ML20244E123
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L7971999-10-20020 October 1999
[Table view]Submits Results of Review of 990521 & 0709 Ltrs Which Provided Core Shroud Insp Results & Tie Rod Stabilizer Assemblies ML20217G1291999-10-15015 October 1999 Forwards Errata to Safety Evaluation for Amend 168 Issued to FOL DPR-63 on 990921.Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20217K2831999-10-14014 October 1999 Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001 ML20217H3211999-10-0808 October 1999 Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls ML20212K8601999-10-0606 October 1999 Responds to Concern in 990405 Petition Re Residual Heat Removal Alternate Shutdown Cooling Modes of Operation at Nine Mile Point Nuclear Station,Unit 2 ML20216J9311999-09-30030 September 1999 Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20212J4651999-09-30030 September 1999 Informs of Completion of mid-cyle PPR of Nine Mile Point Nuclear Station on 990916.Determined That Problems in Areas of Human Performance & Work Control Required Continued Mgt Attention.Historical Listing of Plant Issues Encl ML18040A3701999-09-30030 September 1999 Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs ML20212K8641999-09-30030 September 1999 Informs That During 990927 Telcon Between J Williams & J Bobka,Arrangements Were Made for Administration of Exams at Plant During Wk of Feb 14,2000.Preliminary RO & SRO License Applications Should Be Submitted 30 Days Prior Exam ML20212J8831999-09-30030 September 1999 Informs That Util 980810 & 990630 Responses to GL 98-01 & Suppl 1, Y2K Readiness of Computer Sys at NPPs Acceptable. NRC Considers Subj GL to Be Closed for Plant ML20212E9801999-09-23023 September 1999 Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03 ML20216F7101999-09-17017 September 1999 Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed ML20212B2821999-09-14014 September 1999 Responds to 990712 Correspondence Which Responded to NRC Ltr Re High Failure Rate for Generic Fundamentals Exam of 990407 for Nine Mile Point.Considers Corrective Actions Taken to Be Acceptable ML20212D8981999-09-14014 September 1999 Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl ML20212B2581999-09-10010 September 1999 Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List ML20211P5771999-09-10010 September 1999 Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld ML20212A1341999-09-0707 September 1999 Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f ML20211K8141999-09-0101 September 1999 Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met ML20211L9221999-09-0101 September 1999 Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC ML20211J6461999-08-30030 August 1999 Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity ML20211K3001999-08-30030 August 1999 Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1 ML20211K5031999-08-30030 August 1999 Responds to Ltr Addressed to Chairman Dicus, Expressing Concerns Involving 990624 Automatic Reactor Shutdown.Insp Findings & Conclusions Will Be Documented in Insp Repts 50-220/99-06 & 50-410/99-06 by mid-Sept 1999 ML20211H1921999-08-26026 August 1999 Forwards Application for Amend to License DPR-63,supporting Implementation of Noble Metal Chemical Addition by Raising Reactor Water Conductivity Limits in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b ML20211P5161999-08-26026 August 1999 Discusses Submitted on Behalf of Niagara Mohawk Power Corp Written Comments Addressing 10CFR2.206 Petition & Request That Ltr & Attached Response Be Withheld from Public Disclosure.Request Denied ML20211G4921999-08-26026 August 1999 Advises That Info Re Comments Addressing 10CFR2.206,dtd 990405 Will Be Withheld from Public Disclosure,In Response to ML20211D7731999-08-20020 August 1999 Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630 ML20211B9371999-08-18018 August 1999 Provides Addl Info Re Application of Method a at Nmp,Unit 1 as Described in Generic