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MONTHYEARB12000, Proposed Tech Spec Revs,Expanding Storage Capacity of Spent Fuel Pool by Storing Consolidated Spent Fuel in Fuel Storage Racks1986-05-31031 May 1986 Proposed Tech Spec Revs,Expanding Storage Capacity of Spent Fuel Pool by Storing Consolidated Spent Fuel in Fuel Storage Racks Project stage: Other B12504, Submits Addl Info Re 860521 Application to Amend License DPR-65,allowing Storage of Consolidated Spent Fuel in Spent Fuel Storage Pool,Per 870309 Request.Sys Description of Consolidation Process Encl1987-04-30030 April 1987 Submits Addl Info Re 860521 Application to Amend License DPR-65,allowing Storage of Consolidated Spent Fuel in Spent Fuel Storage Pool,Per 870309 Request.Sys Description of Consolidation Process Encl Project stage: Request B12563, Forwards Summary of Consolidation Process Evaluation,Per NRC Request.Util Reviewed Hot Demonstration Consolidation Process & Determined That Project Safe & Technically Acceptable1987-08-11011 August 1987 Forwards Summary of Consolidation Process Evaluation,Per NRC Request.Util Reviewed Hot Demonstration Consolidation Process & Determined That Project Safe & Technically Acceptable Project stage: Other ML20236H0651987-10-30030 October 1987 Forwards Request for Addl Info Re Spent Fuel Consolidation at Facility Project stage: RAI ML20234D9621987-12-21021 December 1987 Forwards Fr Notice of Consideration of Issuance of Amend to License DPR-65 & Opportunity for Hearing Re 860521 Application for Storage of Consolidated Spent Fuel Project stage: Other ML20234D9991987-12-28028 December 1987 Notice of Consideration of Issuance of Amend to License DPR-65 & Opportunity for Hearing.Amend Deletes Footnote to Tech Spec 3.2.20, Spent Fuel Pool, Removing Limitation Restricting Storage of Consolidated Spent Fuel Boxes to 5 Project stage: Other A06896, Provides Response to Request for Addl Info Re Spent Fuel Consolidation,Per 881117 Telcon.Nrc Understanding Re Noninclusion of Temporary Storage Rack in Recent Tech Spec Change Request Confirmed1988-01-0404 January 1988 Provides Response to Request for Addl Info Re Spent Fuel Consolidation,Per 881117 Telcon.Nrc Understanding Re Noninclusion of Temporary Storage Rack in Recent Tech Spec Change Request Confirmed Project stage: Request A071168, Clarifies Util Containing Interpretation That 10CFR50.59 Would Govern Whether or Not Prior NRC Approval Required to Use Temporary Spent Fuel Racks for long-term Spent Fuel Storage1988-07-29029 July 1988 Clarifies Util Containing Interpretation That 10CFR50.59 Would Govern Whether or Not Prior NRC Approval Required to Use Temporary Spent Fuel Racks for long-term Spent Fuel Storage Project stage: Other 1987-12-28
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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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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) 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) 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 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 ML20212A9011999-09-10010 September 1999 Forwards Environ Assessment & Finding of No Significant Impact Re Application for Exemption,Dtd 990803.Proposed Exemption Would Provide Relief from Requirement of 10CFR50 ML20212A3171999-09-10010 September 1999 Discusses Investigation Rept 1-1998-045 Conducted on 981112 to Determine If Former Senior Health Physics Technician Being Denied Employment at Millstone in Retaliation for Having Raised Safety Concerns in Past.Synopsis Encl 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 ML20212A7501999-09-10010 September 1999 Forwards Staff Requirements Memo Response,Dtd 990525,which Provides Actions NRC Plans for Continued Oversight of safety-conscious Work Environ & Employee Concerns Program 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 ML20211K5171999-09-0202 September 1999 Expresses Appreciation for Support Provided for NRC Public Meeting on 990825 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 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 ML20211N9241999-09-0101 September 1999 Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures ML20211H0741999-08-30030 August 1999 Discusses GL 92-01,Rev 1, Rv Structural Integrity, Issued by NRC on 950519 & NNECO Responses for Millstone Unit 2 & 980715.