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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 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 Amend Deletes Certain TSs Either No Longer Applicable to Permanently Shutdown & Defueled State of Reactor or Duplicate Regulatory Requirements B17901, Submits Statement of Personal Qualification (NRC Form 398)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 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 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 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 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 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 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) 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 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 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 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 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 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 1999-09-30
[Table view] Category:OUTGOING CORRESPONDENCE
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 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 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 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 ML20212L1261999-10-0404 October 1999 Forwards Viewgraphs Presented by Licensee at 990923 Meeting with Nrc,In Response to Request 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 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 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 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 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 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 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 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 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 ML20216J1341999-09-28028 September 1999 Ltr Contract:Task Order 49, Millstone Units 2 & 3 Employee Concerns Program Insp, Under Contract NRC-03-98-021 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 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 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 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 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 ML20211K5171999-09-0202 September 1999 Expresses Appreciation for Support Provided for NRC Public Meeting on 990825 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 ML20211H9971999-08-27027 August 1999 Forwards Insp Rept 50-423/99-07 on 990614-0715.Violations of NRC Requirements Occurred Re Adequacy of C/As for Organizational Changes & Being Treated as NCVs DD-99-09, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-09) Expired.Commission Declined Any Review & Decision Became Final on 990823.With Certificate of Svc.Served on 9908261999-08-26026 August 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-09) Expired.Commission Declined Any Review & Decision Became Final on 990823.With Certificate of Svc.Served on 990826 ML20211F5841999-08-23023 August 1999 Discusses Proposed Rev 21 to Northeast Utils Quality Assurance Program TR for NRC Review & Approval,Iaw 10CFR50.54 ML20211D5701999-08-20020 August 1999 Informs That in May 1999,Northeast Nuclear Energy Co, Restarted Millstone Nuclear Power Station,Unit 2.Licensee Has Been Tasked Charter with Listed Specific Responsibilities ML20211E8051999-08-20020 August 1999 Forwards Insp Rept 50-213/99-02 on 990420-0719.No Violations Noted.Completion of Corrective Actions for Spent Fuel Bldg Ventilation Issues Adequate ML20211C4621999-08-18018 August 1999 Discusses Rev to TS Bases Sections 3/4.5.2 & 3/4.5.3, Emergency Core Cooling Sys Subsystems ML20210S9611999-08-13013 August 1999 Informs That NRC Received Encl Ltr from Pb Johnston Expressing Concern About Certain Impacts on Shareholders of New England Electric Sys with Respect to Nees Proposed Merger with Natl Grid Group ML20210S9511999-08-13013 August 1999 Responds to to Collins Expressing Concerns with Certain Terms of Proposed Merger Between New England Electric Sys & National Grid Group.Nrc Has No Authority to Interject Itself in Nees Merger with National Grid Group ML20210N4921999-08-0909 August 1999 Ack Receipt of 990331 Electronic Transfer of $88,000 for Civil Penalty,Proposed on 990309.Corrective Actions Will Be Examined During Future Insp ML20210J6021999-08-0202 August 1999 Informs That Info Re Orise Technical Survey Assistance to NRC at CT Yankee Is to Include Copies of Listed Documents ML20210C0751999-07-21021 July 1999 Forwards 990721 Notice of Public Meeting Re post-shutdown Decommissioning Activities Rept ML20210A9681999-07-14014 July 1999 Responds to Re Changes to Millstone Physical Security Plan Identified