Implementation Procedure,Rev 2 (GIP-2),NRC Supplemental SER 2 & Documents Ref in GIP-2 Upon Which GIP-2 Is Based ML18040A3691999-08-16016 August 1999 Forwards Response to NRC 990510 RAI Pertaining to NMP Application for Amend Re Conversion of NMPNS Unit 2 Current TS to Its.Nrc Requested Info Re Several Sections,Including Section 3.6, Containment Sys. ML20210Q0031999-08-11011 August 1999 Informs That Due to Printing Malfunction,Some Copies of Author Ltr Dtd 990726,may Not Have Included Second Page of Encl 2 of Ltr ML20210R6661999-08-10010 August 1999 Confirms Conversation on 990721 Re Concerns of Syracuse Anti-Nuclear Effort on Status of 2.206 Petition (Filed 990524) & Upcoming NRC Performance Review Meeting on Nine Mile Point Units 1 & 2 ML20210R8101999-08-10010 August 1999 Forwards 1998 Annual Repts for NMP & co-tenants,including Rg&E,Energy East Corp/Nyse&G,Chg&E & Long Island Power Authority,Per 10CFR50.71(b) ML20210L5321999-08-0606 August 1999 Forwards List of Subjects Discussed During 990714 Telcon with Representatives of Niagara Mohawk Power Corp on Unit 1 Re USI A-46 Issue ML18041A0711999-07-30030 July 1999 Forwards Rev 1 to NMP2-ISI-006, Second Ten Year Interval ISI Program Plan for Nine Mile Point Nuclear Power Station Unit 2. Significant Changes from Rev 0 Listed ML20210J9351999-07-29029 July 1999 Informs That NMP Is Changing Completion Date for Replacement of Valves Having O Rings with Installed Life Greater than Eight Years.Replacement to Be Completed by 991031, During Hydrogen Monitoring Sys Maintenance Outage ML20216E1491999-07-26026 July 1999 Forwards Two Ltrs Received from NMPC Re Nine Mile Point Unit 1 Core Shroud Related to 10CFR2.206 ML20210E9151999-07-23023 July 1999 Discusses Evaluation of Recirculation Line Weld 32-WD-050 Indication Found During 1997 Refueling Outage (RFO14) at NMPNS Unit 1.Requests Notification of Decision to Retain Category F Classification Until Listed Conditions Satisfied ML20209G7911999-07-12012 July 1999 Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions ML20209G3711999-07-12012 July 1999 Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1 ML20209G2001999-07-0909 July 1999 Forwards RFO-15 Core Shroud Insp Summary Rept, as Required by GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs & BWRVIP Rept BWR Core Shroud Insp & Flaw Evaluation Guideline (BWRVIP-01) ML20209F8561999-07-0606 July 1999 Forwards Rev 1 to Nmp,Unit 1 COLR for Cycle 14. Rept Is Being Submitted to Commission in Compliance with TS 6.9.1.f.4 ML20211K5071999-07-0606 July 1999 Submits Concerns Re 990624 Event Involving Automatic Reactor Shutdown.More than 5 Failures Were Identified in Event Number 35857 ML20196J6421999-06-30030 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110 ML20209B7071999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Facilities,As Contained in GL 98-01,Supp 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure,Encl ML20211P5271999-06-29029 June 1999 Submits Written Comments Addressing Petition Dtd 990405, Submitted by R Norway as It Relates to Expressed Concerns That Involve NMPC Activities.None of Relief Requested in Petition Warranted ML20196K6461999-06-29029 June 1999 Discusses Ofc of Investigations Rept 1-98-33 Re Unqualified Senior Reactor Operator Assuming Position of Assistant Station Shift Supervisor at Unit 1 on 980616.One Violation Being Cited as Described in Encl NOV ML20209B3501999-06-25025 June 1999 Submits Torus Shell & Coupon Corrosion Rate Determination for Nmpns,Unit 1.Torus Meets ASME Code Requirements,Iaw NRC 920825 & 940811 SERs ML20212J4431999-06-25025 June 1999 Discusses Responses to RAI Re GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20209B3531999-06-25025 June 1999 Informs NRC That All Actions Associated with NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs, Has Been Completed.Summary of Actions Completed & Other Pertinent Info Is Provided in Attachment ML20196F5721999-06-23023 June 1999 Forwards Rev 3 to NMP1-IST-003, Third Ten Year Inservice Testing Program Plan, Which Will Begin on 991226.Program Plan Conforms to Requirements of 1989 Edition of ASME Boiler & Pressure Vessel Code.Three Relief Requests,Encl ML20196G1461999-06-23023 June 1999 Informs That Actions Requested in GL 96-01, Testing of Safety-Related Logic Circuits Completed 1999-09-07 Category:INTERNAL OR EXTERNAL MEMORANDUM MONTHYEARML20217E1501999-10-0707 October 1999
