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Issue date | Title | Topic | |
---|---|---|---|
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 |
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 |
LD-90-075, Forwards Amend H to CESSAR - Design Certification | 3 October 1990 | Forwards Amend H to CESSAR - Design Certification | Probabilistic Risk Assessment |
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 | |
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 | |
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 | |
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 | |
ML20011E598 | 5 February 1990 | Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj | |
ML20006D691 | 2 February 1990 | Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle | |
ML20006C566 | 31 January 1990 | Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants | Fitness for Duty |
ML20006D661 | 29 January 1990 | Advises That 900117 License Amend Request to Remove Certain cycle-specific Parameter Limits from Tech Specs Inadvertently Utilized Outdated Tech Specs Pages.Requests That Tech Specs Changes Made Via Amends 101/83 Be Deleted | |
ML20011E252 | 29 January 1990 | Forwards Proprietary Safety Analysis Physics Parameters & Multidimensional Reactor Transients Methodology. Three Repts Describing EPRI Computer Code Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790) | |
ML20006C671 | 29 January 1990 | Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Plants Have Established Preventive Maint Program for Intake Structure & Routine Treatment of Svc Water Sys W/Biocide to Control Biofouling | Ultimate heat sink Coatings Biofouling |
ML20006B796 | 29 January 1990 | Forwards Summaries of Latest ECCS Evaluation Model Changes | |
ML18153C095 | 29 January 1990 | Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted | Coatings Biofouling |
ML20006D243 | 26 January 1990 | Provides Info Re Emergency Response Organization Exercises for Plants.Exercises & Callouts Would Necessitate Activation of Combined Emergency Operations Facility Approx Eight Times Per Yr,W/Some Being Performed off-hours & Unannounced | |
ML18153C087 | 26 January 1990 | Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures to Be Revised & Familiarization Sessions Will Be Conducted Prior to Each Refueling Outage | Shutdown Margin |
ML18094B286 | 26 January 1990 | Forwards Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Aggressive Program of Monitoring,Insp & Matl Replacement Initiated in Advance of Generic Ltr 89-13 Issuance | Coatings Biofouling |
ML19354E419 | 25 January 1990 | Comments Re Issuance of OL Amends & Proposed NSHC Determination Re Transfer of Operational Mgt Control of Plants & Views on anti-trust Issues Re Application for Amend for Plants | |
ML20011E204 | 25 January 1990 | Forwards Response to 881216 Request for Addl Info Re CESSAR-DC,Chapters 3,4,5 & 6 Re Turbine Missiles,Control Element Drive Structural Matls,Cleaning & Contamination Protection Procedures & Reactor Internals Matls | Safe Shutdown Tornado Missile Hydrostatic Coatings Nondestructive Examination Tornado Generated Missile Turbine Missile Pressure Boundary Leakage |
ML19354E671 | 24 January 1990 | Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226 | |
ML17347B545 | 24 January 1990 | Informs of Plans to Apply ASME Code Case N-356 at Plants to Allow Certification Period to Be Extended to 5 Yrs.Rev to Inservice Insp Programs Will Include Use of Code Case | |
ML19354E446 | 22 January 1990 | Forwards Proprietary Rev 1 to DPC-NE-2001, Fuel Mechanical Reload Analysis Methodology for MARK-BW Fuel, Adding Section Re ECCS Analysis Interface Criteria & Making Associated Administrative Changes.Rev Withheld | |
ML19354E445 | 22 January 1990 | Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters | |
ML20005G716 | 20 January 1990 | Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl | |
ML20006A800 | 19 January 1990 | Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21) | |
ML16152A909 | 18 January 1990 | Forwards Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. W/900131 Release Memo | |
ML18153C077 | 17 January 1990 | Forwards North Anna Power Station Emergency Plan Table 5.1, 'Min Staffing Requirements for Emergencies' & Surry... Table 5.1, 'Min Staffing Requirements...', for Approval,Per 10CFR50.54(q),NUREG-0654 & NUREG-0737,Suppl 1 | |
ML20006A624 | 16 January 1990 | Forwards Draft Qualified Master Trust Agreement for Decommissioning of Nuclear Plants,For Review.Licensee Will Make Contributions to Qualified & Nonqualified Trust as Appropriate | |
ML20006A201 | 16 January 1990 | Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel in Anchor Darling Swing Check Valves.Eight Subj Valves Identified in Peach Bottom Units 1 & 2 & Will Be Returned to Mfg | Anchor Darling Nondestructive Examination |