Semantic search

Jump to navigation Jump to search
 Issue dateTitleTopic
ML16259A23922 August 1990Forwards Public Version of Rev 27 to Company Crisis Mgt Implementing Procedure CMIP-2, News Group Plan. W/ Dh Grimsley 900906 Release Memo
ML20059C12020 August 1990Forwards Rept Summarizing Util Findings Re Three False Negative Blind Performance Urine Drug Screens Which Occurred During Jan & Feb 1990.Recommends That NRC Consider Generic Communication to Clearly State Reporting Requirement
ML20063Q26714 August 1990Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 36 to CMIP-1,Rev 32 to CMIP-4,Rev 36 to CMIP-5,Rev 41 to CMIP-6,Rev 40 to CMIP-7,Rev 27 to CMIP-8 & Rev 35 to CMIP-9.W/DH Grimsley 900821 Release Memo
ML20055C98525 June 1990Forwards Rev 9 to Training & Qualification Plan.Rev Withheld
ML16152A98419 June 1990Forwards Revised Public Version of Rev 90-03 to Vol B of Epips,Including CP/2/A/2002/04C, Operating Procedure for Post-Accident Liquid Sampling, & Maint Directive 8.1
ML16152A98214 June 1990Forwards Public Version of Rev 90-02 to Vol B to Oconee Nuclear Station Epips. W/Dh Grimsley 900627 Release Memo
ML20044A44914 June 1990Forwards Public Version of Rev 90-05 to Vol C to EPIP Manual. W/Dh Grimsley 900627 Release Memo
ML20043E25731 May 1990Forwards Request for Relief 90-01 from Requirements of Section XI of ASME Boiler & Pressure Vessel Code Re Inservice Insp During Second 10-yr Interval
ML20043F47630 May 1990Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Consisting of Rev 20 to CMIP-13 & Deletion of CMIP-15 & CMIP-17.W/900612 Release Memo
ML20043A54416 May 1990Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project
ML16152A9629 May 1990Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 35 to CMIP-1,Rev 26 to CMIP-2,Rev 31 to CMIP-4,Rev 35 to CMIP-5,Rev 40 to CMIP-6,Rev 39 to CMIP-7 & Rev 26 to CMIP-8.W/DH Grimsley 900517 Release Memo
ML16152A9532 May 1990Forwards Proprietary DPC-NE-2000P-A & Nonproprietary DPC-NE-2000-A, DCHF-1 Correlation for Predicting Heat Flux in Mixing Vane Grid Fuel Assemblies. Proprietary Rept Withheld
ML20042H03230 April 1990Forwards Public Version of Rev 90-04 to Vol C to EPIP Manual
ML15217A10526 March 1990Forwards Revised 1989 Annual Radiological Environ Operating Rept,Consisting of Revised Pages Summarizing Annual Liquid Dose CalculationsAnnual Radiological Environmental Operating Report
ML20012D69421 March 1990Advises of No Human Engineering Discrepancy Mods of Safety Significance for Overall Operation of Plant,Per 880420 Commitment
ML16152A94114 March 1990Forwards Public Version of Rev 90-01 (Vol a) to Emergency Plan Manual & Revs 90-01 (Vol B) & 90-03 (Vol C) to EPIP Manual.W/Dh Grimsley 900329 Release Memo
ML20012B3741 March 1990Requests Extension to Respond to Generic Ltr 90-01 Re Participation in Regulatory Impact Survey Until 900402.Util in Process of Completing Questionnaires for All Units
ML17347B5881 March 1990Responds 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
ML15217A10328 February 1990Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation ManualsOffsite Dose Calculation Manual
Process Control Program
ML18094B32228 February 1990Forwards Executed Amend 14 to Indemnity Agreement B-74
ML20011F38226 February 1990Confirms 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
ML20006G06222 February 1990Forwards 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
ML20012B45421 February 1990Forwards Public Version of Vol C to Rev 90-02 to EPIP Manuals
ML20012B36621 February 1990Forwards Rev 1 to Cycle 12 Reload Rept,Changing Assumed RCS Flow & Correcting Typo
ML20012B16919 February 1990Forwards Public Version of Crisis Mgt Implementing Procedures,Including Rev 34 to CMIP-1,Rev 25 to CMIP-2, Rev 30 to CMIP-4,Rev 34 to CMIP-5,Rev 39 to CMIP-5 & Rev 38 to CMIP-7
ML20006E14416 February 1990Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals
ML20006E90716 February 1990Discusses 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
ML20006E42014 February 1990Requests 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
ML20011E61512 February 1990Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21)
ML20011E4996 February 1990Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested
ML20006D6912 February 1990Provides 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
ML20006C56631 January 1990Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at PlantsFitness for Duty
ML20011E25229 January 1990Forwards Proprietary Safety Analysis Physics Parameters & Multidimensional Reactor Transients Methodology. Three Repts Describing EPRI Computer Code Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790)
ML20006D66129 January 1990Advises 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
ML20006C67129 January 1990Responds 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 BiofoulingUltimate heat sink
Coatings
Biofouling
ML20006B79629 January 1990Forwards Summaries of Latest ECCS Evaluation Model Changes
ML18153C09529 January 1990Forwards 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 NotedCoatings
Biofouling
ML20006D24326 January 1990Provides 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
ML18094B28626 January 1990Forwards 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 IssuanceCoatings
Biofouling
ML18153C08726 January 1990Responds 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 OutageShutdown Margin
ML17347B54524 January 1990Informs 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
ML19354E67124 January 1990Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226
ML20006C71822 January 1990Forwards Rev 30 to Security Plan.W/O Encl
ML19354E44622 January 1990Forwards 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
ML19354E44522 January 1990Submits 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
ML20005G71620 January 1990Forwards 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
ML16152A90619 January 1990Forwards Public Version of Rev 90-01 to Vol C to Oconee Nuclear Station Implementing Procedures Emergency Plan & Rev 89-03 to Vol a to Oconee Nuclear Station Emergency Plan. W/900131 Release Memo
ML20006A80019 January 1990Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21)
ML16152A90918 January 1990Forwards 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
ML18153C07717 January 1990Forwards 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
Retrieved from "https://kanterella.com/Special:Ask/-5B-5BCategory:UTILITY-20TO-20NRC-5D-5D-20-5B-5BSite::Oconee-7C-7C05000000-5D-5D/-3FIssue-20date/-3FTitle/-3FTopic/mainlabel%3D/order%3D-20descending/sort%3D-20Issue-20date/offset%3D0/format%3Dtable/searchlabel%3D-5BTable-20view-5D"