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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
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Ned Hope Ferry Rd. (Route 156), Waterford, CT 06385 Nuclear Energy Maistone Nociear romr sation l Northeast Nuclear Energy Company P.O. Box 128 Waterford, CT 06385-0128 (860) 447-1791 Faz (860) 444-4277 The Northeast Utihties System JLL 241998 j l
Docket No.50-33G B17370 i
U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Staticn, Unit No. 2 Request For Permission to Apply Leak Before Break Methodology To Portions of Safety iniection and the Shutdown Coolino Systems The purpose of this letter is to request NRC review and approval of Leak Before Break (LBB) methodology for portions of the Safety injection (SI) and the Shutdown Cooling (SDC) systoms. The scope of the proposed LBB application is limited to the ASME Class 1 portion of the Si and the SDC systems extending from their respective connection at the main coolant loop (MCL) piping to the first isolation valve. The portions of the Si and SDC piping systems under consideration are designated as high energy, being subject to the normal operating conditions of the MCL piping. All affected piping considered for this application of LBB is located inside containment.
NNECO also expects, in future correspondence, to request NRC review and approval of Leak Before Break methodology for the Pressurizer Surge Line based upon the expected results of ongoing engineering reviews.
A recent evaluation of the walkdown information on the Si and SDC piping systems, completed in May 1998, concluded that the protection of adjacent closed loop piping systems from potential pipe breaks was not provided as part of the original Millstone <
Unit No. 2 design. This concern was reported to the NRC Staff in LER 98-005-00. l NNECO has evaluated various options to address this concern and concluded that the )l application of the LBB technology is the most effective and reasonable approach to ;
ensure adequate pipe break protection of the closed loop piping systems. Other options considered included the installation of whip restraints and jet shields, relocation j ;
j' of targeted piping, and the installation of added secondary isolation valves in the //
l closed loop systems.
4 Using the guidance and criteria provided in NUREG 1061, Volunic 3, the l implementation of the LBB methodology will result in the elimination of the requirement i 9807300353 980724~ '
PDR ADOCK 0500o336 P PDR Ot0422 5 REV,12 95
- U.S. Nucl:ar Regulitory Commission B17370tPage 2 to consider dynamic effects of postulated ruptuies for the Si and SDC piping. The LBB evaluations for the Si and SDC piping are provided herein for NRC Staff review.
This request for permission for the implementation of the Leak Before Break methodology is organized as follows:
Attachment 1 to this letter provides an executive summary of the NNECO submittal.
Attachments 2 provides the background and introductory remarks and system descriptions related to this request.
Attachments 3 and 4 provide a detailed report on the results of the LBB evaluations for the safety injection and the shutdown cooling piping syitems, respectively. These reports address all applicable NRC LBB evaluation criteria contained in NUREG 1061, Volume 3.
Attachment 5 provides a discussion of the plant specific information and service experience to date with the Si and the SDC piping rystems. Issues, such as NDE inspection results, water hammer experience, and th3 i'npect of any other potential sources of degradation, such as fatigue, vibration, corrwion, thermal stratification, etc.
are addressed.
Attachment 6 contains a discussion of the material properties, welding processes and weld procedures that pertain to the Si and SDC piping systems.
Attachment 7 contains a detailed description of the installed leak detection system inside containment.
Attachment 8 provides a qualitative value impact assessment of this request.
Some of the benefits that will accrue from application of LBB technology include elimination of the need for installing the pipe whip restraints and jet barriers on the Si and SDC piping, elimination of associated occupational man-rem exposure during construction, periodic removal and re-installation of these restraints and barriers, less congestion in the containment, and elimination of potential damage to piping from i n ' function of rupture restraints.
There are no regulatory commitments contained within this submittal.
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~ U.S. Nucl=r Regul tory Commission B17370\Page 3 If you have any additional questions conceming this submittal, please contact Mr. Ravi G. Joshi at (8S0) 440-2080.
I Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
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Martin L. Bowling, Jr. U Recovery Officer - Technical Services Attachments cc: H. J. Miller, Region 1 Administrator W. D. Travers, Ph.D., Director, Special Projects Office P. F. McKee, Deputy Director, Licensing and Oversight, Special Projects Office W. D. Lanning, Deputy Director, inspections, Special Projects Office J. P. Durr, Branch Chief Inspections, Special Projects Office D. G. Mcdonald, Jr., NRC Senior Project Manager, Millstone Unit 2 D. P. Beaulieu, Senior Resident inspector, Millstone Unit 2 i I
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Docket No. 50-336 B17370 Attachment 1 Millstone Nuclear Power Station, Unit No. 2 Request For Permission to Apply Leak Before Break Methodology To Portions of Safety injection and the Shutdown Cooling Systems Executive Summary l
July 1998
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U.S. Nucl=r R:gulatory Commission B17370\ Attachment 1\Paga 1 EXECUTIVE
SUMMARY
. This Millstone Unit 2 request to the NRC for implementation of LBB in accordance with l the provisions of General Design Criterion (GDC) 4 of Appendix A to 10CFR Part 50 is based on the methodology described in NUREG 1061, volume 3. The subsequent attachments two through eight provide the technical justification for our LBB submittal.
The scope of requested implementation of LBB is limited to the ASME Class 1 portion of the Safety injection (SI) ar.d the Shutdown Cooling (SDC) systems extending from l their respective connection at the Main Coolant Loop (MCL) to the first isolation valve.
l The portions of the Sl and SDC piping systems under consideration are designated as high energy, being subject to the normal operating conditions of the MCL piping. All l affected piping considered for this application of LBB is located inside the containment.
The subject SI and SDC piping is 12 inch Schedule 140 seamless piping fabricated from 316 SS and extend from their respective connection to the MCL to the first isolation valve. Deterministic Elastic-Plastic Fracture Mechenics (EPFM) J-Integral- i Tearing Modulus (J/T) evaluations were performed for all significant weld locations identified in each piping system. In order to demonstrate the required safety margins of
[ on the accident load combination, factor of two on critical crack length, and margin of 10 on leakage detection, several fracture mechanics evaluations were performed:
The results of fracture mechanics evaluation for the Safety injection piping show that a 4.29 inches long crack will leak at the rate of 11 gpm under normal operating conditions
! and is less than one-half the critical crack length of 8.78 inches calculated for the accident loading condition. This 4.29 inches long crack remains stable under piping loads equal to [ times the accident load condition..
Similarly, the results of fracture mechanics evaluation for the Shutdown cooling piping show that a 7.84 inches long crack will leak at the rate of 12.2 gpm under normal operating conditions and is equal to one-half the critical crack length of 15.68 inches calculated for the accident loading condition. This 7.84 inches long crack remains stable under piping loads equal to 8 times the accident load condition.
The above results were determined based on calculated critical flaw sizes at each weld )'
location uWog generic lower bound base or weld material properties for (a) pressure plus deao weight, plus thermal, plus safe shutdown earthquake (P+DW+TH+SSE) and for (b) 8(P+DW+TH+SSE). Leakage-size-crack (LSC) was then determined as the ,
smaller of one half of the critical crack length calculated for stress condition (a) or full j critical crack length for stress condition (b). Leakage from LSC flaw size established above was then calculated under normal operating load combination of pressure plus ]
dead weight, plus thermal (P+DW+TH). The calculated leakage was then compared to
U.S. Nucl:rr Regulatory Commission B17370\Att: chm::nt 1\Pcgo 2 ten times the installed leak detection capability at Millstone Unit 2 to demonstrate a safety margin of 10 on leakage detection as stipulated in NUREG 1061, volume 3.
Millstone Unit 2 has an installed leak detection capability of 1 gpm unidentified leakage inside containment which is more than u quate to meet the LBB leakage detection requirements calculated above for the di and SDC piping. This capability is in compliance with Regulatory Guide 1.45 requirements.
ASME XI fatigue crack growth analyses of shallow flaws performed for both the SI and the SDC piping systems show an insignificant growth in both flaw depth and flaw length. To account for the reactor water environment, a factor of 2 was applied to the in-air ASME XI crack growth law for austenitic steels. For carbon steel, the ASME Xi fatigue crack growth curve for ferritic steel in water environment was utilized. Deeper flaws grow preferentially through-wall prior to extending in length and becoming unstable.
The susceptibility to degradation mechanisms, such a 3 intergrannular stress corrosion cracking (IGSCC) and flow accelerated corrosion (FAC) were considered and determined not to be a concern for the affected portions of the systems. Similarly, the potential for loadings, such as vibration, water hammer, and thermal stratification was considered. The Safety injection nozzles and safe ends are protected from thermal fatigue by thermal sleeves. The probability of occurrence of water hammer or significant vibrations were considered low. The layout of the Safety injection and the Shutdown Cooling piping systems, including the close proximity of the RCS isolation valves minimizes their susceptibility to thermal stratification. The impact of thermal aging on the material properties of cast stainless steel was also considered.
In summary, Millstone Unit 2 has satisfied the requirements relative to the leak-before-break analysis, stipulated in NUREG 1061, Volume 3, for the high energy portions of the Safety injection and the Shutdown Cooling piping systems and accordingly requests approval to apply the LRB methodology as allowed per GDC-4. This request will eliminate the need to postulate pipe ruptures and consider their associated dynamic effects from the design basis for the high energy portions of the Si and SDC piping.
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Docket No. 50-336 817370 l
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Attachment 2 l Millstone Nuclear Power Station, Unit No. 2
- l. Request For Permission to Apply Leak Sefore Break Methodology l To Portions of Safety injection and the Shutdown Cooling Systems
! Introduction And Background -
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l l U.S. Nucirr R:gulatory Commission l 817370\ Attachment 2\Page 1 INTRODUCTION AND BACKGROUND In the original assessment of high energy line breaks (HELB) inside containment, the protection of closed systems was not addressed. The generic industry oversight in protecting the closed loop systems was recognized in Information Notice 89-55.
Millstone Unit 2 completed a full evaluation of the closed loop systems and supporting walkdowns in May,1998. This review of inside the containment HELB program for its adequacy in protecting closed loop piping systems from a p..stulated impact due to the rupture of an adjacent High Energy Line, identified several deficiencies (Ref.1).
The Safety injection, Shutdown Cooling and Pressurizer Surge Lines were all identified as initiating sources of unacceptabb interaction with closed loop systems. The possible corrective actions for the identified adverse interactions considered options for both targets (moving lines or adding secondary isolation valves) and sources frestraint of ruptured line or elimination of the postulated break).
The best target-related option is the use of a second isolation valve at the containment penetrations to ensure containment integrity under the postulated breaks. While such an approach could provide successful resolution of this issue, it introduces considerable additional maintenance and reliability concerns which would negatively impact plant operation. In total, eight new motor or air operated isolation valves, with associated controls to close on a containment isolation actuation signal (CIAS), would be required to address all identified interactions. The target lines under consideration include four Reactor Building Component Cooling Water (RBCCW) lines (two 6" and two 8" penetrations), two Steam Generator Blowdown (SGBD) lines (two 2" penetrations) and two SGBD Sampling lines (two 1/2" penetrations). The addition of more motor or air operated valves to these systems increases their complexity and decreases their overall efficiency and reliability. Thus, the benefits of this approach are judged to be greatly exceeded by the overall negative impact on plant operation.
Considering the size of the Si and SDC lines (all 12" diameter) and their location within the loop area, where structural attachment locations are minimal, the application of Leak-Before-Break (LBB) methodology to demonstrate low probability of pipe rupture !
provides the oest promise of success. Given that the protection of closed loop systems l is considered a prudent enhancement to the existing LB/DB of Millstone Unit 2, and given the previous industry precedent for application of Leak Before Break methodology for large lines attached to the primary loop, this approach is considered the most effective and reasonable implementation approach.
2.1 SYSTEM DESCRIPTION - SAFETY INJECTION SYSTEM Safety injection System (SIS) is part of the Emergency Core Cooling System (ECCS).
The primary system function is to provide both short and long term core cooling by injecting borated water into the core through each of the four main coolant loop cold legs following a loss-of-coolant-accident (LOCA). The safety injection system is divided into two parts: the High Pressure Safety injection (HPSI) system injects borated 1
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U.S. Nucl:ar Regulatory Commission B17370\ Attachment 2\Page 2 water using HPSI pumps at high pressure with flow capability commensurate with RCS inventory loss during a small break LOCA; and the Low Pressure Safety injection (LPSI) system uses two LPSI pumps to provide borated water for long term core cooling and injecting negative reactivity whenever the RCS pressure decreases rapidly as a result of large break LOCA up to and including the break in the largest RCS main coolant loop pipe.