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 Based on Response Review 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 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 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) 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 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 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 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 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 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 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 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) 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 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) 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 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 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 ML20211N9241999-09-0101 September 1999 Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures 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) 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 B17831, Informs NRC Staff That Change 3 to Rev 25 of Mnps Emergency Plan Was Implemented on 990715.Change Removes Facility Organizational Charts from Emergency Plan & Identifies Relocation to Nuqap1999-07-26026 July 1999 Informs NRC Staff That Change 3 to Rev 25 of Mnps Emergency Plan Was Implemented on 990715.Change Removes Facility Organizational Charts from Emergency Plan & Identifies Relocation to Nuqap B17834, Forwards Proprietary Revised NRC Form 398,which Certifies That SL Doboe Has Completed Eligibility Requirements for Sro,Per 10CFR55.31.Proprietary Info Withheld1999-07-20020 July 1999 Forwards Proprietary Revised NRC Form 398,which Certifies That SL Doboe Has Completed Eligibility Requirements for Sro,Per 10CFR55.31.Proprietary Info Withheld B17836, Forwards Revised NRC Form 396 & Supporting Physician Rept for Licensed Operator Restricted from Licensed Duties, Effective 990628,due to Medical Condition.Without Encl1999-07-20020 July 1999 Forwards Revised NRC Form 396 & Supporting Physician Rept for Licensed Operator Restricted from Licensed Duties, Effective 990628,due to Medical Condition.Without Encl B17811, Submits Response to NRC AL 99-02,requesting That Licensees Provide Numerical Estimates of Licensing Actions to Be Expected to Be Submitted in Fy 2000 & 20011999-07-20020 July 1999 Submits Response to NRC AL 99-02,requesting That Licensees Provide Numerical Estimates of Licensing Actions to Be Expected to Be Submitted in Fy 2000 & 2001 ML20210S9911999-07-18018 July 1999 Requests NRC Intervene for All Shareholders of New England Electric System & to Help with Merger with National Grid Group & That NRC Petition Security & Exchange Commission to Investigate Matter Relative to No Shareholder Options B17835, Forwards Rev 33 to Millstone Station Physical Security Plan, Per 10CFR50.54(p)(2).Licensee Determined That Changes Do Not Decrease Effectiveness of Plan.Rev Withheld from Public Disclosure,Per 10CFR2.790(d)(1)1999-07-16016 July 1999 Forwards Rev 33 to Millstone Station Physical Security Plan, Per 10CFR50.54(p)(2).Licensee Determined That Changes Do Not Decrease Effectiveness of Plan.Rev Withheld from Public Disclosure,Per 10CFR2.790(d)(1) B17818, Provides NRC Staff with Change to TS Bases Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only.Change Was Reviewed & Approved by Unit 3 Plant Operations Review Committee IAW Provisions of 10CFR50.591999-07-16016 July 1999 Provides NRC Staff with Change to TS Bases Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only.Change Was Reviewed & Approved by Unit 3 Plant Operations Review Committee IAW Provisions of 10CFR50.59 B17824, Forwards Monthly Oeprating Rept for June 1999 & Revised Monthly Operating Rept for May 1999 for Millstone Unit 21999-07-13013 July 1999 Forwards Monthly Oeprating Rept for June 1999 & Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20212K1701999-07-13013 July 1999 Submits Concerns Re Millstone & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Should Provide Adequate Emergency Planning in Case of Radiological Accident B17816, Provides Certification That M Lettrich,Has Completed Eligibility Requirements,Per 10CFR55.31 for Operator License.Util Requests That Licensing Action Be Taken for Named Individual1999-07-0101 July 1999 Provides Certification That M Lettrich,Has Completed Eligibility Requirements,Per 10CFR55.31 for Operator License.Util Requests That Licensing Action Be Taken for Named Individual B17801, Forwards 10CFR50.59 Annual Rept for Period Jan-Dec 1998. Various Changes That Were Initiated in Previous Yrs & Completed in 1998,also Incorporated Into Annual Rept1999-06-30030 June 1999 Forwards 10CFR50.59 Annual Rept for Period Jan-Dec 1998. Various Changes That Were Initiated in Previous Yrs & Completed in 1998,also Incorporated Into Annual Rept B17819, Forwards Rev 17 to FSAR & Addendum 6 to Annual Rept.Nneco Recently Completed Review of Unit 2 Design & Licensing Bases Which Resulted in Changes to FSAR Provided in Encl 1.Encl 2 Includes Info Covering Changes Not Included in1999-06-30030 June 1999 Forwards Rev 17 to FSAR & Addendum 6 to Annual Rept.Nneco Recently Completed Review of Unit 2 Design & Licensing Bases Which Resulted in Changes to FSAR Provided in Encl 1.Encl 2 Includes Info Covering Changes Not Included in B17780, Forwards Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) TR, IAW 10CFR50.54(a)(3).Changes to TR Are Shown as Text in Bold Italics1999-06-30030 June 1999 Forwards Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) TR, IAW 10CFR50.54(a)(3).Changes to TR Are Shown as Text in Bold Italics B17723, Responds to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for Units 2 & 3 Encl.Without Encl1999-06-29029 June 1999 Responds to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for Units 2 & 3 Encl.Without Encl B17767, Forwards Rev 12 to FSAR & Addendum 3 to Annual Rept, for Millstone Unit 3,per 10CFR50.71(e) & 10CFR50.4(b)(6). No New Regulatory Commitments Contained in Ltr1999-06-29029 June 1999 Forwards Rev 12 to FSAR & Addendum 3 to Annual Rept, for Millstone Unit 3,per 10CFR50.71(e) & 10CFR50.4(b)(6). No New Regulatory Commitments Contained in Ltr 1999-09-03
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A8071990-09-11011 September 1990 Forwards Core Operating Limits Rept for Four & Three Loop Operation,Per Tech Spec 6.9.1.6.d A08900, 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 ML20055G5331990-07-18018 July 1990 Forwards Decommissioning Financial Assurance Certification Rept A08822, Submits Addl Info Requested Re Util Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls. Charpy Impact Use Values for Welds Provided in Evaluation of Irradiated Capsule W-971990-07-18018 July 1990 Submits Addl Info Requested Re Util Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls. Charpy Impact Use Values for Welds Provided in Evaluation of Irradiated Capsule W-97 B13588, Corrects 900703 Submittal of Results of Second in-cycle Insp of Steam Generators.All Tubes W/Cracks Stacked & Plugged1990-07-18018 July 1990 Corrects 900703 Submittal of Results of Second in-cycle Insp of Steam Generators.All Tubes W/Cracks Stacked & Plugged B13587, Requests Temporary Waiver of Compliance from Tech Spec 3.5.F.2 Re Emergency Diesel Generator (EDG) Limiting Condition for Operation.Waiver Would Extend Available Time to Repair Damaged Electrical Components1990-07-16016 July 1990 Requests Temporary Waiver of Compliance from Tech Spec 3.5.F.2 Re Emergency Diesel Generator (EDG) Limiting Condition for Operation.Waiver Would Extend Available Time to Repair Damaged Electrical Components ML20055D3461990-07-0303 July 1990 Responds to NRC Bulletin 90-001 Re Loss of Fill Oil Transmitters Mfg by Rosemount.Operability Determinations Performed & Documented for All Rosemount 1153 & 1154 Transmitters at Facility ML20055D3481990-06-29029 June 1990 Forwards Addl Info Re Facility Crdr & Isap,Including Justification for Human Engineering Discrepancies Dispositioned for No Corrective Action ML20055D7191990-06-29029 June 1990 Amends 900604 Rev 13 to QA Program B13545, Forwards Rev 3 to Updated FSAR for Millstone Unit 31990-06-29029 June 1990 Forwards Rev 3 to Updated FSAR for Millstone Unit 3 B13550, Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl1990-06-27027 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl B13499, Forwards Corrected Tech Specs Page 3/4 9-1 for Incorporation Into Proposed Amend 36 to License DPR-21 Re Auxiliary Electrical Sys1990-06-26026 June 1990 Forwards Corrected Tech Specs Page 3/4 9-1 for Incorporation Into Proposed Amend 36 to License DPR-21 Re Auxiliary Electrical Sys ML20043F8721990-06-11011 June 1990 Corrects Name of Vendor Supplying Replacement Plug Valves, Per Util 900511 Ltr.Replacement Bolts,Not Valves,Purchased from Cardinal Industrial Products Corp ML20043H0161990-06-0808 June 1990 Requests Exemption from App J to 10CFR50 for 12 Valves in Reactor Bldg Closed Cooling Water Sys.Valves Not within Definition of Containment Isolation Valves in App J & Not Required to Be Tested ML20043E8831990-06-0505 June 1990 Requests NRC Authorization to Use Plugs Fabricated of nickel-chromium-iron Uns N-06690 Matl Alloy 690 to Plug Tubes in Steam Generators of Plant ML20043D0451990-05-30030 May 1990 Discusses Proposed Rev to Tech Specs Re Facility ESF Actuation Sys Instrumentation Trip Setpoint,Per 900330 Ltr ML20042H0311990-05-0909 May 1990 Discusses Steam Generator Safety Assessment.Concludes That Continued Operation Through Remainder of Current Cycle 10 Fully Justified ML20042F0941990-04-30030 April 1990 Provides Addl Info Re Environ Impact of 900226 Application for Amend to License NPF-49,revising Tech Specs to Allow Containment Pressure to Increase to 14 Psia During Modes 1-4,per NRC Request ML20042F0661990-04-30030 April 1990 Responds to NRC 900404 Ltr Re Violations Noted in Safety Insp Rept 50-336/90-01 on 900120-0305.Corrective Action:Ler 90-004 Submitted on 900430 to Document Condition Prohibited by Plant Tech Specs ML20042E8331990-04-27027 April 1990 Forwards Annual Environ Protection Plan Operating Rept for 1989, & Monitoring Marine Environ of Long Island Sound at Millstone Nuclear Power Station Annual Rept 1989. ML20012E2681990-03-23023 March 1990 Responds to NRC 900226 Ltr Re Violations Noted in Insp Rept 50-423/89-23.Corrective Actions:Requirement to Review All Changes on Safety Sys for Potential Operating Procedure Changes Stressed to Operations & Engineering Personnel ML20012C3141990-03-13013 March 1990 Forwards Info Re Insp of Facility Emergency Operating Procedures,Per 900119 Ltr ML20012B4111990-03-0202 March 1990 Provides Addl Info Requested to Clarify Changes Proposed to Tech Spec Action Statements for Inoperable Accumulator B13453, Advises That Mods to Steam Generator Blowdown Sample Sys Completed,Per Violations Noted in Insp Rept 50-423/89-14 & Salp.Sys Will Be Evaluated for Next 2 Wks to Ensure Blowdown Radiation Monitor Operating Reliably1990-02-26026 February 1990 Advises That Mods to Steam Generator Blowdown Sample Sys Completed,Per Violations Noted in Insp Rept 50-423/89-14 & Salp.Sys Will Be Evaluated for Next 2 Wks to Ensure Blowdown Radiation Monitor Operating Reliably ML20011F7541990-02-26026 February 1990 Notifies That Jh Parillo Reassigned & No Longer in Need of License SOP-10263-2 as of 900219 ML20006G1581990-02-21021 February 1990 Forwards Response to & Comments on Initial SALP Rept 50-423/88-99 for Period 880601 - 891015.Procedures Revised to Permit Operators to Adjust Area Monitors to Reduce Nuisance Alarms 1990-09-07
[Table view] |
Text
r- 1 o
o General Offices
- Selden Street, Berlin, Connecticut 9 a s*s exNm iuNw P.O. BOX 270
- * * * ' " * " " "" HARTFORD, CONNECTICUT 06141-0270 k k j 7d C'"C,"w",,",, (203) 665-5000 April 30,1987 Docket No. 50-336 B12504 Re: 10CFR50.36 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Storage of Consolidated Spent Fuel In May,1986,(I) Northeast Nuclear Energy Company (NNECO) submitted to the NRC Staff a request to amend its operating license, No. DPR-65, for Millstone Nuclear Power Station, Unit No. 2, to allow storage of consolidated spent fuel in the Unit No. 2 spent fuel storage pool. As a result of the NRC Staff review of this proposal, the NRC Staff forwarded to NNECO a Request for Additional Information (RAI).(2)
In a subsequent telephone conversation with the NRC Staff on March 17, 1987, the Staff stated that issuance of the requested license amendment would not be delayed pending resolution of this RAI and that the requested license amendment would be issued without proposed Technical Specification (TS) 3.9.19, which is addressed by the RAI. The Staff also stated that all other technical issues have been adequately addressed and that no further NNECO action is necessary for NRC issuance of the license amendment.
The purpose of this letter is to document our understanding of the status of the proposed license amendment and to provide the NRC Staff with the response to this RAI.
NRC Inquiry #1 Proposed TS 3.9.19 would require that candidate fuel assemblies (for consolidation) must have decayed for at ! cast 5 years. Please provide a Justification for the proposed decay time in terms of the consolidation process.
In this regard, you should provide a complete description of the consolidation process and an associated safety analysis.
(1) 3. F. Opeka !ctter to A. C. Thadani, dated May 21,1986, " Millstone Nuclear Power Station, Unit No. 2; Proposed Change to Technical Specifications, Storage of Consolidated Fuel."
(2) D. H. Jaffe letter to E. 3. Mroczka, dated March 9,1987, " Request for Additional Information, Millstone Unit No. 2, Spent Fuel Consolidation."
0705060156 870430 l PDR ADOCK 05000336 8 p PDR \
U.S'. Nuclear Regulatory Commission B12504/Page 2 April 30,1987
Response
The proposed TS 3.9.19 requiring that candidate spent fuel assemblies (for consolidation) have a 5-year decay time is not based on consolidation process considerations.
The May 21, 1986 submittal identifies that the thermal hydraulic design of the consolidated fuel storage box, as well as the design basis heat load for the spent fuel pool (with respect to 688 consolidated boxes), is based upon the 5-year decay criterion. (Refer to submittal pages 1-1, 1-5, 3-11 and Table 3.2-2).
This information is consistent with the March 30, 1984 submittal (3) to the NRC on NNECO's Spent Fuel Disposition Plans for Millstone Unit No. 2 and the May 17, 1984 Summary Meeting with the NRC in Bethesda, Maryland, as documented in the NRC Minutes, dated June 4, 1984.(4) Furthermore, the NRC Minutes identify that the 5-year decay criterion was specifically discussed as a conservative design basis for the storage of consolidated spent fuel.
Attached, for your information, is a copy of a system description on the consolidation process intended for use at Millstone Unit No. 2. Safety evaluations of this consolida:lon process are currently being conducted. NNECO intends to submit the results of these evaluations to the NRC Staff when complete.
NRC Inquiry #2 TS 5.6.3 provides for a total of 1346 storage locations in the spent fuel pool. The
, practical limit for fuel storage is 1277 locations due to the need to allow 5 years
- for decay time of fuel assemblies prior to consolidation. The remaining 69 locations would contain cell blocking devices. You should propose a revised TS 5.6.3, limiting storage to 1277 locations, or justify the need for 1346 locations.
Response
The above referenced paragraph 5.6.3 is the Capacity description that appears in the DESIGN FEATURES portion of the Technical Specifications. The purpose of this description is to delineate the actual number of storage cells associated with i the spent fuel rack inventory in the pool. This description does not establish the spent fuel capacity of the pool which is determined by; (3) W. G. Counsit to 3. R. Miller, dated March 30,1934, " Millstone Nuclear Power Station, Unit No. 2 Spent Fuel Disposition Plans for Millstone Unit No. 2."
! (4) D. B. Osborne to Northeast Nuclear Energy Company, dated June 4,1984,
" Summary of Meeting with NNECO on Spent Fuel Disposition Plans for Millstone Unit No. 2."
~
- U.S. Nuclear Regulatory Commission B12504/Page 3 April 30,1987
- 1. A letter to the NRC Staff, dated May 21', 1986', which states the capacity as 1965 fuel assemblies.
- 2. Attachment 2 to the May 21, 1986 letter, which states on page 1-5, that the storage restrictions and thermal load restrictions imposed by the cooling system establish the maximum spent fuel capacity of 1965 to be distributed as:
10 spare cells 362 Intact fuel assemblies with less than 5-year decay 217 reserved for full core offload 688 cells containing consolidated fuel @ 2:1 (equivalent to 1376 intact fuel assemblies)
- 3. Attachment t to the May 21, 1986 letter, the proposed TS 3.9.20 establishes the storage configuration requirements surrounding the presence or absence of the cell blocking device in Figure 3.9-2 of the
, submittal.
If the cell blocking device is surrounded by consolidated fuel, it may be removed and a consolidated storage box placed in the cavity location.
However, the cell blocking device's primary function is to prevent inadvertent usage of the blocked location when the area is occupied by intact spent fuel assemblies.
Statement (2) above indicated that 362 intact assemblies with less than a 4
5-year decay comprised part of the total capacity. Specifically,157 Intact assemblies would reside in Region I and 205 intact assemb!!es would reside in Region II, requiring 69 blocked locations to support the criticality bases for the assemblies in Region II.
3 Therefore, in order for the total spent fuel pool capacity to support a total spent fuel assembly inventory of 1965, the total spent fuel rack capacity 3
must be 1346 (i.e., 1277 plus 69), as stated in DESIGN FEATURE i Section 5.6.3.
We trust you find the above information responsive to your request.
4 Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY 1
E. J.Tirg' cilla' ~ '
Senior 41ce Preside nt //
cc W. T. Russell, Region I Administrator D. H. Jaf fe, NRC Project Manager, Millstone Unit No. 2 T. Rebelowski, Resident inspector, Millstone Unit Nos. I and 2
Docket No. 50-336 B12504 Attachment 1 Fuel Consolidation Demonstration Program Description April,1937
Rheud 1
- FUEL CONSOLIDATION DEMONSTRATION PROGRAM SYSTEM DESCRIPTION Fuel assemblies to be consolidated, having a mini-mum of 85% burnup and 5 years' oubsequent residence A conaolidation concept has been developed which time in the pool, are deposited in the temporary storage permits the coordinated disassembly of spent fuel rack by the spent fuel handling machine. Consolidation essemblies and subsequent repackaging of the rods into takes place in the work station frame, which supports dense close packed arraye. For this program,the actual seven individual work stations. A traversing carriage in plant work will be perfcrmtaed in the Millstone II on the work station upper plate aligns fuel manipula.
spent fuel pool cask laydown area. Here, as shown in ting equipment accurately with theindividual stations.
Fig.1, the respective work stations, fuel support com- The fuel is dissembled in the first station by cutting ponents, hoisting equipment, filtration system, and off the upper end fitting and then removing fuel rods various handling tools, which comprise the consoli-singly or up to one row at a time by means of a multiple dation system, are insta!!ed. Also located within this rod pulling tool (MRPT). Rod pulling forces are main-general area is the main control console from which tained between preset limits. Fuel rods are then deposit-cperations are maintained and controlled. A temporary ed in an interim transfer canister (ITC) st the next work storage rack, which ie serviced by both the fuel hand- station.The ITC has channels which guide the rodsinto ling machine and the consolidation system hoist, holds a close packed triangular array at the bottom. Damaged intact and consolidation assemblies. fuel rods are deposited in the damaged fuel rod storage station after being separated form the row in the separ-p ation/ recovery station. The fuel rods in the ITC are normally traneferred by gravity into a consolidated fuel
]' storage box located in the next work station. Descent of
,,,,,, l the rods is controlled by a telescoping cylinder through All 6 the bottom of the box. A rod transfer tool can also be used to assist in this operation if required.The close J ; packed triangular rod array resulta in a compaction ratio of 2:1. Ieckable covers are installed on the filled w ,g-
- consolidation fuel boxes before they are removed for
. .. , e a ,,,
?b ~ '- storage in the spent fuel pool.
Fuel assembly end fittings are placed in storage boxes e , at the end fitting storage station, for storage in the fuel l .p ;
q=,vp,g,g,,,vgigo pool since they have high activity. Zircaloy gnd cages and control guide tubes have much lower activity and sainei=o eass ae'* are compacted by hydraulic cylinders in the compaction ews: sisa ssemet, station, for transportation to a radwaste disposal
'o stem hdty evat teams se i avion A filtration system is connected to the fuel disassem-stosaos s'a'io= bly, ITC, transfer and compactor work stations to
, !"!,,'f',""
,,,,,,,,,,1,, * "(',(' *( * ',
,, fN. . .*,*,j',jy;'" collect and filter out radioactive particulates generated j,';o," "" a hoa , . , , , c , , , , , ,,,, by operations performed at these stations.The MRPTis l
f NN s'a'io= enclosed by a shroud assembly which provides guid.
{e g I basemeationie:covse, ance and alignment, and vents released gases to the l
en'ea' ion l g j "'"*" plant gas handling system.
The consolidation system is controlled from a panel at 1 y temposae, stosas esca a work platform on the hoist assembly. Controllogic ia programmable to allow for changes as experience is gained. A TV system is provided for remote viewing of g
all consolidation operations. The overall process la Fig.1. Fuel Cohsolidation Equipment Layout. depicted in the Fig. 2 flow chart.
I t
l _
m- _
Gttc6c.bc.d 1.
BW504 ternal tubing cutter. The consolidation system require:
, j I the use of three variations of this cutter for MillstoneII
........e... fuel, because there are three possible diameters to con-e... s.. e.. e......a t : e v.
e..i s. v....... , s.d e.*... se..... e.' tend with in removing upper and lower end fittings.
... They are as follows-
- 1. Upper end fitting removal of an unsleeved fuel
[ ......a n c assembly.
***pa*'.*' v. v....e., s . ..
- 2. Upper end fitting removal of a sleeved fuel assembiy.
y * - 4
- 3. Cutting within the necked <!own area of the guide i,..... ....
...... a.,....... tube for removal of the lower end fitting.
.....e.,..... , ' *-
, ' , , 'a The commercially available cutter tool bit angles
} ... 4 utilized in the guide tube cutter have been optimized to e.....e....... i .....a n c
"*"'" give reasonable cutter life with an improved cut, which I has no "curlycue" or loose fragment. while also pro-4 8apa's ce*** *ad viding good penetrating characteristics.
c .. i .. .. s. a e.a... - t.. o. c... s..
e... .e a.4 i,..... v.
o,.4 c . . . a . .. . si . i... s,..... e..i 4
i..... .... c... o a... e... c . . . . . ... ,,,,,,,,,,,,
e..i a w . . c .......
4
- v. se... e..e e..i i
I
a.pa * * =......,.i.44.....,.i..
t... s...... e...
Fig. 2. Process Flow Chart.
EQUIPMENT DESCRIPTION The following equipment has been designed and fabricated for use in the program.
Interim Transfer Canister (ITC)
The ITC, shown in Fig. 3, serves to guide the rods from a rectangular array into s triangular array.This is accomplished by providing each rod with a straight line path from top to bottom through an upper gridded sec-tion and a lower section of gradually occurring converg- ,
h ,[p' ing corrugations. !
Attached to the bottom of the canisteris a gate mech-anism, which supports a transferable bottom during '
loading and while transporting fuel from the ITC station to the transfer station.The gate mechanism also alicws the transfer piston to pass through and accept the load of the fuel rods. Actuation of the gate mech-anism allows for the release of the floor for a controlled tran*fer of rods from the ITC into the consolidated canister. the floor then becorning the base of the con-
- ** **" # ##' Mulitple Rod Pulling Tool (MRPI')
The multiple rod pulling tool as shown in vig. 4 is Guide Tube Cutter A guide tube cutter is used to disassemble the fuel comprised of three sub assemblies: the pulling head, the assembly. The guide tube cutter is a single pass. in- shroud and. the mast.
Rhchmed 1 tuzso9 y unao e'= gauge the maximum allowable rod diameter. If a fuel
. O ive,' "neen cas casus rod has an excessive diameter or localized blister,it will
- "3 W " not pass through the alignment bar. Rod slippage will
' occur and identify a possibly damaged rod.The align-a / *.'iIIM&M'."'""
ment bar is then partially retracted to allow the local.
ized deformation to pass by, s.nd then closed to continue alignment and gauging operations.
, , p,3
'i evw=o asas sneovo \ Fi Filter System I. The filter system consists of two pump and filter unita eutono miao N OW' running in parallel, manifolded to four work stations to
N provide positive downward flow in each station.The pump and filter units are sized to ensure sufficient
/u'c o OIle"Ei, Yi velocity at the MRPT and work station interface in l
k e ,[p. order to entrain and filter out released crud before it can i
disperse within the cask laydown area.
