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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
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l' Mrl'HI!AST UTII.ITII!S P O Box 270
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HARTFORD. CONNECTICUT 06101 l C03) 6066911 k k J August 1, 1979 Docket No. 50-336 Mr. Boyce H. Grier, Director Region 1 Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
References:
(1) B. H. Grier letter to W. G. Counsil dated July 18, 1979, transmitting I&E Bulletin #79-14, Revision 1.
(2) B. H. Grier letter to W. G. Counsil dated July 2,1979, transmitting I&E Bulletin #79-14.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Seismic Analyses, I&E Bulletin #79-14 __
Reference (2), as amended by Reference (1), requested Northeast Nuclear Energy Company (NNECON to initiste a program aimed at verifying the accuracy of input information for seismic analyses of safety-related piping. Subsequent to the receipt of this bulletin, communications with the NRC Staf f have resulted in a more concise understanding of the intent of the bulletin requiremerts.
As such, NNECO has embarked upon a program consistent with our present under-standing, with the following excepticns:
(1) Due to the extreme dif ficultica .ssociated with accessibility to portions of the containment spray piping, located on the interior surface of the containment dome, it is the intention of NNECO to examine those portions of the piping and supports using a visual inspection only. This would be performed using binocelors and other visual aids 7here necessary. It has been determined that the correctness of the existing analyses of this system can be verified by visual inspection techniques only.
(2) Insulation around some valves and embedments is extremely dif ficult and time-consuming to remove and replace. NNECO, therefore, intends to verify geometry and function at locations where removal of insula-tion would either result in unnecessary personnel exposure or be
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2009100 594 Q n :. I n
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duly ct becs>me using alternate techniques. This would include a sampliag of components where insulation is most readily removed and s 2rtial inspectirn of the remaining locations using probes and/or
_ucting away smal'. portions of insulation. Favorable results using these alternati.e techniques yielt high confidence from a statistical basis that che existing seismic ana jses are valid.
In response to the requirements of Itc. (1) of Reference (1) and based on subse-quent conversati,ns with the NRC Staf f , the following information is included as Attachment 1.
(1) A list of the safety-related systems to o. examined including their inspection schedule (i.e. , 60 days or 120 days) .
(2) One example system package used for surveillance with the following information:
(a) P&ID - color-coded Red : accessible - inspection within 60 days Blue: inaccessible - inspection within 120 days.
(b) Physical piping drawings - color-coded (c) Va?.ve drawings (d) Floor and wall penetration drawings (e) Pipe support detail drawings (f) A list of the above documents including:
(1) Identif ic ation (ii) Title (iii) Revision number (iv) Date We trust you find the above i-formation responsive to your request.
Very tru:y yours, FORTHEAST NL' CLEAR ENERGY COMPANY
/ /^ l
- h. ( { { -71)v W. G. Counsil Vice President Attach =ent 3_b')[$h)
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DOCKET No. 50-336 ATTACINENT 1 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 SEISMIC ANALYSES, ISE BULLETIN #79-14 AUGUST , 197 9 33.LO:39
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I REDUNDANT ACCESSIBLE !
3 l
SYSTDI YES } NO t YlS(I) NO ( SOME COMMENTS
! :
l I Reactor Coolant X X l t l l '
! !
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I !
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Chemical and Volume !
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Most Piping Outside Control [ X l X Containment is Accessible.
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I I i Emergency Core Cooling i X t i X Most Piping Outside
, Co nt a inment is Accessible.
i , j i
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Containment Spray j X ! X j Most Piping Outside l
Containment is Accessible.
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125 VDC Vital Switchgear l X
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j X l
i
Chilled Water Piping Only.
Vent , :
i i l Spent Fuel Pool Cooling l X X
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I Main Steam l
. X l l X I
l l Feedwater ; ;
X i X From Containment Iso. Vlv.
i j , i to S.G.
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f
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! !
Aux. Feedwater j X X ,
i I
, l
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l Reactor Building Closed , i Redundant to Vital Cooling Water ! X X Components.
I I
l
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Service Water X t X l
- , i l
! I I Diesel Generator X X i
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Miscellaneous Containment Outer side of penetration
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Penetrations X accessible.