The high energy portion of the HPSI piping is located directly adjacent to the reactor coolant loop cold legs and is part of the RCS pressure boundary. The physical layout of the safety injection piping is shown in Figures 2-1 through 2-4.
2.2 STRESS ANALYSIS & ASME CODE COMPLIANCE -
SAFETY INJECTION SYSTEM:
The stress and fatigue design compliance of the safety injection piping in accordance with the Bechtel Design Specification Number 7604-M-290 and the Class 1 requirements of ASME Ill,1971 was performed by Teledyne Engineering Services.
The requirements of I&E Bulletin 79-14 involving as-built verification were subsequently implemented for the safety injection piping.
The piping analyzed extends from each of the four RCS cold leg loop nozzles to their respective safety injection tank at one end of the branch piping and to the containment
- penetration at the other. Each of the four safety injection piping systems is computer analyzed (ADLPIPE) for pressure, dead weight, thermal expansion, OBE and SSE loads. Seismic inertia analysis is based on the enveloped response spectra method.
Teledyne performed thermal transient temperature distribution analysis using simplified chart methods and detailed analyses with one-dimensional and two-dimensional heat
! transfer programs. Code compliance is demonstrated for normal, upset, emergency, faulted and test conditions. Additionally, cumulative fatigue usage factors for 40 year
! service life are shown to be within Code acceptable limit of 1.0. All pressure boundary attachments to Class 1 piping were designed to ASME Section ill, NB requirements.
Structural Steel supports were qualified in accordance with the AISC requirements.
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U.S. Nucirr Regulatory Commission B17370\ Attachment 2\Page 7 j 2.3 SYSTEM DESCRIPTION -SHUTDOWN COOLING SYSTEM The primary system function of the shutdown cooling (SDC) system is to reduce the reactor coolant temperature to cold shutdown condition and to maintain this temperature during refueling. The LPSI pumps are used to draw suction from the Main Coolant Loop 2 hot leg piping and discharge it to each of the four cold legs after removal of decay heat in the shutdown cooling heat exchangers. The high energy portion of the SDC suction piping is located directly adjacent to the reactor coolant loop 2 hot leg and is part of the RCS pressure boundary. The physical layout is shown in ,
Figure 2-5.
The high energy portion of the SDC discharge piping is located directly adjacent to the reactor coolant cold leg loops and is part of the RCS pressure boundary and is the same piping as the Si piping discussed above in Section 2.1.
2.4 STRESS ANALYSIS & ASME CODE COMPLIANCE - SHUTDOWN COOLING I
The stress and fatigue design compliance of the shutdown cooling piping in accordance with the Bechtel Design Specification Number 7604-M-209 and Class 1 requirements of ASME Ill,1971 was performed by Teledyne Engineering Services.
The requirements of I&E Bulletin 79-14 involving as-built verification were subsequently
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implemented for the shutdown cooling piping.
l The shutdown cooling piping system is computer analyzed (ADLPIPE) for pressure, dead weight, thermal expansion, various operating transients, OBE and SSE loads.
Seismic inertia analysis is based en the enveloped response spectra method.
Teledyne performed thermal transient temperature distribution analysis using simplified chart methods and detailed analyses with one-dimensional and two-dimensional heat transfer programs. Compliance with Code is demonstrated for normal, upset, emergency, faulted and test conditions. Additionally, cumulative fatigue usage factor i for 40 year service life is shown to be within the Code acceptable limit of 1.0. Ali pressure boundary attachments to Class 1 piping were designed to ASME Section Ill, NB requirements. Structural Steel supports were qualified in accordance with the AISC requirements.
2.5 REFERENCES
l 1. 25203-EV-98-0063, " Technical Evaluation for NRC Information Notice No. 89-1 55: " Degradation of Containment isolation Capability By a High-Energy 1.ine Break," issued May 15,1998.
U.S. Nuclxr R:gulatory Commission B17370\ Attachment 2\Page 8 l
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Docket No. 50-336 B17370 Attachment 3 Millstone Nuclear Power Station, Unit No. 2 Request For Permission to Apply Leak Before Break Methodology To Portions of Safety Injection and the Shutdown Cooling Systems Report Number SIR-98-048, Rev. O.
Prepared By: Structural integrity Associates l
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July 1998
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