[Table view]Notification of 991022 Meeting with NMPC to Discuss Nine Mile Point Performance as Documented in Mid-Cycle PPR of Nine Mile Point Nuclear Station ML20216F5061999-09-16016 September 1999 Forwards 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 ML20210L6431999-08-0606 August 1999 Notification 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 ML20210C1631999-07-19019 July 1999 Forwards Monthly Rept Which Gives Status of 10CFR2.206 Petitions as of 990630.Six Open NRR,1 OE & 2 NMSS Petitions Available.Attachment 2 Withheld ML20195G6941999-06-0808 June 1999 Rev 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 ML20195C5081999-06-0303 June 1999 Submits 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 ML20207F2701999-05-25025 May 1999 Notification of 990608 Meeting with Licensee in King of Prussia,Pa to Discuss Licensee Recent Initiatives to Improve Corrective Action Program & Processes ML20206R3691999-05-0707 May 1999 Notification 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 ML20154D8211998-10-0505 October 1998 Forwards SE Accepting Licensee 980619 Submittal of Proposed Changes to PT Limits to Provide New Limits Valid to 28 EFPYs ML20151V1241998-09-0909 September 1998 Notification 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 05000220/19980031998-08-20020 August 1998 Forwards Exam Rept 50-220/98-03OL Administered on 980119-23 W/As Given Written Exam,Designated for Distribution ML20237C9501998-08-20020 August 1998 Forwards Facility Submitted Outline & Initial Exam Submittal W/As Given Operating Exam for Tests Administered on 980119- 23 ML20236X5631998-07-31031 July 1998 Discusses 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 ML20217F4411998-03-19019 March 1998 Forwards 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 ML20203A3041998-02-0606 February 1998 Notification 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 ML20199C0771998-01-23023 January 1998 Corrected 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 ML20198J4911998-01-0606 January 1998 Notification 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 ML20202B2321997-12-0101 December 1997 Responds 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 ML20217E8371997-10-0101 October 1997 Notification 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 ML20202B1451997-09-24024 September 1997 Discusses Response to Nine Mile Point on Blow Out Panels ML20199J0971997-08-21021 August 1997 Emails Info Re Plant Blowout Panels ML20149F1531997-07-16016 July 1997 Forwards NRC Approved Operator Licensing Written Retake Exam (Facility Outline & Initial Exam Submittal) for Tests Administered on 970606 ML20199J1041997-07-0707 July 1997 Emails Util Ltr for concurrence,EA-96-079.Comments Requested ML20202B1721997-07-0707 July 1997 Requests Concurrence on by 970714.Partially Withheld ML20138C7071997-04-29029 April 1997 Forwards 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 ML20140C4811997-04-11011 April 1997 Discusses 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 Rods ML20137S3611997-04-0303 April 1997 Notification 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 ML20137L4441997-04-0303 April 1997 Notification 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 ML20147H6501997-04-0101 April 1997 Forwards Copies of Core Shroud Insp Results & Schedules That Licensee Has Telecopied to NRC Staff Since 970320 ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20147D7251997-02-0707 February 1997 Forwards from Mj Mccormick Requesting Data from NRC Sponsored Tests on Pressure Locking