(0 i
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i Q
(1) 60-day inspect ton sc hed ule ,
w h (2) 120-day inspection schedule
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SHEET 1 of 6 REV. O PROJECT: MILLSTONE UNIT 2 JOB 11867-014
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SYSTEM: MAIN STEAM PIPE SlTPORT DRAk'INGS IDENTIFICATION NO. T ITLE REVISION DATE 490004 (R-34) MAIN STEAM - STEAM GENERATOR TO 2 5/8/75 TURBINE 490005 (R-32) MAIN STEAM - STEAM GENERATOR TO 2 5/8/75 TURBINE 490G06 (R-38) MAUi STEAM - STEAM GENERATOR TO 1 5/8/75 TURBINE 490007 (R-37) MAIN STEAM - STEAM GENERATOR TO 1 5/8/75 TURBINE 49000d (R-31) MAIN STEAM G. E. PIPING 1 5/7/75 413007 (h-4) MAE4 STEAM DOWNSTREAM OF ISO 1 5/9/75 VALVES TO TURBINE 413008 (H-7) MAIN STEAM DOWNSTREAM OF ISO 1 1/3/74 VALVES TO TURBDiE 413009 (R-6) MAIN STEAM DOWNSTREAM OF ISO 1 5/7/75 VALVES TO TLLBINE 413010 (H-8) MAIN STEAM DOWNSTREAM OF ISO 1 12/2/74 VALVES TO TURBINE 413011 (R-9) MAIN STEAM DOWNSTREAM OF ISO 2 5/8/75 VALVES TO TURBUiE 413012 (H-11) MAIN STEAM DOWNSTREAM OF ISO 3 1/3/74 VALVES TO TURBINE 413013 (H-13) MAIN STEAM DOWNSTREAM OF ISO 2 2/6/75 VALVES TO TURBINE 413014 (H-24) MAIN STEAM DOWNSTREAM OF ISO 5 5/8/75 VALVES TO TURBINE 413018 (H-6,R-4,R-5) MAIN STEAM 7 5/27/75 413019 (H-15,R-10) MAIN STEAM g. 4 6/4/75 u tb -o .,,r3,>, .,
413020 (H-14) MAIN STEAM 2 5/7/75
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SHEET 2 of 6 REV, O PROJECT: MILLSTONE UNIT 2 JOB 11867-014
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SYSTEM: MAIN STEM 1 PIPE St'PPORT DFA'INGe 1
IDENTIFICATION NO. TITLE REVIS105 DATE
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413021 (H-22,R-18) MAIN STEAM 5 6/4/75 413022 (H-23,R-19 ) MAIN STEAM 2 5/8/75 413023 (R-20) MAIN STEAM 3 5/20/75 413024 (R-21,H-25 ) MAIN STEAM 4 6/4/75 413025 (R-22 ) MAIN STEAM 3 5/7/75 413028 (H-5,R-3) MAIN STEAM SUPPLY DOWNSTREAM OF 2 5/7/75 ISOLATION VALVES TO TURBINE 413029 (R-8) MAIN STEAM 4 5/7/75 413030 (R-23) ESUi STEM 1 2 5/7/75 413031 (H-9,R-7) MAIN STEAM 6 413032 (R-24,R-25) MAIN STEMI DOWNSTREAM OF ISO 7 5/23/75 VALVES TO TURBINE 413033 (H-26) MAIN STEAM DOWNSTREAM OF ISO 2 5/7/75 VALVES TO TURBINE 413037 (H-19) MAIN STEAM DUMP 10 COND. 8 A/B 5 5/14/75 CONTROL VALV 413038 (H-20) MAIN STEAM 1 5/7/75 413039 (H-21,R-16, MAIN STEAM DUMP TO COND. 8A & 8B 8 9/2/75 R-17) 413^41 (R-13) MAIN STEAM 3 5/7/75 413046 (H-12,R-11) MAIN STEAM 4 6/4/75 413071 (R-12) MAIN STEAM GEN TO TUR1 NE 5 o/3/75
- 413071 (H-15) o> so 413071 (H-16) * '^ # "20 d '
- NOTE: These drawings will be submitted at a later date.
