Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L7971999-10-20020 October 1999
Submits Results of Review of 990521 & 0709 Ltrs Which Provided Core Shroud Insp Results & Tie Rod Stabilizer Assemblies
ML20217M1851999-10-19019 October 1999
Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates
JPN-99-035, Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 11999-10-15015 October 1999
Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 1
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
JPN-99-034, Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping1999-10-13013 October 1999
Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping
JPN-99-033, Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon1999-10-0808 October 1999
Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon
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
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
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
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
JPN-99-030, Forwards Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases to Extend LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days1999-09-29029 September 1999
Forwards Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases to Extend LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days
JPN-99-032, Forwards Info Re Potential Environ Effects of Alternatives to Proposed Expansion of FitzPatrick Spent Fuel Pool,In Response to NRC Project Manager Request1999-09-29029 September 1999
Forwards Info Re Potential Environ Effects of Alternatives to Proposed Expansion of FitzPatrick Spent Fuel Pool,In Response to NRC Project Manager Request
ML20212E9801999-09-23023 September 1999
Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03
ML20212F8341999-09-22022 September 1999
Forwards Insp Rept 50-333/99-07 on 990718-0828.No Violations Noted
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
JAFP-99-0262, Forwards Voluntary Response to Administrative Ltr 99-03, Re Preparation & Scheduling of Operator Licensing Exams. Completed NRC Form 536,containing Info Re Proposed Exam Preparation Schedule & Initial Operator License Exams,Encl1999-09-16016 September 1999
Forwards Voluntary Response to Administrative Ltr 99-03, Re Preparation & Scheduling of Operator Licensing Exams. Completed NRC Form 536,containing Info Re Proposed Exam Preparation Schedule & Initial Operator License Exams,Encl
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
ML20212A8341999-09-0909 September 1999
Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics
ML20212A6951999-09-0909 September 1999
Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics
JAFP-99-0258, Forwards Operator License Restriction Change for Tj Pelton, License SOP-10090-3.License Is Requested to Be Reissued with Restriction for Corrective Lenses.Encl Withheld1999-09-0808 September 1999
Forwards Operator License Restriction Change for Tj Pelton, License SOP-10090-3.License Is Requested to Be Reissued with Restriction for Corrective Lenses.Encl Withheld
05000333/LER-1998-015, Forwards LER 98-015-02 Re Logic Sys Functional Test Inadequacies,Per 10CFR50.73(A)(2)(i)(B).Rept Revised to Reflect Scheduled Completion Date for Corrective Action 3 of Jan 15, 2000 & Updates Status of Other C/As as Complete1999-09-0808 September 1999
Forwards LER 98-015-02 Re Logic Sys Functional Test Inadequacies,Per 10CFR50.73(A)(2)(i)(B).Rept Revised to Reflect Scheduled Completion Date for Corrective Action 3 of Jan 15, 2000 & Updates Status of Other C/As as Complete
ML20211N4301999-09-0808 September 1999
Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues
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
JPN-99-028, Informs That Util Requires Extension from 990901 to 1015,to Complete Review of Rvid & Forward Comments to Nrc,Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity1999-08-30030 August 1999
Informs That Util Requires Extension from 990901 to 1015,to Complete Review of Rvid & Forward Comments to Nrc,Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity
JAFP-99-0247, Forwards JAFNPP Effluent & Waste Disposal Semi-Annual Rept for 990101-0630, IAW Amend 93,App B,Section 7.3.C of Plant Ts.Format Used for Rept Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 41999-08-26026 August 1999
Forwards JAFNPP Effluent & Waste Disposal Semi-Annual Rept for 990101-0630, IAW Amend 93,App B,Section 7.3.C of Plant Ts.Format Used for Rept Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 4
ML20211G4921999-08-26026 August 1999
Advises That Info Re Comments Addressing 10CFR2.206,dtd 990405 Will Be Withheld from Public Disclosure,In Response to
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
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
ML20211D7731999-08-20020 August 1999
Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630
JAFP-99-0245, Informs That Two Licensed Operators Have Returned to Site Upon Release for Normal Duties by Physician.R Korthas, License OP-11159,meets ANSI Std 3.4-1983 & R Sarkissian License SOP-10007-3,was Terminated in Mar 19991999-08-19019 August 1999
Informs That Two Licensed Operators Have Returned to Site Upon Release for Normal Duties by Physician.R Korthas, License OP-11159,meets ANSI Std 3.4-1983 & R Sarkissian License SOP-10007-3,was Terminated in Mar 1999
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.
