Semantic search
Jump to navigation
Jump to search
Issue date | Title | Topic | |
---|---|---|---|
ML20206S291 | 5 May 1999 | Informs That on 990420 Council Provided ten-day Comment Period on Council Order 731 Recommending Governor Approval of Amend of Site Certification Agreement for Satsop Power Plant Site | |
ML20202C767 | 22 January 1999 | Forwards Order Terminating Construction Permit CPPR-154 for WNP-3/5 Site.Safety Evaluation Associated with Action Also Encl | |
ML20198Q713 | 4 January 1999 | Forwards EA & Fonsi Re 960808 Application.Assessment Being Forwarded to Ofc of Fr for Publication | |
ML20155J973 | 5 November 1998 | Forwards Addl Detailed Info Re Restoration & Renovation of Site Bldgs Re Util Plans to Renovate Site for Reuse as Industrial Park by Local Government Entity | |
ML20155G779 | 2 November 1998 | Forwards Insp Rept 50-508/98-201 on 981027-28.No Violations Noted.Insp Included Review of Activities to Terminate Construction Permit CPPR-154 | |
ML20116M719 | 8 August 1996 | Requests Termination of Construction Permit (CPPR-154) of Nuclear Project 3 & Withdrawal of Pending OL WNP-3 | |
ML20082A777 | 28 March 1995 | Forwards WPPSS Nuclear Projects 1,3,4 & 5 Restoration Plan | |
ML20078M496 | 3 February 1995 | Advises of Termination of Util Projects 1 & 3 | |
ML20059B768 | 20 October 1993 | Requests Code Case N-520 Approval for Nuclear Projects 1 & 3 | |
ML20057A603 | 3 September 1993 | Forwards Rev 6 to Procedure WMC-051, Preservation of Assets Program, Reflecting Installation of Two Desiccant Type Dehumidifiers for Controlling Relative Humidity within Reactor Auxiliary/Reactor Bldg Superstructure | |
ML17286B274 | 8 October 1991 | Forwards Rev 0 to Washington Nuclear Plant 3 Seismic Design Basis Model Validation,Soil Variation Studies, in Response to Open Items in Draft Safety Evaluation Re Soil/Structure Interaction/Deconvolution Issue | Finite Element Analysis Design basis earthquake |
ML17286B266 | 7 June 1991 | Requests Approval to Revise Tornado Design Criteria,Per Reg Guide 1.76,Section C.1.2 for Rotational & Translational Velocities. Justification for Revised Tornado Design Criteria Encl | |
ML20073P947 | 13 May 1991 | Forwards Rev 5 to WMC-051, WNP-3 Preventive Maint Requirements by Equipment Type | |
ML20072U221 | 12 April 1991 | Forwards Response to NRC 901221 Request for Addl Info Re Ssar for Design Certification (CESSAR-DC) | |
LD-91-014, Forwards Response to NRC Request for Addl Info Re Design Certification,CESSAR-DC,per | 26 March 1991 | Forwards Response to NRC Request for Addl Info Re Design Certification,CESSAR-DC,per | Safe Shutdown Boric Acid Ultimate heat sink Anticipated operational occurrence Tornado Missile Internal Flooding Tornado Missile Protection Coast down |
ML20029C014 | 15 March 1991 | Forwards Response to NRC 890119 Request for Addl Info to Enable NRC to Continue Review of Cessar - Design Certification (CESSAR-DC) | Safe Shutdown Ultimate heat sink Tornado Missile Safe Shutdown Earthquake Probabilistic Risk Assessment Turbine Missile Pressure Boundary Leakage |
ML20029C100 | 15 March 1991 | Forwards Response to NRC 890626 Request for Addl Info Re C-E Std SAR - Design Certification (CESSAR-DC),including Revs to CESSAR-DC | |
ML20029B649 | 4 March 1991 | Forwards Amend 1 to Cessar - Design Certification (CESSAR-DC). | |
LD-91-010, Responds to NRC 881223 Request for Addl Info Re CESSAR-DC. Forwards Proposed Revisions to CESSAR-DC | 4 March 1991 | Responds to NRC 881223 Request for Addl Info Re CESSAR-DC. Forwards Proposed Revisions to CESSAR-DC | Safe Shutdown Probabilistic Risk Assessment Coatings |
LD-91-006, Forwards Summary of Amend I to Std SAR for Design Certification,For Info & Planning Purposes | 30 January 1991 | Forwards Summary of Amend I to Std SAR for Design Certification,For Info & Planning Purposes | Ultimate heat sink |
ML17286A536 | 2 January 1991 | Discusses Interpretation of 10CFR73,App B,Paragraph Ii.B Re Security Records Retention Period | |
LD-90-097, Forwards Response to 901106 Request for Discussion of Differences Between Certain Provisions of EPRI Advanced LWR Util Requirements Document & Sys 80+ Std Design | 21 December 1990 | Forwards Response to 901106 Request for Discussion of Differences Between Certain Provisions of EPRI Advanced LWR Util Requirements Document & Sys 80+ Std Design | Safe Shutdown |