SLEET 3 of 6 REV. O MILLSTONE UNIT 2 JOB 11867-014 PROJECT:
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MAIN STEAM SYSTEM: . . _ . _
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PIPE SUPPORT DRAWINGS IDEh7IFICATION NO. TITLE REVISION DAIE
- 413071 (R-28) 31386 MAIN STEAM 2 3/7/75 505325 MAIN STEAM FROM DUMP VALVE TO ATMOS PHERE O 1/21/75 505324 MAIN STEAM FROM DUMP VALVE TO ATMOS PHERE O 1/15/75 405398 MAIN STEAM FROM DUMP VALVE TO 1 1/13/75 ATMOSPIERE 405942 MAIN STEAM FROM DUMP VALVE TO ATMOS PIERE 3 5/7/75 405389 MAIN STEAM FROM DUMP VALVE TO ATMOSPIERE 1 5/7/75 495388 MAIN STEAM FROM DUMP VALVE TO ATMOS PIERE 3 2/16/75 412002 (R-3) M.S. FROM STM. GEN. TO ISOL VALVE 1 5/12/75 412003 01-3 & R-2) M.S. SUPPLY TO ISOL. VALVE TO TURB. 4 4/25/75 412004 (H-27 & R-26) M. S . S TM . GEN . TO ISOL. VALVE 4 6/11/76 412007 (H-1) M. S . S TM. GEN. TO ISOL. VALVE 3 1/10/75 41-2008 (R-1) M.S. TO AUX. F.W. PUMP TURBINE 0 11/20/73 412009 (H-2) M.S. SUPPLY TO ISOL. V. TO TURB. 5 8/10/75 412010 (H-28 & H-29) M.S. SUPPLY TO ILOL V. TO TURB. 3 5/14/75 412016 (R-1) M.S . SUPPLY TO ISOL. V. TO TURB. 2 5/7/75 LQj. '17.
SHEET 4 of 6 REV. O PROJECT: MILLSTONE UNIT 2 JOB 11867-014
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SYSTEM: MAIN STEAM
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PIPE SUPPORT DRAWINGS IDENTIFICATION NO. TITLE REVISION DATE 4130b' (H-1) M . S . TO S . G . AUX. F . W . PUMP TURB. 2 5/8/75 413062 (R-2 & R-3) M.S. TO S.C. AUX. F.W. PUMP TURB. 3 5/8/75 413063 (R-2, R-4, R-9 M.S. TO S.G. AUX. F.W. PUMP TURB. 0 12/13/73 413065 (R-t) M. S . TO S . G . AUX. F .W. PUMP TURB. 1 1/2/75 413065 (H-3) M.S. TO S . C . AL. . F .W. PUMP TURB. 1 1/3/75 413072 (H-4) M.S. TO S.G. AUX. P.W. PUMP TURB. 1 1/13/75 413073 (H-8 & R-9) M. S . TO S . G . AUX . F .W. PUMP TURB. 2 11/20/74 413074 (H-7) M.S. TO S.G. AUX. F.W. PUMP TURB. 0 1/13/74 413075 (H-6) M.S. TO S.G. AUX, F.W. PUMP TURB. 1 11/26/74 413076 (H-1 & R-1) M.S. TO S.G. AUX, F.W. PUMP TURB. 2 4/28/75 413077 (H-2 & R-2) M.S. TO S.G. AUX. F.W. PUMP TURB. 2 4/23/76 413078 (H-3 & R-12) M.S. TO S.G. AUX. F.W. PUMP TURB. 1 4/23/75 413079 (H-4 & R-3) M.S. TO S.G. AUX. F.W. PUMP TURB. 2 11/19/74 413080 (H-5) M.S. TO S.G. AUX. F.W. PUMP TURB. 1 9/26/74 413081 (R-4) M. S . TO S .G . AUX. F .W. PUMP TURB. 2 5/20/75 413082 (R-5) M. S . TO S . G . AUX . F .W. PUMP TURB. 0 2/5/74 413083 (H-6) M.S. TO S.G. AUX. F.W. PUMP TURB. 2 11/19/74 41.3084 (H-7) M.S. TO S.G. AUX. F.W. PUMP TURB. 1 5/26/74 413085 (H-8 & R-7) M. S . TO S . G . AUX . F . W. PUMP TURB. 1 1/15/75 413103 (M-2 & R-4) M. S . TO S . G . AUX . F . W. PUMP TURB. 0 7/12/74 413104 (R-5) M.S. TO S.G. AUX. F.W. PUMP TURB. 0 7/12/74 413105 (R-3) M.S. TO S.G. AUX. F.W. PUMP TURB. 0 7/16/74 TJ,]] Gj M
SHEET 5 of 6 REV. O PROJECT: MILI. STONE UNIT 2 JOB 11867-014
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SYSTEM: MAIN STEAM
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PIPE SUPPORT DRAWINGS IDENTIFICATION NO. TITLE REVISIOS DATE 413132 (H-5, R-7, R-81 M.S. TO S.G. AUX. F.W. PUMP TURB. 4 5/2/75 413135 (R-0) M.S. TO S.G. AUX. F.W. PUMP TURB. I 11/19/74 413137 (H-10) M.S. TO S.G. AUX. F.W. PUMP TURB. 1 1/30/75 413138 (H-9 & R-9) M.S. TO S.G. AUX, F.W. PUMP TURB. 2 3/7/75 413139 (R-10 & R-11) M.S. TO S . G . AUX . F .'4 PUMP TURB. 0 7/29/74 471210 (R-8) M.S. TO S.G. AUX F.W. PUMP TURB. I 3/25/75 31201 (H-1) MAIN S TEAM FROM S . G. #1 TO ISOLATION VALVE 4 8/22/76 31211 (H-2) MAIN STEAM FROM S.G. #1 TO ISOLATION VALVE 1 3/30/73 31212 (H-1) MAIN STEAM FROM S.G. #1 TO ISOLATION VALVE 11/13/74 31216 (R-2) MAIN STEAM FROM S.G. #1 TO ISOLATION VALVE 4 3/23/75 312017 (R-1) MAIN STEAM FROM S.G. #1 TO ISOLATION VALVE 2 12/26/74 312019 (R-3) MAIN STEAM FROM S.G. #1 TO IS01ATION VALVE 4 513026 (H-3, R-6) MAIN STEAM TO AUX. F.W. PUMP H-21 0 74 513027 (H-4, R-7) MAIN STEAM TO AUX. F.W. PUMP H-21 0 /17/74 513028 (R-8) MAIN STEAM TO AUX. F.W. PUMP H-21 0 10/15/74 31209 (H-2) MAI?1 S TEAM TO I. VALVE S .G. #2 0 3/30/73 31215 (R-2) MAIN S TEAM TO I . VALVE S . G . #2 5 4/16/73 312018 (R-1) MAIN STEAM TO I. VALVE S .G. #2 2 12/24/74 T.i31l W i
SHEET 6 of 6 REV. O PROJECT:
MILLSTONE UNIT 2 - JOB 11867-014
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SYSTEM: MAIN STEAM
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PIPE SUPPORT DRAWINGS IDENTIFICATION NO. TIT LI REVISION DATE 513032 (R-30) MAIN STEAM PUMP TO CONDENSERS 1 5/8/75 8A & 8B CONTROL VALVE 490001 (R-35) MAIN STEAM PIPING IO TURBINE 3 5/8/75 490002 (R-36) MAIN STEAM PIPING TO TURBINE 3 5/8/75 490003 (R-33) MAIN STEAM PIPING TO TURBINE 9 6/11/75 FSK-M-02-029H PIPE SUPPORT DETAILS
- FSK-M-02-096H PIPE SUPPORT DETAILS
- FSK-M-02-027H PIPE SUPPORT DETAILS
- FSK-M-02-025H PIPE SUPPORT DETAILS
- FSK-M-02-097H PIPE SUPPORT DETAILS
- FSK-M-02-026H PIPE SUPPORT DETAILS
- FSK-M-02-028H PIPE SUPPORT DETAILS
- FSK-M-02-021H PIPE SUPPORT DETAILS
- FSK-M-02-007H PIPE SUPPORT DETAILS
- FSK-M-02-031H PIPE SUPPORT DETAILS
- FSK-M-02-030H PIPE SUPPORT DETAILS
- FSK-M-02-022H PIPE SUPPORT DETAILS
- FSK-M-02-024H PIPE SUPPORT DETAILS
- NOTE: Refer to specific detail for revision number.
SHEET 1 of 4
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REV. O PROJECT: MILLSTONE UNIT 2
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SYSTEM: MAIN STEA*!
VA LVE DP1.k'INg
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VENDOR IDENTIFICATIO:; NO. TITLE VENDOE DIEAWd(, /EV. / p A TE VELAN 2-MS-191B 1/2" GLOBE P1 - 063 3 -N- 11 E VELAN 2-MS-16B 1/2"CLOBE P1-0633-N-11 E VELAN 2-MS-12B 2" GLOBE P1-0633-N-11 E VELAN 2-MS-11B 1" GLOBE P1-0633-N-11 E VELAN 2-MS - 191A 1/2" GLOBE P1-0633-N-11 E VELAN 2-MS-16A 1/2: GLOBE P1-0633-N-11 E VELAN 2-MS-220A 2" GLOBE P1-0633-N-11 E VELAN 2-MS-220B 2" GL0 tie P1-0633-N-11 E VELAN 2-MS-12A 2" GLOBE P1-0633-N-11 E VELAN 2 -MS - 11A 1" GLOBE P1-0633-N-11 E VELAN 2-MS-3A 12" GATE P2-0634-N-11 D VELAN 2-MS-3B 12" GATE P2-0634-N-11 D VELAN 2-MS-201 4" GATE MOV P2-0634-N-18 C VELAN 2-MS-202 4" GATE MOV P2-0634-N-18 C VELAN 2-MS-65A 3" GLOBE MOV P2-0634-N-26 A VEIAN 2-MS-65B 3" GLOBE MOV P2-0634-N-26 A CRANE 2-MS-4A 4" CIECK PB-150563 NA CRANE 2-MS-4B 4" CIECK PB-150363 NA COPES-VUILAN 2-MS-190A 8" GLOBE B-147060 7 COPES-VULCAN 2-MS-190B 8" GLOBE 031',').'} ~ B-147060 7
SLEET 2 of 4 REV. 0
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MILLSTONE UNIT 2 PROJECT:
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SYSTEM. MAIN STEAM VALVE DRAWINGS VENDOR IDENTIFICATION NO. TITLE wwtot. m sg gEt ,' M rc ATWOOD &
MORRILL 2 -FS - 64 A 34" CIECK (ISO.) 21241-11 7 ATWOOD &
MORRILL 2 -MS - 64 B 34" CIECK (ISO. ) 21241-11 7 AWOOD &
MORRILL 2-MS-1A 34" CIECK 21252-11 5 A WOOD &
MORRILL 2-MS-1B 34" CIECK 21252-11 5 DRESSER 2-MS-239 6" MSRV CP-1760 NA DRESSER 2-MS-240 6" MSRV C P- 1760 NA DRESSER 2-US-241 6" MSRV CP-1760 NA DRESSER 2-MS-242 6" MSRV CP-1760 NA DRESSER 2 -FG - 243 6" FS RV CP-1760 NA DRESSER 2-MS-244 6" MSRV CP-1760 NA DRESSER 2-MS-245 6" MSRV CP-1760 NA DRESSER 2-MS-246 6" MSRV CP-1760 NA DRESSER 2-MS-247 6" MSRV CP-1760 L\
DRESSER 2-MS-248 6" MSRV CP-1760 NA DRESSER 2-MS-249 6" MSRV CP-1760 NA DRESSER 2-MS-250 6" MSRV C P- 1760 NA DRESSER 2-MS-251 6" MSRV CP-1760 NA DRESSER 2-MS-252 6" MSRV on. g s a CP-1760 NA v d _ .
SHEET 3 of 4
- REV. O PR OJEf'T : MILLSIONE UNIT 2 ,
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SYSTEM: MAIN STEAM VALVE DRAWINGS VENDOR 1DENTIFICATION NO. T ITLE VENCct. ACAwd4 REV. / PA TE
2-MS-147B 1" GIDBE 2-MS-148B 1-1/2" GIDBE 2-MS-149A 3" GLOBE 2-MS-145A 3" GIDBE 2-MS-148A 1-1/2" GLOBE 2-MS-147A 1" GIDBE 2-MS-117A 1" GLOBE 2-MS-117B 3" GIDBE 2-MS-13B 10" GATE 2-MS-13A 10" GATE 2-MS-145 B 3" GIDBE 2-MS-147D 1" GLOBE 2-MS-149B 3" GLOBE 2-MS-219 1" CONTROL VALVE 2-MS-218 1" CONTROL VALVE 2-MS -146 B 2-1/2" CONTROL VALVE 2-MS -146C 2-1/2" CONTROL VALVE 2-MS -146 A 2-1/2" CONTROL VALVE 2-MS -381B 1" CONTROL VALVE 2-MS-60A 24" CONTROL VALVE .
,g.q
.. ..
e w w ed a later dat
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SHEET 4 of 4 REV. O PROJECT: MILLSTONE UNIT 2
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SYSTEM: MAIN STEAM VA L'.'E DPX.?INCS VENDOR IDENTIFICATI05 NO. TITLE bbot. POvid;, grt / parc
- 2-MS-600 24" CONTROL VALVE
- 2-MS-60D 24" CONTROL VALVE * *
- 2-MS-61A 24" CONTROL VALVE * *
- 2-MS-61B 24" CONTROL VALVE * *
- 2-MS-61C 24" CONTROL VALVE * *
- 2-MS-61D 24" CONTROL GLVE *
- These drawings will be supplied at a later date.
e SHEET 1 of 2 REV. O PROJECT 7 MILLSTONE UNIT 2
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SY STE MAIN STEAM FIDOR AND WALL PENETRATION DRAWINGS IDENFIFICATIOS NO. T I TLE REVISION DATE 25203-11163 PENETRATION SCHEDULE O 7/76 25203-20040 CONTAINMENT PENETRATION PIPII'G DETAILS 0 1/20/76 25203-22000 CLOSURE DETAILS FOR PIPING PENETRATIONS THRU WALLS & FLOORS 0 2/5/76 25203-22043 CLOSURE REQUIREMENTS FOR PIPING PENETRATIONS AREAS 6, 7 & 10 ELEV. 45'-6" 0 2/5/76 25203-22044 CLOSURE REQUIREMENTS FOR PIPING PENETRATIONS AREAS 6 & 10 ELEV. 25'-6" 0 2/5/76 25203-22045 CLOSURE REQUIREMENTS FOR PIPING PENETRATIONS AREAS 6 & 10 E LEV . S'-0" 0 2/5/76 25203-22046 CLOSURE REQUIREMENTS F0F iPING PENETRATIONS AREA NO. 6 ELEV. 14'-6" 0 2/5/76
.25203-22049 CLOSURE REQUIREMENTS FOR PIPING PENETRATIONS AREAS 6, 7 & 10 ELEV. 25'-6" 0 2/5/76 25203-22050 CLOSURE REQUIREMENTS FOR PIPING PENETRATIONS AREA 6 ELEV. 25'-6" 0 2/5/76 25203-22051 CLOSURE REQUIREMENTS FOR PIPING PENETRATIONS AREAS 7 ELEV. S'-0" 0 2/5/76
- 25203-22052 CLOSURE REQUIREMENTS FOR PIPING PENETRATIONS AREA 6 ELEV. S'-0" 0 2/5/76 25203-22053 CLOSURE REQUIREMENTS FOR PIPING PENETRATIONS AREAS 6, 7 & 10 ELEV. 45'-6" 0 2/5/76 n y .1 - ..,
SHEET 2 of 2 REV. O PROJECT: MILLSTONE UNIT 2
PIPING IS0 METRICS AND/OR DRAWINGS IDENTIFICATION NO. TITLE REVISION DATE 25203-22054 CLOSURE REQUIREMENTS FOR PIPING PENETRATIONS AREAS 7 & 10 ELEV. 25'-6" 0 2/5/76 25203-22055 CLOSURE REQUIREMENTS FOR PIPING PENETRATIONS AREAS 7 & 10 ELEV. S'-0" 0 2/5/76 25203-22056 CLOSURE REQUIREMEhTS FOR PIPING PENETRATIONS AREAS 7 & 10 ELEV. 14'-6" 0 2/5/76 25203-22060 CLOSURE REQUIREMENTS FOR PIPING PENETRATION 3 AREAS 6 ELEV. S'-0" 0 2/5/76 25203-22063 CLOSURE REQUIREMENTS FOR PIPING PEN 2TRATIONS AREAS 8 ELEV. 14'-6" 0 2/5/76 25203-22066 CLOSURE REQUIREMENTS FOR PIPING PENu' RATIONS AREAS 6 ELEV, S'-0" 0 2/5/76 25203-22067 CLOSURE REQUIREMENTS FOR PIPING PENETRATIONS AREAS 6, 7 & 10 ELEV. 5'-0" 0 2/5/76 25203-22070 CLOSURE REQUIREMEhTS FOR PIPING PENETRATIONS AREAS 9 ELEV. 14'-6" 0 2/5/76 25203-22073 CLOSURE REQUIREMENTS FOR PIPING PENETRATIONS AREAS 5 & 7 ELEV. 14'-6" 0 2/5/76 25203-22098 CLOSURE REQUIREMENTS FOR PAIN STEAM PIPING PENETRATIONS 0 2/5/76 25203-22101 CLOSURE REQUIREMENTS FOR STEAM CEN. FEEDWATER PIPINC PENETRATIONS 0 2/5/76 S 31','h'i.'2
SHEET 1 of 3 REV. O PROJECT: MILLSTONE UNIT 2 - JOB 11867-014
- SYSTEM: MAIN STEAM PIPING IS0 METRICS AND/OR DRAWINGS IDENTIFICATION NO. TITLE REVISION DATE SK-M-939 M.S. FROM DUMP VALVE TO ATM. A 5/7/74 SK-M-317 M. S . S T. TEN. TO TURBINE (IS O. ) 21 5/12/75 SK-M-462 M.S. TO S.G. AUX. F.W. PUMP TURB(ISO) 4 4/3/75 SK-M-463 M.S..TO S.G. AUX. F.W. PUMP TURB(ISO) 3 1/5/74 SK-M-940 M.S . FROM DUMP VALVE TO ATM. 2 5/7/74 SK-M-464 M.S. FROM DUMP VALVE TO ATM. 4 5/12/75 SK-M-685 M.S. FRO'M DUMP VALVE TO AIM. 3 10/1/74 25203-20016 AREA 2 PIPING PLAN @ EL O'-0" 0 1/10/76 25203-20096 MAIN STEAM DUMP TO ATMOS. PIPING 0 1/20/76 25203-20615 AREA 2 PIPING SECTION V-V 1 12/11/78 25203-20035 AREA 5 PIPING PLAN @ EL. (-) 22'-6" 0 1/20/76 25203-20036 AREA 5 PIPING PIAN @ EL. (-) 3'-6" 0 1/20/76 25203-20037 AREA 5 PIPING PLAN @ EL. 14'-6" 0 1/20/76 25203-20038 AREA 5 PIPING PIAN @ EL. 38'-6" 0 1/20/76 25203-20039 AREA 5 PIPING SECTION "A-A" & "B-B" 0 1/20/76 25203-20103 M.S. PIPING SECT. AUX. BLDG, 0 1/20/76 25203-20098 M.S. PIPING PIAN CONTN. & AUX. BLDG. 0 1/20/76 25203-20099 M.S. PIPING PLAN TURBINE BLDG. 0 1/20/76 FSK-M-02-022 STEAM GEN. B. DOWN 8 8/21/74 FsK-M-02-031 B. DOWN SAMPLING LINE 7 8/21/74 FSK-M-02-030 B. DOWN SAMPLING LINE [A']],(}ljl} 6 5/22/75
SIIEET 2 of 3 REV. O PROJE C'T : MI..LSTONE UNIT 2 - JOB 11867-014
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SYSTEM: MAIN STEAM PIPING IS0NTRICS AND/OR DRAWI';GS IDENTIFICATION NO. T IT LE REVISION DA E FSK-M-02-097 S . GENERATOR B, Doh'N TO ISOLATION VA 3 1/24/75 FSK-M-02-029 B. DOb7; SAMPLING LI'iE 11 7/1/75 FSK-M-02-021 B. DOW SAMPLING LINE 5 6/28/74 FSK-M-02-023 S TEAM CENERATOR B. D0'a7; TO I . V . 10 2/24/75 FSK-M-02-024 STFAM GENERATOR B. DOWrI TO I . V . 3 7/10/73 FSK-M-02 025 S TEAM CENERATOR B. DOWN TO I . V. 5 5/21/74 FSK-M-02-026 STEAM GENERATOR B. D0'JN TO I.V. 6 8/21/74 FSK-M-02-027 STEAM GENERATOR B. Dob; TO I . V. 9/4/75 FSK-M-02-028 BLOW-DOWN JAMPLING LINE 4 9/23/74
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FSK-M-02-096 STEAM GENERATOR B. D0'JN TO I . V. 3 1/23/75 FSK-M-02-07 STE *'t GENERATOR B . DOb7; TO I.V. 3 5/21/74 FSK-M-02-08 STEAM ( :'ERATOP B. DOWN TO I.V. 3 5/21/74 FSK-M-02-010 STM. GEN BLOWDOWN TO QUENCH TK 5 4/11/75 FSK-M-02-015 STM. GEN. BLOWDOWN TO QUENCH TK. 5 4/11/75 FSK-M-02-016 SDL GEN. BLOWDOWN TO QUENCll TK. 9 7/8/75 SK-M-1016 Snt CEN. BLobTOWN DOWNSTREAM OF ISO. VALVES 4 7/8/75 SK-M-1015 S TM . GEN. BLOWDOWN DOWNSTREAM OF ISO VALVES 6 8/22/75 FSK-M-02-007H STM. GEN. BLOWDOWN TO ISOLA. VALVES 4 8/7/75 FSK-M-02-008H STM. GEN BLOWDOW'i TO ISOLA. VALVES 2 5/19/75 n n .* y-a t) .r {..r r3'n.t
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SHEET 3 of 3 REV. O PROJECT: MILLSTONE UNIT 2 - JOB 118 57-014
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SYSTEM: MAIN STEAM PIPING IS0 METRICS AND/OR DRAWINGS (USE FOR SUPPORT DETAILS PER WO-30) _
IDENTIFICATION NO. TIT LE REVISION DATE FSK-M-02-021H STM GEN. BLOWDOWN TO ISOIA. VALVES 2 5/6/75 FSK-M-02-022H STM. GEN. BLOWDOWN TO ISOIA. VALVES 5 5/6/75 FSK-M-02-024H STM. GEN BLOWDOWN TO ISOLA. VALVES 5 5/28/75 FSK-M-02-025H STM. GEN. BLOWDOWN TO ISOLA. VALVES 4 5/28/75 FSK-M-02-026H JTM. GEN. BLOWDOWN TO ISOLA. VALVES 3 5/25/75 FSK-M-02-027H STM. GEN. BLOWDOWN TO ISOIA. VALVES 4 6/9/75 FSK-M-02-028h BLOWDOWN SAMPLING LINE 5 o/8/75 FSK-M-02-029H BLOWDOWN SAMPLING LINE 3 8/7/75 FSK-M-02-030H BLOWDOWN SAMPLING LINE 2 2/12/75 FSK-M-02'031H BLOWDOWN SAMPLING LINE 6 6/3/75 FSK-M-02-096H STM. GEN. BLOWDOWN TO ISOLA. VALVES 1 5/10/75 FSK-M-02-047H STM. GEN. BLOWDOWN TO ISOLA. VALVES 1 6/9/75
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.831%.%