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| Issue date | Title | Topic | |
|---|---|---|---|
| ML17250B304 | 20 October 1999 | Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated | |
| ML17265A765 | 8 October 1999 | Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request | Non-Destructive Examination VT-2 Dissimilar Metal Weld |
| ML17265A763 | 5 October 1999 | Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 | VT-2 |
| ML17265A764 | 5 October 1999 | Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel | VT-2 |
| ML20212J356 | 30 September 1999 | Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21 | |
| ML20212J380 | 30 September 1999 | Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21 | |
| IR 05000244/1999005 | 24 September 1999 | Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs | Breakaway torque |
| ML17265A757 | 24 September 1999 | Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs | Breakaway torque |
| ML17265A746 | 31 August 1999 | Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 | |
| ML17265A740 | 26 August 1999 | Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components | Boric Acid Hydrostatic Nondestructive Examination VT-2 Code Reconciliation Through-Wall Leak Dissimilar Metal Weld |
| ML17265A741 | 26 August 1999 | Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded | |
| ML17250B302 | 23 August 1999 | Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 | |
| ML17265A745 | 23 August 1999 | Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) | Fitness for Duty |
| ML17265A727 | 30 July 1999 | Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply | |
| ML17265A715 | 23 July 1999 | Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions | |
| ML17265A706 | 22 July 1999 | Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations | |
| ML17265A719 | 21 July 1999 | Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 | |
| ML17265A714 | 21 July 1999 | Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future | |
| ML17265A704 | 16 July 1999 | Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 | |
| ML17265A691 | 30 June 1999 | Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached | |
| ML17265A687 | 22 June 1999 | Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl | |
| ML17265A684 | 21 June 1999 | Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment | Nondestructive Examination VT-2 |
| ML17265A674 | 15 June 1999 | Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT | |
| ML17265A675 | 11 June 1999 | Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification | Weak link |
| ML17309A655 | 7 June 1999 | Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment | Hot Short Safe Shutdown Boric Acid Half scram Mission time Fire Barrier Earthquake Fire Protection Program |
| ML17265A667 | 1 June 1999 | Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 | |
| ML17265A664 | 25 May 1999 | Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested | |
| ML17265A661 | 24 May 1999 | Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 | |
| ML20206U092 | 13 May 1999 | Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 | |
| ML17265A646 | 12 May 1999 | Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP | Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report |
| ML17265A641 | 12 May 1999 | Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 | Unanalyzed Condition |
| ML20206E722 | 29 April 1999 | Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 | |
| ML20206H691 | 22 April 1999 | Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls | Safe Shutdown |
| ML17265A627 | 19 April 1999 | Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 | Internal Flooding |
| ML17309A650 | 14 April 1999 | Forwards Revised Ginna Station EOPs & Procedures Index | |
| ML17265A612 | 29 March 1999 | Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 | |
| ML17265A604 | 24 March 1999 | Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 | |
| ML17265A564 | 1 March 1999 | Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl | Nondestructive Examination |
| ML17265A567 | 1 March 1999 | Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl | |
| ML17265A555 | 25 February 1999 | Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr | |
| ML17265A556 | 22 February 1999 | Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) | Fitness for Duty |
| ML17265A545 | 12 February 1999 | Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) | Boric Acid Fuel cladding |
| ML17309A649 | 12 February 1999 | Forwards Ginna Station EOPs | |
| ML17265A543 | 9 February 1999 | Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 | |
| ML17265A536 | 2 February 1999 | Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl | Safe Shutdown Safe Shutdown Earthquake Operating Basis Earthquake Earthquake Backfit |
| ML17311A069 | 25 January 1999 | Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date | Fitness for Duty Severe Accident Management Guideline Earthquake |
| ML17311A067 | 14 January 1999 | Forwards Revised Emergency Operating Procedures for Re Ginna NPP | |
| ML17265A513 | 12 January 1999 | Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date | |
| ML17265A511 | 11 January 1999 | Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl | |
| ML17265A510 | 11 January 1999 | Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl | Non-Destructive Examination VT-2 |