ML20210U2621999-08-12012 August 1999
Forwards Insp Rept 50-333/99-06 on 990601-0717.No Violations Noted
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
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)
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
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
JPN-99-025, Forwards Relief Request 17 Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) for Reactor Pressure Vessel Circumferential Shell Weld Exams1999-08-0505 August 1999
Forwards Relief Request 17 Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) for Reactor Pressure Vessel Circumferential Shell Weld Exams
1999-09-09
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARJPN-99-035, Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 11999-10-15015 October 1999
Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 1
ML20217K2831999-10-14014 October 1999
Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001
JPN-99-034, Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping1999-10-13013 October 1999
Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping
JPN-99-033, Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon1999-10-0808 October 1999
Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon
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
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
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
JPN-99-032, Forwards Info Re Potential Environ Effects of Alternatives to Proposed Expansion of FitzPatrick Spent Fuel Pool,In Response to NRC Project Manager Request1999-09-29029 September 1999
Forwards Info Re Potential Environ Effects of Alternatives to Proposed Expansion of FitzPatrick Spent Fuel Pool,In Response to NRC Project Manager Request
JPN-99-030, Forwards Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases to Extend LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days1999-09-29029 September 1999
Forwards Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases to Extend LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days
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
JAFP-99-0262, Forwards Voluntary Response to Administrative Ltr 99-03, Re Preparation & Scheduling of Operator Licensing Exams. Completed NRC Form 536,containing Info Re Proposed Exam Preparation Schedule & Initial Operator License Exams,Encl1999-09-16016 September 1999
Forwards Voluntary Response to Administrative Ltr 99-03, Re Preparation & Scheduling of Operator Licensing Exams. Completed NRC Form 536,containing Info Re Proposed Exam Preparation Schedule & Initial Operator License Exams,Encl
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
05000333/LER-1998-015, Forwards LER 98-015-02 Re Logic Sys Functional Test Inadequacies,Per 10CFR50.73(A)(2)(i)(B).Rept Revised to Reflect Scheduled Completion Date for Corrective Action 3 of Jan 15, 2000 & Updates Status of Other C/As as Complete1999-09-0808 September 1999
Forwards LER 98-015-02 Re Logic Sys Functional Test Inadequacies,Per 10CFR50.73(A)(2)(i)(B).Rept Revised to Reflect Scheduled Completion Date for Corrective Action 3 of Jan 15, 2000 & Updates Status of Other C/As as Complete
JAFP-99-0258, Forwards Operator License Restriction Change for Tj Pelton, License SOP-10090-3.License Is Requested to Be Reissued with Restriction for Corrective Lenses.Encl Withheld1999-09-0808 September 1999
Forwards Operator License Restriction Change for Tj Pelton, License SOP-10090-3.License Is Requested to Be Reissued with Restriction for Corrective Lenses.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
JPN-99-028, Informs That Util Requires Extension from 990901 to 1015,to Complete Review of Rvid & Forward Comments to Nrc,Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity1999-08-30030 August 1999
Informs That Util Requires Extension from 990901 to 1015,to Complete Review of Rvid & Forward Comments to Nrc,Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity
JAFP-99-0247, Forwards JAFNPP Effluent & Waste Disposal Semi-Annual Rept for 990101-0630, IAW Amend 93,App B,Section 7.3.C of Plant Ts.Format Used for Rept Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 41999-08-26026 August 1999
Forwards JAFNPP Effluent & Waste Disposal Semi-Annual Rept for 990101-0630, IAW Amend 93,App B,Section 7.3.C of Plant Ts.Format Used for Rept Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 4
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
ML20211D7731999-08-20020 August 1999
Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630
JAFP-99-0245, Informs That Two Licensed Operators Have Returned to Site Upon Release for Normal Duties by Physician.R Korthas, License OP-11159,meets ANSI Std 3.4-1983 & R Sarkissian License SOP-10007-3,was Terminated in Mar 19991999-08-19019 August 1999
Informs That Two Licensed Operators Have Returned to Site Upon Release for Normal Duties by Physician.R Korthas, License OP-11159,meets ANSI Std 3.4-1983 & R Sarkissian License SOP-10007-3,was Terminated in Mar 1999
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.
