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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
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-4001 R %,l
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March 11. 1998 l
Mr. David A. Lochbaum Nuclear Safety Eng:neer Union of Concemed Scientists 1626 P Street NW., Suite 310 Washington, DC 20036-1495
Dear Mr. Lochbaum:
in your letter dated Jcnuary 6,1998, you indicated that the U.S. Nuclear Regulatory Commission (NRC) Independent Corrective Action Verification Program (ICAVP) lacks objective criteria and, since a large number of issues are being identified by the contractor at Unit 3, the j NRC should either (1) require additional system assessments or (2) formally issue " objective - j standards" for assessing if additional reviews are necessary. In your followup letter dated January 20,1998, you expressed the concem "that the process being used by the NRC staff
)
will provide a restart recommendation whenever Northeast Utilities (NU) seeks it, irregardless of the findings from the independent corrective action verification program (ICAVP) and NRC ]
inspections._
l As stated in the NRC Confirmatorf Order of August 14,1996, the purpose of the ICAVP is to confirm the effectiveness of the licensee's program in assuring that the plant's physical and functional characteristics are in conformance with its licensing and design bases. Accordingly, '
the regulatory standard being used to evaluate this element of the licensee's performance and restart readiness is conformance with the plant's licensing and design bases. Consistent with the ICAVP purpose, the NRC staff established in SECY-97-003, " Millstone Restart Review Process," dated January 3,1997, the term " defect" to represent any condition identified during the ICAVP review that results in the plant being outside its licensing and design bases.
Nonconformances with the licensing and dasign bases are being assessed through the identification of any " defects" during the ICAVP reviews.
In addition to the identification of " defects," the ICAVP reviews include the identification and assessment of other errors that do not meet the definition of a " defect"(e.g., minor calculational errors). Although such findings do not involve nonconformance with the licensing and design bases, they are being reviewed to determine if any programmatic trereds raise a question about conformance with the plant's licensing and design bases.
l As a result of concems from members of the public, expressed in periodic briefings held by the NRC, the NRC staff developed four levels of significance which are being used to categorize findings from the ICAVP. Levels 1,2, and 3 contain findings which would indicate nonconformance with the licensing and design bases (i.e., defects) and Level 4 contains findings which would not question the licensing and design bases. These levels indicate the graded significance the staff would associate with such findings. Given the technical complexity of the ICAVP reviews, the significance of an identified " defect" could vary markedly, and the significance levels developed by the NRC staff are viewe'd as appropriate for establishing a I clear hieratchical grouping of the ICAVP findings.
C'49@'@unligl' _.m g32gg h 3 ' ' ' '
H
David A. Lochbaum in addition to the establishment of the graded significance levels, the NRO developed likely or potential NRC actions corresponding to each significance level. A listing of predetermined NRC actions resulting from ICAVP findings has been requested by some. However, the complexity inherent in detailed licensing and design reviews does not lend itself to the establishment of automatic thresholds to trigger an appropriate expansion of ICAVo scope. The NRC's existing process for performing these reviews, relying on established regulatory requirements ar,d risk insights, provides for a broad consideration of possible ICAVP findings and is consistent in its use of the licensing and design bases as the regulatory standard for measuring the licensee's performance. The NRC has recently provided additionalinformation on the NRC process in letters to the Connecticut Nuclear Energy Advisory Council, NU, and the ICAVP contractors.
This additional information (see enclosure) was also discussed at a meeting with the public on Jsnuary 27,1998.
The ICAVP oversight plan, described in SECY-97-003 dated January 3,1997, allows the NRC staff to make informed judgments based not only on an assessment of the individual issues, but also on the licensee's corrective actions for that issue, including the identification of root cause(s) and causal factors associated with the issue, the proposed resolution to the issue, the applicability of the issue to other systems, and broader programmatic and operational implications. An important element in the ICAVP process is the NRC staffs or ICAVP contractor's independent verification of corrective actions being taken by the licensee in response to ICAVP findings. This independent verification of the adequacy of corrective actions results in additional ICAVP evaluations of the plant's conformance to its licensing and design bases.