of motor-operated Gate Valves ML20133J4681997-01-13013 January 1997 Discusses 961114 AEOD Presentation of Assessment of Spent Fuel Cooling Viewgraph 13, Reduced Time to Boil at Nine Mile Point Unit 2, & Forwards Figures ML20203J4821997-01-0303 January 1997 Forwards SE Re Reactor & Turbine Building blow-out Panels IA-97-375, Forwards SE Re Reactor & Turbine Building blow-out Panels1997-01-0303 January 1997 Forwards SE Re Reactor & Turbine Building blow-out Panels ML20203J4611997-01-0202 January 1997 Forwards SE Accepting Subj Panels as Modified & Supported by Discussed Engineering Analysis Results ML20135C6361996-12-0404 December 1996 Forwards Signed Original of Order Imposing Monetary Penalty for Plant,Unit 1.W/o Encl ML20129K2561996-11-0505 November 1996 Notification 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 ML20129J4781996-11-0404 November 1996 Summarizes 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 Encl ML20199J0911996-05-0101 May 1996 Requests Technical Assistance Supplement 1,in Determining If Util Interpretation Re Reactor & Turbine Bldgs Blowout Panels,Per 10CFR50.59 SE Requirements ML20199J0841996-03-13013 March 1996 Submits 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 Encl1994-06-29029 June 1994 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 Encl ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant IR 05000220/19860171989-05-24024 May 1989 Advises 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 ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B6421989-04-15015 April 1989 Forwards 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 ML20245B6191989-04-15015 April 1989 Forwards 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 ML20245B7501989-04-15015 April 1989 Forwards 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 ML20246G9211989-02-24024 February 1989 Documents 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 Room1988-05-0202 May 1988 Forwards Ltr Received by Chairman Zech on 880428 Re Allegations of Drunk Employee in Control Room ML20247N5151988-05-0202 May 1988 Forwards Ltr Received by Chairman Zech on 880428 Re Allegations of Drunk Employee in Control Room 1999-09-16 Category:MEMORANDUMS-CORRESPONDENCE MONTHYEARML20217E1501999-10-0707 October 1999
[Table view]Notification of 991022 Meeting with NMPC to Discuss Nine Mile Point Performance as Documented in Mid-Cycle PPR of Nine Mile Point Nuclear Station ML20216F5061999-09-16016 September 1999 Forwards 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 ML20210L6431999-08-0606 August 1999 Notification 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 ML20210C1631999-07-19019 July 1999 Forwards Monthly Rept Which Gives Status of 10CFR2.206 Petitions as of 990630.Six Open NRR,1 OE & 2 NMSS Petitions Available.Attachment 2 Withheld ML20195G6941999-06-0808 June 1999 Rev 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 ML20195C5081999-06-0303 June 1999 Submits 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 ML20207F2701999-05-25025 May 1999 Notification of 990608 Meeting with Licensee in King of Prussia,Pa to Discuss Licensee Recent Initiatives to Improve Corrective Action Program & Processes ML20206R3691999-05-0707 May 1999 Notification 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 ML20154D8211998-10-0505 October 1998 Forwards SE Accepting Licensee 980619 Submittal of Proposed Changes to PT Limits to Provide New Limits Valid to 28 EFPYs ML20151V1241998-09-0909 September 1998 Notification 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 05000220/19980031998-08-20020 August 1998 Forwards Exam Rept 50-220/98-03OL Administered on 980119-23 W/As Given Written Exam,Designated for Distribution ML20237C9501998-08-20020 August 1998 Forwards Facility Submitted Outline & Initial Exam Submittal W/As Given Operating Exam for Tests Administered on 980119- 23 ML20236X5631998-07-31031 July 1998 Discusses 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 ML20217F4411998-03-19019 