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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: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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 ML20212H6661999-06-15015 June 1999 Forwards RAI Re 990315 Application Request for Approval of Proposed Indirect Transfer of Seabrook Station,Unit 1 License & Proposed Indirect Transfer of Millstone,Unit 3 License to Extent Held by Nepco 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 ML20195J3121999-06-15015 June 1999 Expresses Concern Re M Casey 990523 Column, Gaffes Turn Into Cash at NRC, & Disagrees with New London Day Earlier Editorial Criticism of NRC Investigations of Harassment & Intimidation of Employees at Millstone NPPs ML20195K0601999-06-15015 June 1999 Forwards Request for Addl Info Re fire-related IPEEE Analysis,Per GL 88-20 ML20195J4761999-06-10010 June 1999 Forwards Insp Rept 50-336/98-219 on 981214-18,990126-29 0208-19 & 0301-05.Four Violations Identified & Being Treated as Noncited Violations ML20195J0321999-06-10010 June 1999 Expresses Appreciation for Serving as Moderator for 990209 Public Meeting at Waterword,Ct.Questions Raised by Interested Members of Public & NRC Responses Encl.Staff Reply to Blanch Also Encl ML20196J5091999-06-0404 June 1999 Requests Assistance to Review Petition Submitted Under 10CFR2.206 of NRC Rules.Petition Concerns EP Issues for Millstone Nuclear Power Station ML20207G1121999-06-0303 June 1999 Forwards Insp Repts 50-245/99-05,50-336/99-05 & 50-423/99-05 on 990302-0419.No Violations Noted.Closure of 15 Significant Items List (SIL) Issues at Unit 2 Signifies Completion of Insp for Entire Unit 2 SIL ML20207G6271999-06-0303 June 1999 Forwards Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Replace Specific Titles in Section 6.0 of TSs for All Three Millstone Units with Generic Titles 1999-09-30
[Table view] |
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NAY-25-1999: 08:00 USNRC Rl/OFC OF REG ADM 6103375241 P.02/10 k' k_ UNITED STATES
, 'NUCl. EAR RE2U1.ATURY COMMISSION
- $ AEGloN I -
-*- 4 ~ 475 ALLENDALE RoAo KING OF FRusslA, PENNSYLVANIA 1940614.)
1 % on .e. *.
May 25,1999 EA 96-1511 Mr. R. P. Neoci, Vice President, Nuclear - -
- Oversight arx. Regulatory Affairs .
)
- /o Mr. David A. Smith, Manager Rege*,atory . ; 3-
~ Affairs : .,
l
. Northeast Nuclear Energy Company -
.- . . 4 Post Office Box 128 ,
Waterford, Connecticut 06385 -
. i. x 1
SUBJECT:
' NOTICE OF VIOL.ATION AND EXERCISE OF ENFORCEMENT DISCRETiONr *
(Investigation Report No.1-94-021) 4 .
l
Dear Mr. Necci:
This letter refers to the investigation conducted.at the Millstone Nuclear Power Station, by the NRC's Office ofInvestigations (01), conceming the performance of fuel offloads at Millstone Unit .
1 prior to 1993. The synopsis of the 01 investigation is enclosed (Enclosure 2).
Based on the information developed during the 01 investigation, fourviolations of NRC requirements
' are being cited as described in the enclosed Notice of Violation (Notice).. Specifically, the NRC determined that, in careless disregard of NRC requirements you (1) pennned Loth partial and full core reactor fuel offloads prior to the decay times assumed in the FSAR without the appropriate engineering analyses; (2) utilized uriapproved and unanalyzed system configurations to augme,nt spent fuel pool (SFP) cooling during refueling outages, without procedures to govem those !
activities; and (3) in two instances submitted incomplete and inaccurate information to the NRC
- related to the performance of fuel offloads that were actually being commenced before the delay
. times assumed in the analyses submitted to the NRC.
These violations, which existed for a long period of time, appear to be the result of the deficient safety culture which contributed to the shutdown of all three units for an extended period, and resulted in a number of other violations for which the NRC issued a $2,100,000 civil penalty to NNEco on December 10,.1997. That penalty was based, in part, on (1) the failure to assure that the plant was maintained in the configuration as designed and specified in the licensing basis, and (2) the failure to promptly correct nonconforming conditicns, in the letter transmitting that civil penalty, the NRC Executive Director for Operations noted that "...many of these violations and undertying causes were long-standing and iriicative of a deficient safety culture, fostered by plant L and corporate management, which neither set high standards or actively encouraged workers to identify and report safety issues or act upon issues once they were reported." The NRC concluded that management's failure to establish standards to ensure that the plant was maintained and operated as designed, and to ensure that nonconforming conditions were promptly identified and corrected, constituted careless disregard of requirements. As such, the violations that resulted from 4
, 1 9906080076 990525 POR COP 998 fWtCC
' CORRESPONDENCE PDR ;
i
.MAY-25-1999 .08:01 Us@C R1/OFC OF REG RDt1 6103375241 P.03/10
? ,
2 !
l Northeast Nuclear Energy Company.