In carrying out its evaluations of ICAVP findings and the licensee's corrective actions, the NRC staff is using, in past, the requirements of 10 CFR 50, Appendix B, Criteria XVI, and the guidance contained in NRC Generic Letter No. 91-18 (GL-91-18) Revision 1, dated October 8, 1997. Both Appendix B and GL-91-18 address actions necessary for the resolution of degraded and nonconforming conditions. These actions include evaluation for both operability and reportability to NRC, and prompt disposition of the finding using an effective corrective action program. An important element of effective corrective action, in accordance with Appendix B, is to ensure that the root cause is identified and the issue is fully addressed in a l timely manner, j You have indicated a concem with the number of deficiency report (DRs) findings identified and how those numbers would extrapolate to the other safety systems. The third-party contractor I has reviewed 15 of the 88 risk-significant or safety-related systems, as categorized by the Maintenance Rule, in conducting its Tier 1 review at Unit 3. Additionally, portions of another 22 s systems were reviewed as part of the Tier 2 review.
The large number of DRs that you have referenced are preliminary in that they have not been reviewed by NU. NU may provide additional information to the contractor that may, subject to review and styreement by the ICAVP contractor, demonstrate that the discrepancy was: a)
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, Divid A. Lochbaum previously discovered during Configuration Management Plan; or b) that it is not an issue and the plant is in conformance with its licensing and design bases. In these two cases, the DRs are categorized respectively as "previously identified" and "nondiscrepant." NU may also agree with the contractor that the DR is a true nonconformance which was not previously identified.
These are called " confirmed" DRs and these are what are reported by the staff and trended.
The number of confirmed DRs, as of February 27,1998, is 184 for Unit 3. Of 937 DRs issued as preliminary, as of February 27,1998, caly 301 have been " closed." (" Closed DRs are those that are either " confirmed," "nondiscrepant," or "previously identified.") Thus far, the contractor review has confirmed six findings which involve a nonconformance with the licensing bases 1 (Level 3). With such a small percentage of DRs closed, it is premature to draw meaningful conclusions. However, as previously discussed, the NRC staff has developed a listing of likely i or potential NRC actions corresponding to each significance level.
The NRC's program is focused on assuring that each Millstone unit is in compliance with its licensing and design bases, including applicable NRC regulations. The NRC expects that the licensee will correct any safety-significant areas of noncompliance before restart. Corrective actions that the licensee is planning to defer until after restart are being reviewed by the NRC staff to ensure that the licensee's process for identifying deferable actions and for carrying out the corrective actions, inciuding the timing of these actions, is adequate and commensurate with the safety importance of the issue.
The NRC staff, consistent with the ICAVP Confirmatory Order dated August 14,1996, is d. wen not by schedule, but by the primary task of determining whether the Millstone licensee has effectively carried out a comprehensive, broad-scope program to identify and correct its weaknesses, in addition, the Commission has consistently indicated that their decisions on restart do not presuppose that any of the three plants will restart by any certain date, j Sincerely, Originalsignedby SamuelJ. Collins Samuel J. Collins, Director Office of Nuclear Reactor Regulation Docket No. 50-423 3
Enclosure:
As stated I
cc: See next page i
Distribution: See next page DOCUMENT NAME: AdLOCHBAUM.LTR *See previous concurrence To receive a copy of this document, Indicate in the box "C" copy wfo attachtenci "E" copy wfattach/enci "N" OFFICE TA-SPO C D-SPO C D:NRR C EDO C OCM k NAME RPerchtsr* WTravers* SCollins* JCallan# ,
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DATE 2/5/98 2/5/98 2/11/98 L /l3/98 3 li193 D8 OFFICIAL RECORD COPY
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Northeast Nuclear Energy Company Millstone Nuclear Powor Station Unit 3 cc:.
Lillian M. Cuoco, Esquire Mr. William D. Meinert Senior Nuclear Counsel Nuclear Engineer Northeast Utilities Service Company Massachusetts MunicipalWholesale P. O. Box 270 Electric Company Hartford, CT 06141-0270 P.O. Box 426 Ludlow, MA 01056
. Mr. Kevin T. A. McCarthy, Director -
Monitoring and Radiation Division Joseph R. Egan, Esquire Department of Environmental Protection Egan & Associates, P.C.