March 1998 Forwards 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 ML20203A3041998-02-0606 February 1998 Notification 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 ML20199C0771998-01-23023 January 1998 Corrected 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 ML20198J4911998-01-0606 January 1998 Notification 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 ML20202B2321997-12-0101 December 1997 Responds 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 ML20217E8371997-10-0101 October 1997 Notification 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 ML20202B1451997-09-24024 September 1997 Discusses Response to Nine Mile Point on Blow Out Panels ML20199J0971997-08-21021 August 1997 Emails Info Re Plant Blowout Panels ML20149F1531997-07-16016 July 1997 Forwards NRC Approved Operator Licensing Written Retake Exam (Facility Outline & Initial Exam Submittal) for Tests Administered on 970606 ML20202B1721997-07-0707 July 1997 Requests Concurrence on by 970714.Partially Withheld ML20199J1041997-07-0707 July 1997 Emails Util Ltr for concurrence,EA-96-079.Comments Requested ML20138C7071997-04-29029 April 1997 Forwards 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 ML20140C4811997-04-11011 April 1997 Discusses 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 Rods ML20137S3611997-04-0303 April 1997 Notification 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 ML20137L4441997-04-0303 April 1997 Notification 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 ML20147H6501997-04-0101 April 1997 Forwards Copies of Core Shroud Insp Results & Schedules That Licensee Has Telecopied to NRC Staff Since 970320 ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20147D7251997-02-0707 February 1997 Forwards from Mj Mccormick Requesting Data from NRC Sponsored Tests on Pressure Locking of motor-operated Gate Valves ML20133J4681997-01-13013 January 1997 Discusses 961114 AEOD Presentation of Assessment of Spent Fuel Cooling Viewgraph 13, Reduced Time to Boil at Nine Mile Point Unit 2, & Forwards Figures IA-97-375, Forwards SE Re Reactor & Turbine Building blow-out Panels1997-01-0303 January 1997 Forwards SE Re Reactor & Turbine Building blow-out Panels ML20203J4821997-01-0303 January 1997 Forwards SE Re Reactor & Turbine Building blow-out Panels ML20203J4611997-01-0202 January 1997 Forwards SE Accepting Subj Panels as Modified & Supported by Discussed Engineering Analysis Results ML20135C6361996-12-0404 December 1996 Forwards Signed Original of Order Imposing Monetary Penalty for Plant,Unit 1.W/o Encl ML20129K2561996-11-0505 November 1996 Notification 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 ML20129J4781996-11-0404 November 1996 Summarizes 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 Encl ML20199J0911996-05-0101 May 1996 Requests Technical Assistance Supplement 1,in Determining If Util Interpretation Re Reactor & Turbine Bldgs Blowout Panels,Per 10CFR50.59 SE Requirements ML20199J0841996-03-13013 March 1996 Submits 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 Encl1994-06-29029 June 1994 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 Encl ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20245L5981989-08-17017 August 1989 Staff Requirements Memo on 890802 Briefing in Rockville,Md Re Status of Nine Mile Point Unit 1 IR 05000220/19860171989-05-24024 May 1989 Advises 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 ML20245B7501989-04-15015 April 1989 Forwards 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 ML20245B6191989-04-15015 April 1989 Forwards 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 ML20245B6421989-04-15015 April 1989 Forwards 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 ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20246G9211989-02-24024 February 1989 Documents 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 Room1988-05-0202 May 1988 Forwards Ltr Received by Chairman Zech on 880428 Re Allegations of Drunk Employee in Control Room 1999-09-16 Category:NRC TO ACRS MONTHYEARML20244E2231974-07-0303 July 1974
