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Issue date | Title | Topic | |
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ML17355A460 | 26 October 1999 | Forwards Revised Epips,Including Revs to 0-EPIP-1102, 0-EPIP-1212,0-EPIP-20110,0-EPIP-20111,0-EPIP-20132, 0-EPIP-20133 & 0-EPIP-20201,per 10CFR50.54(q) & 10CFR50, App E.Epip 0-EPIP-20107,has Been Deleted | |
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 | |
IR 05000244/1999008 | 14 October 1999 | Forwards Insp Rept 50-244/99-08 on 990809-0919.Severity Level IV Violation of NRC Requirements Occurred & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy | |
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 Intergranular Stress Corrosion Cracking Dissimilar Metal Weld |
ML17355A430 | 8 October 1999 | Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included | Safe Shutdown Boric Acid High winds Shutdown Margin Feedwater Heater Integrated leak rate test Earthquake Fire Protection Program Power change Power Uprate |
ML20217B333 | 7 October 1999 | Responds to 990825 Telephone Call Re Presense of Polychlorinated Biphenyl Wastes at Plant,Unit 1 | |
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 |
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 |
ML17355A429 | 4 October 1999 | Forwards Response to NRC Telcon Questions Re License Amend Request Dtd 990727,proposing Amend on one-time Basis to Modify TS 3.8.1.1 & TS 3.4.3 & 3.5.2 to Extend Allowed Outage Time for EDG from 72 H to 7 Days | Fire Barrier Hydrostatic Enforcement Discretion Design basis earthquake Earthquake Fire Protection Program |
ML17355A446 | 4 October 1999 | Notifies NRC of Change in Commitment to Perform Periodic Testing of Critical Welds & Parts on Special Lifting Devices IAW NUREG-0612.Use of Ae Technology Will Provide Same Level of Testing Quality as Did NDE Methods Noted in ANSI Std | Non-Destructive Examination Liquid penetrant |
L-99-208, Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included | 4 October 1999 | Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included | |
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 | |
ML20212M160 | 28 September 1999 | Refers to 990908 Engineering Meeting Conducted at NRC Region II to Discuss Engineering Issues at Lucie & Turkey Point Facilities.List of Attendees & Copy of Presentation Handout Encl | |
IR 05000244/1999201 | 24 September 1999 | Forwards Insp Rept 50-244/99-201 (Operational Safeguards Response Evaluation) on 990621-24.No Violations Noted. Primary Purpose of Osre to Assess Licensee Ability to Respond to External Threat.Insp Rept Withheld | |
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 |
ML17355A425 | 22 September 1999 | Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820 | Generic Fundamentals Examination |
ML20212F448 | 17 September 1999 | Forwards NRC Form 536 Containing Currently Proposed Site Specific Operator Licensing Exam Schedule & Estimates of Number of Applicants for Generic Fundamentals Exams Through Cy 2003 | Generic Fundamentals Examination |
ML20212F705 | 14 September 1999 | Forwards Rev 19 to Ipn,Units 1 & 2 Physical Security Plan. Plan Withheld,Per 10CFR2.790(d) & 73.21 | |
ML17355A411 | 9 September 1999 | Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08 | Fire Barrier |
ML17355A413 | 7 September 1999 | Forwards Revised Relief Request 20 Re Requirement to Perform Exams as Required by IWL-2524 & IWL-2525,Table IWL-2500-1 for Exempt Tendon Insp,Per Recent Discussions with NRC | |
ML17355A414 | 2 September 1999 | Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830 | |
ML20211N068 | 2 September 1999 | Informs That Commission Requested Publication of Notice of Consideration of Issuance of Amend to Fol,Proposed NSHC Determination & Opportunity for Hearing. Amend Changes Senior Reactor License Requirement for Operations Manager | |
ML17265A746 | 31 August 1999 | Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 | |
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 | |
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 Leakage Dissimilar Metal Weld |
ML20211H629 | 26 August 1999 | Forwards NPDES Discharge Monitoring Rept for July 1999 for Indian Point,Units 1,2 & 3. Rept of Noncompliance Is Attached for Noncompliance Which Occurred at Unit 3 | |
ML17355A407 | 23 August 1999 | Informs That FPL Has Completed Review of Info Listed in Reactor Vessel Integrity Database,Version 2 & Found Listed Discrepancies,Re Closure of GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. | |
ML17355A404 | 23 August 1999 | Forwards Info to Support Assessment of Potential Risks Associated with Proposed Civil Aircraft Operations at Former Homestead Air Force Base to FP&L Turkey Point Nuclear Facility Units 3 & 4 | |
ML17355A406 | 23 August 1999 | Forwards Semiannual FFD Performance Rept for Period of Jan- June 1999,for Turkey Point Units 3 & 4.List of Events Reported & Summary of Mgt Actions Taken,Included | Fitness for Duty |
ML17265A745 | 23 August 1999 | Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) | Fitness for Duty |
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 | |
ML17355A400 | 20 August 1999 | Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance | Fitness for Duty |
ML20211E153 | 18 August 1999 | Forwards Semi Annual fitness-for-duty Program Performance Data for 990101-990630,IAW 10CFR26.71(d) | Fitness for Duty |
ML20211H605 | 18 August 1999 | Forwards Rev 8 to Security Force Training & Qualification Plan, for Indian Point 3 Nuclear Power Plant.Rev Facilitates Transition of Duty Weapons Carried by Security Force Members from Revolvers to Semiautomatic Pistols | |
ML20211A924 | 11 August 1999 | Informs That IPS Currently Estimates,That Approx Two Licensing Actions Will Be Submitted to NRC During Remainder of 1999 NRC Fiscal Yr & Approx Ten Will Be Submitted During 2000 NRC Fiscal Yr | |
ML20211B788 | 10 August 1999 | Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 | Shutdown Margin Missed surveillance Large early release frequency Thermal fatigue |
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 | |
ML17355A394 | 27 July 1999 | Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01 | |
ML20210M725 | 26 July 1999 | Forwards Projection of Ability to Pay Retrospective Premium Adjustment for Period of Aug 1999 to 000731, Which Demonstrates That Ceny Will Have Sufficient Cash Flow &/Or Cash Reserve Available Throughout Period to Pay Premium | |
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 | |
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 | |
ML17265A719 | 21 July 1999 | Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 | |
ML20210G891 | 20 July 1999 | Forwards Application for Amend to License DPR-5 for Proposed New TS 3.2.1.i,revising Senior Reactor License Requirement for Operations Manager | |
ML17355A387 | 16 July 1999 | Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants | |
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 | |
ML20209H692 | 15 July 1999 | Forwards Comments on Preliminary Accident Sequence Precursor Analysis Provided in NRC Re Operational Condition Reported in LER 269/1998-04 | |
ML17355A385 | 14 July 1999 | Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of Rept | Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report |