The filtering occurs in several stages to minimize
/) """IIs'iIio'A a '=i isvoimia W .' filter usage and therefore minimize the volume of waste v$
,vmI,N,'iaY[vneen 4
evaimo asao avios sae ,
'"'" products. A strainer at the pumpinlet protects the pump
'"" $ v,,,*',",',b . > es,uan sumo caesu,, from large chips.The filter also collects zirconium alloy
.,'), It chips which may be released in the consolidation effort, Downstream of the pump are two additional stages of
,,,n,,,,,,,, m *i* ty i
..,, r filtering.
ano.o.ime....
i=> eini m
- insa (k*. Volume Reduction Systent/ Compactor
,,ve', o"',',', Q $
eun eco avo==ini sans -t . . ,,vn son The volume reduction system depicted in Fig. 5,is a F hydraulic powered compactor which systematically shears sections of the grid and grid guide tube assembly Fig. 4. Multiple Fuel Rod Pulling Tool. and compacts each section in three directions to form briquettes. The briquettes are then loaded into a waste box and further compacted to achieve a 10:1 compaction The shroud assembly sits on a X.Y positioning table ratio.
cnd can be located above any of four stations (i.e., fuel disa ssembly, ITC, separation. or da ms ged fuel rod).The mast and pulling head assemblies are supported on the '
hoist assembly, and are guided by their shroud during s their vertical travel.The pulling head is the mechanism that graples from one to fourteen fuel rods for removal 4 a/ [
from the fuel assembly.The grippers of the pulling head [
can be oriented to pull up to one row of fourteen rods. N Each gripper can be individually controlled from the 5 main console to either release a rod, or pull the rod with -
/ ii c maximum preset force.Preloaded springs provide fail. '
- l
[
safe gripper closure and a detection system provides information to controllogic regarding rod penetration e .
,l ,
l into the grippers and rod slip. Detection of rod slippage G e
/g'9 immediately stops the hoist pull and informs the opera-O tor of which rod has slipped. \
The fully enclosed shroud is vented to the plant's gas handling system to capture any released gases. Remote- / [
ly Ietractable fuel rod alignment bars are located at the 4
, /\
k [
bottom of the shroud.The alignmentbars are retracted a N to allow the pulling head to exit the shroud and ...ple r/ f. (
the fuel rods. As soon as the pulling head is lifwd past .
(
\
i
[Te l
them, the alignment bars, are closed to maintain precise fuel rod alignment for correct insertion into the ITC.
Fig. 5. Compactor,
.I These fuel rod abgnment bars are also designed to i
b 3
R b c. b e d 1.
. 0125cy Consolidated Fuel Storage Box Temporary Fuel Storage Rack The consolidated fuel storage box shown in Fig. 6,is The temporary fuel storage rack is a free-standing sized to accept the fuel rods from two fuel assemblies anembly, located within the cask laydown area, and is und to temporarily store 9 fuel assemblies in a Sm3 reconfigured into a tightly packed triangular array, The consolidated fuel storage box contains the floor array for batch processing.The spent fuel pool can then be isolated from the processing area by installation of which is transferred from the interim transfer canister to the fuel storage box.The floor design includes flow the cask laydown gate, thus minimizing crud'infil-holes to allow for cooling of the consolidated fuel tration and accidental contamination of the spent fuel assembly. A locking cover assembly is installed mto the pool during the fuel consolidation process.
upper portion of the consolidated fuel storage box to Hoist Assembly contain the fuel rods. The cover design permits grap-pling of the loaded storage box in a manner similar to The gantry styled hoist assembly,similarin design to grappling of the spent fuel assembly. Alocking tab, not the spent fuel handling machine, spans the cask lay-designed to be removable, provides for visual fuel down area, and the assembly is guided on parallel rails accountability.
installed at deck level.The track rails extend beyond the cask laydown area to permit " parking" of the hoist assembly in a remote area, allowin g the spent fuel hand-ling machine to maneuver within the cask laydown area. The hoist assembly has a 6,000 pound load capae-ity with a total vertical travel of 52 feet 22 feet of which " -
is above deck level. g j '
Control Console l
The main control console, located on the work plat- * *-
form of the hoist sesembly, houses a programmable f.
controller and the readouts and controls for the hoist -
i assembly, compactor system, multiple rod puller, filter l ,
system, X Y positioning table and TV system. This l
prorrammable controller monitors the entire fuel con- + !
solidation process, and the controller interfaces the logic of the numerous controls to minimize operator error. In addition, the programmable controller facil-ities modification of the process logie as experience is j
gained. -
t' Lower Work Platform f y 1_
The main fuetion of the lower work platform is to support the individual stations listed below:
- 1. Fuel Disassembly Station I I I U I I
- 2. Interim Transfer Canister Station *
- 3. Damaged Fuel Rod Station
- 4. Separation /Hecovery Station
- 5. End Fitting Station Fig. 6. Consolidated Fuel Storage Box and Cover Assembly.
