 December 2006
CPSES-200602408, Comment (1) Submitted by Txu Power, Mitch Lucas, on Supplememental Proposed Rule 2, 50, 51, and 52, Regarding Licenses, Certifications, and Approvals for Nuclear Power Plants,4 December 2006Comment (1) Submitted by Txu Power, Mitch Lucas, on Supplememental Proposed Rule 2, 50, 51, and 52, Regarding Licenses, Certifications, and Approvals for Nuclear Power Plants,
CPSES-200602392, License Amendment Request 05-005, Supplement 1, Additional Information Regarding Revision to FSAR Chapters 1, 6, & 15, New Methods & Assumptions for Evaluating Radiological Consequences.1 December 2006License Amendment Request 05-005, Supplement 1, Additional Information Regarding Revision to FSAR Chapters 1, 6, & 15, New Methods & Assumptions for Evaluating Radiological Consequences.
CPSES-200602332, Planned Licensing Actions for Accident Analysis Methodologies and Power Uprate21 November 2006Planned Licensing Actions for Accident Analysis Methodologies and Power Uprate
ML06324036020 November 2006Notice of Forthcoming Meeting with Txu Generation Company, to Discuss Proposed Digital Modifications
IR 05000445/20060069 November 2006NRC Security Inspection Report 05000445-06-006 and 05000446-06-006Significance Determination Process
Affidavit
IR 05000445/20060046 November 2006NRC Integrated Inspection Report 05000445-06-004 and 05000446-06-004Shutdown Margin
Temporary Modification
Significance Determination Process
Maintenance Rule Program
Siren
IR 05000445/20064013 November 2006Commanche Peak Steam Electric Station - NRC Inspection Report 05000445/2006401 and 05000446/2006401
CPSES-200602072, Response to Request for Additional Information, 2RF08 Steam Generator Tube Inservice Inspection Report1 November 2006Response to Request for Additional Information, 2RF08 Steam Generator Tube Inservice Inspection Report
ML06312016031 October 2006Flowserve Corporation, 10 CFR Part 21 Notification
ML06304001431 October 2006Notice of Forthcoming Meeting with Txu Generation Company, LP Re Radiological Consequences of Design-Basis Accidents for Comanche Peak Steam Electric Station
ML06305018925 October 2006Transmittal of Unit 1 Reactor Vessel Surveillance Capsule X Analysis Report
CPSES-200602137, Submittal of Unit 2, Cycle 10 Core Operating Limits Report25 October 2006Submittal of Unit 2, Cycle 10 Core Operating Limits ReportShutdown Margin
TAC:MB979023 October 2006
CPSES-200602131, License Amendment Request 06-011, to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using Consolidated Line Item Improvement Process23 October 2006License Amendment Request 06-011, to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using Consolidated Line Item Improvement ProcessSafe Shutdown
Incorporated by reference
ML07023040120 October 2006Pre-DBA and Post DBA Pictures
CPSES-200602162, Transmittal of Report on Txu Power Sponsored Coatings Letter20 October 2006Transmittal of Report on Txu Power Sponsored Coatings LetterCoatings
CPSES-200601634, License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators13 October 2006License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel GeneratorsSafe Shutdown
Anticipated operational occurrence
Probabilistic Risk Assessment
Significance Determination Process
Large early release frequency
Offsite Circuit
ML06272022113 October 2006Staff'S Review of the Revision to Technical Specification Surveillance Requirements 3.3.1.2 & 3.3.1.3, Reactor Trip System Instrumentation (RTS)Anticipated operational occurrence
ML07023040210 October 2006Description of Pictures Txu Comanche Peak Ses Report #06-0413
ML0628405386 October 2006NRC Initial Operator Licensing Examination Report 05000445/2007-301; 05000446/2007-301
ML0625500765 October 2006Issuance of Amendments Revisions to TS 3.3.2, ESFAS (Engineered Safety Features Actuation System) Instrumentation; and TS 3.5.2, ECCS (Emergency Core Cooling System) - OperatingStroke time