ML17286A357 | 12 October 1990 | Requests That Name Be Kept on Mailing List & That Firm Name Be Changed to Winston & Strawn in Response to 900927 Ltr | |
LD-90-075, Forwards Amend H to CESSAR - Design Certification | 3 October 1990 | Forwards Amend H to CESSAR - Design Certification | Probabilistic Risk Assessment |
ML20062A898 | 1 October 1990 | Responds to NRC Re Wish to Remain on Mailing List | |
ML20059M090 | 27 September 1990 | Informs That Name Will Be Removed from Mailing List Unless Notification of Wish to Remain on List to Continue to Receive Info Re Facility Received within 30 Days | |
ML20059M092 | 27 September 1990 | Advises That Name Will Be Removed from Mailing List Unless Notification of Wish to Remain on List to Continue to Receive Info Re Facility Received within 30 Days | |
LD-90-060, Forwards Proposed Changes to Sys 80+ Licensing Review Basis Document,Per | 28 August 1990 | Forwards Proposed Changes to Sys 80+ Licensing Review Basis Document,Per | |
ML20059A541 | 16 August 1990 | Provides Notice of Changes in Key Personnel | |
ML20056A717 | 27 July 1990 | Forwards Partial Vol 1 & Vols 4,5,6 & 7 of FSAR Re Potential Subduction Zones Earthquakes in State of Wa Coastal Area.W/O Encls | Earthquake |
LD-90-046, Forwards Addl Copies of Amend G to CESSAR-DC | 12 July 1990 | Forwards Addl Copies of Amend G to CESSAR-DC | |
ML20044A553 | 18 June 1990 | Advises That Licensee Will Submit Application for Final Design Approval & Design Certification of Process Inherent Ultimate Safety Reactor in FY92 & That Safe Integral Reactor Anticipated in FY93,in Addition to Sys 80+ Under Review | |
ML20044A493 | 8 June 1990 | Requests That NRC Review of Facility Seismic Rept Completed & SER Issued as Soon as Possible.Facility Seismic Issue Resolution to Minimize Uncertainties Surrounding Economic Evaluations of Deferred Plants Important | |
ML20042G397 | 11 May 1990 | Forwards Revised WMC-051, Washington Nuclear Plant-3 Preservation of Assets Program, Incorporating Changes Noted Through Preservation Experience & Successes Achieved in Improving Environ within Plant Bldgs | |
ML20042E900 | 30 April 1990 | Forwards Amend G to CESSAR-design Certification,Per Draft Licensing Review Basis Document | |
ML17347B588 | 1 March 1990 | Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits | |
ML20012B694 | 1 March 1990 | Forwards Compilation of Responses to Regulatory Impact Survey Questionnaire,Per Generic Ltr 90-01 | |
ML18094B322 | 28 February 1990 | Forwards Executed Amend 14 to Indemnity Agreement B-74 | |
ML15217A103 | 28 February 1990 | Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals | Offsite Dose Calculation Manual Process Control Program |
ML20011F382 | 26 February 1990 | Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices | |
ML20055C392 | 26 February 1990 | Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) | |
ML20006G062 | 22 February 1990 | Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld | |
ML20006E588 | 20 February 1990 | Forwards Proprietary Response to NRC 890725 Questions Re Vipre Core Thermal Hydraulic Section of Topical Rept DPC-NE-3000 & Rev 2 to Pages 3-69,3-70,3-78 & 3-79 of Rept. Encls Withheld (Ref 10CFR2.790) | |
ML20006E144 | 16 February 1990 | Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals | |
ML20006E907 | 16 February 1990 | Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures | |
ML20006E420 | 14 February 1990 | Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 | |
ML18094B329 | 14 February 1990 | Forwards Printouts Containing RW-859 Nuclear Fuel Data for Period Ending 891231 & Diskettes | |
ML20011E615 | 12 February 1990 | Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) | |
ML20011E557 | 8 February 1990 | Forwards Us Bankruptcy Court for Eastern District of Tennessee Orders & Memorandum on Debtors Motion to Alter or Amend Order & Opinion Re Status of Sales Agreement Between DOE & Alchemie.Doe Believes Agreement Expired on 890821 | |
ML20011E499 | 6 February 1990 | Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested |