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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] |
Text
- _ _ _ . _ _ - - _ _ _ _ _ . . - _ - _ . _ _ . . . _ . .
Ernest C. Hadley, Esq. ^EI" ' '
1040 B Main Street
. P.O. Box 549 West Wareham, MA 02576
Dear Mr. Hadley:
This letter provides an update of the 10 CFR 2.206 Petition you submitted on August 21, 1995, as supplemented August 28, 1995, on behalf of Mr. George Galatis and the group, We the People, Inc. The staff has not completed its review of the Petitioners' remaining request for enforcement action pursuant to 10 CFR 50.5 and 50.9. On April 15, 1997, the staff responded to a letter relating to spent fuel pool issues. The staff's letter
- is enclosed for your information. Please call me at (301) 415-1455, if you have any questions concerning this issue.
Sincerely, ORIGINAL SIGNED BY:
Stephen Dembek, Project Manager Special Projects Office - Licensing Office of Nuclear Reactor Regulation Docket No. 50-245 l-
Enclosure:
As stated 1
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'+ , . . . . . ,o April 22, 1997 Ernest C. Hadley, Esq.
1040 B Main Street
,P.O. Box 549 West Wareham, MA 02576
Dear Mr. Hadley:
This letter provides an update of the 10 CFR 2.206 Petition you submitted on August 21, 1995, as supplemented August 28, 1995, on behalf of Mr. George Galatis and the group, We the People, Inc. The staff has not completed its review of the Petitioners' remaining request for enforcement action pursuant to 10 CFR 50.5 and 50.9. On April 15, 1997, the staff responded to a letter relating to spent fuel pool issues. The staff's letter is enclosed for your information. Please call me at (301) 415-1455, if you have any questions concerning this issue.
Sincerely, 1
,/ k!
Stephen Dembek, Project Manager Special Projects Office - Licensing Office of Nuclear Reactor Regulation Docket No. 50-245 j
Enclosure:
As stated
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% UNITED STATES s* j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001 l
j
% # April 15, 1997 j Mr. Paul M. Blanch '
135 Hyde Road West Hartford, CT 06117
Dear Mr. Blanch:
I am writing to respond to the technical concerns described in your letters dated January 3 and January 13, 1997, regarding a loss of spent fuel pool
- (SFP) water inventory. I have forwarded your concerns about statements by Mr. Wayne Lanning and other NRC officials to the NRC Inspector General for
- disposition.
! Regarding your request for additional analyses of postulated SFP events specific to the Millstone site, I believe that the staff's evaluations.of SFP
, safety have been focused, methodical, and well documented. Consequently, I 4
believe that a careful reading of the staff's reviews will highlight that the staff has thoroughly considered the issues you raised. The following paragraphs describe my basis for this statement.
- As you observed in your January 3, 1997 letter, a purpose of the NUREG-1353 study (NUREG-1353, " Regulatory Analysis for the Resolution of Generic Issue 82
, [GI-82), 'Beyond Design Basis Accidents in Spent Fuel Pools'") was to evaluate the level of safety associated with high density storage of irradiated fuel and determine if the cost of any proposed enhancements to fuel storage 4
facilities are commensurate with the increase in the level of safety provided i by the modification. Many of the concerns you have expressed involve assumptions made during the performance of the regulatory analysis and how the
]
results of the analysis fit into the NRC's regulatory process.
Each SFP and related system at licensed reactors has an associated design basis that the NRC staff reviewed and approved during licensing proceedings.
, The design basis consists of the information that identifies the function of the structure or system and the ranges of values' for important parameters for which the structure or system is designed to perform its function. As used in the title to NUREG-1353, the term "beyond design basis accidents" refers to classes or magnitudes of postulated events that were not used in the design
- process to define the function of structures or systems nor to establish the i ranges of values for important parameters. Exclusion of events in a certain
- class of or a certain magnitude from the design process is not necessarily indicative of their likelihood relative to other events, such as large break loss-of-coolant accidents (LOCAs), that were considered during plant design.
However, the Commission must ensure that the integrated capability that evolves from the events used in the design process provides adequate protection for public health and safety.
With regard to the statement about the reporting requirements of 10 CFR 50.72 in your letter dated January 3, 1997, the reporting requirements mentioned (i.e.,10 CFR 50.72(b)(ii)(A) and (B)) apply following the actual occurrence of an event or condition that places the plant in an unanalyzed condition or a
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e P. Blanch condition outside the design basis of the plant. The postulated occurrence of events or conditions involving functional capabilities greater or different than those considered in the design process or assumed parameter values outside the range of values used in the design process do not constitute reportable events or conditions pursuant to 10 CFR 50.72. However, Northeast Nuclear Energy, the licensee for the Millstone reactors, has submitted several reports pursuant to 10 CFR 50.72 and 50.73 about actual events or conditions related to the SFP that the licensee believed placed the plant in an unanalyzed condition or a condition outside the design basis of the plant (e.g., piping having the function of retaining pressure following exposure to the stress values imposed by a seismic event had not been analyzed for that capability, and irradiated fuel was transferred to the SFP with a decay time that was outside of the range of values used in the design evaluation of the SFP cooling system).
Nevertheless, analyses of postulated event sequences serve an important purpose in the regulatory process. Through these analyses, event sequences can be evaluated for their level of risk. Where the risk is significant, the NRC employs the backfit process of 10 CFR 50.109 to modify the design or operation of a nuclear power plant. The evaluation documented in NUREG-1353 determined that the level of risk from beyond design basis SFP accidents was low, but the evaluation also examined the potential of specific enhancements to improve the level of safety.
A number of SFP event analyses were documented in NUREG-1353 to support resolution of GI-82. Events evaluated included seismic events of a magnitude greater than that used in the design process for the SFP structure, pneumatic seal failures, inadvertent drain down due to pipe breaks or system misalignments, and extended loss of cooling and makeup events. The analyses documented in NUREG-1353 estimated the probable radiological consequences of these events and the frequency with which the event would progress to the state producing the estimated radiological consequence.
In response to your concerns about adequate consideration of full core off- i loads, you should note that the staff did consider the size and timing of the fuel off-load for events where the frequency of occurrence was strongly influenced by these factors. For example, the evaluation explicitly considered the impact of a full core off-load occurring 5 days after reactor )
shutdown for extended loss of pool cooling and makeup sequences because the '
size and timing of the off-load have an effect on the probability of recovery. j Conversely, the size and timing of fuel off-load has negligible influence on the progression of events initiated by large-magnitude seismic and other low- i probability external events. For example, SFP structural failures due to such l events as missile strikes and aircraft acciaents were assumed to progress to rapid cladding oxidation regardless of the size and timing of the most recent off-load because the event was assumed to preclude coolant addition to the SFP. Because of the independence of the progression of externally initiated events from the size and timing of the most recent off-load, the staff believes that the use of a more probable radionuclide inventory (e.g., a j i
l
)
P. Blanch one-third core discharge at 90 days decay) rather than an extreme inventory (e.g., a full core discharge with a short decay time) provides a more accurate assessment of risk.
With regard to the consequences of the various events analyzed, the staff calculated best-estimate and worst-case consequences for events progressing to rapid cladding oxidation. The best-estimate case assumed that one third of a core ignited as a result of the particular event sequence. The best-estimate case calculated radioisotope inventory based on the one-third core beir.g placed in the SFP 90 days prior to the event occurring. Finally, as you observed, the best-estimate case assumed a typical population density of 340 people per square mile.
In contrast, the worst-case consequence estimate assumed that (1) the event progression involved the ignition of the entire inventory of stored spent fuel (a full fuel pool consisting of multiple cores stored over the life of the plant), (2) the radioisotope inventory included the inventory of the most recent one-third core discharge with 30 days decay plus all previous '
discharges, and (3) the assumed population density was 860 people per square mile, which was based on the Zion facility - a high population density site.
The staff does not believe further analysis of the offsite consequences considering the radioisotope inventory of a recently off-loaded full core is warranted given the highly conservative nature of the existing worst-case estimate. ,
It is also important to understand that the worst-case consequence estimates '
were carried over into the value impact analysis. The value impact portion of NUREG-1353 quantified cost and benefits for two alternatives that were judged likely to mitigate the sequences that resulted in spent fuel fires (i.e., the use of low density racks or increased use of dry storage). Both the best-estimate and the worst-case consequence estimates were factored into these cost-benefit evaluations. The staff also quantified costs and benefits for ;
improvements to SFP cooling systems. Those cooling system modifications considered were judged likely to have only limited impact on averted offsite >
dose because'the modeling of loss of pool cooling events did not support the assumption of rapid cladding oxidation. Instead, the analyses of loss of pool 1 cooling events assumed cladding failure, which does not result in significant ;
offsite consequences even when the decay time is as short as a few days.
The bases for your assertions that "the probabilities and consequences of this accident have increased significantly" and that "the risk. is now 100 times
' that previously assumed" are not clear. However, it appears that they are attempts to reconcile the results of recent staff evaluations of SFP safety '
with the results and conclusions in NUREG-1353.
Note that the postulated loss of spent fuel water inventory events quantified in NUREG-1353 were total loss of water events that resulted in ignition of the ,
stored spent fuel. NVREG-1353 specifically stated that "... spent fuel pools are designed to preclude significant (a few inches) fuel uncovery due to the ;
- l P. Blanch leakage..." as a result of seal failures, pipe breaks, and other leakage !
events considered during plant design. The analytical models used to support j the analyses in NUREG-1353 indicated that near total fuel uncovery (i.e.,
water level more than 12 feet below the top of the fuel) would be necessary for the significant fuel damage and ignition that formed the basis of the !
severe consequences quantified in NUREG-1353.
As part of the recent Task Action Plan for Spent Fuel Storage Pool Safety (Action Plan), the staff examined the features incorporated in the design of every operating reactor SFP to prevent coolant loss. The staff determined that all SFP designs had been reviewed and accepted by the NRC staff and that the designs provided adequate protection against loss of coolant events.
However, certain plants had features inconsistent with current SFP design guidance that could be enhanced to further reduce the probability of significant coolant inventory loss. As described in the staff's report to the Commission on the Action Plan, which was provided to you on September 11, 1996, the staff is performing regulatory analyses for those plants in order to determine if a substantial increase in the level of safety at a justifiable cost can be achieved by modifying the SFP design or operation at those facilities. No enhancements to SFP design features were identified at the Millstone units with regard to reducing the probability of a significant coolant inventory loss, but Hillstone Unit I was identified for potential enhancement of SFP temperature instrumentation if it is justified on a cost-benefit basis.
The staff study, AE0D/S96-02, which you cited in your letter, further quantified the probability of SFP leakage events. AE0D/S96-02 did state that events involving a loss of SFP inventory greater than one foot have occurred at a rate of about one per 100 reactor years. The report notes that, as a result of human interaction, all actual events were terminated with approximately 20 feet of water remaining over the top of the fuel. As you correctly point out, an estimate for the frequency of loss of pool level of greater than one foot is in no way equivalent to an estimate of the frequency of a postulated loss of pool level down to the top of the stored fuel much less a total loss of inventory. Because NUREG-1353 accounts for human intervention to mitigate loss of inventory events due to seal failures or inadvertent drainage, there is no reason to believe that the estimates for these events in NUREG-1353 are inadequate or are inconsistent with the findings of AE0D/S96-02. Thus, the requantification of the events in NUREG-1353 based on the findings of AE0D/S96-02 is not warranted for Millstone or any other site.
The staff believes that the SFP safety studies conducted over the past few years, including NUREG-1353, the Task Action Plan for Spent Fuel Storage Pool Safety, and AE00/S96-02, have provided significant insight into the relative risks posed by the storage of irradiated fuel in storage pools at the nations's power reactor facilities. These studies have identified the issues and facilities where specific design and operational improvements may be justified by reviewing previous analyses, such as NUREG-1353, and new information in a methodical manner. At the same time, these studies provide
l P. Blanch I part of the justification for the staff's statement in Partial Director's 1 Decision DD-96-23 that the safety significance of certain full core off-load i practices at Millstone I was low. The staff's November 9, 1995, safety evaluation supporting the license amendment related to the practice of full core off-loads was also used to develop D0-96-23.
I do not believe that performing a site-specific analysis of beyond design basis SFP accidents, which would be necessary to answer many of the detailed questions in your February 28, 1995, and January 3, 1997, letters, would yield information that could be used by the staff to improve SFP safety. Rather, I believe that staff's efforts to complete the actions identified for resolution l of the Action Plan represent the most effective means of ensuring l accomplishment of the NRC's mission of protecting public health and safety l with regard to SFPs. Additionally, I believe these actions represent a highly '
responsive and responsible approach to the concerns you have raised.
On an administrative note, in your January 13, 1997, letter, you stated that your request was being made under the provisions of the Freedom of Information Act (F0IA). The existing staff analyses for spent fuel storage pool safety i are documented in NUREG-1353, the July 26, 1996, report to the Commission on l the Action Plan and in AE0D/S96-02. NUREG-1353 was provided to you during a drop-in meeting with me in March 1995. The Actica Plan report was forwarded j to you on September 11, 1996. From your letters, it appears that you already have access to AE00/S36-02. As noted above, the staff's November 9, 1995, safety evaluation supporting the licensee's full core off-load amendment was also used to develop DD-96-23. This document is publicly available. There are no other " safety analyses" that substantiate the staff's conclusions, therefore, there is nothing to provide to you under F01A that you do not already have or have access to.
If you have any additional questions on this matter, please do not hesitate to contact me.
Sincerely, u
John . Zwolinski, Deputy Director Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation