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Category:CORRESPONDENCE-LETTERS
MONTHYEARDD-99-12, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 9910281999-10-28028 October 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 991028 ML20217N8261999-10-25025 October 1999 Discusses Errata Re 991021 Filing of Northeast Nuclear Energy Co Answer to Request for Hearing & Petition to Intervene ML20217P3791999-10-21021 October 1999 Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls ML20217N2521999-10-20020 October 1999 Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC ML20217K3161999-10-19019 October 1999 Forwards Amend 195 to License DPR-61 & Safety Evaluation. Amend Deletes Certain TSs Either No Longer Applicable to Permanently Shutdown & Defueled State of Reactor or Duplicate Regulatory Requirements B17901, Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)1999-10-18018 October 1999 Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6) B17886, Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 21999-10-18018 October 1999 Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 2 05000336/LER-1999-012, Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl ML20217K7541999-10-15015 October 1999 Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units ML20217G9491999-10-14014 October 1999 Forwards Exemption from Requirements of 1-CFR50,App E, Section IV.F.2.c,re Conduct of full-participation Exercise in Sept 1999,at Plant,Units 1,2 & 3 B17900, Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 11999-10-14014 October 1999 Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 1 ML20217G6751999-10-13013 October 1999 Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1 ML20217D9671999-10-12012 October 1999 Forwards Copy of Transcript of Public Meeting Held by NRC Staff & NNECO on 990825 at Waterford,Connecticut on Decommissioning Program for Millstone,Unit 1.Without Encl CY-99-137, Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50 App B,Qa Program to Activities Related to Development of ISFSI at Haddam1999-10-12012 October 1999 Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50 App B,Qa Program to Activities Related to Development of ISFSI at Haddam DD-99-11, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-11) Expired & That Commission Declined Any Review.Decision Became Final Action on 9910041999-10-0808 October 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-11) Expired & That Commission Declined Any Review.Decision Became Final Action on 991004 ML20217D3011999-10-0707 October 1999 Forwards Request for Addl Info Re Util 990118 Request for Amend to License NPF-49 to Allow full-core Offloads to Spent Fuel Pool During Core Offloads to Spent Fuel Pool During Core Offload Events ML20217G1071999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Vogtle & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Plans to Conduct Core Insps at Facility Over Next Six Months ML20217P1201999-10-0606 October 1999 Informs NRC of Proposed Acquisition of Parent Holding Company of Central Maine & Requests NRC Concurrence,Based on Threshold Review,That Proposed Acquisition Does Not,In Fact, Constitute Transfer Subject to 10CFR50.80 ML20217F0031999-10-0606 October 1999 Forwards Original Petition to Intervene Being Filed on Behalf of Clients,Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone,Iaw Provisions of 10CFR2.714 B17892, Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC1999-10-0505 October 1999 Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC ML20217B4711999-10-0404 October 1999 Informs That Staff Did Not Identify Any Safety Concerns Re Licensee Proposals to Modify Commitments Made for Action Items 4.2.1,4.2.2,4.5.1 & 4.5.2 of GL 83-28 by Providing Addl Justifications or Safety Bases for Changes ML20212L1261999-10-0404 October 1999 Forwards Viewgraphs Presented by Licensee at 990923 Meeting with Nrc,In Response to Request ML20212L2171999-10-0101 October 1999 Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island ML20212L2081999-10-0101 October 1999 Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance ML20212L1971999-10-0101 October 1999 Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety ML20212L1831999-10-0101 October 1999 Responds to Recent Ltr to Wd Travers Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Performance of Millstone to Ensure Adequate Protection to Public Health ML20212K1241999-10-0101 October 1999 Responds to Recent Ltrs to Chairman Jackson,Commissioners & Wd Travers,Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performace of Millstone to Ensure That Public Health & Safety,Adequately Protected ML20212J9991999-10-0101 October 1999 Responds to Recent Ltr to President Clinton,H Clinton, Chairman Jackson &/Or Wd Travers Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performance of Plant to Ensure That Public Health & Safety Adequately Protected ML20212J3051999-10-0101 October 1999 Discusses GL 97-06 Re Degradation of SG Internals,Dtd 971230.GL Requested Each PWR Licensee to Submit Info That Will Enable NRC Staff to Verify Whether PWR SG Internals Comply & Conform to Current Licensing Basis for Facilities ML20212J2451999-10-0101 October 1999 Informs That Util 980807 & 990629 Responses to GL 98-01, Y2K Readiness of Computer Sys at NPPs Acceptable.Nrc Considers Subj GL to Be Closed for Units 2 &3 ML20217B0141999-10-0101 October 1999 Forwards Insp Repts 50-424/99-06 & 50-425/99-06 on 990725- 0904 at Vogtle Units 1 & 2 Reactor Facilities.Determined That One Violation Occurred & Being Treated as non-cited Violation ML20216J9161999-10-0101 October 1999 Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20216J9041999-10-0101 October 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20212J6621999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Units 2 & 3 on 990916.Identified Several Recent Instances in Which Condition Repts Were Not Initiated,Resulting in Untimely or Inadequate C/As.Historical Listing of Plant Issues Encl ML20217A9271999-09-30030 September 1999 Discusses Investigation Conducted at Millstone Nuclear Power Station by NRC OI Region I on 980319 to Determine If Contract Training Instructor Was Terminated for Raising Concerns About Quality of Training Matls ML20217B3221999-09-30030 September 1999 Refers to Investigation Rept 1-1997-035 Conducted at Millstone Nuclear Power Station by NRC Ofc of Investigation Field Ofc,Region I on 970915 to Determine Whether Former Health Physics Technician Discriminated Against B17887, Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer1999-09-28028 September 1999 Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer ML20216J1341999-09-28028 September 1999 Ltr Contract:Task Order 49, Millstone Units 2 & 3 Employee Concerns Program Insp, Under Contract NRC-03-98-021 B17890, Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-09-27027 September 1999 Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal B17883, Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-62301999-09-27027 September 1999 Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-6230 B17888, Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 9909151999-09-24024 September 1999 Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 990915 B17884, Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-031999-09-24024 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-03 ML20212D0341999-09-20020 September 1999 Expresses Appreciation for Accepting NRC Request for Tour of Haddam Neck Facility During on 991014.Invites R Mellor to Participate in NRC 1999 Decommissioninng Power Reactor Work- Shop:Nrc Insp Program at Decommissioning Power Reactors ML20212F4961999-09-20020 September 1999 Forwards Insp Repts 50-245/99-08,50-336/99-08 & 50-423/99-08 on 990615-0809.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs,Consistent with App C of Enforcement Policy 05000336/LER-1999-001, Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl ML20212E7481999-09-20020 September 1999 Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl ML20212E8751999-09-20020 September 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl B17867, Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports1999-09-17017 September 1999 Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports B17865, Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal1999-09-16016 September 1999 Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal B17876, Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant1999-09-16016 September 1999 Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217N8261999-10-25025 October 1999 Discusses Errata Re 991021 Filing of Northeast Nuclear Energy Co Answer to Request for Hearing & Petition to Intervene ML20217P3791999-10-21021 October 1999 Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls ML20217N2521999-10-20020 October 1999 Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC B17901, Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)1999-10-18018 October 1999 Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6) B17886, Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 21999-10-18018 October 1999 Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 2 ML20217K7541999-10-15015 October 1999 Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units 05000336/LER-1999-012, Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl B17900, Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 11999-10-14014 October 1999 Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 1 ML20217G6751999-10-13013 October 1999 Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1 CY-99-137, Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50 App B,Qa Program to Activities Related to Development of ISFSI at Haddam1999-10-12012 October 1999 Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50 App B,Qa Program to Activities Related to Development of ISFSI at Haddam ML20217P1201999-10-0606 October 1999 Informs NRC of Proposed Acquisition of Parent Holding Company of Central Maine & Requests NRC Concurrence,Based on Threshold Review,That Proposed Acquisition Does Not,In Fact, Constitute Transfer Subject to 10CFR50.80 ML20217F0031999-10-0606 October 1999 Forwards Original Petition to Intervene Being Filed on Behalf of Clients,Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone,Iaw Provisions of 10CFR2.714 B17892, Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC1999-10-0505 October 1999 Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC ML20216J9161999-10-0101 October 1999 Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20216J9041999-10-0101 October 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves B17887, Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer1999-09-28028 September 1999 Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer B17890, Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-09-27027 September 1999 Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal B17883, Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-62301999-09-27027 September 1999 Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-6230 B17884, Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-031999-09-24024 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-03 B17888, Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 9909151999-09-24024 September 1999 Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 990915 ML20212E7481999-09-20020 September 1999 Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl ML20212E8751999-09-20020 September 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl 05000336/LER-1999-001, Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl B17867, Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports1999-09-17017 September 1999 Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports B17876, Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant1999-09-16016 September 1999 Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant B17865, Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal1999-09-16016 September 1999 Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal ML20212C2191999-09-16016 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, Which Is Current Need for NRC Operator Licensing Exams for Years 2000 Through 2003 of Plant Vogtle,Per Administrative Ltr 99-03 B17882, Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6) B17859, Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 9801281999-09-15015 September 1999 Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 980128 B17881, Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6) B17880, Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6) B17872, Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 11999-09-14014 September 1999 Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 1 B17838, Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls1999-09-10010 September 1999 Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls ML20211J9291999-09-0303 September 1999 Forwards mark-ups & Retypes of Proposed Conforming License Changes Required in Connection with Transfers Being Sought in 990615 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests ML20216H0591999-09-0202 September 1999 Responds to Re Issues Submitted by Cullen on Behalf of Several Petitioners Concerning Offsite Emergency Prepardeness for Millstone Nuclear Power Station 05000336/LER-1999-010, Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 11999-09-0202 September 1999 Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 1 CY-99-111, Submits Clarification of Changes Made to Connecticut Yankee QA Program,Per Util 990810 Submittal.Change Will Be Submitted to NRC in Dec 1999 as Part of Annual Update1999-09-0202 September 1999 Submits Clarification of Changes Made to Connecticut Yankee QA Program,Per Util 990810 Submittal.Change Will Be Submitted to NRC in Dec 1999 as Part of Annual Update ML20211N9241999-09-0101 September 1999 Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures ML20211J5291999-08-30030 August 1999 Forwards Snoc Copyright Notice Dtd 990825,re Production of Engineering Drawings Ref in VEGP UFSAR ML20211J5251999-08-30030 August 1999 Forwards Response to NRC 990727 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20211J7381999-08-27027 August 1999 Informs That Licensee Vessel Data Is Different than NRC Database Based on Listed Info,Per 990722 Request to Review Rvid B17851, Forwards Semiannual fitness-for-duty Program Performance Data for 990101-990630 for Millstone Nuclear Power Station, Units 1,2 & 3,IAW 10CFR26.71(d)1999-08-27027 August 1999 Forwards Semiannual fitness-for-duty Program Performance Data for 990101-990630 for Millstone Nuclear Power Station, Units 1,2 & 3,IAW 10CFR26.71(d) ML20211E9251999-08-23023 August 1999 Forwards fitness-for-duty Performance Data for Jan-June 1999,as Required by 10CFR26.71(d).Data Reflected in Rept Covers Employees at Vogtle Electric Generating Plant B17855, Forwards NRC Forms 398 & 396 in Support of License Renewal for SRO TE Grilley,SOP-4053-04.Encl Withheld,Per 10CFR2.7901999-08-17017 August 1999 Forwards NRC Forms 398 & 396 in Support of License Renewal for SRO TE Grilley,SOP-4053-04.Encl Withheld,Per 10CFR2.790 B17849, Forwards Second Quarter Backlog Performance Rept for 1999, Which Represents Fourth Rept on Mnps Performance Since Restart of Unit 3 & First Status Update for Unit 2.No Regulatory Commitments Are Contained in Ltr1999-08-16016 August 1999 Forwards Second Quarter Backlog Performance Rept for 1999, Which Represents Fourth Rept on Mnps Performance Since Restart of Unit 3 & First Status Update for Unit 2.No Regulatory Commitments Are Contained in Ltr B17854, Forwards Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2,per TS 6.9.1.7.Revised Repts for May & June Also Encl Which Reflect Correct Faulty Printometer Readings1999-08-14014 August 1999 Forwards Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2,per TS 6.9.1.7.Revised Repts for May & June Also Encl Which Reflect Correct Faulty Printometer Readings B17850, Forwards First Lhc Quarterly Assessment Rept for Assessment Performed 990621 to 990701.NNECO Taking Appropriate Actions to Address Observations in Rept1999-08-11011 August 1999 Forwards First Lhc Quarterly Assessment Rept for Assessment Performed 990621 to 990701.NNECO Taking Appropriate Actions to Address Observations in Rept B17837, Forwards COLR for Cycle 7, for Millstone Unit 3,IAW TS 6.9.1.6.Explanation of Changes to COLR Also Encl1999-08-0707 August 1999 Forwards COLR for Cycle 7, for Millstone Unit 3,IAW TS 6.9.1.6.Explanation of Changes to COLR Also Encl B17657, Requests Schedular Exemption from Emergency Plan Exercise Requirements of 10CFR50,App E,Part Iv,Section F,Paragraph 2.c.Requests That Nrc/Fema Evaluated Exercise Be Conducted in Mar 2000 Rather than Sept 19991999-08-0303 August 1999 Requests Schedular Exemption from Emergency Plan Exercise Requirements of 10CFR50,App E,Part Iv,Section F,Paragraph 2.c.Requests That Nrc/Fema Evaluated Exercise Be Conducted in Mar 2000 Rather than Sept 1999 B17845, Forwards Revised Commitment for Surveillance Scheduling & Tracking.Options for Surveillance Scheduling & Tracking Methodologies to Be Incorporated in Standardized Station Surveillance Program Are Currently Being Reconsidered1999-08-0202 August 1999 Forwards Revised Commitment for Surveillance Scheduling & Tracking.Options for Surveillance Scheduling & Tracking Methodologies to Be Incorporated in Standardized Station Surveillance Program Are Currently Being Reconsidered 1999-09-03
[Table view] Category:UTILITY TO NRC
MONTHYEARA08900, Responds to Expressing NRC Views on Access to Util Internal or third-party Assessment Repts.Believes Internal Analysis to Support Amend of One of Util NRC OLs to Authorize Higher Power Level Is within NRC Purview & Access1990-09-11011 September 1990 Responds to Expressing NRC Views on Access to Util Internal or third-party Assessment Repts.Believes Internal Analysis to Support Amend of One of Util NRC OLs to Authorize Higher Power Level Is within NRC Purview & Access ML20064A8071990-09-11011 September 1990 Forwards Core Operating Limits Rept for Four & Three Loop Operation,Per Tech Spec 6.9.1.6.d B13628, Forwards Correction to Error Discovered in Util 900727 Response to Notice of Violation from Insp Rept 50-336/90-09. Statement Corrected to Read That Contract Personnel That Have long-term Assignments,Certified as Testing Personnel1990-09-0707 September 1990 Forwards Correction to Error Discovered in Util 900727 Response to Notice of Violation from Insp Rept 50-336/90-09. Statement Corrected to Read That Contract Personnel That Have long-term Assignments,Certified as Testing Personnel ELV-02056, Forwards Operator Exam Schedule for Facility,Per Generic Ltr 90-07 Request,Including Number of Candidates to Be Examined During NRC Site Visits,Requalification Schedules & Number of Candidates to Participate in Generic Fundamentals Exam1990-09-0606 September 1990 Forwards Operator Exam Schedule for Facility,Per Generic Ltr 90-07 Request,Including Number of Candidates to Be Examined During NRC Site Visits,Requalification Schedules & Number of Candidates to Participate in Generic Fundamentals Exam B13624, Forwards Addl Info Re Relief Request from ASME Code Section XI Requirements for Temporary Repair to Piping Adjacent to Valve 2-SW-97A,per 900817 Telcon1990-09-0505 September 1990 Forwards Addl Info Re Relief Request from ASME Code Section XI Requirements for Temporary Repair to Piping Adjacent to Valve 2-SW-97A,per 900817 Telcon A08977, Advises of Commitment to Install Hardened Wetwell Vent at Facility,In Response to NRC .Util Will Be Proceeding W/Initial Design & Engineering of Hardened Vent, to Support Installation During 1993 Refueling Outage1990-09-0404 September 1990 Advises of Commitment to Install Hardened Wetwell Vent at Facility,In Response to NRC .Util Will Be Proceeding W/Initial Design & Engineering of Hardened Vent, to Support Installation During 1993 Refueling Outage ELV-01599, Discusses Mods to HED-1114 Re Plant Dcrdr,Per . Amber Monitor Light Covers Installed for Spare Pumps to Make Status of Pumps Readily Apparent to Operator1990-09-0404 September 1990 Discusses Mods to HED-1114 Re Plant Dcrdr,Per . Amber Monitor Light Covers Installed for Spare Pumps to Make Status of Pumps Readily Apparent to Operator B13596, Forwards Millstone Unit 3 Individual Plant Exam for Severe Accident Vulnerabilities, Per Generic Ltr 88-20.Rept Identified That No Major Severe Accident Vulnerabilities Requiring Corrective Action Needed1990-08-31031 August 1990 Forwards Millstone Unit 3 Individual Plant Exam for Severe Accident Vulnerabilities, Per Generic Ltr 88-20.Rept Identified That No Major Severe Accident Vulnerabilities Requiring Corrective Action Needed B13626, Informs That Info Provided in Re safety-related Equipment Classification Programs Also Applicable for Unit 3 of Facility1990-08-31031 August 1990 Informs That Info Provided in Re safety-related Equipment Classification Programs Also Applicable for Unit 3 of Facility B13622, Forwards Crdr Human Engineering Discrepancy Info for Plant1990-08-30030 August 1990 Forwards Crdr Human Engineering Discrepancy Info for Plant ELV-02059, Clarifies 900409 Response to 900323 Confirmation of Action Ltr.Util Made 31 Successful Start Attempts for Diesel Generator (DG) 1A & 29 Successful Start Attempts for DG 1B1990-08-30030 August 1990 Clarifies 900409 Response to 900323 Confirmation of Action Ltr.Util Made 31 Successful Start Attempts for Diesel Generator (DG) 1A & 29 Successful Start Attempts for DG 1B ELV-02050, Responds to Violations Noted in Insp Repts 50-424/90-08 & 50-425/90-08.Corrective Actions:Administrative Procedures Controlling Verification & Validation of Emergency Operating Procedures Will Be Evaluated & Revised as Required1990-08-30030 August 1990 Responds to Violations Noted in Insp Repts 50-424/90-08 & 50-425/90-08.Corrective Actions:Administrative Procedures Controlling Verification & Validation of Emergency Operating Procedures Will Be Evaluated & Revised as Required ELV-01956, Forwards Listed Documents in Response to Request for Addl Info Re Settlement Monitoring Program,Per 900614 Request1990-08-30030 August 1990 Forwards Listed Documents in Response to Request for Addl Info Re Settlement Monitoring Program,Per 900614 Request B13618, Forwards Addl Info on Util 900815 Relief Request from ASME Code Section XI Requirements,Per 10CFR50.55a(g)(6)(i),for Repairs to Pipe 3SWP-006-050-031990-08-24024 August 1990 Forwards Addl Info on Util 900815 Relief Request from ASME Code Section XI Requirements,Per 10CFR50.55a(g)(6)(i),for Repairs to Pipe 3SWP-006-050-03 ML20059C2061990-08-23023 August 1990 Forwards Vols 1 & 2 to Semiannual Radioactive Effluents Release Rept Jan-June 1990, Per 10CFR50.36a.Rept Includes Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents B13617, Requests NRC Revise Confirmatory Order for Plant to Specify New Completion Date of Cycle 16 Refueling Outage for Item II.E.1.2.Util Intends to Implement Design Change During Next Refueling Outage to Resolve Listed Issues1990-08-22022 August 1990 Requests NRC Revise Confirmatory Order for Plant to Specify New Completion Date of Cycle 16 Refueling Outage for Item II.E.1.2.Util Intends to Implement Design Change During Next Refueling Outage to Resolve Listed Issues A08918, Responds to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-245/90-08.Mitigation of Civil Penalty Requested.Corrective Action:List of Procedural Changes Provided1990-08-22022 August 1990 Responds to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-245/90-08.Mitigation of Civil Penalty Requested.Corrective Action:List of Procedural Changes Provided ELV-02022, Forwards Revised LER Re Apparent Personnel Error Leading to Unsecured Safeguards Info.Ler Withheld1990-08-22022 August 1990 Forwards Revised LER Re Apparent Personnel Error Leading to Unsecured Safeguards Info.Ler Withheld ELV-02028, Forwards Fitness for Duty Performance Data for First Six Month Period,Per 10CFR26.71(d)1990-08-22022 August 1990 Forwards Fitness for Duty Performance Data for First Six Month Period,Per 10CFR26.71(d) ELV-02027, Forwards Rev 0 to Core Operating Limits Rept, for Cycle 3, Per Amends 32 & 12 to Licenses NPF-68 & NPF-79,respectively1990-08-20020 August 1990 Forwards Rev 0 to Core Operating Limits Rept, for Cycle 3, Per Amends 32 & 12 to Licenses NPF-68 & NPF-79,respectively B13615, Requests That 900705 Request for Amend to License DPR-61 Be Approved on Emergency Basis & That Temporary Waiver of Compliance from Tech Spec 4.4.6.2.1.g Be Given Until NRC Acts on Emergency Amend1990-08-20020 August 1990 Requests That 900705 Request for Amend to License DPR-61 Be Approved on Emergency Basis & That Temporary Waiver of Compliance from Tech Spec 4.4.6.2.1.g Be Given Until NRC Acts on Emergency Amend B13611, Forwards, Semiannual Radioactive Effluents Release Rept for Jan-June 19901990-08-16016 August 1990 Forwards, Semiannual Radioactive Effluents Release Rept for Jan-June 1990 B13610, Requests Relief from ASME Boiler & Pressure Vessel Code Section XI Requirements Re Mods to Pipe 3SWP-006-050-03. Results of Insps & Required Repairs Will Determine Schedule for Future Insps1990-08-15015 August 1990 Requests Relief from ASME Boiler & Pressure Vessel Code Section XI Requirements Re Mods to Pipe 3SWP-006-050-03. Results of Insps & Required Repairs Will Determine Schedule for Future Insps B13602, Submits Addendum to Plant Control Room Design Review Summary Rept,Per .Lists 10CFR50 App R-related Mods Outside Control Room That Could Not Be Reviewed Until After Final Implementation of Changes1990-08-14014 August 1990 Submits Addendum to Plant Control Room Design Review Summary Rept,Per .Lists 10CFR50 App R-related Mods Outside Control Room That Could Not Be Reviewed Until After Final Implementation of Changes B13595, Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-13941990-08-14014 August 1990 Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-1394 ELV-01973, Submits Rept Re Results of Leakage Exams Conducted During Spring 1990 Refueling Outage,Per TMI Item III.D.1.1.None of Identified Leakage Considered Excessive.Work Orders Issued in Effort to Reduce Leakage to Level as Low Practical1990-08-14014 August 1990 Submits Rept Re Results of Leakage Exams Conducted During Spring 1990 Refueling Outage,Per TMI Item III.D.1.1.None of Identified Leakage Considered Excessive.Work Orders Issued in Effort to Reduce Leakage to Level as Low Practical B13580, Discusses Revised Tech Spec Conversion Program,Reflecting Conversion of Tech Spec to Westinghouse Sts.Future Upgrade of Tech Specs Should Be Conducted on Voluntary Basis Consistent W/Nrc Policy Statement1990-08-10010 August 1990 Discusses Revised Tech Spec Conversion Program,Reflecting Conversion of Tech Spec to Westinghouse Sts.Future Upgrade of Tech Specs Should Be Conducted on Voluntary Basis Consistent W/Nrc Policy Statement B13607, Requests Relief from ASME Code Section XI to Reflect Mod to Piping Adjacent to Valve 2-SW-97A,in Response to Generic Ltr 90-051990-08-10010 August 1990 Requests Relief from ASME Code Section XI to Reflect Mod to Piping Adjacent to Valve 2-SW-97A,in Response to Generic Ltr 90-05 A08845, Responds to NRC Backfit Analyses of Hardened Wetwell Vent, Contained in .Benefit of Installing Hardened Wetwell Vent to Satisfy Basic Design Objective of Preventing core-melt Event Not Sufficient for Immediate Decision1990-08-0808 August 1990 Responds to NRC Backfit Analyses of Hardened Wetwell Vent, Contained in .Benefit of Installing Hardened Wetwell Vent to Satisfy Basic Design Objective of Preventing core-melt Event Not Sufficient for Immediate Decision ML20058M8321990-08-0707 August 1990 Discusses Spent Fuel Racks Poison Surveillance Coupon Boraflex Degradation.Visual Exam of Remaining Surveillance Coupons Revealed Similar Situation Existed in All Coupon Samples ML20058N2181990-08-0707 August 1990 Notification of Change in Senior Operator Status.Util Determined That Need to Maintain Senior OL of LS Allen No Longer Exists.Determination Effective 900719 ELV-01918, Responds to NRC 900612 Request for Comments & Suggestions on Draft risk-based Insp Guide.Util Conducting Individual Plant Exam & Will Withhold Comment on risk-based Insp Guide Until Completion1990-08-0303 August 1990 Responds to NRC 900612 Request for Comments & Suggestions on Draft risk-based Insp Guide.Util Conducting Individual Plant Exam & Will Withhold Comment on risk-based Insp Guide Until Completion B13603, Withdraws 900731 Request for Temporary Waiver of Compliance W/Tech Spec 3.7.1.2 Re Inoperability of Auxiliary Feedwater Pumps1990-08-0202 August 1990 Withdraws 900731 Request for Temporary Waiver of Compliance W/Tech Spec 3.7.1.2 Re Inoperability of Auxiliary Feedwater Pumps B13590, Responds to NRC 900718 Request for Addl Info Re Util 900418 Request for Schedular Exemption from 10CFR50,App E,Section IV.F.3 to Allow Dec 1990 Full Participation Exercise to Be Exchanged W/Oct 1991 Partial Participation Exercise1990-08-0101 August 1990 Responds to NRC 900718 Request for Addl Info Re Util 900418 Request for Schedular Exemption from 10CFR50,App E,Section IV.F.3 to Allow Dec 1990 Full Participation Exercise to Be Exchanged W/Oct 1991 Partial Participation Exercise B13601, Requests Temporary Waiver of Compliance from Tech Spec 3.7.1.2,allowing Plant to Remain in Mode 3 for Addl 14 Days Beyond Current Action Statement Limits W/One or of Two Auxiliary Feedwater Pumps Inoperable1990-07-31031 July 1990 Requests Temporary Waiver of Compliance from Tech Spec 3.7.1.2,allowing Plant to Remain in Mode 3 for Addl 14 Days Beyond Current Action Statement Limits W/One or of Two Auxiliary Feedwater Pumps Inoperable A08881, Responds to NRC Re Violations Noted in Insp Rept 50-423/90-08.Corrective Action:Operators Directly Involved W/Event Removed from Licensed Duties & Counseled by Operations Manager on Causes of Event1990-07-31031 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-423/90-08.Corrective Action:Operators Directly Involved W/Event Removed from Licensed Duties & Counseled by Operations Manager on Causes of Event B13594, Forwards Rev 13 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21(b) & 2.790(a))1990-07-30030 July 1990 Forwards Rev 13 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21(b) & 2.790(a)) ML20055J4621990-07-27027 July 1990 Advises That Need to Maintain OL or Senior OL for Listed Individuals No Longer Exists,Effective 900701 ELV-01943, Responds to Violation & Proposed Imposition of Civil Penalty in Insp Repts 50-424/90-11 & 50-425/90-11.Corrective Action: Complete Audit of Contents of Safeguards Info Container Performed & Unassigned Safeguards Info Dispositioned1990-07-27027 July 1990 Responds to Violation & Proposed Imposition of Civil Penalty in Insp Repts 50-424/90-11 & 50-425/90-11.Corrective Action: Complete Audit of Contents of Safeguards Info Container Performed & Unassigned Safeguards Info Dispositioned ELV-01949, Forwards Info Re Status of Pen Branch Fault Investigation. Investigations Conducted So Far Still Indicate That Pen Branch Fault Not Capable1990-07-26026 July 1990 Forwards Info Re Status of Pen Branch Fault Investigation. Investigations Conducted So Far Still Indicate That Pen Branch Fault Not Capable A08565, Responds to NRC 900302 Request for Addl Info Re LPCI Swing Bus Transfer Design & Single Failure Vulnerabilities1990-07-26026 July 1990 Responds to NRC 900302 Request for Addl Info Re LPCI Swing Bus Transfer Design & Single Failure Vulnerabilities B13585, Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys1990-07-26026 July 1990 Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys ELV-01500, Forwards Nuclear Decommissioning Funding Plan for Plant.Info Provides Assurance That NRC Prescribed Min Funding Will Be Available to Decommission Facilities1990-07-25025 July 1990 Forwards Nuclear Decommissioning Funding Plan for Plant.Info Provides Assurance That NRC Prescribed Min Funding Will Be Available to Decommission Facilities B13592, Requests Extension to Respond to NRC Backfit Analyses of Hardened Wetwell Vent1990-07-24024 July 1990 Requests Extension to Respond to NRC Backfit Analyses of Hardened Wetwell Vent ML20055H6441990-07-23023 July 1990 Submits Summary of Snubber Types & Sample Plans for Functional Testing to Be Performed During Sept 1990 Outage ML20063P9791990-07-23023 July 1990 Notification of Change in SL Jackson Status Effective 900701,due to Permanent Reassignment within Util B13566, Advises That Util Has Reasonable Assurance That Safety Relief Valves Operable & Will Perform as Expected Until Next Outage1990-07-20020 July 1990 Advises That Util Has Reasonable Assurance That Safety Relief Valves Operable & Will Perform as Expected Until Next Outage B13563, Discusses Util Comprehensive Review of Options Re Degraded Grid Undervoltage Protection.Confirms Previous Conclusion That Splitting Loss of Normal Power Logic Would Have Overall Adverse Impact on Plant Safety1990-07-20020 July 1990 Discusses Util Comprehensive Review of Options Re Degraded Grid Undervoltage Protection.Confirms Previous Conclusion That Splitting Loss of Normal Power Logic Would Have Overall Adverse Impact on Plant Safety B13571, Clarifies 900625 Tech Spec Change Request Re Limit of 160 Failed Fuel Rods for Cycle 16 Operation1990-07-19019 July 1990 Clarifies 900625 Tech Spec Change Request Re Limit of 160 Failed Fuel Rods for Cycle 16 Operation ML20055G5331990-07-18018 July 1990 Forwards Decommissioning Financial Assurance Certification Rept 1990-09-07
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. e geogtT9tEAST UTILITIES o.n r.i Omc.. seio.a street. Berna. cona.ct'cui H RTFORD. CONNECTICUT 061414270 L L iJ [ (( E [E.7,"w ~- m 665- M October 17,1986 Docket Nos. 50-213 50-245 50-336 50-423 B12287 U.S. Nuclear Regulatory Commission Office of Resource Management Division of Accounting and Finance Washington, D.C. 20535 Gentlemen:
Haddam Neck Plant Millstone Nuclear Power Station, Unit Nos.1,2 and 3 Payment of Facilities and Materials License Fees Northeast Utilities is in receipt of Invoices #1697W, #1729W, #1730W, and
- 1731W for Facilities and Materials License Fees for the Haddam Neck Plant and Millstone Nuclear Power Station, Unit Nos.1,2 and 3, respectively, for the first quarter of 1986. Enclosed is a check in the amount of $134,675.00 as full payment of these invoices.
Very truly yours, NORTHEAST UTILITIES SERVICE COMPANY
[ .D J. F. Opeka '
Senior Vice President By: C. F. Sears Vice President A* Ene 5 NO * '
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NIC FORM 233 UA. NUCLE AW i.E;;ULATwY COMMIS&lON INVOICE NUMBER (8 84) 1697W INVOICE FOR lhSPECTION FEES FOR INVOICE DATE PAYMENT DUE DATE FACILITIES AND MATERIALS LICENSES 0 1986 OCT 3 01986 LICE NSE E MAKE CHECKS PAYABLE TO:
Connecticut Yankee Atomic Power Co.
ATTN: Mr. John F. Opeka RECElVED """""*"'*"""'"'"
Senior Vice President of tic. of R.sou,c. Mana...n.ni Nuclear Engineering & Operations DCT o o' >iaa a' aaa a a a r a <-
P. O. Box 270 - 1986 ..,'n n,,o n, oc n 3 3 3 Hartford, CT 06141-0270 trgroa yicg , PRES! DENT N::&:t EnNnen.ng S 0 * -
PLANT LICENSE NUMBE R FEE CATEGORY INSFECTION (10 CF R 170) DATE AMOUNT DUE T YP E lAEPORT NUMBER DPR-61 INS-R 39,319.00 INS-NR 2,385.00 TOTAL TERMS Interest wdl accrue from the mvoice date at the rate of b % per annum. (see terms; 41.704.00 sucept that no mterest wdl be charged rf the total amount es paid m full by the payment due date above.
NOTICE. One June 20, 1984 the NRC revised its regulatons and adopted a revised license fee schedule (10 CFR 1701. A copy of the revised regula tons was mailert to all NRC lecensees The revised schedule ecludes the assessment of fees for facdety and materels routme and non-routine inspectons This mvo.ce shows the fee assessed for the recent espection(s) conducted by the Office of Inspect.on and Enforcement of your licensed program 10 CFR 170 41 FAILURE BY APPLICANT TO PAY PRESCRIBED FEES. In any case where the NRC finds that an applecant or a lecensee has faded to pay a prescribed fee required m thrs part, the Commssion wdl not process any applicateon and may suspend or revoke any license or approvat essued to the applicant or lecensee or may asue an order weth respect to lecensed activit.es as the Commasion determines to be approprete or necessary m order to corry out the provsons of the part, Parts 30, 32 ttwough 35, 40. 50, 61. 70, 71, 72, and 73 of ths Chapter, and of the Act 10 CFR 170 51 RIGHT TO REVIEW AND APPEAL OF PRESCRIBED FEES. All debtor's requests for review of the fees assessed and appeal or disagreement with the prescribed fee (staff hours and contractual) must be submitted m accordance with the provrsions of 10 CFR 15 31. "Dsputed Debts " of the tstle.
10 CFR 170 51 RIGHT TO REVIEW AND, APPEAL OF PRESCRIBED FEES. All debtor's requests for review of the fees assessed and appeal or dsagreement with the prescribed fee (Asff hours and contractuali must be submitted m accordance with the provssons of 10 CFR 15 31. " Disputed Debts." of this title CONTACT. Questens relating to the assessment of fees under the revised fee schedule, and'or correctness of the address. Call (301) 432-7225 or derect correspondence to U S. Nuclear Regulatory Commsson Off.ce of Adminrstraten License Fee Management Branch Washmgton. DC 20555
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1697C l
Attachment Facility Fee Bill (10CFR170.21(A))
Licensee: License No.: DPR-61 Connecticut Yankee Atomic Power Co. Docket No.: 50-213 ATTN: Mr. John F. Opeka Senior Vice President Facility: Haddam Neck Nuclear Engineering & Operations P.O. Box 270 Period: 12/22/85 - 3/29/86 Hartford, CT 06141-0270 Inspection Review Costs Report Number Routine keactive See attached Subtotal: $ 38,319 $ 2,385 Contract Costs: $ 1,000 $
Total By Type: $ 39,319 $ 2,385 Fee Code: AA903-INS-R AA903-INS-NR Total This Bill: $ 41,704
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N2C FO*.M 233 U;J. NUCLE AR LE4ULATuY COMMISSION INVOICE NUMBER wasi 1729W INVOICE FOR INSPECTION FEES FOR NvoicE DATE PAYMENT DUE t ATE FACILITIES AND MATERIALS LICENSES SEP 3 01986 0CT 3 01986 LIC E NSE E Northeast Nuclear Energy Company Attn: Mr. John F. Opeka U.S. Nuclear Regulatory Commission Senior Vice President o,,,c, ,,p.,,,,,,u ,,,,,,,,,,
Engineering and Operations P.O. Box 270 RECEIVED o- -ofA - ~ ~ -
wa nin, ton, oC nm Hartford, CT 06141-0270 DCT 3 1986 EMOR VICE MES!CEilT N-r--r-,,,,,i_n-.
PLANT LICENSE NUMBE R P EE CATEGORY INS'E CTION f 0 CF R 1701 AMOUNT DUE DATE TYPE REPORT NUMBE R DPR-21 AA903-INS-R $4,522.00 AA903-INS-NR 769.00 TOTAL
__ b % per annum. [see term:1 $5,291.00 TEAMS Interest wdl accrue from the mvoice date at the rate of encept that no :nterest well be charged d the total amount a paid m full by the payment due date above NOTICE. One June 20.1984, the NRC revsed its regulatons and adopted a revised hcense fee schedule f10 CFR 170) A copy of the revised regula tons was mailed to all NRC heensees. The revsed schedule ecludes the assessment of fees for facdity and rnatenals routme and non routine inspectons l This invoice shows the fee assessed for the recent especton(s) conducted by the Office of inspecton and Enforcement of your hcensed program.
10 CFR 170 41 FAILURE BY APPLICANT TO PAY PRESCRISED FEES. In any case where the NRC fmds that an apphcant or a hcensee has failed to l
, pay a prescribed fee required m the part. the Commisson wdl not process any apphcaton and rnay suspend or revoke any hcense or approval asued to l the apphcant or Icensee or may ssue an order with respect to hcensed activites as the Comrnisson determines to be appropnate or necessary in order to carry out the provmons of thes part. Parts 30. 32 through 35, 43. 50. 61. 70. 71. 72, and 73 of thrs Chapter. and of the Act.
10 CFR 170 51 RIGHT TO REVIEW AND APPEAL OF PRESCRIBED FEES. All debtor's requests for review of the fees assessed and appeal or dsagreement with the prescribed fee (sta# hours and contractus0 must be submitted m accordance with the provmons of 10 CFR 15 31. "Dsputed Debts." of thrs tette 10 CFR 170 51 RIGHT TO REVIEW AND APPEAL OF PRESCRIBED FEES. All debtor's requests for revew of the fees assessed and appeal or desagreement with the prescnbed fee Ma# hours and contractuali must be submitted m accordance with the provssons of 10 CFR 15 31. "Dsputed Debts." of thrs title CONTACT. Questens relatmg to the assessment of fees under the revsed fee schedule, and/or correctness of the address, call 1301) 4927225 or direct correspondence to U S Nuclear Regulatory Commsseon Office of Adminstraton License Fee Management Branch l
Washington. DC 20565 l
. . - ~ ~ -
. . l 7&9u)
Attachment Facility Fee Bill (10 CFR 170.21(A))
Licensee: License No.: DPR-21 Northeast Nuclear Energy Company Docket No.: 50-245 ATTN: Mr. John F. Opeka Senior Vice President Facility: Millstone 1 Engineering and Operations P.O. Box 270 Period: 12/22/85 - 3/29/86 Hartford, CT 06141-0270 Inspection Review Costs Report Number Routine Reactive See attached Subtotal: $ 3,286 $ 769 Contract Costs: $ 1,236 $
Total By Type: $ 4,522 $ 769 Fee Code: AA903-INS-R AA903-INS-NR Total This Bill: $ 5,291 I
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NIC FORM 233 UA. NUCLE A,4 LE4ULATORY COMMISSION INVOICE NUMBER C 841 1730W INVOICE FOR INSPECTION FEES FOR INVOICE DATE PAYMENT DUE DATE FACILITIES AND MATERIALS LICENSES SEP 3 01986 0CT 3 01986 LIC E NSE E MAKE CHECKS PAYA8LE TO.
Northeast Nuclear Energy Company Attn: Mr. John F. Opeka RECEIVED U.S. Nuclear Regulatory Commission ViCe President, Nuclear o,,,,,,,,,,,,,,,,,,,,,,,,,
Engineering P.O. Box 270 OCT 9 -
1986 o' lil a t ac= uean " na on -
- w. nineton, oc asss Hartford, CT 06101 SEm0R VICE PRES! CENT Nu2n En7mening S OP FLANT ,
LICE NSE NUMBE R F A OM W EC N (10 CF R 170) AMOUNT DUE DATE TYPE REPORT NUMBE R DPR-65 AA903-INS-R $4.319.00 AA-903-INS-NR 769.00 l
l TOTAL.
TERMS Interest will accrue from the mvoice date at the rate of _3 % per annum. (see terms) $5,088.00 ocept that no eterest wdl be charged #f the total amount a poed m fuit by the payment due date above NOTICE. One June 20. 1984 the NRC reveed its regoletons and adopted a revised Icense fee schedule (10 CFR 170L A copy of the revised regula-tions was mailed to all NRC licensees. The revesed schedule celudes the assessment of fees for facdity and matenals routme and non-routine inspectons
- This evo.ce shows the fee assessed for the recent mapoctonist conducted by the Office of Inspecten and Enforcement of your hcensed program 10 CFR 170 41 FAILURE 8I APPLICANT TO PAY PRESCRIBED FEES. In any case where the NRC finds that an applicant or a hcensee has failed to pay a prescribed fee required m the part, the Commason will not process any apphcaton and may suspend or revoke any hcense or approval asued to the appi. cant or heenaee or may asue an order wrth respect to licensed activites as the Commssion determenes to be approprote or necessary in order to l carry out the provtseons of thrs part. Parts 30,32 through 35,40,50,61. 70,71,72, and 73 of the Chapter, and of the Act.
10 CFR 170.61 RIGHT TO REVlfW AND APPEAL OF PRESCRIBED FEES. All debtor's requests for review of the fees assessed and appeal or dsagreement with the prescrced fee (sta# hours and contractual) must be submrtted m accordance wrth the provssons of 10 CFR 15.31. "Dsputed Debts " of the trtie. .
to CFR 170 61 RIGHT TO REVIEW AND, APPEAL OF PRESCRIBED FEES. AM debtor's requests for review of the fees assessad end appeal or dsagreement with the presenbod fee Itta# hours and contractualf must be submetted in accordance with the provesons of 10 CFR 15 31, "Desputed
- Debts." of thes title CONTACT. Questons rotating to the assessment of fees under the revrsed fee schedule and/or correctness of the address. call 13011 492 7225 or direct correspondence to U S Nuclear Regulatory Commesson Office of Adminsstraton License Fee Management Branch Washmgton. DC 20555 i
I730 W Attachment Facility Fee Bill (10 CFR 170.21(A))
Licensee: License No.: DPR-65 Northeast Nuclear Energy Company Docket No.: 50-336 ATTN: Mr. John F. Opeka Vice President, Nuclear Facility: Millstone 2 Engineering P.O. Box 270 Period: 12/22/85 - 3/29/86 Hartford, CT 06101 Inspection Review Costs Report Number Routine Reactive See attached Subtotal: $ 3,180 $ 769 Contract Costs: $ 1,139 $
Total By Type: $ 4,319 $ 769 Fee Code: AA903-INS-R AA903-INS-NR Total This Bill: $ 5,088
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A C F 0 7.M 200 Up, NUCLE Aa kE A ULATORY COMMISSION INVOICE NUMBER w, 1 1731W INVOICE FOR INSPECTION FEES FOR INVOICE DATE PA) MENT DUE DATE FACILITIES AND MATERIALS LICENSES SEP 3 01986 0CT 3 01986 LIC E NSE E MAKE CHECKS PAYABLE TO.
Northeast Nuclear Energy Company Attn: Mr. John F. Opeka Vice President, Nuclear RECEIVED ">~-'- -' ~"- -
o,,,,e o, R u,,, uan....ent Engineering oi.i ion at Accounun .anin.nc.
P.O. Box 270 OCT 3 g w.,n,n,,on, oC nis, Hartford, CT 06101 SENIOR Nu:Im. gnyinem.ngVICE
~~S! DENT n p,.....
PLANT PEE CATEGORY INSPE CTION AMOUNT DUE LICE NSE NUM BE R (10 CPR t?0) DaTE TYPE REPORT NUMBE R NPF-44 AA903-INS-R $75,810.00 AA903-INS-NR 6,782.00 TOTAL TERMS. Interest en accrue from the mvoice date at the rate of b % per annum. (see terms > $E2.592.00 except that no eterest ma be charged if the total amount e paid m fun by the payment due date above.
NOTICE. One June 20,1984, the NRC revoed its regulations and adopted a revised hcense fee schedule 110 CFR 1701. A copy of the revised regula-tions was mailed to all NRC bcensees. The revised schedule meludes the essessment of fees for facihty and matenals routme and non-routme mspections This mvo.ce shows the fee assessed for the recent inspection (s) conducted by the Office of inspection and Enforcement of your hcensed program.
10 CFR 170 41 FAILURE BY APPLICANT TO PAY PRESCRIBED FEES. In any case where the NRC finds that an apphcant or a hcensee has failed to pay a presenbed fee required in the part, the Commession mH not process any apphcation and may suspend or revoke any hcense or approval asued to the opphcant or hcensee or may asue an order eth respect to hcensed activites as the Commasion determenes to be appropnate or necessary m order to carry out the provis.ons of the part, Parts 30,32 through 35, 40, 50, 61, 70, 71, 72, and 73 of the Chapter, and of the Act.
10 CFR 170 51 RIGHT TO REVIEW AND APPEAL OF PRESCRIBED FEES. All debtor's requests for review of the fees assessed and appeal or disagreement eth the prescribed fee fsta# hours and contractuan must be submrtted m accordance with the provssons of 10 CFR 15 31 " Disputed Debts," of this tnie.
10 CFR 170 51 RIGHT TO REVIEW AND, APPEAL OF PRESCRISED FEES. AM debtor's requests for revew of the fees assessed and appeal or disagreement eth the prescnbod fee Ida# hours and contractus0 must be submitted in accordance with the provssons of 10 CFR 15 31, "Desputed Debts, of this title CONTACT. Questions retarmg to the assessment of fees under the revised fee schedule, and/or correctness of the address, call f301) 492-7225 or direct correspondence to U S. Nuclear Regulatory Commar, son
, Office of Admmestration License Fee Manager,ent Branch Washington, DC 20565
. - llblLY Attachment Facility Fee Bill (10 CFR 170.21(A))
Licensee: License No.: NPF-44 Northeast Nuclear Energy Company Docket No.: 50-423 ATTN: Mr. John F. Opeka Vice President, Nuclear Facility: Millstone 3 Engineering P.O. Box 270 Period: 11/25/85 - 3/29/86 Hartford, CT 06101 Inspection Review Costs Report Number Routine Reactive See attached l
Subtotal: $ 74,810 $ 424 Contract Costs: $ 1,000 $ 6,358 Total By Type: $ 75,810 $ 6,782 Fee Code: AA903-INS-R AA903-INS-NR
+ .
Total This Bill: $ 82,592 8
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