[Table view]Forwards SER Re Niagara Mohawk Power Corp Application for full-term OL for Util.Acrs Review Complete Except Unresolved Items Listed.Complete Rev of Tech Specs Indicated in Subj SER ML20235E9251972-12-21021 December 1972 Forwards to Applicants Re Consequences of Postulated Pipe Failures Outside Containment Structure ML20244B0861971-01-27027 January 1971 Forwards Rept 2 to Acrs,Nine Mile Point Nuclear Station Power Increase, for Review by ACRS ML20244E1631970-11-23023 November 1970 Forwards Rept on Niagara Mohawk Power Corp Application for Power Increase for Nine Mile Point Nuclear Station for ACRS Review ML20244E1411970-05-0202 May 1970 Forwards H Denton to RW Staehle Re Recommendations for Course of Action to Be Taken for Repair of Safe Ends on Reactor Vessels of Utils for Committee Use ML20244E1231969-04-0303 April 1969 Forwards CF Cheng 690324 Rept, Corrosion Evaluation - Nine Mile Point Reactor Vessel, for Committee Info ML20244E0261969-03-17017 March 1969 Forwards ORNL EC Miller & P Patraiarca 690307 Consulting Rept on Util Reactor Vessel for Committee Review ML20244D9791969-02-20020 February 1969 Forwards AEC Requesting Licensee to Furnish Info Re Repair & Insp of Defective Stub Tube Field Welds & Plans for Implementing Surveillance Program for Util Pressure Vessel Sensitized Stainless Steel Matl ML20244D5121968-08-16016 August 1968 Forwards AEC Requesting Util to Furnish Info Re Design Mods Made to Control Rod Drive Hydraulic Line Penetrations to Util Primary Containment,For Info ML20244D5531968-08-13013 August 1968 Requests for Info Listed Re Design Mods to Control Rod Drive Hydraulic Line Penetrations to Util Primary Containment ML20244D4851968-08-0808 August 1968 Forwards AEC to Util Requesting Addl Info Re Facility Electrical Sys,Instrument Air Sys & Actuation Signals for ESF ML20244D4711968-06-20020 June 1968 Forwards AEC W/List of Comments Re Addl Info Required About Seismic Design,Transient Analysis & Accident Design Considerations ML20244C8251968-02-21021 February 1968 Forwards AEC Requesting Addl Info Re Quality Control Program,Design Changes,Instrumentation,Etc ML20244C8161968-01-0909 January 1968 Forwards Environ Science Svcs Administration 671218 Comments on FSAR & Amend 3 to Niagara Mohawk Application for Provisional OL for Review ML20244C8101967-12-15015 December 1967 Forwards Fish & Wildlife Svc 671206 Comments on Niagara Mohawk Power Corp Application for Provisional Ol,Fsar,Vols I & II Dtd June 1967 for Review ML20244C7761964-10-14014 October 1964 Forwards Us Weather Bureau 641006 Comments on Licensee First Suppl to Preliminary Hazards Summary Rept Nine Mile Point Nuclear Station, Dtd Aug 1964 ML20244C7121964-06-0808 June 1964 Forwards for Committee Use, Niagara Mohawk Power Co, Preliminary Hazards Summary Rept - Nine Mile Point Nuclear Station, Vol I & II, Us Weather Bureau Comments on Hazards Summary Rept 1974-07-03 |
Text
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UNITED STATES ATOMIC ENERGY COMMISSION
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- I WASHINGTON. D.C. 20545 April 3, 1969
- - Docket No. 50-220 l
Dr. Stephen H. Hanauer
- Chairman, Advisory' Committee
!< on Reactor Safeguards U. S. Atomic Energy Commission Washington,-D. C. 20545 i
Dear Dr. Hanauer:
i Eighteen copies of the following are transmitted f for the information of the Committee:
L
'$ NIAGARA MOHAWK PO'.ER CORPORATION i (Nine Mile Point Nuclear Station)
Report entitled " Corrosion Evaluation - Nine Mile.- r, j Point Reactor Vessel," by Craig F. Cheng, ANL,. G i (dated March 24, 1969 ; r i j .
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$ Sincerely, t
4 eau Peter A. Morris, Director Division of Reactor Licensing
Enclosures:
As stated r f ~. p"' *2 r;.
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r 8904240305 890413
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