Semantic search

Jump to navigation Jump to search
 Issue dateTitleTopic
CP-201900070, Commitment to Maintain Severe Accident Management Guidelines4 February 2019Commitment to Maintain Severe Accident Management GuidelinesFLEX
Severe Accident Management Guideline
ML16056A13911 March 2016Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports
CP-201300788, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051), Response to Request for Additional Information3 July 2013Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051), Response to Request for Additional InformationSafe Shutdown Earthquake
Finite Element Analysis
FLEX
Spent Fuel Pool Instrumentation
Battery sizing
Earthquake
CP-200900283, Response to Request for Additional Information Regarding Spent Fuel Pool Criticality License Amendment Request17 February 2009Response to Request for Additional Information Regarding Spent Fuel Pool Criticality License Amendment Request
ML07282030711 October 2007Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists
ML06205001317 July 2006Attachment 1 to TXX-0612 Response to Requests for Additional Information for the Replacement Steam Generator Supplement to Txu Power'S Large and Small Break Loss of Coolant Accident Analysis Methodologies, Pages 75 Through 216Loop seal
ML06205001417 July 2006Attachment 1 to TXX-0612 Response to Requests for Additional Information for the Replacement Steam Generator Supplement to Txu Power'S Large and Small Break Loss of Coolant Accident Analysis Methodologies, Pages 125 Through 168Loop seal
ML06205001517 July 2006Attachment 1 to TXX-0612 Response to Requests for Additional Information for the Replacement Steam Generator Supplement to Txu Power'S Large and Small Break Loss of Coolant Accident Analysis Methodologies, Pages 169 -End & Attachment 2Loop seal
Power change
ML06128058030 June 2006Memo with Enclosures 1 and 2, - Trip Report Regarding Staff Observations Regarding Flume Testing of a Prototype Portion of the Proposed Replacement Suction Screen Design for the Comanche Peak Steam Electric StationCoatings
CPSES-200601160, Revised Response to the 60-Day Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power.29 June 2006Revised Response to the 60-Day Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power.Anticipated operational occurrence
Offsite Circuit
ML07023040013 April 2006Default-Graph 001
ML06087014413 September 2005CPSES-09-2005 - Draft Outline
ML05125047828 March 200503-2005-Draft-Operating ExamBoric Acid
Shutdown Margin
High Radiation Area
Slow transfer
Post Accident Monitoring
Locked High Radiation Area
Job Performance Measure
Operability Determination
ML05125046928 March 200503-2005-Draft-Written Outline
ML05125042628 March 200503-2005-Draft-Operating Test OutlineBoric Acid
ML05123043728 March 200503-2005-Licensee Post-Exam Analysis
ML04013053817 April 2003Response to AIF Generator Survey