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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] Category:UTILITY TO NRC
MONTHYEARML20064A8071990-09-11011 September 1990 Forwards Core Operating Limits Rept for Four & Three Loop Operation,Per Tech Spec 6.9.1.6.d A08900, Responds to Expressing NRC Views on Access to Util Internal or third-party Assessment Repts.Believes Internal Analysis to Support Amend of One of Util NRC OLs to Authorize Higher Power Level Is within NRC Purview & Access1990-09-11011 September 1990 Responds to Expressing NRC Views on Access to Util Internal or third-party Assessment Repts.Believes Internal Analysis to Support Amend of One of Util NRC OLs to Authorize Higher Power Level Is within NRC Purview & Access B13628, Forwards Correction to Error Discovered in Util 900727 Response to Notice of Violation from Insp Rept 50-336/90-09. Statement Corrected to Read That Contract Personnel That Have long-term Assignments,Certified as Testing Personnel1990-09-0707 September 1990 Forwards Correction to Error Discovered in Util 900727 Response to Notice of Violation from Insp Rept 50-336/90-09. Statement Corrected to Read That Contract Personnel That Have long-term Assignments,Certified as Testing Personnel B13624, Forwards Addl Info Re Relief Request from ASME Code Section XI Requirements for Temporary Repair to Piping Adjacent to Valve 2-SW-97A,per 900817 Telcon1990-09-0505 September 1990 Forwards Addl Info Re Relief Request from ASME Code Section XI Requirements for Temporary Repair to Piping Adjacent to Valve 2-SW-97A,per 900817 Telcon A08977, Advises of Commitment to Install Hardened Wetwell Vent at Facility,In Response to NRC .Util Will Be Proceeding W/Initial Design & Engineering of Hardened Vent, to Support Installation During 1993 Refueling Outage1990-09-0404 September 1990 Advises of Commitment to Install Hardened Wetwell Vent at Facility,In Response to NRC .Util Will Be Proceeding W/Initial Design & Engineering of Hardened Vent, to Support Installation During 1993 Refueling Outage B13626, Informs That Info Provided in Re safety-related Equipment Classification Programs Also Applicable for Unit 3 of Facility1990-08-31031 August 1990 Informs That Info Provided in Re safety-related Equipment Classification Programs Also Applicable for Unit 3 of Facility B13596, Forwards Millstone Unit 3 Individual Plant Exam for Severe Accident Vulnerabilities, Per Generic Ltr 88-20.Rept Identified That No Major Severe Accident Vulnerabilities Requiring Corrective Action Needed1990-08-31031 August 1990 Forwards Millstone Unit 3 Individual Plant Exam for Severe Accident Vulnerabilities, Per Generic Ltr 88-20.Rept Identified That No Major Severe Accident Vulnerabilities Requiring Corrective Action Needed B13618, Forwards Addl Info on Util 900815 Relief Request from ASME Code Section XI Requirements,Per 10CFR50.55a(g)(6)(i),for Repairs to Pipe 3SWP-006-050-031990-08-24024 August 1990 Forwards Addl Info on Util 900815 Relief Request from ASME Code Section XI Requirements,Per 10CFR50.55a(g)(6)(i),for Repairs to Pipe 3SWP-006-050-03 ML20059C2061990-08-23023 August 1990 Forwards Vols 1 & 2 to Semiannual Radioactive Effluents Release Rept Jan-June 1990, Per 10CFR50.36a.Rept Includes Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents A08918, Responds to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-245/90-08.Mitigation of Civil Penalty Requested.Corrective Action:List of Procedural Changes Provided1990-08-22022 August 1990 Responds to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-245/90-08.Mitigation of Civil Penalty Requested.Corrective Action:List of Procedural Changes Provided B13610, Requests Relief from ASME Boiler & Pressure Vessel Code Section XI Requirements Re Mods to Pipe 3SWP-006-050-03. Results of Insps & Required Repairs Will Determine Schedule for Future Insps1990-08-15015 August 1990 Requests Relief from ASME Boiler & Pressure Vessel Code Section XI Requirements Re Mods to Pipe 3SWP-006-050-03. Results of Insps & Required Repairs Will Determine Schedule for Future Insps B13595, Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-13941990-08-14014 August 1990 Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-1394 B13607, Requests Relief from ASME Code Section XI to Reflect Mod to Piping Adjacent to Valve 2-SW-97A,in Response to Generic Ltr 90-051990-08-10010 August 1990 Requests Relief from ASME Code Section XI to Reflect Mod to Piping Adjacent to Valve 2-SW-97A,in Response to Generic Ltr 90-05 A08845, Responds to NRC Backfit Analyses of Hardened Wetwell Vent, Contained in .Benefit of Installing Hardened Wetwell Vent to Satisfy Basic Design Objective of Preventing core-melt Event Not Sufficient for Immediate Decision1990-08-0808 August 1990 Responds to NRC Backfit Analyses of Hardened Wetwell Vent, Contained in .Benefit of Installing Hardened Wetwell Vent to Satisfy Basic Design Objective of Preventing core-melt Event Not Sufficient for Immediate Decision ML20058N2181990-08-0707 August 1990 Notification of Change in Senior Operator Status.Util Determined That Need to Maintain Senior OL of LS Allen No Longer Exists.Determination Effective 900719 ML20058M8321990-08-0707 August 1990 Discusses Spent Fuel Racks Poison Surveillance Coupon Boraflex Degradation.Visual Exam of Remaining Surveillance Coupons Revealed Similar Situation Existed in All Coupon Samples B13590, Responds to NRC 900718 Request for Addl Info Re Util 900418 Request for Schedular Exemption from 10CFR50,App E,Section IV.F.3 to Allow Dec 1990 Full Participation Exercise to Be Exchanged W/Oct 1991 Partial Participation Exercise1990-08-0101 August 1990 Responds to NRC 900718 Request for Addl Info Re Util 900418 Request for Schedular Exemption from 10CFR50,App E,Section IV.F.3 to Allow Dec 1990 Full Participation Exercise to Be Exchanged W/Oct 1991 Partial Participation Exercise A08881, Responds to NRC Re Violations Noted in Insp Rept 50-423/90-08.Corrective Action:Operators Directly Involved W/Event Removed from Licensed Duties & Counseled by Operations Manager on Causes of Event1990-07-31031 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-423/90-08.Corrective Action:Operators Directly Involved W/Event Removed from Licensed Duties & Counseled by Operations Manager on Causes of Event B13594, Forwards Rev 13 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21(b) & 2.790(a))1990-07-30030 July 1990 Forwards Rev 13 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21(b) & 2.790(a)) ML20055J4621990-07-27027 July 1990 Advises That Need to Maintain OL or Senior OL for Listed Individuals No Longer Exists,Effective 900701 A08565, Responds to NRC 900302 Request for Addl Info Re LPCI Swing Bus Transfer Design & Single Failure Vulnerabilities1990-07-26026 July 1990 Responds to NRC 900302 Request for Addl Info Re LPCI Swing Bus Transfer Design & Single Failure Vulnerabilities B13585, Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys1990-07-26026 July 1990 Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys B13592, Requests Extension to Respond to NRC Backfit Analyses of Hardened Wetwell Vent1990-07-24024 July 1990 Requests Extension to Respond to NRC Backfit Analyses of Hardened Wetwell Vent ML20063P9791990-07-23023 July 1990 Notification of Change in SL Jackson Status Effective 900701,due to Permanent Reassignment within Util B13566, Advises That Util Has Reasonable Assurance That Safety Relief Valves Operable & Will Perform as Expected Until Next Outage1990-07-20020 July 1990 Advises That Util Has Reasonable Assurance That Safety Relief Valves Operable & Will Perform as Expected Until Next Outage B13563, Discusses Util Comprehensive Review of Options Re Degraded Grid Undervoltage Protection.Confirms Previous Conclusion That Splitting Loss of Normal Power Logic Would Have Overall Adverse Impact on Plant Safety1990-07-20020 July 1990 Discusses Util Comprehensive Review of Options Re Degraded Grid Undervoltage Protection.Confirms Previous Conclusion That Splitting Loss of Normal Power Logic Would Have Overall Adverse Impact on Plant Safety ML20055G5331990-07-18018 July 1990 Forwards Decommissioning Financial Assurance Certification Rept A08822, Submits Addl Info Requested Re Util Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls. Charpy Impact Use Values for Welds Provided in Evaluation of Irradiated Capsule W-971990-07-18018 July 1990 Submits Addl Info Requested Re Util Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls. Charpy Impact Use Values for Welds Provided in Evaluation of Irradiated Capsule W-97 B13588, Corrects 900703 Submittal of Results of Second in-cycle Insp of Steam Generators.All Tubes W/Cracks Stacked & Plugged1990-07-18018 July 1990 Corrects 900703 Submittal of Results of Second in-cycle Insp of Steam Generators.All Tubes W/Cracks Stacked & Plugged B13587, Requests Temporary Waiver of Compliance from Tech Spec 3.5.F.2 Re Emergency Diesel Generator (EDG) Limiting Condition for Operation.Waiver Would Extend Available Time to Repair Damaged Electrical Components1990-07-16016 July 1990 Requests Temporary Waiver of Compliance from Tech Spec 3.5.F.2 Re Emergency Diesel Generator (EDG) Limiting Condition for Operation.Waiver Would Extend Available Time to Repair Damaged Electrical Components ML20055D3461990-07-0303 July 1990 Responds to NRC Bulletin 90-001 Re Loss of Fill Oil Transmitters Mfg by Rosemount.Operability Determinations Performed & Documented for All Rosemount 1153 & 1154 Transmitters at Facility ML20055D3481990-06-29029 June 1990 Forwards Addl Info Re Facility Crdr & Isap,Including Justification for Human Engineering Discrepancies Dispositioned for No Corrective Action ML20055D7191990-06-29029 June 1990 Amends 900604 Rev 13 to QA Program B13545, Forwards Rev 3 to Updated FSAR for Millstone Unit 31990-06-29029 June 1990 Forwards Rev 3 to Updated FSAR for Millstone Unit 3 B13550, Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl1990-06-27027 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl B13499, Forwards Corrected Tech Specs Page 3/4 9-1 for Incorporation Into Proposed Amend 36 to License DPR-21 Re Auxiliary Electrical Sys1990-06-26026 June 1990 Forwards Corrected Tech Specs Page 3/4 9-1 for Incorporation Into Proposed Amend 36 to License DPR-21 Re Auxiliary Electrical Sys ML20043F8721990-06-11011 June 1990 Corrects Name of Vendor Supplying Replacement Plug Valves, Per Util 900511 Ltr.Replacement Bolts,Not Valves,Purchased from Cardinal Industrial Products Corp ML20043H0161990-06-0808 June 1990 Requests Exemption from App J to 10CFR50 for 12 Valves in Reactor Bldg Closed Cooling Water Sys.Valves Not within Definition of Containment Isolation Valves in App J & Not Required to Be Tested ML20043E8831990-06-0505 June 1990 Requests NRC Authorization to Use Plugs Fabricated of nickel-chromium-iron Uns N-06690 Matl Alloy 690 to Plug Tubes in Steam Generators of Plant ML20043D0451990-05-30030 May 1990 Discusses Proposed Rev to Tech Specs Re Facility ESF Actuation Sys Instrumentation Trip Setpoint,Per 900330 Ltr ML20042H0311990-05-0909 May 1990 Discusses Steam Generator Safety Assessment.Concludes That Continued Operation Through Remainder of Current Cycle 10 Fully Justified ML20042F0941990-04-30030 April 1990 Provides Addl Info Re Environ Impact of 900226 Application for Amend to License NPF-49,revising Tech Specs to Allow Containment Pressure to Increase to 14 Psia During Modes 1-4,per NRC Request ML20042F0661990-04-30030 April 1990 Responds to NRC 900404 Ltr Re Violations Noted in Safety Insp Rept 50-336/90-01 on 900120-0305.Corrective Action:Ler 90-004 Submitted on 900430 to Document Condition Prohibited by Plant Tech Specs ML20042E8331990-04-27027 April 1990 Forwards Annual Environ Protection Plan Operating Rept for 1989, & Monitoring Marine Environ of Long Island Sound at Millstone Nuclear Power Station Annual Rept 1989. ML20012E2681990-03-23023 March 1990 Responds to NRC 900226 Ltr Re Violations Noted in Insp Rept 50-423/89-23.Corrective Actions:Requirement to Review All Changes on Safety Sys for Potential Operating Procedure Changes Stressed to Operations & Engineering Personnel ML20012C3141990-03-13013 March 1990 Forwards Info Re Insp of Facility Emergency Operating Procedures,Per 900119 Ltr ML20012B4111990-03-0202 March 1990 Provides Addl Info Requested to Clarify Changes Proposed to Tech Spec Action Statements for Inoperable Accumulator B13453, Advises That Mods to Steam Generator Blowdown Sample Sys Completed,Per Violations Noted in Insp Rept 50-423/89-14 & Salp.Sys Will Be Evaluated for Next 2 Wks to Ensure Blowdown Radiation Monitor Operating Reliably1990-02-26026 February 1990 Advises That Mods to Steam Generator Blowdown Sample Sys Completed,Per Violations Noted in Insp Rept 50-423/89-14 & Salp.Sys Will Be Evaluated for Next 2 Wks to Ensure Blowdown Radiation Monitor Operating Reliably ML20011F7541990-02-26026 February 1990 Notifies That Jh Parillo Reassigned & No Longer in Need of License SOP-10263-2 as of 900219 ML20006G1581990-02-21021 February 1990 Forwards Response to & Comments on Initial SALP Rept 50-423/88-99 for Period 880601 - 891015.Procedures Revised to Permit Operators to Adjust Area Monitors to Reduce Nuisance Alarms 1990-09-07
[Table view] |
Text
.
A IMHtTHI!A!iT UTII.ITII!!i
.. t'"""
P O. BOX 270
'", HARTFORD, CONNECTICUT 06101 eo 4 (203) 666-6911 L L ; .
September 10, 1979 Docket Nc. 50-336 Mr. Boyce H. Grier, Director Region 1 Office of Inspection and Enforcement U. S. Nuclear Regul 2'ory Commission 631 Park Avenue King of Prussia, PA 19406
References:
(1) B. H. Grier letter to W. G. Counsil dated August 15, 1979 forwarding I&E Bulletin #79-14, Supplement.
(2) B. H. Grier letter to W. G. Counsil dated July 2,1979 forwarding I&E Bulletin #79-14.
(3) W. G. Counsil letter to B. H. Grier dated August 31, 1979.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 I&E Bulletin #79-14 Reference (2), as amended by Reference (1), requested Northeast Nuclear Energy Company (NNECO) to initiate a program almed at verifying the accuracy of input information for seismic analysis of safety-related pipi " .
In Reference (2), NNECO informed the NRC Staff that during the outage commencing August 8, 1979, inspections were performed on portions of the normally inaccessible seismic systems as required by item 3 in Reference (1), in addition to the inspections required by Item 2 of the same Reference. NNECO hereby submits the attached available results to Items 2 and 3 of Reference (1).
Reference (1) requires inspections of one (1) system in each set of redundant systems, and all non-redundant systems for conformance to the seismic analysis input information set forth in design documents. Included in this inspection program are:
(1) Pipe run geometry.
(2) Support and Restraint design (location, function, clearances).
(3) Floor and wall penetrations.
(4) Embedments (excluding those covered by I&E Bulletin #79-02).
(5) Pipe attachments.
(6) Valve and valve operator location and weights (excluding those covered by I6" Bulletin #79-04) .
1180 269 I
\ r::' i 7910190
The following systems are presently under examination / verification and include b ch accessible and inaccessible areas of the plant as defined in Reference (1) :
e Main Steam o Feedwater e Service Water e Service Water to Chilled Water o Chilled Water to Switchgear e liigh Pressure Safety Injection (ILPSI) e Low Pressure Safety Injection (LPSI) e Containment Spray e Safety Injection Tanks e Reactor Building Closed Cooling Water (RBCCW) a Spent Fuel e Diesel Generator e Chemical and Volume Control System (CVCS) e Boric Acid e Reactor Coolant e Auxiliary Feedwater As of August 27, 1979, approximately ten thousand (10,000) linear f eet of pipe and eight hundred (800) supports have beer examined. Table 1, in the attachmer.L, lists the appra cimate percentage of each system which has been inspected.
The results of the inspections are summarized in Table 2 and a detailed listing of deviations and their preliminary resolution is presented in Table 3 of the attachment. The deviations to date generally fall into one of five categories.
(1) Pipe geometry variances.
(2) Missing or relocated supports.
(3) Additional constraints.
(4) Deviation from support design.
(5) Anchor bolt or base plate (loose nuts, etc. ) .
Deviation Types (1) through (3) are evaluated by a piping stress analyst.
Those requiring a reanalysis, ia the judgment of the analyst, will be scheduled for reanalysis following his review of the completed system walkdown documentation.
The evaluation of Type (4) deviations are performed by pipe support designers only af ter it has been determined that a reanalysis of the piping is not required or when the reanalysis is complete. These evaluations are in progress at this time. Type (5) nonconformances are being evaluated pursuant to I6E Bulletin #79-02.
It is emphasized that there have been no deviations reviewed to date that, by engineering judgment or analysis, affect the operability of any system under verification.
The inspections of the normally inaccessiole systems inside containment, as outlined in Table 1, did not reveal any deviations which affect system opera-bility. Based on the acceptability of the results obtained to date, discrepancies which could impact system operability are not expected to be identified during the remaining examinations of accessible or inaccessible systems.
I180 270
NNECO intends to examine / verify the remaining portions of the inaccessible systems during the next refueling outage. This decision is based on the following:
(? No deviations identified to date have adversely af fected the operability of any system under evaluation.
(2, Teledyne Engineering Services provided the original Class I piping stress analysis and examined the geometry for as-built conditions after hot functional testing.
In addition, examinations will be conducted on the inaccessible systems during any outage of sufficient duration occurring before the refueling outage, such as the one which will occur before October 31, 1979. NNECO presently plans to continue the examinations of the accessible piping systems. A final report containing the result of the remaining inspections will be submitted upon comple-tion of the inspections.
We trust you find this information responsive to the NRC Staf f concerns.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY l
.. 2. f7Mian '/
W. G. Counsil Vice President Attachments 1180 271
DOCKET No. 50-336 ATTACHMENT MILLSTONE h"JCLEAR POWER STATION, UNIT No. 2 RESPONSE TO I6E BULLETIN #79-14 SEPTDiBER, 1979 1180 272
MILLSTONE UNIT NO. 2 I&E BULLETIN #79-14 -- 60-DAY S"BMITTAL TABLE 1
% COMPLETE % COMPLETE OUTSIDE OF INSIDE OF SYSTEM CONTAINMENT CONTAINMENT Main Steam 60 85 Feedwater 5 100 Containment Spray 30 30 Safety Injection Tanks N/A 20 RBCCW 25 10 CVCS --
10 Service Water 95 N/A Chilled Water 100 N/A HPSI 55 --
LPSI 50 --
Spent Fuel Pool 85 --
Diesel Systems 100 N/A Auxiliary Feedwater 85 N/A
/
1180 273
LIST OF ABBREVIATIONS USED IN TABLE 2 AUX. F.W. . . . . . . . . . . . . Auxiliary Feedwater Cnds. . . . . . . . . . . . . . . Condensate Etorage Tank C.V. . . . . . . . . . . . . . . . Check Valves C.S. . . . . . . . . . . . . . . . Containment Spray Htx. . . . . . . . . . ., . . . . Heat Exchanger TK . . . . . . . . . . . . . . . . Tank S.W. . . . . . . . . . . . . . . . Service Water D.G. . . . . . . . . . . . . . . . Diesel Generator 1180 274
/
fi Table 2 Sheet 1 of 4 MILLSTONE UNIT 2 IE BULLETIN 79-14 60 DAY WALKD(MN RESULTS IS SYSTEM OPERABILITY QUANTITY & TYPE OF DEVIATION IS PIPING AFFECTED ANALYSIS TYPE TYPE TYPE TYPF. TYPE RIANALYSIS (ENGINEERINC/ IS SUPPORT REANALYSIS SYSTEM SUBSYSTEM PROBLEM # le 2* 3* 4* 5* QQUIRED JUDCMENT) ADEQUATE SCHEDULE COMMENT Diesel Exhaust Rerouted and Reanalyzed by NUSCO Diesel Intake 420 2 1 No No Relocate Supports As Designed Diesel Systems Diesel Intake 421 1 1 No No Starting Air 410 2 5 2 No Chilled S.W. To Chillers No Rerouted and Reanalyzed by NUSCO Water Pump Soction 49C 1 No Walkdown Incomplete Spent Fuel Pool outlet 50 1 3 1 1 No Portion Inaccessible Fuel Pool Pump Disch. 164 1 1 1 4 No Walkdown incomplete Cooling Fuel Pool Return 166 4 1 2 No Portion Inaccessible
-= S.W. From
- Intake Structure 114 1 7 No
- Portion Inaccessible CD C
- Note: Type (1) Geometry Change, Type (2) Missing or Relocated Supports. Type (3) Additional Constraints Type (4) Deviation From Support Design (5) Anchor Bolts and Base Plates - IE Bulletin 79-02 CD
lable 2 Sheet 2 of 4 MILLSTONE UNIT 2 IE BULLt. TIN 79-14 60 DAY WALKIxk'N RESULTS IS SYSTEM OPERABILITY QUANTITY & TYP. )F DEVIATION IS PIPING AFFECTED ANALYSIS TYPE TYPE TYPE TYPE TYPE R MNALYS IS (ENGINEERING / IS SUPPORT RL\N\ LYSIS PROBLEM i la 2* 3* 4* 5* REQUIRED JUDCMENT) ADEQUATE SCHEDUI.E COMMENT SYSTEM SUBSYSTEM S.W. Return 114 1 7 ?k) Portion inaccessible From D.C.
S.W. Return 121 2 1 6 No To Stress 8/29 From D.C.
S.W. Return 122 1 2 No To Stress 8/29 From D.C.
Service S.W. Supply 115 7 2 6 3 No Water To D.G. Coolers S.W. Supply To 118 1 1 3 8 No D.C. Coolers
- S.W. Supply To 119 1 1 fk)
D.G. Coolers O S.W. Supply To 120 1 3 2 ti, O D.C. Coolers Nj S.W. Return From 112 3 11 14 2 No y RBCCW Cooler 411 1 3 No
- Note: Type (1) Geometry Change, Type (2) Missing or Relocated Supports, Type (3) Additional Constraints Type (4) Deviation From Support Design (5) Anchor Bolts and Base Plates - IE Bulletin 79-02
Table 2 Sheet 3 of 4 MILLSTONE UNIT 2 IE BULLETIN 79-14 60 DAY WALKIX&"4 RESULTS IS SYSTEM OPEPABILITY QUANTITY & TYPE OF DEVIATION IS PIPING AFFECTED ANALYSIS TYPE TYPE TYPE TYPE TYPE REANALYSIS (ENGINEERING / IS SUPPORT REAMLYSIS SYSTEM SUBSYSTEM PROBLEM f 1* 2* 3* 4* 5* REQUIRED JUDGME.NT) ADEQUATE SCllEDULE COMMENT Feed- Inside Containment 21 2 2 No Water 22 1 No Pump Disch. To 61 3 No Partial Package lit x . & Rad. Mon.
Supply Hdrs. From 66 1 No Partial Package RBCCW RBCCW Exchanger Pump Suct. From 70 1 1 1 1 No Partial Package RBCCW Surge Tk.
Ret. From Engr. 129 1 2 No Partial Package Safeguard Room Air Recirc. Colls W
y CN DS . From Stor. 35 1 No Partial Package g Tk. To F.W. Pumps Aux. F.W. Pumps 101 1 1 3 4 No Partial Package N Pumps Disch. To N CV's.
N
- Note: Type (1) Geometry Change, Type (2) Missing or Relocated Supports Type (3) Additional Constraints Type (4) Deviation From Support Design (5) Anchor Bolts and Base Plates - IE Bulletin 79-02
Table 2 Sheet 4of4 MILLSTONE PNIT 2 IE BULLETIN 79-14 (Al DAY WALKIMEN RF.StTLTS IS SYSTEM OPERAhlLITY qtlANTITY & TYPE OF DEVIATION IS PIPING AFFECTFD ANALYSIS TYPE TYPE TYPE TYPE TYPE luANALYSIS (ENGINEERING / IS SUPPORT PEANALYSIS JUIx; MENT) ADEQlfATE SCHEDt'LE COMMENT PROBI.EM i 1* 2* 3* 4* 5* REqu i t:ED SYSTEM SUBSYSTEM tb Partial Package Cnds. To Aux. 102 1 F.W. Pumps
!b Partial Package Aux. F.W. Fron 103 1 Aux. C.V.'s To Isol, Feed- VaAves water Parttal Package 2 3 No Cnds. From Stor. 110 1 Tk. To F.W. Pumps 3 !b Partial Package Aux. F.W. From 100 3 C.V.'s to isol.
Valves Na Part tal Package Main N/A 13 1 23 Steam
!b Partial Package Safety 1.PS I 44 1 1 inlection !b Parttal Package LPSI/C.S. 46 4 3 2
" !b Parttal Packace ItPSI 47 1 Q
CD
- Note: Type (1) Geometry Changa, Type (2) Missing or Relocated Supports. Type (3) AJJ1ttonal Constraints N Type (4) Deviation From Support Design (5) Anchor Bolts and Base Plates - IE Bulletin 79-02 C
TABLE 3 NOTATIONS NOTATION EXPLANATION Stress . . . . . . . . . . . . . . . . Refers to the analytical group designated to review and evaluate non-conformities identified in I&E Bulletin #79-14, which may affect the original stress analysis.
Support . . . . . . . . . . . . . . . Refers to the analytical group designated to review and evaluate non-conformities identified in I&F. Bulletin #79-14 involving pipe support or constraint.
Supt. . . . . . . . . . . . . . . . . Support Dwg. . . . . . . . . . . . . . . . . Drawing i180 279
MILLSTONE UNIT 2 TALLE 3 INITIAL RESOLUTIONS OF NONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM DIESEL GEN. INTAKE P61D N/A PRELIMINARY PROBLEM NO. NONCONFORMANGE EVALUATION RESOLUTION 420 SK-M-1091-B25058 Support Relocated Stress Group to Review Relocate Support as Designed SK-M-1091 - No Restraint Dwg. Pipe Support Group to Review Perding 421 SK-M-1092 - Pipe Branch Eliminated To Be Revies?d by Stress Group Acceptable But Must Check Support for New Loads SK-M-1092 - No Clearance Through To Be Reviewed by Stress Group Acceptable Penetration 410 FSK-M-003 Support Dwg. #4057S7 To Be Reviewed l'nder IE Recorque Anchor Bolts Bulletin #79-02 FSK-M-003 Support Dwg. #405789 To Be Reviewed Under IE Retorque Anchor Bolts Bulletin #79-02 FSK-M-003 Penetration Constrains To Be Reviewed by Stress Group Pending Pipe FSK-M-003 Unidentified Support To Be Reviewed by Stress Group Pending FSK-M-003 Support Dwg. #405789 To Be Reviewed by llanger Group Pending Installation Not Per Design FSK-M-018-004 Miscellaneous Support To Be Reviewed by lla"ger Group Pending Installations Do Not Agree With Design M
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MILLSTONE UNIT 2 TABLE 3 ,
1NITIAL RESOLUTIONS OF NONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM SPENT FUEL POOL COOLING (CONTINUED) P&ID 25203-26023 PRELIMINAP.Y PROBLEM NO. NONCONFORMANCE INALUATION RESOLUTION 166 SK-M-563 Support Dwg. #403111 To Be Reviewed Under IE Bulletin Retorque Anchor Bolts Base Plate Not Snug #79-02 SK-M-563 Support Dwg. #403112 To Be Reviewed Under IE Bulletin Retorque Anchor Bolts Base Plate Not Snug #79-02 SK-M-568 Penetrations Grouted To Be Reviewed by Stress Group Pending SK-M-563 Support Dwg. #403112 To Be Reviewed by Pipe Support Pending Weld Not Per Design Group CD N
CO N
MILLSTONE UNIT 2 TABLE 3 INITIAL RESOLUTIONS OF NONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM RBCCW P&ID 25203-26022 PRELIMINARY PROBLEM NO. NONCONFORMANCE EVALUATION RESOLUTION 61 SK-M-534 - Supt. Dwg. #450071 Support Group to Verify Seismic Acceptable Supt. Dif fers f rom Design Dwg. Integrity SK-M-534 - Supt. Dwg. #405498 Support Gro*2p to Check if 2 Fix Support '.fith 4 Bolts Per Design Supt. Differs from Design Dwg. Bolts on Plate Are Adequate Dwg.
SK-M-533 - Supt. Dwg. #405617 Stress to Review Ef fect on Install Shim Pla':e to heduce Excessive Clearance at Support Seismic Integrity Clearance to 1/16" 66 SK-M-446 - Supt. Dwg. #350038 Support Group to Verify if Acceptable Supt. Differs from Design Dwg. Support is Acceptable 70 SK-M-452 - Supt. Dwg. #405555 Support Group to Review Strut Length Acceptable / Plant to Sway Strut is 5 1/2" Too Long Position Clamp Per Design Drawing Pipe Clamp Loc. Incorrect SK-M-452 - Supt. Dwg. #505016 Base Plates and Bolts to be 'lant Maint. to Resolve - Retorque, Bolts Loose at Plate Checked Under IE Bulletin #79-02 e.r Repl. Bolts if required.
SK-M-476 - Supt. Dwg. #405242 Review Incompl.
Bent Rod From Spring Can Touches Adjacent Piping SK-M-476 - Supt. Dwg. #305916 Review Incompl.
Support is Missing M
CD N
CD U
MILLSTONE UNIT 2 TABLE 3 INITIAL RESOLUTIONS OF NONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM RBCCW (CONTINUED) P6ID 25203-26002 PRELIMINARY PROBLEM NO. NONCONFORMANCE EVALUATION RESOLUTION 129 SK-M-839 - Supt. Dwg. #405460 Civil Engr. to Verify Load Sup- Pending Supt. Inverted and Attached to porting Capability of CMU Wall CMU Wall Not Conc. Wall SK-M-839 - Supt. Dwg. #405457 Stress to Evaluate as Built Loc. Pending Supt. Not at Loc. Set by Design Dwg.
SK-M-839 - Supt. Dwg. #405454 Civil Engr. to Verify Load Sup- Pending Supt. Attached to CMU Wall Not a porting Capability of CMU Wall Conc. Wall CD N
CD
MILLSTONE UNIT 2 TABLE 3 INITIAL RESOLUTIONS OF NONCONFORMINCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM FEEDWATER P&ID 25203-26005 PRELIMINARY PROBLEM NO. NONCONFORMANCE EVALUATION RESOLUTION 22 SK-M-326 Sup. Dwg. #412018 Support To Be Checked Under IE Bulletin Items 2,3 and 4 Design 3/4" #79-02 Actual 5/8" 21 SK-M-326 Sup. Dwg. #412013 Deviation No Affect on Support Design Acceptable from Support Design SK-M-326 Sup. Dwg. #412015 1/8" To Be Checked Under IE Bulletin Cap Between Plate and Wall #79-02 SK-M-326 Sup. Dwg. #412017 1/8 " To Be Checked Under IE Bulletin Cap Between Plate and Wall #79-02 SK-M-326 Sup. Dwg. #412013 Support Insignificant Deviation Acceptable Projected f rom Wall 3" > Design. Ad-ditional Plates Added to Snubber Attachment to Make Up Difference M
CD N
CD LT1
TABLE 3 MILLSTONE UNIT 2 INITIAL RESOLUTIONS OF NONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM LPSI P&ID 25203-.!6015 PRELIMINARY EVALUATION RESOLUTION PROBLEM NO. NONCONFORMANCE_
44 SK-M-513 - Supt. Dwg. #402006 Support Group to Check Acceptable 1 Support Member Larger Than Reg'd Per Design Dwg.
SK-M-513 - Supt. Dwg. #402007 Bolts To Be Checked Under IE Bulletin Plant Maint. to Retorque Bolts Loose at Plate #79-02 46 CK-M-523 - Supt. Dwg. #402002 "o Be Checked Under IE Bulletin Plant Maint. to Retorque Bolts (2) Loose Bolts at Plate #79-02 SK-M-523 - Supt. Dwg. #402008 To Be Checked Under IE Bulletin Plant Maint. to Retorque Bolts (2) Loose Bolts at Plate #79-02 SK-M-523 - Supt. Dwg. #402097 Review Incomplete Supt. Loc. Incorrect SK-M-523 - Supt. Dwg. #402120 Supt. Review Incomplete Loc. Incorrect CD N
CO Os
MILLSTONE UNIT 2 TABLE 3 ,
INITIAL RESOLUTIONS OF NONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM CONTAlle!ENT SPRAY P&ID 25203-26015 PRELIMINARY PROBLEM NO. NONCONFORMANCE EVALUATION RESOLUTION 46 SK-M-425 - Supt. Dwg. #401008 Supt. Review Incomplete Location Incorrect SK-M-425 - Supt. Dwg. #301126 Supt. Review Incomplete Location Incorrect SK-M-425 -- Sup t . Dwg. #501024 Review Incomplete Incorrect Mark No. on Supt.
CD N
CO N
MILLSTONE UNIT 2 TABLE 3 INITIAL RES7LUTIONS OF NONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM IIPSI P&ID 25203-26015 PRELIMINARY EVALUATION RESOLUTION PROBLEM NO. NONCONFORMANCE 46 SK-M-424 - Supt. Dwg. #502019 Review Incomplete Welds Not Per Design Dwg.
SK-M-424 - Supt. Dwg. #30292 Review Incomplete Differs From Design Dwg.
SK-M-423 - Supt. Dwg. #401001 Review Incomplete S.S. ahield Missing 47 SK-M-423 - Supt. Dwg. #401003 Review Incomplete S.S. Shield Missing M
C N
ro CO
MILLSTONE UNIT 2 TABLE 3 INITIAL RESOLUTIONS OF NONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM AUXILIARY FEEDWATER (AUX. F.W. ) psIn 25203-26005 PRELIMINARY PROBLEM NO. NONCONFORMANCE EVALUATION RESOLUTION 35 SK-M-615 - Supt. Dwg. #405350 Stress to Verify Supt. Pending Supt. Structure Incomplete 101 SK-M-1008 - Valves-2FW-56A & 't are Stress Group to Review for Ad- Pending 6" Not 4" as Per Design Dwg. ditional Weight Effect Upon Analysis SK-M-1008 - Supt. Dwg. #413130 Bent To Be Checked Under IE Bulletin Plant Maint. to Retorque Bolt or Bolt in Base Plate #79-02 Replace if Reg'd.
SK-M-1008 - Supt. Dwg. #413205 Cap To Be Checked Under IE Bulletin Plant Maint. to Retorque Bolt or Between (2) Plates and Wall #79-02 Replace if Req'd.
SK-M-1008 - Supt. Dwg. #413122 Supt. Support Group to Chec k Acceptable Does Not Look Like Design Dwg.
SK-M-679 - 11 ping Geomet ry Dif fers Stress to Check Pending From Design Dwg.
SK-M-679 - Supt. Dwg. #413111 Loc. Stress to Check Pending Differs From Design Dwg.
CD SK-M-598 - Piping Geometry Differs Review Incomplete o From Design Dwg.
N SK-M-598 - Supt. Dwg. #513019 Gap To be Checked Under IE Bulletin Plant Maint. to Retorque Bolts CO Between Plate and Wall #79-02 4
SK-M-598 - Supt. Dwg. #413153 Loose To be Checked Under IE Bulletin Plant Maint. to Retorque Bolts Nets at Plate #79-02 102 SK-M-673 - New Support Added Stress to Review for Possible Pending Effects on Analysis
MILLSTONE UNIT 2 TABLE 3 INITIAL RESOLUTIONS OF NONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM AUX. F.W. (CONTINUED) P&ID 25203-26005 __
PRELIMINARY PROBLEM NO. NONCONFORMANCE EVALUATION RESOLUTION 103 SK-M-1008 - Supt. Dwg. #413124 Loose To Be Checked Under IE Bulletin Plant Maint. to Retorque Bolts Bolt at Plate-Gap Betw. Plate & Wall #79-02 110 SK-M-674 - Supt. Dwg. #505330 Supt. Stress to Check Pending Does Not Agree With Design Dwg.
SK-M-6 74 - Sup t. Dwg. #505330 (2) To Be CLecked Under IE Bulletin Plant Maint. to Retorque Bolts Bolts Loose at Plate #79-02 SK-M-674 - Supt. Dwg. #505061 Base To Be Checked Under IE Bulletin Pending Plate Bolts Wrong Size #79-02 SK-M-674 - Supt. Dwg. #505262 Supt. Stress to Check Pending Off Design Location SK-M-674 - Supt. Dwg. #405331 Plate Support Group to Check Acceptable Size Differs From Design Dwg.
SK-M-674 - Supt. Dwg. #405331 To Be Checked Under IE Bulletin Plant Maint. to 8etorque Bolts 1 Corner of Plate Loose From Wall #79-02 100 SK-M-616 - Supt. Dwg. #413187 Supt. Review Incomplete Does Not Agree With Design Dwg.
SK-M-616 - Supt. Dwg. #413189 Supt. Review Incomplete Does Not Agree With Design Dwg.
SK-M-616 - Supt. Dwg. #413189 Gap To Be Checked Under IE Bulletin Plant Maint. to Retorque Bolts Betw. Plate and Wall #79-02
] SK-M-616 - Supt. Dwg. #313074 'to Be Checked Under IE Bulletin Plant Maint. to Retorque Bolts g ( 3) Loose Bolts at Plate #'/9-02 O
rJ W
Q
MILLSTONE UNIT 2 TABLE 3 INITIAL RESOLUTIONS OF NONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM AUX. F.W. (CONTINUED) psip 25203-26005 PRELIMINARY PROBLEM NO. NONCONFORMANCE EVALUATION RESOLUTION 100(Cont'd) SK-M-616 - Supt. Dwg. #413186 To Be Checked Under IE Bulletin Plant Maint. to Retorque Bolts (2) Loose Bolts at Plate #79-02 SK-M-616 - Supt. Dwg. #413186 Supt. Review Incomplete Does Not Agree With Design Dwg.
M CD N
4
MILLSTONE UNIT 2 TABLE 3 INITIAL RESOLUTIONS OF NONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 5YSTEM MAIN STEAM P&ID 25203-26002 PRELIMINARY PROBLEM NO. NONCONFORMANCE EVALUATION RESOLUTION _
13 S K- M-317- Su p t . Dwg. No. 490005 Support Group To Check Acceptable Supt. Differs From Design Dwg.
SK-M-317-Supt. Dwg. No. 490006 Support Group To Check Acceptable Supt. Differs From Design Dwg.
SK-M-317-Supt. Dwg. No. 490008 Support Group To check Interference Must Be Corrected To Pipe Movement Restrained By Allow Pipe To Move Freely. (NUSCO Interference Between Supt. & Suggests To Check For Correct Supt.
Structural Steel. Loc. During Shut-Down).
SK-M-317-Supt. Dwg. No. 490003 Support Group To Check Acceptable Joints Welded Rather Than Bolted SK-M-317-Supt. Dwg. No. 490009 Support Group To Check Acceptable Joints Welded Rather Than Bolted SK-M-- 317-S u p t . Dwg. No. 413011 Support Group To Check Acceptable Snubber Adj. Incorrect SK-M-317-Supt. Dwg. No. 413019 Support Group Ta Check Acceptable Supt. Does Not Look Like Design Dwg.
SK-M-317-Supt. Dwg. No. 413024 Support Group To Check Acceptable Supt. Differs From Design Dwg.
SK-M-317-Supt. Dwg No. 413025 Support Group To Check Action Req'd-Calculation is Reg 'd for
] Supt. Differs From Design Dwg. Upper Snubber For Design Piston Settings.
SK-M-317-Supt. Dwg. No. 413014 Support Group To check Acceptable C Supt. Differs From Design Dwg.
N
'O N'
MILLSTONE UNIT 2 TABLE 3 INITIAL RESOLUTIONS OF MONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM MAIN STEAM (Conti ad) P&ID 25203-26002 PRELIMINARY PROBLEM NO. NONCONFORMANCE EVALUATION RESOLUTION 13 SK-M-317-Supt. Dwg. No. 413014 Support Group To Check Acceptable (Continued) Supt. Differs From Design Dwg.
SK-M-317-Supt. Dwg. No. 413020 Support Group To check Acceptable Supt. Differs From Design Dwg.
SK-M-3.7-Supt. Dwg. No. 413041 Support Group To Check Acceptable Snubber Is Installed Closer To The Pipe-No t Per Design Dwg.
SK-M-317-Supt. Dwg. No. 413023 Support Group To Check Acceptab'e Supt. Attached To Beam Larger Than That Shown On Design Dwg.
SK-M-317-Supt. Dwg. No. 413022 Support roup To Check Acceptable Supt. Differs From Design Dwg.
SK-M-317-Supt. Dwg. No. 413046 Detailed Analysis Is Reg d Pending Some Supt. Parts Missing SK-M-317-Supt. Dwg. No. 413010 keview Incomplete Possibly Wrong Size Sway Strut SK-M-317 Supt. Dwg. No. 413031 Support Group To Check New load Calcu'.ation Required Some Supt. Parts Are Wrong Size SK-M-317-Supt. Dwg. No. 413033 Support Group To Check Acceptable Sway Strut Size Possibly
', Incorrect.
O SK-M-317-Supt. Dwg. No. 413032 Support Group To Check Acceptable Support Differs From Design
.g Dwg.
.J v4
MILLSTONE UNIT 2 TABLE 3 INITIAL RESOLUTIONS GF NONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM MAIN STEMI (Continued) P&ID 25203-26002 PRELIMINARY PROBLEM NO. NONCONFORMANCE EVALUATION RESOLUTION 13 SK-M-317-Supt. Dwg. No. 513034 Support Group To Check .cceptable (Continued) Support Dif fers From Design Dwg.
S K-M-317-S u p t . Dwg. No. 413071 Support Group To Check !1d Calculation Required & Web Welds Incorre.u & (1) Stiff Crippling Calculation Plate Missing SK-M-317-Supt. Dwg. No. 413C29 Review Incomplete Supt. Differs From Design Dwg.
SK-M-317-Supt. Dwg. No. 413030 Review Incomplete SK r'!-317-Supt. Dwg. No. 413021 Support u..ip To Check Acceptable Support Differs from Design Drawing M
O r'd
'J b
MILLSTONE UNIT 2 TABLE 3 .
INITIAL RESOLUTIONS OF NONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM SERVICE WATER P&ID 25203 - 26008 PRELIMINARY PROBLEM NO. NONCONFORMANCE EVALUATION RESOLUTION 112 SK-M-560 To Disch. Conduit
-Unidentified Support Stress Group To Review Pending
-Unidentified Penetration (Thru. F1. El. 3' - 0")
-Unidentified Penetration (Thru. F. (-) 5' - 0")
-Unidentified Penetration (Thru. Wall El. 9' - 4")
SK-M-573 Return From RBCCW IIcat Exchangers
-4 Bolts Not Tight - Support Dwg. To Be Reviewed Under IE Bulletin Retorque Anchor Bolts No. 42710 79 - 02
-Support 11-6 Bolts & Nuts Loose To Be Reviewed Under IE Bulletin Retorque Anchor Bolts (See Dwg. No. 427099A & B) 79 - 02
-Unidentified llanger See SK-M-573 Stress Group To Review Pending
-New IIangers 427070 & 427071
-Unidentified Penetration (Thru F. At El. 3' - 0")
-Unidentified Penetration (Thru Fl. El. (-) 5'- 0")
-Unidentified Penetration (Thru. Wall El. 9' - 4")
SK-M-486
-3" Bypass Added Arouni Valve TV - 6306 Stress Group To Review Pending
-Valve 25WCC Operator Orientation
-^
Changed Stress Group To Review
-Valve 25W8.lc Operator
~} Orientation Changed Stress Group To Review
_)
rd
- 7) f 13
MILLSTONE UNIT 2 TABLE 3 INITIAL RESOLUTIONS OF NONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM SERVICE WATER CONTINUED P&ID 25203 - 26008 PRELIMINARY PROBLEM NO. NONCONFORMANCE EVALUATION RESOLUTION 112 SK-M-484 Return From RBCCW Heat Exchangers 24" @ Lines Prevented From Stress Group To Review Pending Moving North (See Sketch 79-14-003)
-Pipe Support H-8 Not Marked Stress Group To Review Pending
-Pipe Support R-18 Incorrect Stress Group To Review Pending Location
-Pipe Support H-7 (Not As Designed) Support Group To Review Acceptable Sec Dwg. No. 427102A
-Pipe Support R-11 (Does Not Look Support Group To Review Pending As Designed) See Dwg. No. 427113 SK-M-483
-Valve TV-6308 Operator Stress Group To Review Pending Orientation Changed
-Valve 2-SW-9A Operator Stress Group To Review Pending Orientation Changed
-Pipe Suppor t H-10 (Not As Support Group To Review Pending Designed)(See Dwg. No. 527068B)
-Pipe Support R-12 (Not As Designed) Support Group To Review Pending (See Dwg. No. 427016A)
SK-M-485
-Valve 2-SW18.1B Operator Stress Group To Review Pending Orientation Changed
-Unidentified Pentration Stress Group To Review Pending 114 SK-M-691-Supt. Dwg. No. 527039, Stress to Check Anchor Replace Broken Bolts Bolts Sheared Off & Struct. Loade & Re-evaluate Bolt Member Sizes Incorrect Sizes CD c:3 SK-M-690 & 691 equence of Valves Stress Review Req'd. Pending Stress Review pg Is Reversed W
Ch
TABLE '.,
MILLSTONE UNIT 2 INITIAL RESOLUTIONS OF NONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM SERVICE WATER CONTINUED P&ID 25203 - 26008 PRELIMINARY PROBLEM NO. NONCONFORMANCE EVALi'ATION RESOLUTION 114 SK-M-690-Supt. Dwg. No. 327076 Base Plates & Bolts To Be Checked Re-Torque Or Replace Bolts Base Pl. Loose At Wall. Under IE Bulletin 79-02. As Required.
SF-M-691-Supt. Dwg. No. 427048 Base Plates & Bolts To Be Checked Re-Torque Or Replace Bolts Bol'.s Loose At Plate Under IE Bulletin 79-02 As Required.
SK-M-691-Supt. Dwg. No. 427047 Base Plates & Bolts To Be Checked Re-Torque Or Replace Bolts Bolts Loose At Plate Under IE Bulletin 79-02 As Required.
SK-M-690-Supt. Dwg. No. 327075 Base Plates & Bolts To Be Checked Re-Torque Or Replace Bolts Bolts Loose At Plate Under IE Bulletin 79-02 As Required.
SK-M-691-Supt. Dwg. No. 327077 Base Plates & Bolts To Be Checked Re-Torque Or Replace Bolts Bolts Loose At Plate. Under IE Bulletin 79-02. As Required.
SK-M-691-Supt. Dwg. No. 427046 Base Plates & Bolts To Be Checked Re-Torque Or Replace Bolts Bolts Loose At Plate. Under IE Bulletin 79-02 As Required.
115 SK-M-569-Supt. Dwg. No. 427083 Support Group To Check Existing Acceptable Welds Not Per Design Weld For Adequacy SK-M-625-Support Not Shown On Stress Review Reg'd Pending Design Drawing SK-M-569-Support Not Shown On Stress Review Reg'd Pending Design Drawing 2 SK-M-487-Supt. Dwg No. 427074 To Be Reviewed Under IE Bulletin 79-02 Pending m Eccentric Load On Base Plate CD SK-M-487-Supt. Dwg. No. 427113A To Be Reviewed Under IE Replace And Retorque Bolts N Bolts Loose or Bent At Plate Bulletin 79-02 As Required.
W N
MILLSTONE UNIT 2 TABLE 3 INITIAL RESOLUTIONS OF NONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM SERVICE WATER CONTINUED P&ID 25203 - 26008 PRELIMINARY PROBLEM NO. NONCONFORMANCE EVALUATION RESOLUTION 115 SK-M-625-Supt. Dwg. No. 427064 Support Group Review Required Acceptable "As Built" No t Per Design Drawing SK-M-569-Geometry Change Stress to Review Pending SK-M-569-Supt. Dwg. No. 427080 Support Group to Review Acceptable Welds Not Per Dwg.
SK-M-487-Valve Orientations Stress to Review Pending Not On Iso.
SK-M-625-Supt. Dwg . No . 327012 To Be Reviewed Under IE Pending 3/4" Designed Plate is 5/8" Bulletin 79-02 SK-M-625-Supt. Dwg. No. 327013 Support Group to Review Pending Weld Not Correct
-- SK-M-488-Operator Orientations Stress to Review Pending CX3 C;) SK-M-488-Supt. Dwg. No. 427075 Support Group to Review Pending Installation Not Per Design
[jf SK-M-488-Supt. Dwg. No. 427076 Support Group to Review Pending Installation Not Per Design SK-M-488-Supt. Dwg. No. 427114 To Be Reviewed Under IE Pending Plate Not Snug Bulletin #79-02.
118 SK-M-727-Supt. Dwg. No. 427092 To Be Reviewed Under IE Re-Torque or Replace Bolts Bolts Loose or Bent At Plate Bulletin #79-02. As Required' SK-M-725-Supt. Dwg. No. 427 04 7 To Be Reviewed Under IE Replace Bolt & Grout As Missing Anchor Bolt & Grout Bulletin #79-02. Necessary.
SK-M-725-Supt. Dwg. No. 327157 To Be Reviewed Under IE Re-Torque Anchor Bolts.
Base Plate Not Snug to W all Bulletin #79-02.
MILLSTONE UNIT 2 TABLE 3 INITIAL RESOLUTIONS OF NONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM SERVICE WATER CONTINUED P&ID 25203-26008 PRELIMINARY PROBLEM NO. NONCONFORMANCE EVALUATION RESOLUTION 118 SK-M-727-Supt. Dwg. No. 327147 To Be Reviewed Under IE Pending Anchor Bolts 5/8" In Lieu of 3/4" Bulletin 79-02 SK-M-727-Supt. Dwg. No. 327149 To Be Reviewed By Stress Pending Missing Support SK-M-727-Unidentified Support To Be Reviewed By Stress Pending Added.
SK-M-727-Supt. Dwg. No. 427094 To Be Reviewed Under IE Retorque Anchor Bolts Base Plate Not Snug Bulletin 79-02 SK-M-726 Supt. Dwg. No. 527073 To Be Reviewed Under IE Crout As Necessary Base Plate Not Grouted Bulletin 79-02 SK-M-726 Supt. Dwg No.527019 To Be Reviewed By Pipe Support Pending Single Stiffner Replaced by Two Designer SK-M-726-Supt. Dwg. No. 327121 To Be Reviewed Under IE Retorque Anchor Bolts Base Plate Not Snug Bulletin 79-02 SK-M-726-Supt. Dwg. No. 327122 To Be Reviewed Under IE Retorque Anchor Bolts Base Plate Not Snug Bulletin 79-02.
SK-M-726-Supt. Dwg. No. 327159 To Be Reviewed By Pipe Support Pending Dwg. Not Available Designer
__. SK-M-725-Supt. Dwg. No. 527015 Shorter Strut Is Better Acceptable
.__. Strut Length CD 119 CD SK-M-724-11' - 9" Dim. Is 9' - 0", Stress To Evaluate As Built Pending Support Not Marked On Iso.
N W
W
MILLSTONE UNIT 2 TABLE 3 INITIAL RESOLUTIONS OF NONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM SERVICE WATER CONTINUED P&ID 25203 - 26008 PRELIMINARY PROBLEM NO. NONCONFORMANCE EVALUATION RESOLUTION 120 SK-M-625-Additional Support Not Stress To Review Pending Shown On Iso.
SK-M-625-427092 - 1/2" Anchor Bolts Review Under IE Pulletin Pending Installed In Lieu of 5/8" Per Design. 79-02.
SK-M-625-427026-Different Steel Pipe Support Designers To Pending Attachment Than Design Review SK-M-625-380352-W 5 x 5 VSPO Used Pipe Support Designers To Pending In Lieu Of 4W13 Review SK-M-625-327135-Base Plates Incorrect Review Under IE Bulletin Pending Size; Not Snug To Wall 79-02.
SK-M-625-327133-Additional Plate Pipe Support Designers To Pending On Support Steel Review 121 SK-M-1028-Supt. Dwg. No. 327021 To Le Reviewed Under IE Pending Base Plate Reoriented Bulletin 79-02.
SK-M-1028-Supt. Dwg. No. 527060 To Be Reviewed Under IE Retorque Anchor Bolts Base Plate Not Snug. Bulletin 79-02 SK-M-1028-Supt. Dwg. No.527059 To Be Reviewed Under IE Retorque Anchor Bolts Base Plate Not Snug. Bulletin 79-02 SK-M-1028-Supt. Dwg. No.327042 To Be Reviewed Under IE Retorque Anchor Bolts
- Base Plate Not Snug Bulletin 79-02 Q SK-M-1028-Supt. Dwg. No.527034 To Be Reviewed Under IE Retorque Anchor Bolts O Base Plate Not Snug Bulletin 79-02.
SK-M-1028-Supt. Dwg. No.527001 To Le Reviewed Under IE Retorque Anchor Bolts g Base Plate Not Snug. Bulletin 79-02
MILLSTONE UNIT 2 TABLE 3 INITIAL RESOLUTIONS OF NONCONFORMANCES IDENTIFIED BY IE BULLETIN 79-14 SYSTEM SERVICE WATER CONTINUED P&ID 25201 ?finnR PRELIMINARY PROBLEM NO. NONCONFORMANCE EVALUATION RESOLUTION 121 SK-M-1208-Supt. Dwg. No. 527001 To Be Reviewed By Support Group Pending Members Not Same As Design SK-M-1208-Penetrations Fixed To Be Reviewed By Stress Pending 122 SK-M-1029-Supt. Dwg. No. 527026 To Be Reviewed By Stress Pending Support Missing SK-M-1209-Supt. Dwg. No. 527022 To Be Reviewed Under IE Retorque Anchor Bolts Base Plate Not Snug Bu1]etin 79-02 SK-M-1209-Supt. Dwg. No. 527093 To Be Reviewed Under IE Retorque Anchor Bolts Base Plate Not Snug Bulletin 79-02 411 SK-M-1031-General Configuration Review Incomplete Does Not Agree With Design Dwg.
SK-M- 1031-S up t . Dwg. No. 427107 Review Incomplete Part of Supt. Is Missing SK--M-1031-Su p t . Dwg. No. 427005 Review Incomplete Supt. Differs From Design Dwg.
SK-M-1031-Supt. Dwg. No. 427007 Review Incomplete Supt. Differs From Design Dwg.
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