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 Issue dateTitleTopic
ML20059L66521 September 1990Forwards Application for Amend to License NPF-1,consisting of License Change Application 203,Rev 1.Rev Reduces Scope of Previous Changes Re Tech Spec Table 3.6-1, Containment Isolation Valves
ML20059J96914 September 1990Forwards Estimates of Facility Operator Licensing, Requalification & Generic Fundamentals Exam Requirements for FY91-94,per Generic Ltr 90-07
ML20059J98414 September 1990Responds to Re Violations Noted in Insp Rept 50-344/90-21.Corrective Action:Individual Employee Terminated on Day of Event
ML20059J0327 September 1990Requests That Six Listed Candidates Take PWR & Generic Fundamentals Exam to Be Administered on 901010
ML20059D80331 August 1990Forwards Update on Actions for NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs
ML20059D08330 August 1990Revises Response to Violations Noted in Insp Rept 50-344/90-02.License Document Change Request Correcting FSAR Discrepancy Noted in App A,Violation C Re Request for Design Change Initiated & Will Be Incorporated Into Amend 14
ML20059D24030 August 1990Extends Commitment Date from 900831 to 901031 to Amend FSAR Per Util 900404 Response to Notice of Violation
ML20059C17428 August 1990Forwards Rev 31 to Security Plan.Rev Withheld (Ref 10CFR73.21)
ML20059D32028 August 1990Responds to Deficiencies Identified by FEMA During 891115 Emergency Preparedness Exercise at Plant.Corrective Actions: Procedures Revised to Prioritize Roadblocks & Clearly Define Roadblocks for 5-mile & 10-mile Locations
ML20059D56028 August 1990Forwards Fitness for Duty Performance Rept for 900103-0630. Overall Positive Rate for All Testing Conducted at Plant from 900103-0630 Is 0.71%Fitness for Duty
ML20058M7863 August 1990Forwards Monthly Operating Rept for Jul 1990.W/o Encl
ML20056A15531 July 1990Forwards Updated Response to Address Maint/Surveillance Area of SALP for Period from Jan 1989 - Mar 1990.Overall Plant Performance During Period Acceptable & Found to Be Directed Toward Safe Operation
ML20055J34226 July 1990Forwards Decommissioning Financial Assurance Certification Rept for Plant,Per 10CFR50.75.Certifies That Finanical Assurance Utilizing Methodology as Listed Will Be Available to Decommission Plant
ML20055G71320 July 1990Comments on Operator Licensing Exams Administered on 900717
ML20055G71419 July 1990Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Plant Has Four Rosemount Model 1153DD6 Differential Pressure Transmitters Installed to Associated Logics for Safety Injection
ML20055F87916 July 1990Forwards 1989 Annual Repts for Portland General Corp,Eugene Water & Electric Board & Pacific Power & Light Co
ML20055F69113 July 1990Responds to Generic Ltr 90-04, Request for Info on Status of Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions
ML20055F81613 July 1990Advises of New Addressee for Nrc/Util Correspondence
ML20055F24412 July 1990Forwards Response to SALP Evaluation for Jan 1989 - Mar 1990 Re Maint/Surveillance.Util Plans to Improve Performance in Areas of Operation Through Commitment of Support from Nuclear Div Mgt & Personal Involvement of Corporate Mgt
ML20055E3406 July 1990Forwards Application for Renewal of Plant NPDES Permit
ML20055F2966 July 1990Forwards Addl Info Re ATWS Mitigating Sys Actuation Circuitry
ML20055E1756 July 1990Provides Update to 891130 Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Rev to Maint Procedure 12-4, Valve Air Actuators, to Include Maint Insp Completed in Apr 1990
ML20055E0286 July 1990Informs That Actions Committed to in Util Re Replacement of Breaker During 1990 Refueling Outage & Provision of Rept Documenting Replacement of Breaker, Complete,Per NRC Bulletin 88-010
ML20055E0246 July 1990Responds to NRC Re Violations Noted in Insp Rept 50-344/90-11.Corrective Actions:Generic Issues That Contributed to Violation Will Be Discussed During Mgt Meetings & Quality Insp Supervisor Counseled
ML20058K48930 June 1990Discusses Reduced Min Measured RCS Flow for Plant.Encl Figure 3.2-3 & Evaluation Support Operation W/No Tech Spec Setpoint Changes
ML20055D04129 June 1990Discusses Design Verification Program Re Main Steam Support Structure.Extension of Completion Date for Project Justified Since Documentation,Not Mod of Main Steam Support Structure Is Reason for Delay
ML20055D04429 June 1990Advises That Response to Generic Ltr 90-04 Re Status of Generic Safety Issues at Facility Delayed from 900629 to 900713
ML20055D70926 June 1990Forwards Steam Generator Tube Plugging Rept,Per Inservice Insp
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
ML18094B32228 February 1990Forwards Executed Amend 14 to Indemnity Agreement B-74
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
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
ML20055C26920 February 1990Responds to NRC Re Violations Noted in Insp Rept 50-344/89-30.Corrective Actions:Administrative Order 5-8 Temporary Mods to Be Evaluated for Need to Improve Control Over Temporary Mods Issued for Both Trains of Sys
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
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
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
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
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)
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
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