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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20059L448 | 18 September 1990 | Forwards Responses to Rer 900709-13 Team Visit Findings, Per .Responses Withheld (Ref 10CFR73.21) | |
| ML17309A449 | 13 September 1990 | Forwards Slides Presented by Facility & Westinghouse to NRC in 900724 Meeting.Encl Withheld | |
| ML17262A133 | 11 September 1990 | Responds to Violations & Several Unresolved Items Noted in SSFI Rept 50-244/89-81.Update of Appropriate Unresolved Items Encl.Specific Actions Re All NRC Unresolved Items Being Tracked to Completion | Condition Adverse to Quality |
| ML17261B151 | 29 August 1990 | Forwards Semiannual Radioactive Effluent Release Rept Jan- June 1990 & Rev 3 to Process Control Program for Ginna Station, Per Tech Specs 6.9.1.4 & 6.16,respectively | Process Control Program |
| ML17261B148 | 28 August 1990 | Lists Understanding of Issues Util Planning to Address Re Containment Integrity,Per 900718 Telcon.Any Concerns or Action Items Different from Listed Submittal Should Be Provided to Util Prior to NRC 900905 & 06 Visit to Plant | |
| IR 05000244/1988026 | 20 August 1990 | Submits Update on Util Plans to Provide Appropriate Ventilation to Intermediate Bldg Clean Side,Per Violation Noted in Insp Rept 50-244/88-26.Extensive Program to Manually Close All External Openings Implemented | |
| ML17261B150 | 20 August 1990 | Submits Update on Util Plans to Provide Appropriate Ventilation to Intermediate Bldg Clean Side,Per Violation Noted in Insp Rept 50-244/88-26.Extensive Program to Manually Close All External Openings Implemented | |
| ML17261B137 | 17 August 1990 | Forwards Rev 0 to, Inservice Insp Rept for Third Interval (1990-1999),First Period,First Outage (1990) at Re Ginna Nuclear Power Plant. | |
| ML17309A448 | 16 August 1990 | Responds to NRC 900717 Ltr Re Violations Noted in Insp Rept 50-244/90-80.Corrective Actions:Westinghouse Drawing E-2508 Approved & Issued to Central Records | |
| ML17261B135 | 15 August 1990 | Provides Info & Assessment on Integrity of Connection of Containment Bldg to Foundation,Per 900808 Telcon.Util Believes That Existing Condition Not Safety Concern & No Reason Exists to Suspect Joint Will Not Perform Function | Earthquake |
| ML17261B136 | 14 August 1990 | Responds to Commitment Tracking Concerns Noted in Insp Rept 50-244/90-09 & Planned Corrective Actions.Util Confirms Commitments Dates for Implementation of Effective Shelf Life Program & Comprehensive Preventive Maint Program for Parts | |
| ML17261B133 | 13 August 1990 | Recommits to Performing Enhanced primary-to-secondary Leak Rate Monitoring,Per NRC Bulletin 88-002 | |
| ML17261B126 | 30 July 1990 | Clarifies Commitment Made in 900316 RO Re Restoring Inoperable Fire Damper I-411-21-P.Util Plans to Design Removable Track Which Will Allow Charcoal Drawer to Be Manipulated.Definitive Schedule Will Be Provided in 60 Days | Hourly Fire Watch |
| ML20055H929 | 23 July 1990 | Forwards Revised Page 6:4 of Plant Security Plan.Page Withheld Per 10CFR73.21 | |
| ML17261B109 | 20 July 1990 | Advises That Structural Evaluations of Containment Sys Being Performed in Response to Containment Integrity Insp | |
| ML17309A447 | 17 July 1990 | Forwards Decommissioning Rept, for Plant,Per 10CFR50.33(k) & 50.75(b) | |
| ML17261B088 | 13 July 1990 | Provides Update to Util 860616 Ltr Re Implementation of NUREG-0737,Item 6.2,Suppl 1, Emergency Response Capability. | Safe Shutdown Boric Acid Shutdown Margin Grab sample Fuel cladding |
| ML17261B092 | 11 July 1990 | Responds to 900709 Request for Addl Info Re Containment Integrity Insp.Util Will Provide Preliminary Results by 900716 Re Where Groundwater Entering Annular Access Area. Meeting Proposed for Wk of 900723 | High Radiation Area |
| ML20044B048 | 10 July 1990 | Discusses Review of Station Blackout Documentation,Per 10CFR50.63.Licensee Will Complete Enhancements to Station Blackout Documentation Identified in Attachment 1 as Indicated & Other Items Will Be Completed within 2 Yrs | Safe Shutdown |
| ML17309A446 | 9 July 1990 | Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions | Scram Discharge Volume |
| ML17261B093 | 9 July 1990 | Responds to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Util Completed All Actions Requested in Generic Ltr & Will Retain Documentation Verification for Min of 2 Yrs | |
| ML17261B090 | 9 July 1990 | Advises That Licensee Will Install Containment Isolation Signal Going to Valve AOV 745 by End of 1992 Refueling Outage,Per Util 900608 Ltr Notifying of Condition Outside Design Basis of Plant Under 10CFR50.72 Criterion | |
| ML17250B215 | 29 June 1990 | Forwards Application for Amend to License DPR-18, Reformatting Auxiliary Electrical Sys Tech Specs & Action Statements for Offsite & Onsite Power Sources Available for Plant Auxiliaries | |
| ML17261B085 | 28 June 1990 | Forwards LER 89-016-02 Re 891117 Failure of Safety Injection Block/Unblock Switch Which Could Render Both Trains of Safety Injection Sys Inoperable.Also Reported Per Part 21 | |
| ML17250B199 | 8 June 1990 | Responds to NRC 900509 Ltr Re Violations Noted in Insp Rept 50-244/89-81.Corrective Actions:Improved Battery Load Profile Developed Incorporating Calculational Improvements Contained in Current Industry Std IEEE 485-1983 | Internal Flooding Battery sizing |
| ML17250B195 | 5 June 1990 | Responds to Generic Ltr 89-08, Erosion/Corrosion Induced Pipe Wall Thinning. Util Developed Erosion/Corrosion Program for Single & Two Phase Sys Consistent W/Requirements of NUREG-1344 & NUMARC 870611 Rept | |
| ML17250B185 | 1 June 1990 | Forwards Application for Amend to License DPR-18,providing Guidance for Action Statements Associated W/Power Distribution Limit Specs | |
| ML17261B069 | 1 June 1990 | Discusses Testing Frequency for Insp of Incore Neutron Monitoring Sys Thimble Tubes,Per NRC Bulletin 88-009.Thimble Tube Indicating Greatest Wear Recently Repositioned in Effort to Minimize Future Wear | |
| ML17250B181 | 31 May 1990 | Forwards Addl Info Re Response to Notice of Violation from Insp Rept 50-244/90-04.Info Withheld (Ref 10CFR73.21) | |
| ML17250B180 | 29 May 1990 | Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Util Does Not Need to Develop Enhanced Surveillance Program to Monitor Currently Installed Transmitter Based Upon Limited Installed Quantity | |
| ML17250B184 | 29 May 1990 | Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel (SS) Internal Pre-Load Bolting.... Valves Disassembled & 410 SS Studs Removed & Visually & Liquid Penetrant Examined | Anchor Darling Liquid penetrant |
| ML17261B096 | 29 May 1990 | Responds to NRC 900427 Ltr Re Violations Noted in Insp Rept 50-244/90-07.Corrective Actions:Worker Records Immediately Corrected Indicating That Worker Received No Significant Exposure for Time While Error Occurred | |
| ML17250B172 | 18 May 1990 | Forwards Rev 1 to Summary Exam Rept for 1990 Steam Generator Eddy Current Insp. Rept Summarizes Observations & Corrective Actions Resulting from Insps Performed During 1990 Outage | |
| ML20042G893 | 8 May 1990 | Forwards Revised Emergency Operating Procedures,Including Rev 3 to AP-RHR.2,Rev 1 to ES-0.3 & Rev 11 to ES-1.3 | |
