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Category:CORRESPONDENCE-LETTERS
MONTHYEARDD-99-12, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 9910281999-10-28028 October 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 991028 ML20217N8261999-10-25025 October 1999 Discusses Errata Re 991021 Filing of Northeast Nuclear Energy Co Answer to Request for Hearing & Petition to Intervene B17901, Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)1999-10-18018 October 1999 Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6) B17886, Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 21999-10-18018 October 1999 Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 2 05000336/LER-1999-012, Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl B17900, Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 11999-10-14014 October 1999 Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 1 ML20217G9491999-10-14014 October 1999 Forwards Exemption from Requirements of 1-CFR50,App E, Section IV.F.2.c,re Conduct of full-participation Exercise in Sept 1999,at Plant,Units 1,2 & 3 ML20217D9671999-10-12012 October 1999 Forwards Copy of Transcript of Public Meeting Held by NRC Staff & NNECO on 990825 at Waterford,Connecticut on Decommissioning Program for Millstone,Unit 1.Without Encl ML20217D3011999-10-0707 October 1999 Forwards Request for Addl Info Re Util 990118 Request for Amend to License NPF-49 to Allow full-core Offloads to Spent Fuel Pool During Core Offloads to Spent Fuel Pool During Core Offload Events ML20217F0031999-10-0606 October 1999 Forwards Original Petition to Intervene Being Filed on Behalf of Clients,Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone,Iaw Provisions of 10CFR2.714 ML20217P1201999-10-0606 October 1999 Informs NRC of Proposed Acquisition of Parent Holding Company of Central Maine & Requests NRC Concurrence,Based on Threshold Review,That Proposed Acquisition Does Not,In Fact, Constitute Transfer Subject to 10CFR50.80 B17892, Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC1999-10-0505 October 1999 Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC ML20217B4711999-10-0404 October 1999 Informs That Staff Did Not Identify Any Safety Concerns Re Licensee Proposals to Modify Commitments Made for Action Items 4.2.1,4.2.2,4.5.1 & 4.5.2 of GL 83-28 by Providing Addl Justifications or Safety Bases for Changes ML20212K1241999-10-0101 October 1999 Responds to Recent Ltrs to Chairman Jackson,Commissioners & Wd Travers,Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performace of Millstone to Ensure That Public Health & Safety,Adequately Protected ML20212J3051999-10-0101 October 1999 Discusses GL 97-06 Re Degradation of SG Internals,Dtd 971230.GL Requested Each PWR Licensee to Submit Info That Will Enable NRC Staff to Verify Whether PWR SG Internals Comply & Conform to Current Licensing Basis for Facilities ML20212L2081999-10-0101 October 1999 Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance ML20212J9991999-10-0101 October 1999 Responds to Recent Ltr to President Clinton,H Clinton, Chairman Jackson &/Or Wd Travers Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performance of Plant to Ensure That Public Health & Safety Adequately Protected ML20212L1971999-10-0101 October 1999 Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety ML20212J2451999-10-0101 October 1999 Informs That Util 980807 & 990629 Responses to GL 98-01, Y2K Readiness of Computer Sys at NPPs Acceptable.Nrc Considers Subj GL to Be Closed for Units 2 &3 ML20212L1831999-10-0101 October 1999 Responds to Recent Ltr to Wd Travers Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Performance of Millstone to Ensure Adequate Protection to Public Health ML20212L2171999-10-0101 October 1999 Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island ML20217A9271999-09-30030 September 1999 Discusses Investigation Conducted at Millstone Nuclear Power Station by NRC OI Region I on 980319 to Determine If Contract Training Instructor Was Terminated for Raising Concerns About Quality of Training Matls ML20217B3221999-09-30030 September 1999 Refers to Investigation Rept 1-1997-035 Conducted at Millstone Nuclear Power Station by NRC Ofc of Investigation Field Ofc,Region I on 970915 to Determine Whether Former Health Physics Technician Discriminated Against ML20212J6621999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Units 2 & 3 on 990916.Identified Several Recent Instances in Which Condition Repts Were Not Initiated,Resulting in Untimely or Inadequate C/As.Historical Listing of Plant Issues Encl B17887, Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer1999-09-28028 September 1999 Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer ML20216J1341999-09-28028 September 1999 Ltr Contract:Task Order 49, Millstone Units 2 & 3 Employee Concerns Program Insp, Under Contract NRC-03-98-021 B17883, Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-62301999-09-27027 September 1999 Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-6230 B17890, Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-09-27027 September 1999 Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal B17888, Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 9909151999-09-24024 September 1999 Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 990915 B17884, Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-031999-09-24024 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-03 ML20212F4961999-09-20020 September 1999 Forwards Insp Repts 50-245/99-08,50-336/99-08 & 50-423/99-08 on 990615-0809.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs,Consistent with App C of Enforcement Policy 05000336/LER-1999-001, Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl B17867, Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports1999-09-17017 September 1999 Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports B17865, Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal1999-09-16016 September 1999 Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal B17876, Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant1999-09-16016 September 1999 Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant B17882, Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6) B17881, Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6) B17859, Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 9801281999-09-15015 September 1999 Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 980128 B17880, Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6) B17872, Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 11999-09-14014 September 1999 Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 1 ML20212A9011999-09-10010 September 1999 Forwards Environ Assessment & Finding of No Significant Impact Re Application for Exemption,Dtd 990803.Proposed Exemption Would Provide Relief from Requirement of 10CFR50 ML20212A3171999-09-10010 September 1999 Discusses Investigation Rept 1-1998-045 Conducted on 981112 to Determine If Former Senior Health Physics Technician Being Denied Employment at Millstone in Retaliation for Having Raised Safety Concerns in Past.Synopsis Encl B17838, Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls1999-09-10010 September 1999 Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls ML20212A7501999-09-10010 September 1999 Forwards Staff Requirements Memo Response,Dtd 990525,which Provides Actions NRC Plans for Continued Oversight of safety-conscious Work Environ & Employee Concerns Program ML20211J9291999-09-0303 September 1999 Forwards mark-ups & Retypes of Proposed Conforming License Changes Required in Connection with Transfers Being Sought in 990615 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests ML20211K5171999-09-0202 September 1999 Expresses Appreciation for Support Provided for NRC Public Meeting on 990825 05000336/LER-1999-010, Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 11999-09-0202 September 1999 Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 1 ML20216H0591999-09-0202 September 1999 Responds to Re Issues Submitted by Cullen on Behalf of Several Petitioners Concerning Offsite Emergency Prepardeness for Millstone Nuclear Power Station ML20211N9241999-09-0101 September 1999 Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures ML20211H0741999-08-30030 August 1999 Discusses GL 92-01,Rev 1, Rv Structural Integrity, Issued by NRC on 950519 & NNECO Responses for Millstone Unit 2 & 980715.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 Based on Response Review 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217N8261999-10-25025 October 1999 Discusses Errata Re 991021 Filing of Northeast Nuclear Energy Co Answer to Request for Hearing & Petition to Intervene B17886, Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 21999-10-18018 October 1999 Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 2 B17901, Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)1999-10-18018 October 1999 Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6) 05000336/LER-1999-012, Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl B17900, Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 11999-10-14014 October 1999 Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 1 ML20217P1201999-10-0606 October 1999 Informs NRC of Proposed Acquisition of Parent Holding Company of Central Maine & Requests NRC Concurrence,Based on Threshold Review,That Proposed Acquisition Does Not,In Fact, Constitute Transfer Subject to 10CFR50.80 ML20217F0031999-10-0606 October 1999 Forwards Original Petition to Intervene Being Filed on Behalf of Clients,Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone,Iaw Provisions of 10CFR2.714 B17892, Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC1999-10-0505 October 1999 Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC B17887, Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer1999-09-28028 September 1999 Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer B17883, Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-62301999-09-27027 September 1999 Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-6230 B17890, Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-09-27027 September 1999 Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal B17884, Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-031999-09-24024 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-03 B17888, Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 9909151999-09-24024 September 1999 Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 990915 05000336/LER-1999-001, Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl B17867, Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports1999-09-17017 September 1999 Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports B17876, Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant1999-09-16016 September 1999 Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant B17865, Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal1999-09-16016 September 1999 Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal B17881, Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6) B17880, Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6) B17859, Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 9801281999-09-15015 September 1999 Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 980128 B17882, Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6) B17872, Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 11999-09-14014 September 1999 Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 1 B17838, Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls1999-09-10010 September 1999 Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls ML20211J9291999-09-0303 September 1999 Forwards mark-ups & Retypes of Proposed Conforming License Changes Required in Connection with Transfers Being Sought in 990615 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests 05000336/LER-1999-010, Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 