[
G that deficient safety culture, which fostered such dismgard, are considered willfulin accordance with
. the " General Statement of Policy and Procedures for NRC Enforcement Action (NUREG.t600)"
- (Enforcement Policy) ,
N.; ..' i With respect to the cited violations, you failed to meet the requirements of 10 CFR 50.5g when you performed fuel offloads commencing prior to the decay times analyzed in the FSAR during most of the refuelmg outages between ig74 and igg 1, and did not perform safety evaluations to support r these activities. .During these refueling outages, you also used the shutdown cooling (SDC) system to augment the SFP cooling system for SFP heat removal, as assumed in the FSAR analysis for the abnormal offload scenario.tlilowever, no analysis was performed at the time to assure that the design SFP heat loads were not exceeded when considering the shorter decay times.' Additionally, the SDC system was poss-tied with the SFP cooling system without approved procedures to govem the activity, contrary to 10 CFR Part 50, Appendix B, Criterion V.
. Y ,c .
Finally, you had opportunities to identify that fuel offloads were not being performed consistent with
<M 'Uthe FftMnalysis when'you prepared license. amendment requests for SFP rerecking.. However, in those requests you provided informatiori.to the NRC regarding scenarios described in the FSAR without indicating that those scenarios did not accurately reflect your refueling practices. These
- scenarios were less conservative tnan the analyzed scenarios that supported the amendment requests. Also, when you reported the nonconforming conditim in Ucensee Event Report (LER)
M g3-011 in igg 3, you described a hypothetical scenario that was more conservative than conditions. .
W. # thattactually existed, and you failed to report the dates and times of occurrences that the SFP 7" - design temperature limit could have been exceeded, contrary to the requirements of 10 CFR 50.73.
l Although you were slow to recognize, after the issue was raised in June 19g2, that the performance
.M uw "of full core offloads after only 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> decay time was potentially a condition outside of the design 4.+ M basis of the plant, the NRC conduded that.the delay did not constitute.a violation of NRC
' Ww B: requirements.' This is because no core offloads.were. conducted while you were evaluating the. ;
- C e tissue and the issue was promptly. reported once theran'alysis conducted by your contractor was - I wW n.availabler t ' .; . 1
< . a ( _ .w. .. ... m , , _2, ..
f The NRC recognizes that there were no' actual safety consequences as a result of commencing i; ' core offloads prior to the decay times specified in the FSAR, because the actual heat load never exceeded the total available SFP cooling capability, when augmented by shutdown cooling, and the temperature of the SFP never exceeded the design limit. However, the maximum actual SFP heat !
'r ' load during most of these refueleg outages exceeded the design capability of the SFP cooling l
', ' system heat exchangers. Therefore, the potential: existed for the design temperature limit of the SFP to be exceeded, as you reported in your LER dated October 18,1993. The operation of the SDC system, cross-tied with the SFP cooling system, without approved procedures permitted operation of the systems in an uncontrolled, potentially less reliable manner.-
- The NRC is concemed that in prepdration'of your license amendment requests for SFP reracking, you either failed to recognize that core offloads were not being perfon'ned in socordance with the FSAR, or if you did recognize such, you did not inform the NRC. In support of these license
-amendment requests, your staff analyzed fuel offload scenarios to demonstrate that there was
. sufficie6t'SFP heat removal capatWlity to accommodate the increase in SFP. storage capecity
- requested in the license amendments. This analysis provided an obvious opportunity for your staff
, to consider the actual refueling practices that were used at Millstone Unit 1. However, no one
MAV-25-1999 08:01 USNRC RI/OFC OF REG.ADM. 6103375241 P.04/10
- Northeast Nuclear Energy Company '3
- involved in the preparation and review process for the amendment requests questioned whether the analyzed scenarios were representative of actual omond practices. The NRC is also concerned that when you did recognize that core omoads were performed that were not consistent with the
' FSAR, you failed to ~ provide complete information to the NRC with respeict to the extent and significance of the deviation from the licensing basis.
. In consideration of (1) the undesirable consequences of performance of unanalyzed core omoads and failure to ensure that SFP heat removal was conducted in accordance with approved procedures; (2) the significance of providing incomplete and inaccurate information to the NRC; and (3) the significance that the NRC places on careless disregard of its requirements, the four violadons set forth in the enclosed Notice have been classified, in the aggregate, as a Severity I evel l Ill problem in accordance with the Enforcement Policy, issuance of a civil penalty for this Severity 1 Level lil problem would normally be considered in accordance with the Enforcement Policy. Since -
, the violations occurred more than five NWs ago, they are outside the statute of limitations for ,
' issuance of a civil penalty, with the exception of violation D for which you waived the Statute of J Limitations on October 15,1998. Even if the statute of limitations had not expired, the NRC determined that it would be appropriate to exercise discretion and not issue a civ1 penalty because:
(1) these violations at Unit 1, which has permanently shut down, were additional examples of the '
underlying performance problems at all the Millstone units for which the NRC issued the $2,100.000 civil penalty to you in December 1997; (2) you maintained all three of the Millstone units in a
. shutdown condition for approximately 2 years to address underlying performance problems at the facility; and (3) you essentially replaced the entire management infrastructure since the time these fuel omond problems occurred, and the new management team has been reasonabry effective in managing the restart and operation of Millstone 2 and 3. Therefore, I have been authorized, after consultation with the Co amission, to exercise discretion and not issue a civil penalty for these violations. In sum, discretion is appropriate because you have already implemented corrective actions to address the underlying performance problems at Millstone and further enforcement action is not necessary to achieve additional remedial actions.
