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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20065D582 | 19 September 1990 | Forwards Rev 25 to Security Plan.Rev Withheld (Ref 10CFR73.21) | |
| ML20059L343 | 13 September 1990 | Forwards Application for Amends to Licenses DPR-42 & DPR-60, Revising Tech Spec Section 6.7.A.6.b | |
| ML20059E867 | 6 September 1990 | Forwards Rev 24 to Security Plan.Rev Withheld (Ref 10CFR73.21) | |
| ML20064A641 | 6 September 1990 | Amends 900724 Certification for Financial Assurance for Decommissioning Plant,Per Reg Guide 1.159.Util Intends to Seek Rate Relief by Pursuing Rehearing & Appeal of Rate Order by Initiating New Rate Proceeding | |
| ML20028G840 | 29 August 1990 | Forwards Effluent & Waste Disposal Semiannual Rept for Jan- June 1990 & Revised Effluent & Waste Disposal Semiannual Rept for Second Half of 1989,which Includes Previously Omitted Fourth Quarter Analyses Results of Sr-89 & Sr-90 | |
| ML20058Q402 | 2 August 1990 | Informs NRC of Potentially Generic Problem Experienced W/Westinghouse DB-50 Reactor Trip Breaker.Info Being Provided Due to Potential Generic Implications of Deficiencies in Westinghouse Torquing Procedues | |
| ML20056A337 | 31 July 1990 | Forwards Rev 2 to, ASME Code Section XI Inservice Insp & Testing Program,Second 10-Yr Insp Interval of Operation | |
| ML20055J444 | 26 July 1990 | Submits Supplemental Info to Violations Noted in Insp Repts 50-282/89-26 & 50-306/89-26.Training of Supervisory Personnel Not Completed Until 900719 Due to Time Constraints Encountered During Feb 1990 Unit 1 Refueling Outage | |
| ML20055G398 | 28 June 1990 | Forwards Annual Rept of Changes,Tests & Experiments for 1989 & Rev 8 to Updated SAR for Prairie Island Nuclear Generating Plant | |
| ML20043F734 | 11 June 1990 | Responds to NRC 900420 Ltr Re Violations Noted in Insp Repts 50-282/90-04 & 50-306/90-04.Corrective Actions:Operations Procedure D61 Will Be Revised to More Clearly Identify Requirements for Logging Openings | |
| ML20043D568 | 5 June 1990 | Rev 23 to Security Plan.Rev Withheld (Ref 10CFR73.21) | |
| ML20043C773 | 25 May 1990 | Informs That on 900425,yard Fire Hydrant Hose House 7 Declared out-of-svc Due to Const in Area,Per Tech Spec 3.14.F.2.Const in Area Will Prevent Return to Svc of Hydrant Hose House 7 Until Approx 900630 | |
| ML20043A445 | 9 May 1990 | Responds to NRC 900319 Ltr Re Violations Noted in Insp Repts 50-282/89-29 & 50-306/89-29.Corrective Actions:Changes Will Be Made to Review & Approval Process for Work Packages | |
| ML20043A453 | 2 May 1990 | Responds to NRC 900319 Ltr Re Violations Noted in Insp Repts 50-282/89-29 & 50-306/89-29.Corrective Actions:Incoming Workers Will Be Specifically Trained in Fire Prevention Practices & Permanent Workers Will Be Reminded at Meetings | Emergency Lighting Condition Adverse to Quality |
| ML20042F868 | 30 April 1990 | Submits Supplemental Info on Response Time Testing of Instrumentation,In Response to Concerns Raised in Insp Repts 50-282/88-12 & 50-306/88-12.No Addl Changes to Current Response Time Testing Program Necessary | |
| ML20042E808 | 27 April 1990 | Forwards Radiation Environ Monitoring Program Rept 1989. | |
| ML20012E426 | 28 March 1990 | Forwards Inservice Insp-Exam Summary 900103-0219 Refueling Outage 13,Insp Period 2,Second Interval. Exam Plan Focused on Pressure Retaining Components & Supports of RCS & Associated Sys,Fsar Augmented Exams & Eddy Current Exam | |
| ML20012D913 | 22 March 1990 | Forwards Rev 0 to Core Operating Limits Rept Unit 1 - Cycle 14 & Rev 0 to Core Operating Limits Rept Unit 2 - Cycle 13. | |
| ML20012E009 | 21 March 1990 | Forwards Completed Questionnaire in Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. | |
| 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 |
| ML20012A313 | 26 February 1990 | Forwards Rev 0 to Effluent Semiannual Rept,Jul-Dec 1989, Supplemental Info, Amend to Effluent & Waste Disposal Semiannual Rept for First Half of 1989 & Rev 11 to Odcm. Analyses for Sr-89 & Sr-90 Will Be Included in Next Rept | |
| 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 | |
| ML20006G193 | 26 February 1990 | Forwards Rev 22 to Security Plan & Advises That Changes Do Not Decrease Effectiveness of Plant Security Plan & May Be Implemented W/O Prior NRC Review & Approval.Rev Withheld (Ref 10CFR73.21) | |
| 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 | |
| ML20006F863 | 22 February 1990 | Provides Steam Generator Tube Plugging & Sleeving Info,Per Tech Spec 4.12.E.1.Following Recent Inservice insp,15 Tubes Plugged for First Time & 37 Tubes W/New Indications Sleeved | |
| ML20042E187 | 19 February 1990 | Forwards Response to NRC 900118 Ltr Re Violations Noted in Insp Repts 50-282/89-30 & 50-306/89-30.Response Withheld (Ref 10CFR73) | |
| 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 | |
| ML20006E803 | 16 February 1990 | Forwards Request for Relief from Schedule Requirements of NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor/Darling Valves. | Anchor Darling |
| 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 | |
| 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) | |
| 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 | |
| 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 |
| 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 |
| 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 |
| 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 | |
| ML20006B929 | 29 January 1990 | Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Procedure Will Be Developed to Periodically Inspect Emergency Intake Crib Located in River | Ultimate heat sink Coatings Biofouling |
| ML20006B904 | 29 January 1990 | Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Boron Concentration Will Be Calculated W/Provisions for One Shuffle Alteration | Shutdown Margin |
| ML20006B796 | 29 January 1990 | Forwards Summaries of Latest ECCS Evaluation Model Changes | |
| 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) | |
| 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 |
| 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 |
| 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 | |
| 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 | |
| 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 | |
| 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 |