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)
JPN-99-026, Forwards Relief Requests 18 & 19 to Jaf ISI Program Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) & Relief from ASME Section XI Code Re Insp of RPV Vertical Shell & Shell to Flange Welds1999-08-0505 August 1999
Forwards Relief Requests 18 & 19 to Jaf ISI Program Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) & Relief from ASME Section XI Code Re Insp of RPV Vertical Shell & Shell to Flange Welds
JPN-99-025, Forwards Relief Request 17 Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) for Reactor Pressure Vessel Circumferential Shell Weld Exams1999-08-0505 August 1999
Forwards Relief Request 17 Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) for Reactor Pressure Vessel Circumferential Shell Weld Exams
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
JAFP-99-0229, Forwards Three Sets of Corrected Summaries of Changes for Inclusion Into Security Plan for Ja FitzPatrick Nuclear Power Plant,Rev 19 & Security Contingency Plan,Rev 5.Encls Withheld Per 10CFR73.21 & 10CFR2.790)d)(1)1999-07-22022 July 1999
Forwards Three Sets of Corrected Summaries of Changes for Inclusion Into Security Plan for Ja FitzPatrick Nuclear Power Plant,Rev 19 & Security Contingency Plan,Rev 5.Encls Withheld Per 10CFR73.21 & 10CFR2.790)d)(1)
JAFP-99-0228, Forwards Rept Re Changes & Errors in ECCS Evaluation Models, Per 10CFR50.46(a)(3)(ii) for Period from 980701-990630.No Commitments Contained in Submittal1999-07-21021 July 1999
Forwards Rept Re Changes & Errors in ECCS Evaluation Models, Per 10CFR50.46(a)(3)(ii) for Period from 980701-990630.No Commitments Contained in Submittal
JAFP-99-0208, Provides Clarification of Info Re Proposed Its, & 0601.Table Reconciling Differences,Encl1999-07-14014 July 1999
Provides Clarification of Info Re Proposed Its, & 0601.Table Reconciling Differences,Encl
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
ML20209G7911999-07-12012 July 1999
Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions
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
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
ML20210C9031999-06-30030 June 1999
Summarizes Impact of Changes & Errors in Methodology Used by GE to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.Summary of Changes & Errors Provided in Attached Table
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
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
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
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
1999-09-08
[Table view]
Category:UTILITY TO NRC
MONTHYEARJPN-90-063, Responds to NRC Re Deviations Noted in Insp Rept 50-333/90-19.Interim Corrective Action:Temporary Procedure Change Implemented to Administratively Prohibit Concurrent Closure of Upstream Feeder Breakers Until Issue Resolved1990-09-18018 September 1990
Responds to NRC Re Deviations Noted in Insp Rept 50-333/90-19.Interim Corrective Action:Temporary Procedure Change Implemented to Administratively Prohibit Concurrent Closure of Upstream Feeder Breakers Until Issue Resolved
JPN-90-061, Forwards Analyses Re Installation of Hardened Wetwell Vent, Including Benefits of Elevated Vs Ground Level Gas Release. Analyses Provide Further Evidence That Addition of Elevated Release to Existing Hardened Vent Not Cost Beneficial1990-09-0707 September 1990
Forwards Analyses Re Installation of Hardened Wetwell Vent, Including Benefits of Elevated Vs Ground Level Gas Release. Analyses Provide Further Evidence That Addition of Elevated Release to Existing Hardened Vent Not Cost Beneficial
JPN-90-060, Forwards Info to Satisfy 900716 Commitment Re Switchgear Deficiency,Per SSFI Insp Rept 50-333/89-80.Waiver Requested Re Design Requirements for Three Phase Bolted Fault Criteria for Switchgear Configuration for Diesel Generator Testing1990-09-0404 September 1990
Forwards Info to Satisfy 900716 Commitment Re Switchgear Deficiency,Per SSFI Insp Rept 50-333/89-80.Waiver Requested Re Design Requirements for Three Phase Bolted Fault Criteria for Switchgear Configuration for Diesel Generator Testing
ML17056A9771990-08-30030 August 1990
Forwards Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Revs 4 & 5 to Odcm.