11999-09-0202 September 1999 Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 1 ML20216H0591999-09-0202 September 1999 Responds to Re Issues Submitted by Cullen on Behalf of Several Petitioners Concerning Offsite Emergency Prepardeness for Millstone Nuclear Power Station ML20211N9241999-09-0101 September 1999 Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures B17851, Forwards Semiannual fitness-for-duty Program Performance Data for 990101-990630 for Millstone Nuclear Power Station, Units 1,2 & 3,IAW 10CFR26.71(d)1999-08-27027 August 1999 Forwards Semiannual fitness-for-duty Program Performance Data for 990101-990630 for Millstone Nuclear Power Station, Units 1,2 & 3,IAW 10CFR26.71(d) B17855, Forwards NRC Forms 398 & 396 in Support of License Renewal for SRO TE Grilley,SOP-4053-04.Encl Withheld,Per 10CFR2.7901999-08-17017 August 1999 Forwards NRC Forms 398 & 396 in Support of License Renewal for SRO TE Grilley,SOP-4053-04.Encl Withheld,Per 10CFR2.790 B17849, Forwards Second Quarter Backlog Performance Rept for 1999, Which Represents Fourth Rept on Mnps Performance Since Restart of Unit 3 & First Status Update for Unit 2.No Regulatory Commitments Are Contained in Ltr1999-08-16016 August 1999 Forwards Second Quarter Backlog Performance Rept for 1999, Which Represents Fourth Rept on Mnps Performance Since Restart of Unit 3 & First Status Update for Unit 2.No Regulatory Commitments Are Contained in Ltr B17854, Forwards Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2,per TS 6.9.1.7.Revised Repts for May & June Also Encl Which Reflect Correct Faulty Printometer Readings1999-08-14014 August 1999 Forwards Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2,per TS 6.9.1.7.Revised Repts for May & June Also Encl Which Reflect Correct Faulty Printometer Readings B17850, Forwards First Lhc Quarterly Assessment Rept for Assessment Performed 990621 to 990701.NNECO Taking Appropriate Actions to Address Observations in Rept1999-08-11011 August 1999 Forwards First Lhc Quarterly Assessment Rept for Assessment Performed 990621 to 990701.NNECO Taking Appropriate Actions to Address Observations in Rept B17837, Forwards COLR for Cycle 7, for Millstone Unit 3,IAW TS 6.9.1.6.Explanation of Changes to COLR Also Encl1999-08-0707 August 1999 Forwards COLR for Cycle 7, for Millstone Unit 3,IAW TS 6.9.1.6.Explanation of Changes to COLR Also Encl B17657, Requests Schedular Exemption from Emergency Plan Exercise Requirements of 10CFR50,App E,Part Iv,Section F,Paragraph 2.c.Requests That Nrc/Fema Evaluated Exercise Be Conducted in Mar 2000 Rather than Sept 19991999-08-0303 August 1999 Requests Schedular Exemption from Emergency Plan Exercise Requirements of 10CFR50,App E,Part Iv,Section F,Paragraph 2.c.Requests That Nrc/Fema Evaluated Exercise Be Conducted in Mar 2000 Rather than Sept 1999 B17845, Forwards Revised Commitment for Surveillance Scheduling & Tracking.Options for Surveillance Scheduling & Tracking Methodologies to Be Incorporated in Standardized Station Surveillance Program Are Currently Being Reconsidered1999-08-0202 August 1999 Forwards Revised Commitment for Surveillance Scheduling & Tracking.Options for Surveillance Scheduling & Tracking Methodologies to Be Incorporated in Standardized Station Surveillance Program Are Currently Being Reconsidered B17831, Informs NRC Staff That Change 3 to Rev 25 of Mnps Emergency Plan Was Implemented on 990715.Change Removes Facility Organizational Charts from Emergency Plan & Identifies Relocation to Nuqap1999-07-26026 July 1999 Informs NRC Staff That Change 3 to Rev 25 of Mnps Emergency Plan Was Implemented on 990715.Change Removes Facility Organizational Charts from Emergency Plan & Identifies Relocation to Nuqap B17834, Forwards Proprietary Revised NRC Form 398,which Certifies That SL Doboe Has Completed Eligibility Requirements for Sro,Per 10CFR55.31.Proprietary Info Withheld1999-07-20020 July 1999 Forwards Proprietary Revised NRC Form 398,which Certifies That SL Doboe Has Completed Eligibility Requirements for Sro,Per 10CFR55.31.Proprietary Info Withheld B17836, Forwards Revised NRC Form 396 & Supporting Physician Rept for Licensed Operator Restricted from Licensed Duties, Effective 990628,due to Medical Condition.Without Encl1999-07-20020 July 1999 Forwards Revised NRC Form 396 & Supporting Physician Rept for Licensed Operator Restricted from Licensed Duties, Effective 990628,due to Medical Condition.Without Encl B17811, Submits Response to NRC AL 99-02,requesting That Licensees Provide Numerical Estimates of Licensing Actions to Be Expected to Be Submitted in Fy 2000 & 20011999-07-20020 July 1999 Submits Response to NRC AL 99-02,requesting That Licensees Provide Numerical Estimates of Licensing Actions to Be Expected to Be Submitted in Fy 2000 & 2001 ML20210S9911999-07-18018 July 1999 Requests NRC Intervene for All Shareholders of New England Electric System & to Help with Merger with National Grid Group & That NRC Petition Security & Exchange Commission to Investigate Matter Relative to No Shareholder Options B17835, Forwards Rev 33 to Millstone Station Physical Security Plan, Per 10CFR50.54(p)(2).Licensee Determined That Changes Do Not Decrease Effectiveness of Plan.Rev Withheld from Public Disclosure,Per 10CFR2.790(d)(1)1999-07-16016 July 1999 Forwards Rev 33 to Millstone Station Physical Security Plan, Per 10CFR50.54(p)(2).Licensee Determined That Changes Do Not Decrease Effectiveness of Plan.Rev Withheld from Public Disclosure,Per 10CFR2.790(d)(1) B17818, Provides NRC Staff with Change to TS Bases Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only.Change Was Reviewed & Approved by Unit 3 Plant Operations Review Committee IAW Provisions of 10CFR50.591999-07-16016 July 1999 Provides NRC Staff with Change to TS Bases Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only.Change Was Reviewed & Approved by Unit 3 Plant Operations Review Committee IAW Provisions of 10CFR50.59 B17824, Forwards Monthly Oeprating Rept for June 1999 & Revised Monthly Operating Rept for May 1999 for Millstone Unit 21999-07-13013 July 1999 Forwards Monthly Oeprating Rept for June 1999 & Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20212K1701999-07-13013 July 1999 Submits Concerns Re Millstone & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Should Provide Adequate Emergency Planning in Case of Radiological Accident B17816, Provides Certification That M Lettrich,Has Completed Eligibility Requirements,Per 10CFR55.31 for Operator License.Util Requests That Licensing Action Be Taken for Named Individual1999-07-0101 July 1999 Provides Certification That M Lettrich,Has Completed Eligibility Requirements,Per 10CFR55.31 for Operator License.Util Requests That Licensing Action Be Taken for Named Individual B17801, Forwards 10CFR50.59 Annual Rept for Period Jan-Dec 1998. Various Changes That Were Initiated in Previous Yrs & Completed in 1998,also Incorporated Into Annual Rept1999-06-30030 June 1999 Forwards 10CFR50.59 Annual Rept for Period Jan-Dec 1998. Various Changes That Were Initiated in Previous Yrs & Completed in 1998,also Incorporated Into Annual Rept B17819, Forwards Rev 17 to FSAR & Addendum 6 to Annual Rept.Nneco Recently Completed Review of Unit 2 Design & Licensing Bases Which Resulted in Changes to FSAR Provided in Encl 1.Encl 2 Includes Info Covering Changes Not Included in1999-06-30030 June 1999 Forwards Rev 17 to FSAR & Addendum 6 to Annual Rept.Nneco Recently Completed Review of Unit 2 Design & Licensing Bases Which Resulted in Changes to FSAR Provided in Encl 1.Encl 2 Includes Info Covering Changes Not Included in B17780, Forwards Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) TR, IAW 10CFR50.54(a)(3).Changes to TR Are Shown as Text in Bold Italics1999-06-30030 June 1999 Forwards Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) TR, IAW 10CFR50.54(a)(3).Changes to TR Are Shown as Text in Bold Italics B17723, Responds to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for Units 2 & 3 Encl.Without Encl1999-06-29029 June 1999 Responds to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for Units 2 & 3 Encl.Without Encl B17767, Forwards Rev 12 to FSAR & Addendum 3 to Annual Rept, for Millstone Unit 3,per 10CFR50.71(e) & 10CFR50.4(b)(6). No New Regulatory Commitments Contained in Ltr1999-06-29029 June 1999 Forwards Rev 12 to FSAR & Addendum 3 to Annual Rept, for Millstone Unit 3,per 10CFR50.71(e) & 10CFR50.4(b)(6). No New Regulatory Commitments Contained in Ltr 1999-09-03
[Table view] |
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/ h[ Ikge Ferry Rd. (Route 156), %:erford, CT 06385 T Minstore Nuclear Power Station p
Nortlicaat Nurlear Energy Cornpany P.O. Box 12A Toterford, Cr 06385 0128 (860) 447-1791 Faz (860) 444 4277 j ne Northcet Utilitice System i
FEB 2 61998 Ddet No. 50423 B17021 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 '
Millstone Nuclear Power Station, Unit No. 3 I NRC Request for Additional information Regarding the Millstone Unit 3 Emeroency Diesel Generetor Exheuet Stack (TAC No. M97508)
On September 15, 1997,__ Nuclear Regulatory Commission (NRC) forwarded two questions to Norheast Nuclear Energy Company (NNECO) relating to the " Tornado Missile Risk Analysis of Millstone Unit 3 Emergency Generator Enclosure Openings,"
dated March 1985. This analysis had been provided to the NRC to address S!gnificant items List, item No. 75, NNECO provided a response to NRC_ Question 1 in a letter dated January 21,1998. Attachment 1 to this letter responds to NRC Question 2 and-completes NNECO's response to the NRC on this matter. Attachment 2 contains a listing of any NNECO commitments made in this response.
-Should you have any questions regarding this matter, please contact Mr. David A.
Smith at (860) 437-5840.
Very truly_yours, NORTHEAST NUCLEAR ENERGY COMPANY Martin L. Bowling, Jr. /
Millstone Unit No. 2 - Recovery Officer cc: H. J. Miller, Region I Administrator J. W. Andersen, NRC Project Manager, Millstone Unit No. 3 ^
/A;'.y i A. C. Corne, Senior Resident inspector, Millstone Unit No. 3 W. D. Travers, Ph.D., Director, Special Projects Office DWDM (uy40
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Docket No. 50-423 B17021 Attachment i Millstone Nuclear Power Station, Unit No. 3 NRC Request for Additional Information Regarding the Millstone Unit 3 Emeroency Diesel Generator Exhaust Stack (TAC No. M97508)
February 1998
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.. U.S' Nuclear Regulatory Commission B17021\ Attachment 1\Page 1 Request for Additionalinformation Concoming Emergency Diesel Generator Exhaust Stacks TAC NO. M97508 M4C Question
- 2. Your risk assessment for protection against tornado generated missiles only addresses the acceptance criteria for a single vulnerability, i.e., the EDG exhaust system. In order to rely on probabilistic arguments that tornado missile protection is not required, the risk assessment must also show that the overall risk from tornado generated missiles has not been increased (by not providing -
protection for the EDG exhaust system) beyond the acceptance riteria discussed in the guidance of Standard Review Plan (SRP) Section 2.2.3, which deals with identification of design basis events using probabilistic methods.
Therefore, the analysis should also consider all other Structurea, Systems, or Components (SSCs) not protected from tornado generated missiles that are required to prevent a release of radioactivity in excess of 10_CFR Part 100 that are not protected from tornado generated missiles. This guidance states that an expected rate of occurrence of potential exposures in excess of _the 10 CFR Part 100 guidelines of approximately 10-6 per year is acceptable if, when combined with reasonable qualitative arguments, the risk can be expected to be lower. ,
This-request for additional information need not be addressed if all other-safety-related SSCs (other than the EDG exhaust system) are adequately protected (by existing barriers / structures) from the effects of tornado generated missiles.
NNECO Response A~ Tornado event Probabilistic Risk - Assessment (PRA) addressing all unprotected structures, systems and components required to prevent a release of radioactivity has not been prepared for Millstone Unit 3. NNECO's'dscision to evaluate the damage i probability associated with a potential Tornado missile impact to the Emergency Diesel-Generator (EDG) exhaust stacks was_ based on a review of the Millstone Unit No. 3 licensing basis requirements transmitted in NUREG-1031, " Safety Evaluation Report related to the operation of Millstone Nuclear Power Station, Unit No. 3," Supplement No.1, dated March 1985. In Section 3.5.2 of Supplement No.1 of_ the Safety-Evaluation Report (SER), the NRC identified several options available to NNECO for resolving the open issue relating to Tomado missile protection of the EDG exhaust stacks,- including the development of 3 limited PRA. It is NNECO's belief that the options identified in Section 3.5.2 of SER Supplement 1 continue .to represent acceptable analysis approaches under the Millstone Unit No. 3 licensing basis.
U.S'. Nuclear Regul: tory Commission I ' B170' 21\ Attachment 1\Page 2 A
in its January 21,1998 letter, NNECO stated that other unprotected targets had been identified and that an evaluation of safe shutdown capability assuming loss of the individual targets was underway. Enclosure 1 (8 pages) to this ietter provides the results of NNECO's evaluation. As discussed in Enclosure 1, all but one of the targets identified are either not required for safe shutdown, have been previously reviewed and accepted under the Millstone Unit No. 3 licensing basis, or have been shown through analysis to be able to support safe shutdown with degraded capability. The evaluation is based on the c~ollity of available systems, struc'ures and components to remove decay heat in support of achieving safe shutdown following a Tornado event with consequential Loss Of Offsite Power (LOOP) and coincident single failure and with no additional design basis events occurring simultaneously with the Tornado. This latter ;
provision is consistant with the guidance provided in NRC Regulatory Guide 1.117, "
" Tornado Design Classification."
The single new target of concern is discussed in item 52 of Enclosure 1. Line 3-FWA-006-81-4 is a recirculation heating loop for the Demineralized Water Storage Tank.
The DWST is missile protected and provides the suction source for the Auxillary Feedwater System, The line is automatically isolated on a loss of power condition.
However, if power remains available throughout the event, tailure of this line due to a missile impact would result in a loss of DWST inventory. While this scenario is considered unlikely, corrective action will be taken to eliminate the potentici failure mode prior to entry into Mode 2. It is expected that administrative controls can be effectively implemented to require that the line be isolated upon receipt of a Tornado Warning.
U.S', Nuclear Regulatory Commission B17021%ttechment 1\Page 3 Docket No. 50-423 B17021 Enclosure 1 Millstone Nuclear Power Station, Unit No. 3 NRC Request for Additional information Regarding the Millstone Unit 3 Emeroency Diesel Generator Exhaust Stack (TAC No. M97508)
February 1998
I Attachment 4 Engineering Record Correspondence ,
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DATE: 02/19/98 25212-ER 98-0051 Rev. O TO: D. Dodson _m o FROM: J.D. Dakers [fhk t/liff6 INDEPENDENT M. Urick Y REVIEWER /[_ r] 8[/f!/f ,
APPROVED R.A. Andren h _e _ 2,/2. /)y
SUBJECT:
MP3 Tornado Missile Vulnerab'lities
REFERENCES:
Walkdown Resu!ts MP3-WLKDWN-98-097 DACKGRQUED Attachment A of this ERC, is a letter which was received tror.1 the NRC requesting additional information on items which are not protected from tornado missiles. Question 1 has previously been responded to, and this ERC will form the foundation for a response to question 2. Question 2 requests information on any additional potential tomado missile targets, specifically whether probabilistic methods have been used as the basis for not protecting certcin safety related items.
There are no other known 5 cations, which Millstone 3 has specifically used probabilistic methods to address targets unprotected from tornado missiles, but thera are other potential targe's which could contribute to risk during a tornado event. To provide an adequate response to the NRC question, it was decided a walkdown should be conducted to identify any potential targets which may be vulnerable to tornado missiles. Walkdown MP3-WLKDWN-98-097 was performed and documented. This walkdown ideritified 12 items which require formal review in preparation for the response to the NRC. The specific items are included in the scope section of this ERC. The identified items are reviewed and en assessment of the significance on plant shutdown capability made, which then can be used as input in response to the NRC request. It is expected that the PRA group will also review these items to address their significance from a probabilistic point of view.
s 25212-ER-98-0051 NGP 5.31 Rev.3 Page 1 of 6
t SCOP _E i The scope of this ERC covers the following items:
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Item No. Photo No. Desenption 3 5 MSV Bldg Roof: 43ets of ten main steam safety valve exhaust stacks.
17 6 MSV B!dg Roof: Typical of 4 main steam bypass valve exhaust y stacks.
18 7 MSV Bldg Roof: Typical of 4 main steam atmospheric dump stacks 19 8 MSV Bldg Roof: Unidentified candelabra shapod vent.
20 9 MSV Bldg Roof; Doorways on southwest and northwest corners of high roof have safety related items inside.. 3HW'JB5002,3HW'AOD5082 23 15 MSV Bldg South Outer Wall: Safety related conduit and junction box E 3JB'9834 inejde security door 371S at ground level.
25 18 ESF Bldg Roof: Y type vent to Teny Turbine.
26 19 ESF Bldg Roof: Elbow type vent to Terry Turbine.
32 22 Auxiliary Bldg Roof: Unidentified ducpork.
49 -
Large 10'x10' Duct (Overhead) Between TB and Secondary Containment: Unprotected. _
52 14,9 DWST: One overflow line, two backflow prevent lines and one unidentified line with a heat tracing wire all located on the outside.
61
_- Fall Pipe (Ground Leve:; Outside Southeast Corner EGE: Unprotected.
t REEERERCES i
- 1. MP3 FSAR Sections 3.8, 9.4.3, 9.f.4.2 and 10.3.3 2, Walkdown Report MP3-WLKDWN 98-097 I
- 3. Westinghouse Letter NS-OPLS OPL l 91 171, dated March 27,1391, Millstone 3 Better 1
, Estimate loss of Normal Feedwater / Station Blackout Analysis. (Presently being revised) 1 4. Regulatory Guide 1.117 Revision 1, April 1978 i
- 5. NRC Letter from J.W. Anderson to N.S. Carns, Request for Additional information Regarding i the Millstone Unit 3 Emergency Diesel Generator Exhaust Stack. (Attachment A)
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- 6. Drawing EM 117A (25212 26917 sh.1) revision 16 P&lD Emergency Generator Fuel Oil System i
- 7. Drawing EM 123A (25212 26923 sh.1), revision 30 P&lD Main Steam and Reheat
- 8. Drawing EM 123D (25212 26923 sh. 4), revision 10 P&lD Main Steam and Reheat
- 9. Drawing EM 123E (25212 26923 sh. 5), revision 17 P&lD Main Steam and Reheat
- 10. Drawing EM 130B (25212 26930 sh. 4), revision 31 Feedwater System i
- 11. Drawing EM 1528 (25212 26925 sh. 2), revision 11 ESF and MSV Buildings Ventilation t 12. Proto Power Calculation 96-067 Revision 0, up to Change 3 I
3 !
25212 ER 98-0051 NGP 5 31 Rev. 3 Pace 2 of G
DODY The above list was developed after screening the items identified from the plant walkdown, considering safety related items which are exposed to toniadu missiles, or non safety related rtems which have the possibiltty of affecting the perf.ormance of safety related items. Accordingly this list conservattvely presents potantial targets, since av noted in Regulatory Guide 1.117
- lt is not necessary to maintain the function &l 6 apability of all Sr.lsmic Category I structures, systems
! and components because the probability of the joint occurrence of low probability events (loss-of
-coolant accident with DBT or smaller tornado, or earthquake with DBT or smaller tomado) is sufficiently small. However, equipment used to provide long-term core cooling following a LOCA l should be protectcd.' Considering this logic the specifics of each of above items is further I
reviewed and an assessment of the significance on plant shutdown capability, item 16 Mainsteam Safety relief valves 3 MSS *RV22A D,23A-D,24A-D,25A D and 26A-D are protected from tomado missiles, but the exhaust stacks from these valves protrude through the roof of the Mainsteam Vatve Building and are not protected from potential tomado missiles. The Mainsteam Safety relief valve exhaust stacks although safety related are not required for safe shutdown of 4
the plant. Cooldown by release of secondary side steam can be accomplished by the pressure i relieving or pressure relieving bypass valves.
i Item 17
} The pressure relieving bypass valves 3 MSS *MOV74A D are protected from tornado missiles, but the exhaust stacks from these valves extend through the roof of the Mainsteam Valve Building.
The pressure relieving bypass valves are not the primary path for secondary side cooldown of the i plant. As discussed in item 18 below, FSAR Section 10.3.3 discusses possible tornado damage to I the steam relief system. Basad on this 'icensed position adequate redundancy is provided to
( l ensure plant shutdown capability, i
i Item 18 l
i The pressure relieving valves 3 MSS *PV20A-D are protected from tornado missiles, but the exhaust stacks from these valves extend thisugh the roof oi the Mainsteam Valve Building. FSAR Section 10 3.3 indicate:. *Four main steam pressure relieving bypt as valves are provided to ensure a secure path around the main steam pressure relieving valves in the event that the primary path is no longer available due to tornado missile o seismic damage to the discharge silencers. or loss of power or air to the main steam pressure relieving valves." Due to the I
reoundancy provided by the pressure relieving bypass valves, no specific quantitative probabilistic I arguments have been used to ensure that the safe shutdown of the plant can still be i accomplished after a tomado event. Based on this licensed position adequate redundancy is l provided to ensure plant shutdown capability.
25212 ER 95-0051 NGP 5.31 Rev. 3 Page 3 of 6
Item 19 This item is an atmospheric vent off line 3-MSS-006-210-4 from the Mainsteam System, on tho i
roof of the Mainsteam Valvo Building. This line relieves steam off the mainsteam isolation valves i solenoids, is not safety related, and is not required for safe shutdown of the plant.
! Item 20 On the roof of the Mainsteam Valvo Building inside of ths .,Clation enclosure are 3HVV'AOD50A2 and 3HVV'AOD5082 which are fully protected from potential tomado missiles.
Conduits 3CC9870K7 and 3CC987PT feeding these AOD's are exposed to tomado missiles.
These AOD's are for isolation of the Mainsteam Valve Building HVAC system for SLCRS purposes. The integnty of the Cantainment Enclosure Building is not maintained during a tomado as indicated in FSAR Section 3.8. Since the SLCRS function is lost there is no consequence to the failure of those dampers.
Item 23 Junction box 3JB'9836 and associated ductline 3DC986P09 as well as junction box 3JB'9834 and associated conduit 3CC986PR are inside of the Mainsteam Valve Building, but could be i exposed to potential tomado missiles through an adjacent denrway. Junction box 3JB*0836 and i associated ductline 3DC386P09 contain no cable, accordingly there is no tomado vulnerability.
I Junction box 3JB'9854 and associated conduit 3CC986PR service 3HW'TS27A, which is used to prevent overcooling of the Mainsteam Valve Building. This component is not required for safe shutdown of the plant under tomado conditions.
Item 25 and 26 i
I These items are associated with the steam drivsn auxiliary feedwater pump. One of the items is the primary steam exhaust path from the turbine via line 3-MSS-012-160 3, and the other is vent i
line 3-MSS-003111-4. Obviously with the lines exposed, the possibility of impact from a tomado missile cannot be produded. The possibility that a missile would damage this line such that i operation of the turbine driven pump would be affected is highly unlikely, but if an analogy similar to that of the diesel exhaust pipe is used, it could lead to the failure of the steam driven pump.
The unit s;>ecific Detter Estimate Loss of Normal Feedwater/ Station Blackout Analysis of the auxiliary feedwater system, from nominal full power conditions, shows the required decay heat can be removed by a minimum flow of 330 gpm delivered to two intact steam generators. This can be accomplished utilizing a single motor driven auxiliary feedwater pump,(assuming a single failure disables the other motor driven auxinary feedwater pump), as documented in Reference i
- 12. Reference 12 shows a single motor driven pump can deliver 354 gpm to 2 intact steam generators Accordingly, safe shutdown c'the niant can be achieved without the use of the
! steam driven auxiliary feedwater pump, from nominal full power conditions. In the unlikely event i of a loss of all feodwater EOP 35FR-H.1 would then be entered to mitigate the consequences of the loss of 'eedwater.
25212 ERE::51 NGP 5 31 Rev. 3 Page 4 of 6
Item 32 The identified duct on the roof of the Auxiliary E>uilding is an exhaust duct from the Auxiliary Building Ventilation System (ABVS) and SLCRS system. As noted in FSAR Section 9.4.3, only certain portions of the ABVS are safety related. As noted in FEAR Section 3.8 the Containment Enclosure Building siding is lost during a tornado which ehminates the SLCRS system during tomado events. In addition any tornado missile damage to the ductwork would not result in a loss of the abihty 's exhaust from the safety related portions of the HVAC system, due to the i light gage of the material which would easily be penetrated by the tornado missiles. Collapse of I
the ductwork to preclude the ability to exhaust is not a credible failure mode for this system.
I Item 49 The 10 foot by 10 foot duct on the roof of the Auxiliary Building is an exhaust duct from the Auxiliary Building Ventilation System (ABVS) and SLCRS system. As noted in FSAR Section 9.4.3, only certain portions of the ABVS are safety related. As noted in FSAR Section 3.8 the containment enclosure building siding is lost during a tornado which eliminates the SLCRS system during tomado events, in addition any tornado missile damage to the ductwork would not result in a loss of the ability to exhaust from the safety related portions of the HVAC system, due to the light gage of the material which would easily be nenetrated by the tomado missiles.
Collapse of the ductwork to prevent exhaust is not a credible failure mode for this system.
Item $2 The lines identified entering missile protected DWST enclosure are non safety related 3-FWA-002129-4 for tank heat,3 FWA-006-81-4 for overflow,3 SGF 500 2v. for chemical addition, and 3 FWA 002145-4 for water treating. None of these lines are required for safe shutdown of the plant during a tomado event. 3 FWA 006-81-4,3-SGF 500-27-4 and 3-FWA 002-145-4 enter the tank at the top of the tarik, accordingly a failure of these lines would not lead to draining the tank. Line 3 FWA 006-81-4 is part of a loop which recirculates from the bottom of the tank to the top of the tank, through the DWST neater and associated pump. This line is isolated on a Loss of Power, which is the most probable case durir,g a tornado. A failure in this line prior to the Loss of Power could lead to some loss of tank inventory due to the pump continuing to run, or due the line draining. Condition Report MS 98-0955 has been initiated to identify the corrective actions to preclude the potentialloss of inventory from the DWST.
