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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20217L797 | 20 October 1999 | Submits Results of Review of 990521 & 0709 Ltrs Which Provided Core Shroud Insp Results & Tie Rod Stabilizer Assemblies | EVT-1 |
| ML20217G129 | 15 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 | |
| ML20217K283 | 14 October 1999 | Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001 | |
| ML20217H321 | 8 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 | |
| ML20212K860 | 6 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 | |
| ML18040A370 | 30 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 | Post Accident Monitoring Scram Discharge Volume Fuel cladding |
| ML20212K864 | 30 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 | |
| ML20212J883 | 30 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 | |
| ML20212J465 | 30 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 | |
| ML20216J931 | 30 September 1999 | Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions | Hydrostatic |
| ML20212E980 | 23 September 1999 | Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03 | Generic Fundamentals Examination |
| ML20216F710 | 17 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 | |
| ML20212D898 | 14 September 1999 | Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl | |
| ML20212B282 | 14 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 | Generic Fundamentals Examination |
| ML20212B258 | 10 September 1999 | Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List | |
| ML20211P577 | 10 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 | |
| ML20212A134 | 7 September 1999 | Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f | |
| ML20211K814 | 1 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 | |
| ML20211L922 | 1 September 1999 | Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC | |
| ML20211J646 | 30 August 1999 | Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity | |
| ML20211K300 | 30 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 | Offsite Dose Calculation Manual Process Control Program |
| ML20211K503 | 30 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 | |
| ML20211G492 | 26 August 1999 | Advises That Info Re Comments Addressing 10CFR2.206,dtd 990405 Will Be Withheld from Public Disclosure,In Response to | |
| ML20211H192 | 26 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 | |
| ML20211P516 | 26 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 | |
| ML20211D773 | 20 August 1999 | Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630 | Fitness for Duty |
| ML20211B937 | 18 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 | Safe Shutdown Safe Shutdown Earthquake Earthquake Backfit |
| ML18040A369 | 16 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. | High Radiation Area Post Accident Monitoring Hydrostatic |
| ML20210Q003 | 11 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 | |
| ML20210R810 | 10 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) | |
| ML20210R666 | 10 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 | Unanalyzed Condition Hydrostatic |
| ML20210L532 | 6 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 | |
| ML18041A071 | 30 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 | |
| ML20210J935 | 29 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 | |
| ML20216E149 | 26 July 1999 | Forwards Two Ltrs Received from NMPC Re Nine Mile Point Unit 1 Core Shroud Related to 10CFR2.206 | EVT-1 |
| ML20210E915 | 23 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 | |
| ML20209G791 | 12 July 1999 | Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions | Generic Fundamentals Examination |
| ML20209G371 | 12 July 1999 | Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1 | |
| ML20209G200 | 9 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) | |
| ML20211K507 | 6 July 1999 | Submits Concerns Re 990624 Event Involving Automatic Reactor Shutdown.More than 5 Failures Were Identified in Event Number 35857 | Safe Shutdown Packing leak High Radiation Area Non-Destructive Examination Slow transfer Water Inventory Control Hydrostatic Probabilistic Risk Assessment Nondestructive Examination Temporary Modification Locked High Radiation Area Condition Adverse to Quality Residual transfer Foreign Material Exclusion Scram Discharge Volume Frazil ice Earthquake Fire Protection Program Scaffolding |
| ML20209F856 | 6 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 | |
| ML20196J642 | 30 June 1999 | Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110 | |
| ML20209B707 | 30 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 | |
| ML20196K646 | 29 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 | |
| ML20211P527 | 29 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 | |
| ML20212J443 | 25 June 1999 | Discusses Responses to RAI Re GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity | |
| ML20209B353 | 25 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 | |
| ML20209B350 | 25 June 1999 | Submits Torus Shell & Coupon Corrosion Rate Determination for Nmpns,Unit 1.Torus Meets ASME Code Requirements,Iaw NRC 920825 & 940811 SERs | |
| ML20196F572 | 23 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 | |
| ML20196G146 | 23 June 1999 | Informs That Actions Requested in GL 96-01, Testing of Safety-Related Logic Circuits Completed |