79 Elm Street 2300 N Street, NW )
Hartford, CT 06106-5127 Washington, DC 20037 Regional Administrator, Region i Mr. F. C. Rothen U.S. Nuclear Regulatory Commission Vice President-Work Services 475 Allendale Road Northeast Utilities Service Company King of Prussia, PA 19406 P. O. Box 128 Waterford, CT 06385 First Selectmen Town cf Waterford Emest C. Hadley, Esquire Hall of Records 1040 B Main Street 200 Boston Post Road P.O. Box 54g Waterford, CT 06385 West Wareham, MA 02576 Mr. Wayne D. Lanning Mr. John Buckingham Deputy Director ofInspections Department of Public Utility Control Special Projects Office Electric Unit 475 Allendale Road 10 Liberty Square King of Prussia, PA 19406-1415 New Britain, CT 06051 l Mr. M. H. Brothers Mr. James S. Robinson, Manager Vice President- Operations Nuclear investments and Administration Northeast Nuclear Energy Company New England Power Company P.O. Box 128 25 Research Drive Waterford, CT 06385 Westborough, MA 01582 Mr. M. R. Scully, Executive Director Mr. D. M. Goebel Connecticut Municipal Electric Vice President- Nuclear Oversight Energy Cooperative Northeast Utilities Service Company 30 Stott Avenue P. O. Box 128 Norwich, CT 06360 Waterford, CT 06385 Mr. David Amerine Vice President - Nuclear Engineering ;
and Support Northeast Utilities Service Company P. O. Box 128 Waterford, CT 06385
Northeast Nuclear Energy Company Millstone Nuclear Power Station Unit 3 cc:
Deborah Katz, President Mr. B. D. Kenyon Citizens Awareness Network Chief Nuclear Of'icer- Millstone P.O. Box 83 Northeast Nuclear Energy Company Shelburne Falls, MA 03170 P.O. Box 128 Waterford, CT 06385 Senior Resident inspector Millstone Nuclear Power Station Mr. Daniel L. Curry clo U.S. Nuclear Regulatory Commission Project Director P.O. Box 513 Parsons Power Group Inc. I Nientic, CT 06357 2675 Morgantown Road Reading, PA 19607 Mr. Allan Johanson, Assistant Director Office of Policy and Management Mr. Don Schopfer i Policy Development and Planning Verification Team Manager I Division Sargent & Lundy 450 Capitol Avenue - MS# 52ERN 55 E. Monroe Street P. O. Box 341441 Chicago,IL 60603 i Hartford, CT 06134-1441 Mr. J. A. Price Citizens Regulatory Commission Unit Director- Millstone Unit 2 ATTN: Ms. Susan Perry Luxton Northeast Nuclear Energy Company 180 Great Neck Road P.O. Box 128 l Waterford, CT 06385 Waterford, CT 06385 '
The Honorable Terry Concannon Mr. J. P. McE' wain Nuclear Energy Advisory Council Vice President (Acting) - Millstone 3 Room 4035 Northeast Nuclear Energy Company Legislative Office Building P.O. Box 128 Capitol Avenue Waterforo, CT 06385 Hartford, CT 06106 Mr. G. D. Hicks Legislative Office Building Unit Director- Millstone Unit 3 Captio! Avenue Northeast Nuclear Energy Company Hartford, CT 06106 P.O. Box 128 Waterford, CT 06385 Mr. Evan W. Woollacott Co-Chair Nuclear Energy Advisoy Council 128 Terry's Plain Road 4 Simsbury, CT 06070 Little Harbor Consultants, Inc.
Millstone -ITPOP Project Office P.O. Box 0630 Niantic, CT 06357-0630
DISCUSSION OF NRC ACTIONS RELATED TO ICAVP FINDINGS A further discussion of corresponding NRC actions related to the ICAVP findings, as follows, is -
intended to better explain and document the process being used by the NRC staff.
Level 1: System does not meet licensing and design bases and cannot perform its f intended function. J NRC Action: Would likely result in selection of additional system (s) for ICAVP review Additional Discussion:
If either the ICAVP contractor review or the NRC staff review confirms a Level 1 finding, the NRC staff anticipates that, as a minimum, an additional system or systems will be added to the current scope of the ICAVP review. Following confirmation of a Level 1 finding, the Special Proiects Office (SPO) staff will immediately present the finding and recommendations for ICAVP scope expansion to the Director, Office of Nuclear Reactor Regulation (NRR), and the Executive Director for Operations (EDO). Expansion of ICAVP scope will involve an additional system or systems review by the ICAVP contractor, the NRC staff, or both. Absent a negative determination by the EDO, the SPO staff will require tin expansion of the ICAVP scope. The NRC staff determl nation and bases for requiring scope expans!on will be communicated to the licensee by written correspondence.
Level 2: Single train of redundant system does not meet licensing and design bases and cannot perform its intended function.
NRC Action: Would likely result in expansion of ICAVP scope to evaluate for similar nonconformance issues in other systems Additional Discussion:
If either the ICAVP contractor review or the NRC staff review confirms a Level 2 finding, the NRC staff anticipates that the scope of the ICAVP would be expanded to, as a minimum, require the evaluation of similar operational, procedural, or design attributes in other safety-related or risk-significant systems for potential nonconformances. Following confirmation of a Level 2 finding, the SPO staff will immediately present the finding and recommendations for ICAVP scope expansion to the Director, NRR. The extent of reviews required under any expansion of the ICAVP will be based on (1) an NRC staff assessment of the licensee's root cause of the Level 2 finding, and (2) an NRC staff assessment of the corrective actions taken by the licensee to address both the staff's specific finding and any broader programmatic implications. Absent a negative determination by the Director, NRR, the SPO staff will require the appropriate expansion of the ICAVP scope. The NRC staff determination and bases for requiring scope expansion will be communicated to the licensee by written correspondence.
Level 3 : System does not meet licensing and design bases but able to perform its intended function.
NRC Action: Could result in expansion of ICAVP scope to evaluate for similar nonconformance issues in other systems Enclosure
l Additional Discussion: !
If either the ICAVP contractor review or the NRC staff review confirms a Level 3 finding, the NRC sta# will consider expanding the scope of the ICAVP to require the evaluation of similar operational, procedural, or design attributes in other safety-related or risk-significant systems for potential nonconformances. The SPO staff will present confirmed Level 3 findings and recommendations regarding ICAVP expansion to the Millstone Restart Assessment Panel (RAP). The staff recommendation on possible ICAVP expansion for individual findings will consider the specific finding, and the effectiveness of the licensee's corrective actions. The effectiveness of corrective actions will be independently verified by the NRC staff, or the ICAVP contractor, and will consider the requirements of Appendix B, Criterion XVI, and the guidance of GL-gi-18. The staff expects that, for an individual Level 3 finding, effective licensee corrective action to address both the specific
- defect," as well as any broader implication for other systems, would lead to an NRC staff determination that the ICAVP need not be expanded.
Conversely, a negative determination on effective licensee corrective action would be expected to result in a decision to expand the ICAVP. The RAP decision on ICAVP expansion will be documented in the RAP meeting minutes, and the Director, NRR, will approve any expansion of ICAVP scope. The NRC staff determination and bases for requiring scope expansion will be ,
communicated to the licensee by written correspondence, l in addition to evaluating individual Level 3 findings, the NRC staff (Chief, ICAVP Branch, SPO, NRR), will periodically, at least biweekly, consider the collective group of confirmed Level 3 findings identified during the conduct of the ICAVP reviews. Negative trends established by I these Level 3 findings, which raise a question about licensing and design bases conformance in other systems, would, in the absence of effective corrective actions by the licensee, be expected to result in expansion of the ICAVP to address possible similar nonconformances in other systems. In its evaluation of possible trends, the NRC staff will consider whether or not (1) the findings represent a large fraction of items reviewed; (2) the findings are implementation errors (e.g., program or procedural requirements were not properly performed; (3) the findings are concentrated in a particular discipline (e.g., mechanical, electrical, instrument and controls, or structural); and (4) the findings are concentrated in a particular type of document (e.g.,
operating procedure, calculation, drawing, FSAR, maintenance procedure). Any decision to expand the scope, based on negative trends associated with Level 3 findings, will be approved by the Director, NRR. The NRC staff determination and bases for requiring scope expansion will be communicated to the licensee by written correspondence.
Level 4: System meets licensing and design bases but contains minor calculational errors or inconsistencies of an editorial nature.
NRC Action: Multiple examples could result in expansion of ICAVP scope to evaluate for similar errors / inconsistencies in other systems Additional Discussion
- Although they do not result in the plant being outside its licensing and design bases (i.e., the ICAVP regulatory standard / acceptance criteria), Level 4 findings will be assessed by the NRC staff. Level 4 findings will be assessed to determine whether trends exist which could raise a question regarding the plant's licensing and design bases. Confirmed Level 4 findings are l
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, , being assessed initially by the contractors to determine if licensee corrective actions are appropriate. The NRC staff, on an ongoing basis, is also reviewing these findings for identification of multiple examples of specific findings and corresponding trends. In its evaluation of possible trends, the NRC staff will consider whether or not (1) the findings represent a large fraction of items reviewed; (2) the findings are implementation errors (e.g.,
program or procedural requirements were property performed); (3) the findings are concentrated in a particular discipline (e.g., mechanical, electrical, instrument and controls, or structural); and (4) the findings are concentrated in a particular type of document (e.g.,
operating procedure, calculation, drawing, FSAR, maintenance procedure). The staff j anticipates that if licensee corrective actions are determined to be effective, and trends which '
raise questions about the licensing and design bases are not identified, the scope of the ICAVP would not be expanded The status of Level 4 findings are periedically presented to the RAP.
Any expansion of ICAVP scope resulting from Level 4 findings will be approved by the EDO.
The NRC staff determination and bases for requiring scope expansion will be communicated to the licensee by written correspondence.
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Distribution:
Docket File (w/originalincoming) l PUBLIC
.EDO - 980012 & 980036 SPO R/F
- 1 NRR Mailroom (w/ incoming) j
. Elmbro JCallan !
-PMcKee 'AThadani !
SReynolds HThompson !
PEselgroth PNorry -
Collins /Miraglia JBlaha l RZimmerman HMiller, RI !
BSheron JLieberman, OE i JRoe KCyr, OGC i SBurns, OGC :
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i j EDO Principal Correspondence Control DUE: 02/05/98--
'~ EDO CONTROL: G980036 M A. Lochbaum DOC DT: 01/20/98 FINAL REPLY:
n of Concerned Scientists hommission SIGNATURE OF : **
- PRI mint'~ CRC NO: 98-0059 OS-T ,6.32.2-w/ Oh c" * * ~~~
ROUTING:
hLSTONE UNIT 3 Callan Thadani Thompson Norry Blaha 01/26/98 Burns
%ED TO:
Lieberman, OE CONTACT: Miller, RI Cyr, OGC NRR ,
Collins kLINSTRUCTIONSORREMARKS:
., G980012.
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NRR ACTION: SPO: Travers ACTION NRR RECEIVED: January 27. l'8 i
n ,-e NRR WUTItG: Collins /,'iragl' a DUE TO NRR DIRECi0n.
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' OFFICE OF THE SECRETARY CORRESPONDENCE CONTROL TICKET PAPER HUMBER: CRC-98-005? LOGGING DATE: Jan 23 98 ACTION OFFICE: EDO AUTHOR: DAVID LOCHBAUM AFFILIATION: DISTRICT OF COLUMBIA ADDRESSEE: CHRM. JACKSON /COMRS.
LETTER DATE: Jan 20 98 FILE CODE: ID&R 5 MILLSTONE
SUBJECT:
MILLSTONE UNIT 3 ACTION: Signature of Chairman DISTRIBUTION: CHAIRMAN, COMRS, SECY, RF SPECIAL HANDLING: SECY TO ACK CONSTITUENT:
NOTES: g- ;
DATE DUE: Feb j '98 SIGNATURE: . DATE SIGNED:
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EDO -- G980036