Item 61 The oil fill vent pipes 3 EGF-003 53-4 and 3-EGF-003 54-4 for the diesel generator fuel oil tanks protrude through the roof of the fuel oil vault. This line has previously been addressed by NRC Question 430.70. An update to FSAR Section 9.5.4.2, as a result of this question, indicates
'Should the filllines become damaged, the fuel oil storage tanks also can be filled from within
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their enclosure through a manhole on the top of the tanks.' '3ased on this, the filllines are not an issue during a tomado event.
l25212 ER4B-00Si NGP 5.31
! Rev.3 Page 5 of G
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CONCLUSjQN The affect of damage to potential targets not protected from tornado missiles has been assessed in the ERC. Th., speofics for each target are addressed in the body of this ERC. This assessment provides the foundation for a response to the NRC addressing the request in referenco 5.
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i 25212 ER 98-0051 NGP 5.31 Rev. 3 Page 6 of 6
,M*
- ggg .i Cart; Ie ce i ce F res 'ent AII^lN Mb'JI #'
- -$ Chief Nuclear Of ficer PA6 t i Of# 2.
',: Meast Nuclear Energy Cn!
c.; Ms. Patricle t. Loftus Director . Regulatory /f fatri P.O. Box !?8 daterford, C106335 SLE)[CT: RE0 JEST FOR AD0li:'JAL liFORMil0N REGARDING Till MILLSTONE UN!13 EMERGENCY Di[SEL GENERATOR En%UST STACK (TAC NO. H97508)
Dear Hr. Carns:
Dy letter dated July 22. 1997, the staff provided you an update of the NRC's Hillstone Restart Assessment Plan ' Plan). Encl:sure 3 to the Plan contained the Significant items List (Sil) for Hillstone Unit 3. Sil (75 fc Hills cne Unit 3 addressed two inspector follow up items; one concerning the emergency diescl generatc* exhaust stack, The NRC staff has reviewed the closure package for this item and in order to support further NRC evaluation, you are requested to provide the NRC with answers to the enclosed questions. Fiease respond to this request for additional infonnation expeditiously in order for the staff to complete its review in a timely manner.
Sincerely, James W. Andersen, Project Manager Special Projects Office Licensing Office of Nuclear Reactor Regulation Oxlet No. 50 423
Enclosure:
As stateri cc w/ enc 1: Ses next-page l
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- 1. Based on o probabilistic rip uses! ent (PRA) described in the final sunwry report. *iornado H15511e Risk Analysis of HWstone vit 3 [mergency Generator Enclosure Openings,* dated March 1985, Northeast Nuclear Energ Comp!*y O!NECO) concluded that the probability of significant damage to an errergency diesei genera:or (EDG) exhaust piping from tornado generated missiles is l 1ess than ! x 10 6 per year. Accor:1ngly, a change was implemented in the last amendment (dated roarch 1996) to the firial Saft:y Analysis Report (fSAR) to delete the licensing comitment, which required NNECO to open the [M exha>.st piping access hatches during a tornado alert. The staff finds that the above cited RA was col,, pe-forced to demonstrate the risk of tornado generated missiles, which could enter ry of Pe openings in the exhaust plenums to cause damage to the
[0G exhaust system. It does not adress the probability of the EDG exhaust stacts located outside the building teing M: by 1;'nado generated missiles. Therefore, provide a PRA to demonstrate the risk of torr!;o gercated missiles, which could cause damage to any portion of the [0G cxhaust stacts. Th11 FRA s* >uld consider all potential modes of tornado missile damage to the exhaust stacks, not Nst the orobability that missiles will enter one of the openings of the exhaust plenum
- 2. Your risk assessment for prc.f:tior gainst tornado generated missiles only addresses the acceptance criteria for a sv;te vOerability, i.e., the EDG exhaust system. In order to rely on probabilistic arguents Pat to-ado missile protection is not required, the risk assessment must also show that the overall rip from tornado generated missiles has not been increased (by not providing protection fo* the LM exhaust system) beyond the acceptance criteria discussed in the guidance of Standard Re,*es Plr (SRP) Section 2.2.3, which deals with identification of ,
design basis events using r*;:3bW tic methods. Therefore, the analysis should also consider all other structures. syste !. or c:nponents (SSCs) not protected from tornado generated missiles that are re::;1 red - prevr a release of radioactivity in excess of 10 CFR Part 100 that are not protected fro- :rna0: generated missiles. This guidance states that an expected rate of occurrence of poterc 9.1 W:sures in excess of the 10 CFR Port 100 guidelines of approximately 10 6 pr year s accciabic if, when combined with reasonable qualitative arguments, the risk can be Mecte: to be lower. This request for additional information need not be addressed if til otm safe -related SSCs (other than the EDG exhaust system) are adequately protectec {bj ec.:1ng :vriers/ structures) from the effects of tornado generated missiles.
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Attachment 2 Millstone Nuclear Power Station, Unit No. 3 NRC Request for Additional Information Regarding the Millstone Unit 3 Emeroency Diesel Generator Exhaust Stack (TAC No. M97508)
Commitments February 1990 N
o U. 8., Nuclear Regulatory Commission B17021%ttachment 2\Page 2 List of Regulatory Commitments The following table identifies those actions committed to by NNECO in this document. i Please notify the Manager - Regulatory Compliance at the Millstone Nuclear Power Station, Unit No. 3 of any questions regarding this document or any associated i regulatory commitments. ;
i Commitment Committed l Date j Implement corrective actions to eliminate Prior to entry potential loss of DWST inventory due to a into Mode 2 tornado missile impact to line 3 FWA-006-81-4 (Ref:M3-98-0955).
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