ML0627503715 October 2006Relief Request A1; Extension of Risk-Informed Inservice Inspection Program Plan to Second 10-Year IntervalProbabilistic Risk Assessment
Large early release frequency
Exemption Request
Dissimilar Metal Weld
ML0628401025 October 2006Technical Specification, Revisions to TS 3.3.2, ESFAS Instrumentation; and TS 3.5.2, ECCS - Operating
CPSES-200601983, Relief Request B-6 to Unit 1 Inservice Inspection Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date - August 13, 2000, Second Interval)3 October 2006Relief Request B-6 to Unit 1 Inservice Inspection Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date - August 13, 2000, Second Interval)Weld Overlay
Hydrostatic
Nondestructive Examination
Liquid penetrant
Dissimilar Metal Weld
DM weld
CPSES-200602196, WCAP-16610-NP, Rev. 0, Analysis of Capsule X from the Txu Energy Company Comanche Peak Unit 1 Reactor Vessel Radiation Surveillance Program.30 September 2006WCAP-16610-NP, Rev. 0, Analysis of Capsule X from the Txu Energy Company Comanche Peak Unit 1 Reactor Vessel Radiation Surveillance Program.
CPSES-200601971, Submittal of Additional Information Related to License Amendment Request 05-007, Revision to Technical Specification 5.6.6 Regarding Pressure and Temperature Limits Report29 September 2006Submittal of Additional Information Related to License Amendment Request 05-007, Revision to Technical Specification 5.6.6 Regarding Pressure and Temperature Limits ReportHydrostatic
Pressure and Temperature Limits Report
CPSES-200601944, Operator Licensing Examination Data28 September 2006Operator Licensing Examination DataGeneric Fundamentals Examination
CPSES-200601951, Supplement to License Amendment Request (LAR) 05-010 and Response to Request for Information28 September 2006Supplement to License Amendment Request (LAR) 05-010 and Response to Request for InformationStroke time
ML06251019227 September 2006Relief Request for 10-Year Pump and Valve Inservice Testing Program - RR P-1 for Safeguards Building Sump PumpsIncorporated by reference
ML06286057525 September 2006Comment (45) of D. R. Woodlan, Supporting Nrc'S Low Level Radioactive Waste Program
CPSES-200601897, License Amendment Request (LAR) 05-005, Revision to Technical Specification 3.7.10, Control Room Emergency Filtration/Pressurization System (Crefs).18 September 2006License Amendment Request (LAR) 05-005, Revision to Technical Specification 3.7.10, Control Room Emergency Filtration/Pressurization System (Crefs).
CPSES-200601880, Response to RAI Relief Request A-1 for the Unit 2 Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Class 1 and 2 Piping Welds.15 September 2006Response to RAI Relief Request A-1 for the Unit 2 Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Class 1 and 2 Piping Welds.Non-Destructive Examination
Mission time
Probabilistic Risk Assessment
ML06258011712 September 2006Technical Specifications, Issuance of Amendments Steam Generator Tube Surveillance Program, MC9498 and MC9499Post Accident Monitoring
Operating Basis Earthquake
Nondestructive Examination
Pressure Boundary Leakage
CPSES-200601797, Response to Request for Additional Information Related to License Amendment Request 05-08, Revision to Technical Specification for Nominal Trip Setpoints and Allowable Value Setpoints for SG Water Level Low-Low and High-High12 September 2006Response to Request for Additional Information Related to License Amendment Request 05-08, Revision to Technical Specification for Nominal Trip Setpoints and Allowable Value Setpoints for SG Water Level Low-Low and High-High
ML06234005712 September 2006License Amendment, Issuance of Amendments Steam Generator Tube Surveillance Program, MC9498 and MC9499
ML06256027711 September 20069/11/2006 Fax to Licensee - Informal Request for Additional Information for Discussion Via Telephone - Risk-Informed Inservice Inspection Relief Request A-1Probabilistic Risk Assessment
Nondestructive Examination