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 Issue dateTitleFromTo
ML20204J4775 August 1986Informs of Intent to Request Amends to Licenses NPF-4 & NPF-7 to Permit Redesign of Reactor Coolant Pump & Steam Generator Supports Per Requirements of GDC 4.Scope & Justification for Pending Request EnclDominion
Stewart W
Office of Nuclear Reactor Regulation
Rubenstein L
Harold Denton
ML18149A24815 August 1986Forwards Final Response Re Implementation Status of Various Generic Items,Per 860430 RequestDominion
Stewart W
Office of Nuclear Reactor Regulation
Rubenstein L
Harold Denton
ML20213D77731 October 1986RCS Leakage Detection Assessment for Elimination of RCS Main Loop Pipe Break Protective DevicesDominion
ML20213D76031 October 1986RCS Loads & Component Support Margins Evaluation for Elimination of Rcs,Main Loop Pipe Break Protective DevicesDominion
ML20213D7306 November 1986Application for Amends to Licenses NPF-4 & NPF-7,adding License Condition Per Encl Proprietary & Nonproprietary WCAP-11163 & WCAP-11164,respectively, Technical Bases for Eliminating.... Proprietary Rept Withheld (Ref 10CFR2.790)Dominion
Stewart W
Office of Nuclear Reactor Regulation
Rubenstein L
Harold Denton
NRC Generic Letter 1989-2119 October 1989NRC Generic Letter 1989-021: Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) RequirementsPartlow J
Office of Nuclear Reactor Regulation
ML18153B99929 November 1989Forwards Response to Generic Ltr 89-21 Re Status of Implementation of USI Requirements at Facilities.Actions Re USI A-26, Reactor Vessel Pressure Transient Protection Completed Via Amends 55 & 56 to SER on 800304Dominion
Stewart W
Office of Information Resources Management
ML20137C85418 March 1997Submits TS Bases Change for Review Re Containment Gaseous & Particulate Radiation MonitorsDominion
Ohanlon J
Office of Information Resources Management
ML09282015430 September 2009Updated Final Safety Analysis Report, Revision 45, Chapter 5, Reactor Coolant SystemDominionOffice of Nuclear Reactor Regulation
ML11119009327 April 2011License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation.Dominion
Price J
Office of Nuclear Reactor Regulation
Document Control Desk
ML17033B51829 September 2016Redacted Updated Final Safety Analysis Report Chapter 5V Sreenivas
Plant Licensing Branch II
Dominion
Heacock D
ML20246G70731 January 2020Enclosure 4: Attachment 4 - WCAP-11164-NP, Rev. 2, Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for North Anna Units 1 and 2 Nuclear Power Plants for the Subsequent License RenewalWestinghouse
Johnson E
Office of Nuclear Reactor Regulation
ML20309A59630 September 20206 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant SystemDominionOffice of Nuclear Reactor Regulation