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 Issue dateTitle
ML18207A2728 August 2018Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-ichi Accident
ML15174A2571 September 2015Letter to Licensees Coordination of Request for Information for Flooding Hazard Reevaluations and Mitigating Strategies for Beyond-Design-Basis External Events
ML14169A64516 June 20142014-06 Draft Written Exam
ML14111A1479 May 2014Seismic Screening and Prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights
ML14030A04620 February 2014Letter from Eric J. Leeds Supplemental Information Related to Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1
ML13044A5611 March 2013Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Flooding Hazard Reevaluation for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
ML12054A73512 March 2012Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
ML12054A67912 March 2012Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation
ML12056A04512 March 2012Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
ML12056A04412 March 2012Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status
NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status12 March 2012Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status
NRC-2012-0068, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events12 March 2012Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
ML10214038730 July 2010Nuclear Regulatory Commission Biweekly Notice - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations - Publication Date of August 10, 2010
ML10049099218 February 2010Response to Comanche Peak Disputed Non-Cited Violation 05000445-09-004-05 and 05000446-09-004-05
IR 05000445/20090059 February 2010IR 05000445-09-005, 05000446-09-005; on 09/20/2009 - 12/31/2009; Comanche Peak Steam Electric Station, Units 1 and 2; Operability Evaluations, Refueling and Other Outage Activities, Access Control to Radiologically Significant Areas, Other
CP-200901579, Denial of Noncited Violation in NRC Integrated Inspection Reports 05000445-09-004, 05000446-09-00423 November 2009Denial of Noncited Violation in NRC Integrated Inspection Reports 05000445-09-004, 05000446-09-004
CP-200901403, Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Cover Page Through Attachment a, Page 30 of 4513 October 2009Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Cover Page Through Attachment a, Page 30 of 45
CP-200901403, Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Cover Page Through Attachment a, Page 30 of 4513 October 2009Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Cover Page Through Attachment a, Page 30 of 45
ML09261079110 September 2009Comanche Peak Supplement Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
CP-200801606, Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Introduction Through Attachment a26 November 2008Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Introduction Through Attachment a
CP-200801606, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Introduction Through Attachment a26 November 2008Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Introduction Through Attachment a
CP-200800962, Licensing Basis on Use of Manual Actions for Fire Protection24 July 2008Licensing Basis on Use of Manual Actions for Fire Protection
ML05174020613 June 2005Comment (10) of D. R. Woodlan on Behalf of Strategic Teaming and Resource Sharing on Draft GL-05-0XX; Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power
CPSES-200500996, Comment (1) of Fred W. Madden Draft Regulatory Guide DG-11304 May 2005Comment (1) of Fred W. Madden Draft Regulatory Guide DG-1130
CPSES-200500464, 90-day Response to NRC GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors7 March 200590-day Response to NRC GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors
ML0329401047 October 2003Riv Backfit Status
ML03113057228 March 2003Strategic Teaming and Resource Sharing (Stars) Comments on Review Standard for Extended Power Uprates
ML03294009827 March 2003Riv Backfit Status
CPSES-200300262, Supplemental Information for Consideration During Significance Determination Process Review of Apparent Violation 50-445/02-09-015 March 2003Supplemental Information for Consideration During Significance Determination Process Review of Apparent Violation 50-445/02-09-01
ML02311010325 October 2002Comment from D. R. Woodlan on DG-1099, Anchoring Components and Structural Supports in Concrete.
CPSES-200200611, Appeal of the Final Significance Determination for a White Finding and Reply to a Notice of Violation6 March 2002Appeal of the Final Significance Determination for a White Finding and Reply to a Notice of Violation
ML03111044913 October 1999Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes
RIS 1999-02, Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes13 October 1999Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes
NRC Generic Letter 1983-1124 June 1999NRC Generic Letter 1983-011, Supplement 1: Licensee Qualification for Performing Safety Analysis
ML20205R57014 April 1999Rev 6 to ER-ME-067, TU Electric Engineering Rept,Evaluation of Thermo-Lag Fire Barrier Sys
NRC Generic Letter 1998-0114 January 1999NRC Generic Letter 1998-001, Supplement 1: Year 2000 Readiness of Computer Systems at Nuclear Power Plants
NRC Generic Letter 1998-0414 July 1998NRC Generic Letter 1998-004: Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material i
NRC Generic Letter 1998-0228 May 1998NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition
ML20216E1057 April 1998Comment Supporting Draft RG DG-1029 Titled Guidelines for Evaluating Electromagnetic & Radio-Frequency Interference in Safety-related Instrumentation & Control Sys
ML20217H36126 March 1998Comment Opposing Draft GL 97-XX, Lab Testing of Nuclear Grade Charcoal, Issued on 980225.Advises That There Will Be Addl Implementation Costs
NRC Generic Letter 1997-0630 December 1997NRC Generic Letter 1997-006: Degradation of Steam Generator Internals
NRC Generic Letter 1997-0517 December 1997NRC Generic Letter 1997-005: Steam Generator Tube Inspection Techniques
ML20198Q71824 October 1997Rev 5 to ER-ME-067, Evaluation of Thermo-Lag Fire Barrier Systems
NRC Generic Letter 1997-0430 September 1997NRC Generic Letter 1997-004: NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules
ML20206E34019 September 1997Requests That NRR Conduct Review of Licensee Backfit Claim to Determine of plant-specific Backfit Exists & Submits Recommended Actions to Be Taken If One Does Exists
IR 05000445/19970124 September 1997Requests Addl Info for Examples 3 & 4 of Violation B & D Re Insp Repts 50-445/97-12 & 50-446/97-12 & Nov,Dtd 970611. Responses Did Not Supply Sufficient Info to Determine That Corrective Actions Were Adequate to Preclude Recurrence
NRC Generic Letter 1997-0215 May 1997NRC Generic Letter 1997-002: Revised Contents of Monthly Operating Report
ML20135D39528 February 1997Provides Response to SE Open Items on CPSES Unit 1 Re Thermo-Lag Cable Functionality Issues
Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents24 February 1997Implementation of a New Constraint on Radioactive Air Effluents
NRC Generic Letter 1995-0631 January 1997NRC Generic Letter 1995-006: Changes in Operator Licensing Program
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