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Issue date | Title | Topic | |
---|---|---|---|
ML20236F691 | 29 May 1998 | Rev 6 to AP600 Emergency Response Guidelines, Including Guidelines SDG-1,SDG-2,SDG-3 & Change Pages for Background Documents AE-1,SDF-0.1,SDG-1,SDG-2 & SDG-3 | Shutdown Margin Severe Accident Management Guideline Fuel cladding |
ML20198S747 | 31 October 1997 | Rev 5 to AP600 Emergency Response Guidelines | Shutdown Margin Loop seal Probabilistic Risk Assessment Squib |
ML20149H511 | 1 July 1997 | Rev 4 to GW-GJR-100, AP600 Emergency Response Guidelines | Shutdown Margin |
ML20141B655 | 31 May 1997 | to AP600 Emergency Response Guidelines | Shutdown Margin Squib |
ML20141H150 | 16 May 1997 | Rev 3 to DE-AC03-90SF18495, Simplified Passive Advanced LWR Plant Program,AP600 Certified Design Matl | Safe Shutdown Boric Acid Safe Shutdown Earthquake Post Accident Monitoring Hydrostatic Probabilistic Risk Assessment Nondestructive Examination Squib Emergency Lighting Earthquake Pressure boundary leak |
ML20134A562 | 15 January 1997 | Rev 2 to Design Reviews | |
ML20117J107 | 30 August 1996 | Revised Background Info for AP600 Emergency Response Guidelines,Including Rev 1A to EA-1,Rev 1A to AES-1.1,Rev 1A to AES-1.2 & Rev 1A to AE-2 | Boric Acid Coast down |
ML20116J833 | 31 July 1996 | Rev 2 to SDG-6, AP600 Response to Unexpected RCS Temp Changes During Shutdown | Boric Acid Shutdown Margin |
ML20116J823 | 31 July 1996 | Rev 2 to SDG-5, AP600 Response to Cold Overpressure During Shutdown | |
ML20116J815 | 31 July 1996 | Rev 2 to SDG-4, AP600 Response to Increasing Nuclear Flux During Shutdown | Boric Acid Shutdown Margin |
ML20116J810 | 31 July 1996 | Rev 2 to SDF-3, AP600 Response to High Containment Radiation During Shutdown | |
ML20116J803 | 31 July 1996 | Rev 2 to SDG-2, AP600 Response to Loss of Rns During Shutdown | Shutdown Margin |
ML20116J800 | 31 July 1996 | Rev 2 to SDF-1, AP600 Response to Loss of RCS Inventory During Shutdown | Shutdown Margin |
ML20116J794 | 31 July 1996 | Rev 2 to SDF-0.1, AP600 Shutdown Safety Status Tree During Shutdown | Shutdown Margin |
ML20116A442 | 31 July 1996 | Westinghouse AP600 Chapter 14,Initial Test Program | Safe Shutdown Boric Acid Shutdown Margin Ultimate heat sink Grab sample Hydrostatic Squib Emergency Lighting Flow Induced Vibration |
ML20107C740 | 8 April 1996 | Non-proprietary Programmatic Level Description of AP600 Human Factors Verification & Validation Plan | Probabilistic Risk Assessment |
ML20107C742 | 8 April 1996 | Non-proprietary Man-In-The-Loop Test Plan Description | |
ML20101N834 | 31 March 1996 | Non-proprietary Version of AP600 Reactor Internals Flow-Induced Vibration Assessment Program | Hydrostatic Flow Induced Vibration |
ML20095E672 | 8 December 1995 | Plan to Resolve AP600 PRA MAAP4 Success Criteria Issues | |
ML20134A550 | 1 June 1995 | Rev 2 to AP600 Sys Specification Documents | |
ML20134A600 | 1 June 1995 | Rev 1 to Control of Subcontractor Submittals | |
ML20085E426 | 31 May 1995 | AP600 Emergency Response Guidelines | Boric Acid Shutdown Margin |
ML20083C932 | 12 May 1995 | Rev 0 to Document 00395PP95, PANTHERS-IC Test Procedures | |
