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 Issue dateTitleTopic
ML17355A46026 October 1999Forwards 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
ML17250B30420 October 1999Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated
IR 05000244/199900814 October 1999Forwards 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
ML17265A7658 October 1999Forwards 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 RequestNon-Destructive Examination
VT-2
Intergranular Stress Corrosion Cracking
Dissimilar Metal Weld
ML17355A4308 October 1999Forwards 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,IncludedSafe Shutdown
Boric Acid
High winds
Shutdown Margin
Feedwater Heater
Integrated leak rate test
Earthquake
Fire Protection Program
Power change
Power Uprate
ML20217B3337 October 1999Responds to 990825 Telephone Call Re Presense of Polychlorinated Biphenyl Wastes at Plant,Unit 1
ML17265A7645 October 1999Requests 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 VesselVT-2
ML17265A7635 October 1999Requests 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 31,2000VT-2
ML17355A4294 October 1999Forwards 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 DaysFire Barrier
Hydrostatic
Enforcement Discretion
Design basis earthquake
Earthquake
Fire Protection Program
ML17355A4464 October 1999Notifies 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 StdNon-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 Included4 October 1999Forwards 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
ML20212J35630 September 1999Forwards 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
ML20212J38030 September 1999Forwards 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
ML20212M16028 September 1999Refers 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 05000244/199920124 September 1999Forwards 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 05000244/199900524 September 1999Forwards 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 & SvcsBreakaway torque
ML17265A75724 September 1999Forwards 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 & SvcsBreakaway torque
ML17355A42522 September 1999Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820Generic Fundamentals Examination
ML20212F44817 September 1999Forwards NRC Form 536 Containing Currently Proposed Site Specific Operator Licensing Exam Schedule & Estimates of Number of Applicants for Generic Fundamentals Exams Through Cy 2003Generic Fundamentals Examination
ML20212F70514 September 1999Forwards Rev 19 to Ipn,Units 1 & 2 Physical Security Plan. Plan Withheld,Per 10CFR2.790(d) & 73.21
ML17355A4119 September 1999Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08Fire Barrier
ML17355A4137 September 1999Forwards 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
ML17355A4142 September 1999Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830
ML20211N0682 September 1999Informs 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
ML17265A74631 August 1999Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726
ML17265A74126 August 1999Forwards 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
ML17265A74026 August 1999Requests 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 ComponentsBoric Acid
Hydrostatic
Nondestructive Examination
VT-2
Code Reconciliation
Through-Wall Leakage
Dissimilar Metal Weld
ML20211H62926 August 1999Forwards 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
ML17355A40723 August 1999Informs 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.
ML17355A40423 August 1999Forwards 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
ML17355A40623 August 1999Forwards 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,IncludedFitness for Duty
ML17265A74523 August 1999Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d)Fitness for Duty
ML17250B30223 August 1999Informs 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
ML17355A40020 August 1999Informs 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 PerformanceFitness for Duty
ML20211E15318 August 1999Forwards Semi Annual fitness-for-duty Program Performance Data for 990101-990630,IAW 10CFR26.71(d)Fitness for Duty
ML20211H60518 August 1999Forwards 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
ML20211A92411 August 1999Informs 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
ML20211B78810 August 1999Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714Shutdown Margin
Missed surveillance
Large early release frequency
Thermal fatigue
ML17265A72730 July 1999Forwards 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
ML17355A39427 July 1999Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01
ML20210M72526 July 1999Forwards 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
ML17265A71523 July 1999Forwards 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
ML17265A70622 July 1999Forwards 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
ML17265A71421 July 1999Withdraws 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
ML17265A71921 July 1999Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999
ML20210G89120 July 1999Forwards Application for Amend to License DPR-5 for Proposed New TS 3.2.1.i,revising Senior Reactor License Requirement for Operations Manager
ML17355A38716 July 1999Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants
ML17265A70416 July 1999Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603
ML20209H69215 July 1999Forwards Comments on Preliminary Accident Sequence Precursor Analysis Provided in NRC Re Operational Condition Reported in LER 269/1998-04
ML17355A38514 July 1999Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of ReptOffsite Dose Calculation Manual
Annual Radiological Environmental Operating Report