ML18038A3231990-08-30030 August 1990
Forwards Semiannual Radioactive Effluent Release Rept Jan- June 1990 & Revs 6-8 to Odcm. Radioactive Effluent Release Rept Includes Summary of Liquid,Gaseous & Solid Effluents & Justification for Revs to ODCM
ML18038A3221990-08-24024 August 1990
Forwards NRC Form 474, Simulation Facility Certification & Supporting Documentation
ML18038A3201990-08-21021 August 1990
Discusses Status of Completion of Generic Safety Issue 75, Item 2.2.2 Re Vendor Interface for safety-related Components
ML18038A3251990-08-20020 August 1990
Forwards Rev 3 to Nine Mile Point Requalification Program Action Plan, Certifying That All short-term Corrective Actions Completed
ML20058Q1151990-08-15015 August 1990
Forwards Response to Regulatory Effectiveness Review on 900604-08.Response Withheld (Ref 10CFR73.21)
JPN-90-057, Forwards GE Supplemental Rept of Ultrasonic Indications in Top Head Weld VC-TH-1-2 at Ja Fitzpatrick Power Station1990-08-14014 August 1990
Forwards GE Supplemental Rept of Ultrasonic Indications in Top Head Weld VC-TH-1-2 at Ja Fitzpatrick Power Station
JAFP-90-0581, Forwards Proposed Rev 6 to IAP-2, Classification of Emergency Conditions, Per Insp Rept 50-333/90-15,Unresolved Item 89-11-03.Rev Incorporates Changes Assuring That Applicable Initiating Conditions,Per NUREG-0654,addressed1990-07-30030 July 1990
Forwards Proposed Rev 6 to IAP-2, Classification of Emergency Conditions, Per Insp Rept 50-333/90-15,Unresolved Item 89-11-03.Rev Incorporates Changes Assuring That Applicable Initiating Conditions,Per NUREG-0654,addressed
JPN-90-055, Forwards Comments on Installation of Hardened Wetwell Vent at Plant,Per 891027 Response to Generic Ltr 89-16.Concludes That Hardened Vent Not Cost Beneficial & Consideration of Mods Be Deferred Until Individual Plant Evaluation Complete1990-07-25025 July 1990
Forwards Comments on Installation of Hardened Wetwell Vent at Plant,Per 891027 Response to Generic Ltr 89-16.Concludes That Hardened Vent Not Cost Beneficial & Consideration of Mods Be Deferred Until Individual Plant Evaluation Complete
ML20055G5261990-07-18018 July 1990
Forwards Decommissioning Rept Indicating Reasonable Assurance That Funds Available to Decommission Facility. Financial Assurance of Cotenants Also Encl
05000333/LER-1990-012, Advises That Suppl Rept to LER 90-012 Re Svc Water Check Valves Will Be Submitted by 9008201990-07-18018 July 1990
Advises That Suppl Rept to LER 90-012 Re Svc Water Check Valves Will Be Submitted by 900820
05000333/LER-1989-012, Advises That Suppl to LER 89-012-00 Re Postulated Fault 4 Kv Bus Fault Will Be Submitted by 9009041990-07-16016 July 1990
Advises That Suppl to LER 89-012-00 Re Postulated Fault 4 Kv Bus Fault Will Be Submitted by 900904
ML20044A9311990-07-0606 July 1990
Responds to NRC 900611 Ltr Re Violations Noted in Insp Rept 50-333/90-17.Corrective Action:Suspended Surveillances Reinstated on 900507
ML17058A5841990-06-27027 June 1990
Forwards Rev 8 to Updated FSAR for Nine Mile Point Unit 1. Changes Re Findings Noted in Insp Rept 50-220/88-201 Included in Rev.Rev Does Not Reflect Changes Re Reg Guide 1.97,Rev 2
ML18038A3051990-06-26026 June 1990
Responds to Generic Ltr 90-04 Re Status of Implementation of Generic Safety Issue Requirements.Tabulated Info Re Generic Safety Issue Title,Applicability,Status & Remarks Encl
ML20043J0101990-06-21021 June 1990
Forwards Application for Amend to License DPR-59,making Temporary Change Re LPCI Pump Flow Permanent,Per 900228 Ltr. Change Reduced Surveillance Test Flow Acceptance Value for RHR Pump