ML20086H502 | 10 May 1995 | Rev 1 to 25A5677, Giraffe Helium Test Specification Legend or Description of Group | Hydrostatic |
ML20101F338 | 1 May 1995 | Rev 1 to PPCP-QA-01, Panda Project Control Plan | |
ML20083B890 | 28 February 1995 | Rev 3 to Simplified Passive Advanced Light Water Reactor Plant Program AP600 Probabilistic Risk Assessment | Safe Shutdown Reactor Vessel Water Level Mission time Anticipated operational occurrence Probabilistic Risk Assessment Squib |
ML20077R325 | 31 January 1995 | BWR Vessel & Internals Project Program Plan | Coatings |
ML20080H546 | 27 January 1995 | Rev 0 to Test Spec 25A5677, Giraffe Test Spec | Hydrostatic |
ML20078R014 | 9 January 1995 | Rev 3 of Test Spec 23A6999, Isolation Condenser & Passive Containment Condenser Test Requirements | Loop seal |
ML20073C910 | 26 August 1994 | Rev 2 to WCAP-13234, Test Spec for Long-Term Cooling Test | Reactor Vessel Water Level |
ML20072T264 | 23 August 1994 | Isolation Condenser & Passive Containment Condenser Test Requirements Legend or Description of Groups | Loop seal |
ML20071G211 | 28 June 1994 | Sys 80+ Emergency Operations Guidelines, Replacement Pp | |
ML20065M297 | 31 May 1994 | Draft Advanced Reactor Research & Development Programs 5-Yr Plan for Advanced Reactor Activities Under Energy Policy Act of 1992 | Safe Shutdown |
ML20065A473 | 22 March 1994 | AP600 Design Certification Test Program Overview, Rev 5.W/ Ten Oversize Drawings | |
ML20134A580 | 11 March 1994 | Rev 2 to AP600 Design Criteria Documents | |
ML20067D344 | 10 February 1994 | Rev 2 to NPX80-SQP-0101.0, Software Program Manualfor Nuplex 80+ | Post Accident Monitoring Coatings Weak link |
ML20058C306 | 10 November 1993 | Rev 1 to NPX80-SQP-0101.0, Software Program Manual for Nuplex 80+ | |
ML20058C325 | 10 November 1993 | Draft Rev to Sys 80+ Emergency Operations Guidelines, Functional Recovery Guideline | |
ML20059J941 | 5 November 1993 | Draft Sys 80+ Emergency Operations Guideline, SBO Recovery Guideline | Safe Shutdown Shutdown Margin |
ML20059J933 | 5 November 1993 | Draft Sys 80+ Emergency Operations Guideline, Excess Steam Demand Event Recovery | |
ML20059J919 | 5 November 1993 | Draft Sys 80+ Emergency Operations Guideline, Loss of Offsite Power Recovery Guideline | Shutdown Margin |
ML20059J911 | 5 November 1993 | Draft Sys 80+ Emergency Operations Guideline, Loss of All Feedwater Recovery | Shutdown Margin |
ML20059H593 | 3 November 1993 | SG Tube Rupture Recovery Guideline | Shutdown Margin |
ML20059H599 | 3 November 1993 | LOCA Recovery Guideline | Boric Acid Shutdown Margin Fuel cladding |
ML20059H582 | 3 November 1993 | Diagnostic Actions | |
ML20059H553 | 3 November 1993 | Reactor Trip Recovery Guideline | |
ML20059H522 | 3 November 1993 | Standard Post Trip Actions Recovery Guideline | |
ML20059B739 | 19 October 1993 | Pcc Test Plan & Procedures, Rev 0 | |
ML20058N094 | 30 September 1993 | Plant Designers Operational Support Info Plan for ABB-CE Sys 80+ (Tm) | Safe Shutdown Temporary Modification |
ML20058N085 | 29 September 1993 | Rev 2 to NPX80-IC-DP790-01, Human Factors Program Plan for Sys 80+ (Tm) Std Plant Design | Safe Shutdown Post Accident Monitoring Probabilistic Risk Assessment |