as Rev 32,submitted Per Provisions of 10CFR50.54(p).No NRC Approval Is Required,Based on Util Determination That Revs Do Not Decrease Plan Effectiveness ML20209E7341999-07-12012 July 1999 Discusses Util Responses to GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. Responses Acceptable.Info Revised in Reactor Vessel Integrity Database (Rvid) & Is Releasing as Rvid Version 2 ML20209G2921999-07-0909 July 1999 Forwards Insp Repts 50-336/99-06 & 50-423/99-06 on 990420-0614.Ten Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20210C1491999-07-0101 July 1999 Responds to ,Which Responded to NRC Ltr & NOV & Informs That Engagement in Any Similar Wrongdoing in Future May Result in More Significant Enforcement Action. No Further Action Will Be Taken at This Time DD-96-23, Informs That on 961226,NRC Issued Partial Director'S Decision DD-96-23,in Response to Petition Submitted,Per 10CFR2.206,on 9508211999-07-0101 July 1999 Informs That on 961226,NRC Issued Partial Director'S Decision DD-96-23,in Response to Petition Submitted,Per 10CFR2.206,on 950821 ML20196J5031999-06-30030 June 1999 Responds to 990414 Petition,Submitted Per 10CFR2.206 to Nrc. NRC Solicited Support from FEMA to Ensure That Appropriate Response to Enhancements Identified to Offsite EP in Event of Radiological Emergency at Millstone,Developed ML20196J2111999-06-30030 June 1999 Forwards SE Concluding Licensee USI A-46 Implementation Program Meets Purpose & Intent of Criteria in Generic Implementation Procedure for Seismic Verification of NPP Equipment, Rev 2 ML20196J1131999-06-29029 June 1999 Forwards Notice of Receipt & Availability for Comment of Post-Shutdown Decommissioning Activities Rept, Re .Notice Provided for Public Comments to Be Submitted within 30 Days of Notice Date ML20196G9531999-06-24024 June 1999 Discusses Changes Provided by NNECO on 990504 to TS Bases Sections 3/4.7.7 & 3/4.7.8.Returns TS Bases to NNECO to Be Inserted in TS to Ensure That NRC Staff & NNECO Have Identical TS Bases Pages ML20212H9661999-06-21021 June 1999 Confirms 990611 & 14 Telcons with M Selden,In Which Beckman & Assocs,Inc Was Advised to Stop Work Under Mod 4 to Task Order 005,under Contract NRC-03-98-021 ML20212J0751999-06-15015 June 1999 Forwards Notice of Withdrawal of Amend Request for Allowed Outage Time Extensions for Emergency Diesel Generators & Low Pressure Safety Injection Trains of Emergency Core Cooling Sys ML20195K0601999-06-15015 June 1999 Forwards Request for Addl Info Re fire-related IPEEE Analysis,Per GL 88-20 1999-09-30
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l g \ UNITED STATES
} NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. enana annt
$g% December 23, 1996 Mr. Francis J. Limerick l Mrs. Mary Limerick 47 Strickland St.
Manchester, CT 06040
Dear Mr. Francis and Mrs. Mary Limerick:
I am responding to your letter of August 8,1996, to President Clinton, which was forwarded to the U.S. Nuclear Regulatory Commission (NRC) for review and appropriate action on October 18, 1996. In your letter, you expressed concern about the NRC's oversight of the Millstone and Haddam Neck nuclear plants and the impact of the plants being shut down upon the State of Connecticut.
Before addressing your concerns, I would like to provide some background on the situation leading to the shutdown of the three Millstone units. The decline in safety performance at the Millstone facility during the past several years has been recognized and documented by the NRC staff. Declining performance has been a matter of discussion in NRC systematic assessment of licensee ~ performance (SALP) reports and the subject of discussion at NRC senior management meetings. During the last several years, there have been numerous and significant enforcement actions taken against Northeast Utilities (NU) for noncompliance with NRC's requirements. Although the NRC staff has pursued issues regarding performance problems at Millstone, the extent of the I performance problems and the ineffectiveness of NU's actions to correct the problems were not fully recognized by the NRC until recently.
The decision to shut down the Millstone plants was made by NU. Millstone Unit 1 shut down in November 1995 for the normally scheduled refueling outage; Millstone Unit 2 shut down in February 1996 because of concerns about I excessive suction strainer hole sizes in the containment sump screens; and Millstone Unit 3 shut down in March 1996 because of inoperable containment isolation valves in the auxiliary feedwater system. As the NRC staff became aware of NU's failures to address long-standing safety concerns, the NRC staff acted to put in place requirements that must be addressed before the Millstone units are restarted (Enclosure 1 contains the specific actions the staff has taken to address issues related to the Millstone site).