JAFP-90-0468, Informs That Licensed Operator Requalification Training Program at Plant Completed Transition to Program Based on Sys Approach to Training as Ref to in 10CFR55.4 & 591990-06-14014 June 1990
Informs That Licensed Operator Requalification Training Program at Plant Completed Transition to Program Based on Sys Approach to Training as Ref to in 10CFR55.4 & 59
ML20043G2491990-06-12012 June 1990
Forwards Application for Amend to License DPR-59,revising Tech Specs to Reflect Containment Isolation Valves in RHR & Core Spray keep-full Sys
ML20043H0851990-06-11011 June 1990
Forwards Reload 9/Cycle 10 Core Operating Limits Rept.
ML20043G7561990-06-11011 June 1990
Forwards Application for Amend to License DPR-59 Re Performance Discharge Testing of 125-volt Dc Batteries & LPCI Motor Operated Valve Independent Power Supplies
ML20043G6131990-06-11011 June 1990
Responds to Notice of Violation & Proposed Imposition of Civil Penalties in Amount of $75,000 Re Radiation Exposure. Corrective Actions:Worker Decontaminated & Examined by Physician.Civil Penalty Fee Transferred Electronically
ML20043F5931990-06-11011 June 1990
Forwards GE Nonproprietary Rept, GE11 Lead Test Assembly Fo Ja Fitzpatrick Nuclear Power Plant Reload 9 Cycle 10 & Proprietary Rept GE11 Lead Test Assembly Fuel Bundle.... Proprietary Rept Withheld (Ref 10CFR2.790)
ML20043H0451990-06-0808 June 1990
Responds to NRC 900509 Ltr Re Violations Noted in Insp Rept 50-333/90-02.Corrective Actions:Refuel Floor Work Stopped, Chief Radiation Protection Technician Disciplined & Importance of Following Procedural Guidelines Reinforced
ML20043E8911990-06-0707 June 1990
Forwards IGSCC Insp 1990 Refueling Outage Summary Rept Addendum
ML20043C3381990-05-31031 May 1990
Forwards Application for Amend to License DPR-59,revising Tech Spec 5.5.B to Increase Number of Spent Fuel Assemblies That Can Be Stored in Spent Fuel Pool
ML20043C5091990-05-30030 May 1990
Forwards Application for Amend to License DPR-59,updating Tech Spec Tables 3.2-8 & 4.2-8 to Reflect Installation of post-accident Monitoring Instrumentation,Per Reg Guide 1.97 & Deleting Tables 3.2-6,4.2-6 & 4.7-1
ML20043C7411990-05-25025 May 1990
Forwards Structural Evaluation of Indications in Reactor Top Head at Ja Fitzpatrick Power Station, Based on Evaluation Analyses for Flaw Indications Identified During Routine Inservice Insps
ML20043A7681990-05-16016 May 1990
Responds to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow. Channel Boxes Not Reused After First Lifetime.Methodology Developed by Ge,Vendor for Plant, Used to Account for Channel Bow
ML20043B1021990-05-14014 May 1990
Responds to NRC 900412 Ltr Re Violations Noted in Insp Rept 50-333/90-01.Corrective Actions:Disciplinary Actions Taken & Job Performance Counseling Provided Re Responsibilites for Control Room Operations & Command in Control Room
ML20043A7471990-05-14014 May 1990
Responds to NRC 900413 Ltr Re Violations Noted in Insp Rept 50-333/90-13.Util Requests That Notice of Violation Be Withdrawn & Reclassified as Deviation & That Submittal of Inaccurate Info Be Considered Isolated Case
ML20042G8271990-05-0909 May 1990
Responds to NRC 900410 Ltr Re Violations Noted in Insp Rept 50-333/90-11.Corrective Actions:Mod Error Corrected,New Transmitters Installed & Mod Procedures to Be Revised to Assign Responsibility for Calibr Points Value Calculation
ML20042F3891990-04-30030 April 1990
Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants.'
