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 Issue dateTitleTopic
ML20217E1507 October 1999Notification of 991022 Meeting with NMPC to Discuss Nine Mile Point Performance as Documented in Mid-Cycle PPR of Nine Mile Point Nuclear Station
ML20216F50616 September 1999Forwards Monthly Rept on Status of 10CFR2.206 Petitions as of 990831.During August,Director'S Decision (DD-99-10) on Seabrook Issued & Petition Closed.Six Petitions Open,Five in NRR & One in Nmss.Attachment 2 Withheld
ML20210L6436 August 1999Notification of 990901 Meeting with NMP in Rockville,Md to Discuss NMP Plans to File Application Re Transfer of Interest & Authorities Under Plant Licenses to Amergen
ML20210C16319 July 1999Forwards Monthly Rept Which Gives Status of 10CFR2.206 Petitions as of 990630.Six Open NRR,1 OE & 2 NMSS Petitions Available.Attachment 2 Withheld
ML20195G6948 June 1999Rev 1,rescheduling Notification of 990625 Licensee Meeting 99-32 in King of Prussia,Pa with Util to Discuss Recent Plant Initiatives to Improve Corrective Action Program & Processes
ML20195C5083 June 1999Submits Summary of 990527 Telcon Between J Rajan of NRC & K Korcz of Niagara Mohawk Power Co Re Util Requesting NRC Approval of Proposed Mod to Upper Spring Assembly of Four Core Shroud Tie Rods
ML20207F27025 May 1999Notification of 990608 Meeting with Licensee in King of Prussia,Pa to Discuss Licensee Recent Initiatives to Improve Corrective Action Program & Processes
ML20206R3697 May 1999Notification of Significant Licensee Meeting 99-24 with Util Current Employee on 990513 to Discuss Apparent Violation of 10CFR55,noted in NRC Correspondence to Individual Ref OI Rept 1-1998-033
ML20154D8215 October 1998Forwards SE Accepting Licensee 980619 Submittal of Proposed Changes to PT Limits to Provide New Limits Valid to 28 EFPYs
ML20151V1249 September 1998Notification of 980924 Meeting W/Util & Public in Oswego,Ny to Review NMPC Request to Extend Current Core Shroud Vertical Weld Insp Interval & to Receive Comments/Questions Re NMPC Request to Extend Unit 1 Core Shroud Vertical Weld
IR 05000220/199800320 August 1998Forwards Exam Rept 50-220/98-03OL Administered on 980119-23 W/As Given Written Exam,Designated for Distribution
ML20237C95020 August 1998Forwards Facility Submitted Outline & Initial Exam Submittal W/As Given Operating Exam for Tests Administered on 980119- 23
ML20236X56331 July 1998Discusses NMP & Several Supporting Ltrs, Requesting That NRC Authorize Extension of Insp Interval for Cracks in Plant,Unit 1 Core Shroud Welds from 10,600 Hot Operating H to 14,500 Hot Operating H
ML20217F44119 March 1998Forwards Order Approving Application Re Acquisition of New York State Electric & Gas Corp by Holding Co Affecting License NPF-69,Nine Mile Point Nuclear Station,Unit 2 for Fr Publication
ML20203A3046 February 1998Notification of 980224 Meeting W/Niagara Mohawk Power Corp in Rockville,Md to Discuss Schedules for Current & Projected Licensing Actions & Licensing Activities for Project Mgt Purposes
ML20199C07723 January 1998Corrected Notification of 980128 Meeting W/Nmp in Rockville, Md,To Disduss NRC Position That Exceeding Relief Pressures Stated in FSAR Design Bases for Blowout Panels of Reactor & Turbine Bldgs Should Have Been Reported in 1993
ML20198J4916 January 1998Notification of 980128 Meeting W/Nmp in Rockville,Md to Discuss NRC Position That Exceeding Relief Pressure Stated in FSAR Design Bases for Blowout Panels of Reactor & Turbine Bldgs That Should Have Been Reported to NRC in 1993
ML20202B2321 December 1997Responds to 960313 Memo Requesting NRR Technical Assistance to Determine Adequacy of NMPC Revised Design Calculations for Reactor Bldg & Turbine Bldg Pressure Relief (or Blowout) Panels.Partially Withheld
ML20217E8371 October 1997Notification of 971009 Meeting W/Util in Rockville,Md to Discuss Mgt Aspects of Current & Pending Licensing Activities,Including Plans to Convert Unit 2 to Improved Std TSs Plans Re Unit 1 Core Shroud Insp & Associated Schedule
ML20202B14524 September 1997Discusses Response to Nine Mile Point on Blow Out Panels
ML20199J09721 August 1997Emails Info Re Plant Blowout Panels