, Currently, the NRC's attention is focused on two areas of NU performance:
corrective actions and employee concerns. Because of concerns about the history of programmatic weakness and failures to implement effective corrective actions in the area of design and configuration control, the NRC staff identified a need for an independent review to verify the adequacy of NU's efforts. This effort was announced during the Chairman's visit on August 6, 1996, to the Millstone site. Second, because of concerns about the handling of employees' concerns about safety at Millstone, a senior l Headquarters manager led an evaluation of the history of how NU and the NRC
, have handled employee concerns and allegations related to licensed activities j at Mil; stone. These two areas are further discussed in the enclosure.
1
- Tai ngag
- nagg 6 NRC FILE CENTEll COPY l
P PM
NU has designated a recovery organization for each of the Millstone units to focus attention on action needed for plant startup. NRC's" oversight ~of the ,
restart of the Millstone plants will consist of several major elements, including the issues that have contributed to the decline in performance at all three plants. Salient concerns include communications (employee concerns), the corrective action program, procedural adherence and procedure upgrades, work planning and control, and operational enhancements.
. Before the startup of each of the Millstone units, the NRC will perform an operational safety team inspection (OSTI), which will be tailored to the restart of each unit. The OSTI will cover self-assessments by NU, NU's implementation of its startup plan, control room observations during the !
approach to criticality and power ascension, selected system readiness 1 inspections, and observation of management oversight. The NRC staff has met and will continue to meet with representatives of NU and the public regarding )
the major elements of this restart process.
Effective November 3,1996, the NRC formed a Special Projects Office to focus on oversight, inspection, and licensing actions associated with the Millstone and Haddam Neck sites. The Special Projects Office will make a recommendation regarding restart. The staff will inform the Comission of the staff's and NU's restart activities through Comission papers or comunications to the NRC's Executive Director for Operations. The Comission will then vote on whether to approve the restart of each Millstone unit.
The NRC acknowledges concern about the potential effect of NRC regulatory actions on NU and the public. The mission of the NRC, as provided in the Atomic Energy Act of 1954, as amended, is to ensure adequate protection of public health and safety from radiological consequences of the use of nuclear power. The NRC is dedicating resources to ensure prompt reviews and response to requests regarding licensing actions related to restart of any of the Millstone units. The NRC staff will recomend to the Comission the restart of each unit at the earliest opportunity consistent with this mission. '
Regarding Haddam Neck, on July 22, 1996, the plant commenced a shutdown required by the Technical Specifications when it was discovered that the containment air recirculation fan service water piping may exceed design loads ,
during certain accident scenarios. Because of hardware and programatic I concerns identified before and during this forced outage, NU determined that the concerns should be resolved before restarting the plant. Because of the significant concerns noted by the NRC and NU, on August 9, 1996, the NRC issued a request for information regarding NU's basis for continued operation of Haddam Neck. NU has responded partially to this latest request. However, based on an economic analysis, the owners of Haddam Neck have decided, and recently announced on December 4, 1996, that the Haddam Neck plant will be retired and will not be restarted. The cost of fixing the hardware and programatic concerns that were required to be corrected before startup of the plant were not a significant factor in this decision.
I
, . 4 i !
1 Regarding your conenent on assignment of a full-time person at the plants, in ~
1977 the NRC initiated a program to station resident inspectors at each nuclear power plant under construction and in operation. The NRC later expanded the program to provide at least two resident inspectors at each of the 71 nuclear power plant sites (Millstone currently has 6 resident inspectors). By assigning resident inspectors to reactor sites, the NRC significantly increased the agency's onsite monitoring of the plants. This increased monitoring provides a greater opportunity to ensure plant safety by
- observing the licensee's activities, verifying the licensee's compliance with l 1
NRC's requirements, and responding to operational events at the plant. In l l addition, engineers and specialists from the NRC regional office and
! Headquarters perform ' periodic and special inspections that supplement the '
residentinspector's;effortsinawidevarietyoftechnicaldisciplines.