ML20042E6251990-04-20020 April 1990
Forwards Application for Amend to License DPR-59,changing Tech Specs to Remove cycle-specific Parameter Limits & Ref Core Operating Limits Rept Which Contains Limits,Per Generic Ltr 88-16
ML20042E3741990-04-11011 April 1990
Lists Info Re Unit Containment Vent & Purge Valves,Per NRC 900315 Request
ML20012F0361990-04-0505 April 1990
Forwards Temporary Addendum Rept for Rev 1 to Security Plan. Rept Withheld (Ref 10CFR73.21 & 2.790(d)(1))
ML20012F2161990-04-0202 April 1990
Forwards Application for Amend to License DPR-59,revising Sections 3.5.F & 4.5.F of Tech Specs, Min ECCS Availability.
ML20012F6131990-03-30030 March 1990
Forwards Changes to Security Training & Qualification Plan. Plan Rewritten & Revised to Incorporate performance-oriented Training Program.Plan Withheld (Ref 10CFR2.790(d))
ML20012C9821990-03-13013 March 1990
Forwards Application for Amend to License DPR-59,changing Tech Spec Section 4.9.F, LPCI Motor-Operated Valve Independent Power Supplies, on Page 222a.Changes Purely Editorial in Nature & Revises Surveillance Requirement
ML20012C0441990-03-0909 March 1990
Forwards Application for Amend to License DPR-59,clarifying Spec 3.9.B.3 Re Diesel Generator Operability to Eliminate Erroneous Ref to Both Diesel Generator Sys
ML17056A6721990-03-0202 March 1990
Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 & Rev 3 to Administrative Procedure AP-3.7.1, Unit 2 Radwaste Process Control Program.
ML20012A1021990-03-0101 March 1990
Forwards Inservice Insp Hydrostatic Test Program for Class 2 & 3 Sys Conducted During First 10-Yr Insp Interval. Relief Requested for Second 10-yr Insp Interval for Hydrostatic Relief Requests Contained in Encl
ML17347B5881990-03-0101 March 1990
Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits
ML18094B3221990-02-28028 February 1990
Forwards Executed Amend 14 to Indemnity Agreement B-74
ML15217A1031990-02-28028 February 1990
Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals
ML20012A9301990-02-28028 February 1990
Forwards New York Power Authority Ja Fitzpatrick Nuclear Power Plant Effluent & Waste Disposal Semiannual Rept Jul-Dec 1989 & Rev 7 to Odcm.
ML20012A0201990-02-28028 February 1990
Forwards Response to NRC SALP Initial Rept 50-333/88-99 for May 1988 - Sept 1989.Emergency Operating Procedures Being Upgraded to Rev 4 of Emergency Procedures Guidelines & Will Be in Place Upon Startup from Spring Refueling Outage
ML20011F3821990-02-26026 February 1990
Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices
1990-09-07
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