Regaroing the original question concoming the Millstone 1 full core offload practices, the NRC has drawn a distinction between routinely conducting full core offloads and conducting any omoede prior to the decay times assumed in the FSAR. The NRC has concluded that enforcement action is not warranted at Millstone 1 and other facilities for conducting full core omoads on a routine basis. The use of the terms " abnormal" and ' emergency" in describing the full core omoad scenario in the FSAR could imply that full core omonds were to occur on a less freqcnt basis than partial core offloads. However, the NRC was unable to concWe that the use of these terms represented a specific commitment to limit the frequency with whic;. fall core offloads were conducted at Millstone
- 1. In this regard, NNECo informed the NRC staff ofits practice of omoeding the full core at Millstone
. 1 in a meeting on June 16,1988 associated with the License Amendment 40 request peliaining to SFP raracking. Further, althougi, the analytical constraints and assumptions for the full core amond were generally less restrictive than those for a partial core offload, in licensing actions (typically rerack amendments), the NRC found the plant design for removing the full core acceptable. Finally, as a way of addressing shutdown risk, the NRC encouraged, and still does, the practice of full core !
offloads. Thus, consistent with the conclusions drawn for all other plants that routinely performed I full core offloads, additional enforcement is not being proposed for the Millstone 1 full core omoading Prachces.
. f1HY-6-AWW udiud- UbNRC N V W L & Mrb ADM 6104.175241 P.05/10
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Northeast Nuclear Energy Cornpany. 4 As noted atxwe, enforcement action is being proposed for violations associated with the timing of
) core affloads. in this regani, the Non-Cited Violation (NCV) documented in inspection Report 50-
' 245, 336,423/94 01, dated April 22l 1994, for failure to maintain the spent fuel pool analysis design p ' assumphons (based on LER 93 011) was issued without full knowledge pertaining to the extent that i offloads commenced before the assumed FSAR decay times. The NRC concludes that had it i known at the time the. extent of the issue, as well as the careless disregard toward NRC requireme, a more significant enforcement action would ~ have been warranted. Therefore, pursuant to Section Xill of the Enforcement Policy, this NCV is being reissued as a cited violation
' and is included in the enclosed Notice of Violation.
' The NRC has concluded that you have already addressed the . broad, programmatic problems that led to the violations cited in the enclosed Notice in your response to the $2,100,000 civil penalty. ,
l '
j Corrective actions for the specific issues associated with the vio:stions are no longer applicable
! since Unit 1 is permanently retired. Therefore, you are not required to respond to this letter. If you choose to provide additionalinfotmation, you should follow the instmetions specifed in the enclosed l . Notice.
in accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter will be l
placed in the NRC Public Document Room (PDR). If you have any questions, please contact Mr. .
Wayne D. Lanninis at 610-337-5126.
Sincerely, l .] /
Hubert J. Mil r Regional Adi inistrator Docket No. 50-245 License No. DPR-21
Enclosures:
j
- 1. Notice of Violation -
l
- 2. Synopsis of 01 Report 1-94-021 ,
I
-T - MAY-55-1999; 00:02-- USNRC Rl/0FC OF REG ADM 6103375241 P.06/10 p ;, .
Northeast Nuclear Energy Company 5
.. . oc w/encia:
- B. Kenyon, President - Generation Group L. Olnrier, Senior Vee President & Chief Nuclear Officer - .
- M. Brothers, Vee President - Operations
' J. Carlin, Vee President - Human Services E. Harkness, Director- Unit 1 Operations i J. Price,' Director Unit 2 Operations . -
C. Schwarz, Director- Unit 3 operations D. Arnerine, Vme President - Engineering Services -
F. Rothen, Vee President - Nuclear Work Services
- G. Hicks, Director - Nuclear Training Services (CT) l L Cuoco, Senior Nuclear Counsel
~ J. Egan, Esquire .
~ N. Burton, Esqu'.rs
' V. Juliano, Waterford Library'.
J. Buckingham, Department of Public Utility Control S. Comley, We The People
. State of Connecticut SLO Designee L First Selectmen, Town of Waterford D. Katz, Citizens Awareness Network (CAN)
' R. Bassilskis, CAN J. Block, Attomey, CAN S. Luxton, Citizens Regulatory Commission (CRC)
T. Concannon, Co4 hair, NEAC l . E. Woollacott, Co-Chairman, NEAC i.
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