| ML17261B061 | 26 April 1990 | Advises of Changes to 890201 Commitments Made Under Programmed Enhancement Response to Generic Ltr 88-17.Changes Will Not Reduce Capability to Operate Safely in Reduced Inventory Condition or Scope of Programmed Enhancements | |
| ML17261B059 | 17 April 1990 | Advises That No Interlocks Required for RHR motor-operated Valves 701 & 720 Based on Present Arrangement.Listed Failures Would Have to Occur in Order for Potential Overpressurization of RHR Sys to Occur | |
| ML17261B046 | 12 April 1990 | Responds to Issues Discussed During 900323 Telcon Re Inservice Testing Program Status & Relief Request.Current Test Methodology for Seat Leakage Acceptable Based on Application of Direct Measurement Sys | Cold shutdown justification |
| ML17262A143 | 12 April 1990 | Responds to NRC 900202 Ltr Re Weaknesses Noted in Insp Rept 50-244/89-80.Corrective Actions:Procedure ES-0.3 Modified to Provide Guidance for Rapid Cooldown & Depressurization W/ & W/O Reactor & Vessel Instrumentation Sys | Safe Shutdown |
| ML17250B145 | 6 April 1990 | Discusses Impact of SER Issuance for Inservice Insp & Inservice Testing Programs & Advises That Timing Will Not Affect Util Implementation Plans for Programs,Except as Listed | |
| ML17250B144 | 5 April 1990 | Responds to NRC 900309 Ltr Re Violations Noted in Insp Rept 50-244/90-02.Corrective Actions:Positive Indicator Will Be Installed for All Check Valves to Enhance Visible Positive Position Verification Ability & to Avoid Confusion | Condition Adverse to Quality |
| ML17261B040 | 30 March 1990 | Advises That Final Results of Station Blackout Documentation Review Will Be Submitted to NRC on or About 900501 | |
| ML17261B032 | 28 March 1990 | Forwards Annual Rept of ECCS Model Revs as Applicable to Facility,Per 10CFR50.46.Mods to Model for Small Break LOCA Do Not Affect Calculated Peak Clad Temp | Fuel cladding |
| ML17261B033 | 28 March 1990 | Forwards Info Re Reactor Vessel Issues,Per 900305 Telcon Concerning Change of License Expiration Date | |
| ML17261B023 | 26 March 1990 | Responds to NRC 890222 Ltr Re Violations Noted in Insp Rept 50-244/89-17.Corrective Actions:Personnel Verified Safety Injection Block/Unblock Switch in Proper Position & Operator Procedure 0-1.1 Changed as Indicated | |
| ML17261B028 | 23 March 1990 | Forwards Addl Info Re Proposed Tech Spec Amend Concerning Use of Reconstituted Fuel,Per 900315 Telcon.During Fuel Assembly Reconstitution,Failed Fuel Rods Will Be Placed W/ Filler Rods | |
| ML17261B022 | 22 March 1990 | Provides Revised Test Schedule for motor-operated Valve Diagnostic Test Program,Per IE Bulletin 85-003.NRC Notification of Changes to Valve Operability Program Required by Generic Ltr 89-10,dtd 890828 | |
| ML17261B041 | 20 March 1990 | Forwards Summary of Onsite Property Damage Coverage Currently in Force at Plant,Per 10CFR50.54(w)(4) | |
| ML17261B015 | 19 March 1990 | Responds to Generic Ltr 89-19, Safety Implication of Control Sys in LWR Nuclear Plants (USI A-47). Overfill Protection Provided Through Trip Bistables in Reactor Protection Racks Powered from 120-volt Instrument Buses | Safe Shutdown |
| ML17261B010 | 15 March 1990 | Forwards Application for Amend to License DPR-18,allowing Use of Reconstituted Fuel Assemblies | |
| ML20012D283 | 14 March 1990 | Responds to Issues Discussed During 900307 Telcon W/Util & Eg&G Re Inservice Testing Program Status & Relief Request. Valves 5960A & 5960B Will Be Disassembled to Verify Forward Flow.Relief Requests PR-8 & VR-25 Encl | Cold shutdown justification |