- 6. Fuel Rod Transfer Station
- 7. Compactor Station The lower work platform is supported by the cask lay-down area floor. Adjustable support pads are incor- METHODS DEVELOPMENT ANDTESTING potated into the lower work platform design for proper The fuel consolidation process resulta in rearrange-leveling and load distribution. The platform is located ment of fuel rods from a square or triangular pitch and and stabilized by brackets tied to pool wa!! embed. from a spaced to tight packed array. The analytical i
menta. methods used to satisfy safety and licensing require-
! TV Systerr. ments for seismic, criticality, and thermal hydraulic design analysis were modified to account for these A three camera TV system monitors all aspects of the changes.The following discussion highlights the work process. The monitors and a video recorder are located completed on this aspect of the program.
in the main control console on the work platform.
4, a- --
Abc.beM i
'~
iW2.5&f been completed on a full scale 19 rod triangular Storage Box Loading Configuration Testing pitch heated test section with rods in contact. Test The goal of this effort was to achive a 2:1 consolida. results indicate significant conservatism in an-tion ratio. Packing test with actual depleted UOs rods alytical methods for friction pressure drops and for having the dimensions of Millstone II fuel were per. these tight packed arrays the decay time prior to formed and a optimum storage box was designed.The consolidation may be reduced.
resulting metal to water ratio has been used for seismic, 3. Perform T H design analysis to demonstrate that criticality, and th'ermal hydraulic modeling and the consolidated spent fuel storage design meets analysis. the criteria that bulk boiling of the pool does not Seismic and Structural Testing occur and that maximum fuel clad temperature does not exceed 650*F during both normal oper.
The purpose of this work was to develop analytical f ation and accident conditions.This work has re-
' models and methods for seismic analysis of spent fuel sulted in a consolidated storage rack design which I
racks and storage pools. Full scale tests covering load meets the thermal hydraulic design criteria.
deflection, local stiffness and forced vibration of a loaded storage box have been performed to determine DESIGN AND ANALYSIS characteristics not easily determined by analytical means. Based on this work, model/ test correlation of In this phase of the program, the analytical methods natural frequency, damping and local box stiffness developed were utilized to complete detailed design and properties was performed. Further, a model for the fabrication of the consolidation hardware. Also, the storage box / fuel rack / fuel pool combination was de. developed analytical methods for seismic, criticality, veloped for use in nonlinear time history seismic and thermal hydraulics were used to design racks for storing consolidated fuel.
"""IY'8-Radiological Considerations Criticality It was concluded that fuel consolidation can be per-The purpose of this work was to revise the normal formed at Millstone II with the system developed in the light wster criticality analysis methods for higher rod program with minimal exposure to the plant operators.
density and triangular rod pitch. A calculational model In general, radiation levels due specifically to normal has been developed for use in design and licensing of consolidation operations are very low relative to the consolidated spent fuel racks and has been defined and spent fuel storage pool area radiation level. In the case vertified against existing critical experiments. This of consolidation equipment malfunction, the operator modelis based on a homogenized fuel module represen. dose is well within NU's administrative limits, which tation and 16 neutron energy groups which is suitable are themselves more stringent than 10CFR20 limits. It for design use in both KENO and DOT type analyses. was also concluded that, in the most severe accident The model yielded multiplication factors for critical ex. postulated during fuel consolidation, the dropping of a periments which are comparable to those obtained with loaded consolidation storage box, the site boundary 123 neutron energy group KENO calculations employ.
dose is well within 10CFR100 limits.
ing a more detailed spatial model.
Another aspect of this work is the evaluation of EPRI Spent Fuel Pool Cooling methods for reactivity monitoring and the testing The plant spent fuel cooling system capacity was l of a reactivity monitor for use in a hot consolidation found to be insufficent for the normal operation design demonstration at Millstone II. basis condition with the maximum quantity of spent
' fuel stored in the pool.The addition of a heat exchanger Thermal Hydraulics or technically specifying the allowable pool temper-The objectives of this work were to: ature was recommended. No change was necessary to
- 1. Develop analytical methods for use in evaluating conform to the abnormal operation (fuel core offload) consolidated spent fuel pool thermal hydraulics by design basis.
l1 It is recomended that the cask laydown pool water be I modifying appropriate existing T.H computer codes. VIPRE, GF14W, and CEPOOL were kept isolated from the spent fuel storage pool water by f examined and CEPOOL was selected for design means of the transfer gate during consolidation oper-analysis because it is a proven licensing tool,is ations to prevent contamination from s..tcring the more conservative and requires less computer time spent fuel pool. A submersible filtration unit should be available to clean up any accidental release of crud to than the others.
the cask laydown pool. Separate cooling should be
' 2. Perform heated flow tests to provide thermal hy-draulic data for triangular pitch flow channels to provided for the removal of heat generated in the cask laydown pool by fuel assemblies awaiting consolidation verify analyticalT.H methods. A test program has n
%e%eh 1
~
. ' Bia soy and while being consolidated. Circulation of cooling w:ter through a simpie pipe loop immersed in the pool world be adequate. The decay heat from candidate assemblies is low since they must have reached 85% of design burnup and have been discharged from the re-actor for at least five years.
9
-9
_ _ _ _ _ .