ML20149F15316 July 1997Forwards NRC Approved Operator Licensing Written Retake Exam (Facility Outline & Initial Exam Submittal) for Tests Administered on 970606
ML20199J1047 July 1997Emails Util Ltr for concurrence,EA-96-079.Comments Requested
ML20202B1727 July 1997Requests Concurrence on by 970714.Partially Withheld
ML20138C70729 April 1997Forwards Summary for Two Public Meetings Held W/Nmp on 970414 to Discuss Core Shroud Issues at Plant,Unit 1.Copies of Subj Meeting Videotape Have Been Sent to PDR
ML20140C48111 April 1997Discusses Exams of Core Shroud Welds & Tie Rod Repair Assemblies Conducted During Current Refueling Outage at Plant,Unit 1 & Initiation of Adjustments to One of Core Tie RodsSafe Shutdown
Probabilistic Risk Assessment
Nondestructive Examination
ML20137S3613 April 1997Notification of Cancelled 970410 Meeting W/Util in Rockville Md,Rescheduled on 970414 in Oswego,Ny,To Discuss Evaluations & Conclusions Re Core Shroud Integrity in View of Insp Results That Revealed Cracks in Heat Affected Zones
ML20137L4443 April 1997Notification of 970410 Meeting W/Util in Rockville,Md to Discuss Evaluations & Conclusions Re Core Shroud Integrity in View of Insp Results Revealing Cracks in Heat Affected Zones of Horizontal & Vertical Welds
ML20147H6501 April 1997Forwards Copies of Core Shroud Insp Results & Schedules That Licensee Has Telecopied to NRC Staff Since 970320
ML20136C1036 March 1997Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR
ML20147D7257 February 1997Forwards from Mj Mccormick Requesting Data from NRC Sponsored Tests on Pressure Locking of motor-operated Gate Valves
ML20133J46813 January 1997Discusses 961114 AEOD Presentation of Assessment of Spent Fuel Cooling Viewgraph 13, Reduced Time to Boil at Nine Mile Point Unit 2, & Forwards FiguresTime to boil
ML20203J4823 January 1997Forwards SE Re Reactor & Turbine Building blow-out Panels
IA-97-375, Forwards SE Re Reactor & Turbine Building blow-out Panels3 January 1997Forwards SE Re Reactor & Turbine Building blow-out Panels
ML20203J4612 January 1997Forwards SE Accepting Subj Panels as Modified & Supported by Discussed Engineering Analysis Results
ML20135C6364 December 1996Forwards Signed Original of Order Imposing Monetary Penalty for Plant,Unit 1.W/o Encl
ML20129K2565 November 1996Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness
ML20129J4784 November 1996Summarizes 961030 Operating Reactors Events Briefing 96-14 Re Notification of Senior Managers from Commission,Oe,Aeod, Res,Nrr & Regional Offices of Selected Events That Occurred Since 961023 Briefing.List of Attendees EnclForeign Material Exclusion
ML20199J0911 May 1996Requests Technical Assistance Supplement 1,in Determining If Util Interpretation Re Reactor & Turbine Bldgs Blowout Panels,Per 10CFR50.59 SE Requirements
ML20199J08413 March 1996Submits Request for Technical Assistance to Determine Technical Adequacy of Util Revised Design Calculations for Reactor & Turbine Bldgs Blowout Panels
NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl29 June 1994Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl
ML20056E4575 August 1993Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant
IR 05000220/198601724 May 1989Advises That Insp Rept 50-220/86-17 Re Installation of non-safety Grade Connectors Addresses Technical Significance of Allegations That Ellison Willfully Installed Uncertified Connectors.Civil Penalty of $50,000 Issued to Util
ML20245B65315 April 1989Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys
ML20245B64215 April 1989Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart
ML20245B61915 April 1989Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both
ML20245B75015 April 1989Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart
ML20246G92124 February 1989Documents Info Re Ellison Background/Character Re Alleged Storage of Radioactive Matl in Home,Conviction for Sex Crimes & Trouble in Florida W/Girlfriend
IA-89-305, Forwards Ltr Received by Chairman Zech on 880428 Re Allegations of Drunk Employee in Control Room2 May 1988Forwards Ltr Received by Chairman Zech on 880428 Re Allegations of Drunk Employee in Control Room
ML20247N5152 May 1988Forwards Ltr Received by Chairman Zech on 880428 Re Allegations of Drunk Employee in Control Room