Finally, the reliability of the U.S. bulk electric power system is the :
responsibility of the North American Electric Reliability Council (NERC) and its regional councils. The Connecticut area is under the Northeast Power !
Coordinating Council (NPCC). These councils monitor and evaluate the power l situations in their regions based on the availability of all power generation including nuclear plants. If they identify reliability problems, actions are taken to address the situation such as was done in Connecticut last spring and I summer. However, in some limited situations such as very hot weather, the '
actions required to maintain critical portions of the electric system may get ;
to the point where power to some customers is temporarily cut off. !
The U.S. Department of Energy has been heavily involved in investigating recent power events in the west, and in their August 2, 1996, report to President Clinton stated that the " current system of voluntary self-regulation with respect to reliability remains the best overall scheme for ensuring reliability in the future."
I trust this information is responsive to your concerns.
Sincerely, 1
f -
P O g, Office FrankofJ.Nuclear MiragliReactor
, Jr., Acting Regulation Director Docket Nos. 50-213, 50-245, 50-336, 50-423
Enclosure:
NRC Actions Regarding Millstone l
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NRC ACTIONS ADDRESSING COMPREHENSIVE LESSONS LEARNED FROM THE MILLSTONE EXPERIENCE l
Millstone-Snecific Actions -
In January 1996, a senior NRC regional manager was assigned to oversee l NRC's monitoring of Millstone operations. Similarly, at NRC '
Headquarters, a senior manager was assigned licensing responsibility solely for the Northeast Utilities (NU) plants. Additionally, the NRC increased the number of resident inspectors at Millstone from five to six.
- A senior Headquarters manager led an evaluation of the history of how NU and the NRC have handled employee concerns and allegations related to licensed activities at Millstone. The review included indepth case studies of selected employee concerns and allegations to identify root causes, common patterns among cases, and lessons learned. An independent NRC review has concluded that the work environment and l
failures of NU management are primary reasons for the continuing l employee concern problems at Millstone. Concurrent with issuing the NRC l
team's report, the NRC has issued an order that directs NU to devise and implement a comprehensive plan for handling safety concerns raised by Millstone employees and for ensuring a work environment free of-l retaliation and discrimination. Further, the members of the independent third-party organization must not have had any direct previous involvement with activities at the Millstone station, and the technical l qualifications of the team members' must be approved by the NRC, along l with NU's oversight plan. The NRC staff will review the team's report I anu NU's response to the team's findings for restart issues as well as 1 l for potential enforcement actions. I
- A senior Headquarters manager is leading an evaluation of the NU layoffs in January 1996. The group is examining whether there is any evidence i to suggest that employees engaged in protected activities were likely to have been discharged for raising concerns. This review is ongoing.
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- On December 13, 1995, the NRC issued a letter to the licensee for Millstone Unit I requiring it to inform the NRC, pursuant to Section 50.54(f) of Title 10 of the Code of Federal Reaulations (10 CFR 50.54 (f)), of actions it would be taking at Millstone Unit I to ensure that future operation of that facility would be conducted in accordance with the terms and conditions of the plant's operating license, the Commission's regulations, and the updated final safety analysis report (UFSAR). On February 22, 1996, the licensee issued Adverse Condition l Report 7007, " Event Response Team Report," which describes in detail the underlying causes for numerous inaccuracies contained in the UFSAR for Millstone Unit 1. On March 7 and April 4, 1996, the NRC issued similar letters to the licensee requiring it to inform the NRC, pursuant to 10 CFR 50.54(f), of actions it would be taking at Millstone Units 2 and 3 to ensure that future operation of the facilities would be conducted in
! accordance with the terms and canditions of each plant's operating I license, the Commission's regulations, and each plant's UFSAR. i r
t
. In February 1996, the NRC staff informed NU that a special team l
inspection would be conducted at Millstone to evaluate the methods and processes NU had used to handle degraded and potentially nonconforming plant conditions, including issues affecting the operability of plant equipment. This effort focused on Millstone Units 2 and 3 but was expanded to include the Haddam Neck plant. The team's report that addrerssed concerns pertaining to Haddam Neck was issued on July 31,
! 1996. The report for Millstone was issued on September 20, 1996, i
l
- In January 1996, the NRC placed the Millstone facility on NRC's " Watch List" as a Category 2 facility. Plants in this category have been l identified as having weaknesses that warrant increased NRC attention.
The NRC staff based its actions on the numerous problems identified by both the NRC and the licensee, associated NRC enforcement actions, and the repeated failure of the licensee's corrective action programs to prevent recurrence of these problems. In June 1996, at the direction of the Comission, the staff informed NU that the Millstone site had been designated a Category 3 facility. Plants in this category have significant weaknesses that warrant keeping the plant shut down until the licensee can demonstrate to the NRC that adequate programs have been established and implemented to ensure substantial improvement. A Category 3 rating would also require the NRC staff to obtain the Comission's approval by vote before the plant can restart.
- To ensure that the NRC restart review efforts provide objective measures of restart readiness for each Millstone unit, the NRC staff will follow the process outlined in NRC Inspection Manual Chapter 0350, " Staff Guidelines for Restart Approval." This process will provide assurance that the Millstone units can meet NRC regulations and requirements. If the Comission approves restart, each unit will be placed on the Watch List in Category 2, where they will remain until they have demonstrated that satisfactory performance can be sustained.
- Because of concerns about the history of programatic weakness and failures to implement effective corrective actions in the area of design and configuration control, the NRC staff identified a need for an independent review to verify the adequacy of the licensee's efforts. On August 13, 1996, the licensee submitted its plan and comitment for an independent review. On August 14, 1996, the NRC staff issued the Confirmatory Order Establishing an Independent Corrective Action Verification Program (ICAVP), which confirmed the licensee's comitment to conduct this independent review for each of the Millstone units.
- The NRC has established a Special Projects Office within the Office of Nuclear Reactor Regulation to oversee inspection and licensing activities at the Millstone site. In addition to licensing and inspection activities, the Special Projects Office will be responsible for (1) oversight of the ICAVP, (2) oversight of NU's corrective actions related to safety issues involving employee concerns, and (3) inspections necessary to implement NRC's oversight of the plant's restart activities.
Generic Actions "
The staff reviewed the current licensing basis for the spent fuel pool decay heat removal system and the core offloading practices at all operating reactor facilities. On the basis of the information collected and reviewed, the specific actions taken by the licensees, and the commitments made during this review, the NRC staff concluded that the refueling operating practices are consistent with the licensing basis for the spent fuel pool decay heat removal systems at all plants, or l
will be consistent before the next refueling outage. However, in its survey, the staff determined that licensees of 9 sites (involving 15 units) needed to modify their licensing bases or plant practices to ensure that their refueling practices are clearly within the analytic bounds described in each facility's UFSAR. This finding indicates that these plants may have performed refueling operations that were inconsistent with their licensing basis. As a resuit, the staff is I evaluating the need for enforcement action, as appropriate, to address the instances of noncompliance with the UFSAR.
The staff is reviewing the adequacy of NRC's regulatory guidance for changes made to facilities and their operations to ensure that future ,
operations are conducted in accordance with regulations governing the ;
changes made without prior staff approval. j The staff is conducting a broad-based review of program and inspection l guidance associated with oversight of the UFSAR, nonconforming ;
conditions related to the UFSAR,10 CFR 50.59 evaluations, and licensee l corrective action verification. l 1
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I 1
l Regarding your comment on assignment of a full-time person at the plants, in 1977 the NRC' initiated a program to-station resident inspectors at each nuclear po'wer' plant under. construction and in operation. The NRC later exps.nded the program to-provide at least two resident inspectors at each of l the 71 nuclear power plant sites (Millstone currently has 6 resident
! inspectors). By assigning resident inspectors to reactor sites, the NRC l significantly increased the agency's onsite monitoring of the plants. This l increased monitoring provides a greater opportunity to ensure plant safety by l observing the licensee's activities, verifying the licensee's compliance with ,
l NRC's requirements,.and responding to operational events at the plant. In l addition, engineers and specialists from the NRC regional office and l l Headquarters perform periodic and special inspections that supplement the I resident inspector's efforts in a wide variety of technical disciplines. !
Finally, the reliability of the U.S. bulk electric power system is the l responsibility of the North American Electric Reliability Council (NERC) and l its regional councils. The Connecticut area is under the Northeast Power l Coordinating Council (NPCC). These councils monitor and evaluate the poner l situations in their regions based on the availability of all power generation i including nuclear plants. If they identify reliability problems, actions are l taken to address the situation such as was done in Connecticut last spring and i
summer. However, in some limited situations such as very hot weather, the l actions required to maintain critical portions of the electric system may get l to the point where power to some customers is temporarily cut off.
The U.S. Department of Energy has been heavily involved in investigating i
recent power events in the west, and in their August 2, 1996, report to President Clinton stated that the " current system of voluntary self-regulation with respect to reliability remains the best overall scheme for ensuring l reliability in the future."
1 trust this information is responsive to your concerns.
l Sincerely, l
[ original signed by F. Gillespie) l l
l l C Frank J. Miraglia, Jr., Acting Director l Office of Nuclear Reactor Regulation l Docket Nos. 50-213, 50-245, i 50-336, 50-423 l
l
Enclosure:
NRC Actions Regarding l Millstone
~
DOCUMENT NAME: G:\ANDERSEN\ GREEN'.8'06 *SEE PREVIOUS CONCURRENCE**See attached.
Ta rot,elve a copy of this clocument, Indicate in the box: "C* = Copy without attachment / enclosure "E" = Copy with attachment / enclosure *N* = No copy 0FFICE SP0:PM l PD2-2:LA- l
, NAME JAndersen* LBerry* BCalure JLM* PMcKee*
DATE 11 15 96 / g 0FFICE SP0:D- A NRR:DD (# \ ED0- OCM NAME BTravers* ' s fMiraglikf. ,f JTaylor* **
DATE 11/18/96 ll/20/96/'//hd2/02/96 12/23/96
, . TTFFICIAL RECORD
, *k ,
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EDO Principal Correspondence Control
!FROMt DUE: 11/ 6'/96 '
EDO CONTROL: GT96806 r
DOC DT: 08/09/96 l
g(, { gt[p FINAL REPLY:
Francis J. Limerick l Manchester, CT j ll4 )
TO President Clinton l
l FOR SIGNATURE OP : ** PRI **
CRC NO: 96-1096 I Miraglia l {
i DESCs ROUTING: l
! NORTHEAST UTILITIES PLANTS Taylor !
Milhoan
! Thompson Blaha '
HMiller, RI DATE: 10/24/96
!ASSIGNEDTO: CONTACT:
NRR Miraglia
)
SPECIAL INSTRUCTIO S is.
Put EDO and Chairman on for concurrence. '
Chairman's Office to review response prior i to dispatch.
ACTION
! NRR RECEIVED: OCTOBER 24, 1996 NRR ACTION: DRPE:VARGA DUE TO NRR DIRECTOR'S OFFl"-
NRR ROUTING: MIRAGLIA THADANI 8V y,, [j$-
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ZIMf1ERMAN ~-
SHERON l MARTIN '
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OFFICE OF THE SECRETARY CORRESPONDENCE CONTROL TICKET PAPER NUMBER: CRC-96-1096 LOGGING DATE: Oct 22 96 ACTION OFFICE: EDO AUTHOR: FRANCIS IMERICK AFFILIATION: CONNECTICUT l
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LETTER DATE: Aug 8 96 FILE CODE:
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