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Category:CORRESPONDENCE-LETTERS
MONTHYEARDD-99-12, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 9910281999-10-28028 October 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 991028 ML20217N8261999-10-25025 October 1999 Discusses Errata Re 991021 Filing of Northeast Nuclear Energy Co Answer to Request for Hearing & Petition to Intervene B17901, Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)1999-10-18018 October 1999 Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6) B17886, Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 21999-10-18018 October 1999 Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 2 05000336/LER-1999-012, Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl B17900, Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 11999-10-14014 October 1999 Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 1 ML20217G9491999-10-14014 October 1999 Forwards Exemption from Requirements of 1-CFR50,App E, Section IV.F.2.c,re Conduct of full-participation Exercise in Sept 1999,at Plant,Units 1,2 & 3 ML20217D9671999-10-12012 October 1999 Forwards Copy of Transcript of Public Meeting Held by NRC Staff & NNECO on 990825 at Waterford,Connecticut on Decommissioning Program for Millstone,Unit 1.Without Encl ML20217D3011999-10-0707 October 1999 Forwards Request for Addl Info Re Util 990118 Request for Amend to License NPF-49 to Allow full-core Offloads to Spent Fuel Pool During Core Offloads to Spent Fuel Pool During Core Offload Events ML20217F0031999-10-0606 October 1999 Forwards Original Petition to Intervene Being Filed on Behalf of Clients,Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone,Iaw Provisions of 10CFR2.714 ML20217P1201999-10-0606 October 1999 Informs NRC of Proposed Acquisition of Parent Holding Company of Central Maine & Requests NRC Concurrence,Based on Threshold Review,That Proposed Acquisition Does Not,In Fact, Constitute Transfer Subject to 10CFR50.80 B17892, Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC1999-10-0505 October 1999 Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC ML20217B4711999-10-0404 October 1999 Informs That Staff Did Not Identify Any Safety Concerns Re Licensee Proposals to Modify Commitments Made for Action Items 4.2.1,4.2.2,4.5.1 & 4.5.2 of GL 83-28 by Providing Addl Justifications or Safety Bases for Changes ML20212K1241999-10-0101 October 1999 Responds to Recent Ltrs to Chairman Jackson,Commissioners & Wd Travers,Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performace of Millstone to Ensure That Public Health & Safety,Adequately Protected ML20212J3051999-10-0101 October 1999 Discusses GL 97-06 Re Degradation of SG Internals,Dtd 971230.GL Requested Each PWR Licensee to Submit Info That Will Enable NRC Staff to Verify Whether PWR SG Internals Comply & Conform to Current Licensing Basis for Facilities ML20212L2081999-10-0101 October 1999 Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance ML20212J9991999-10-0101 October 1999 Responds to Recent Ltr to President Clinton,H Clinton, Chairman Jackson &/Or Wd Travers Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performance of Plant to Ensure That Public Health & Safety Adequately Protected ML20212L1971999-10-0101 October 1999 Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety ML20212J2451999-10-0101 October 1999 Informs That Util 980807 & 990629 Responses to GL 98-01, Y2K Readiness of Computer Sys at NPPs Acceptable.Nrc Considers Subj GL to Be Closed for Units 2 &3 ML20212L1831999-10-0101 October 1999 Responds to Recent Ltr to Wd Travers Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Performance of Millstone to Ensure Adequate Protection to Public Health ML20212L2171999-10-0101 October 1999 Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island ML20217A9271999-09-30030 September 1999 Discusses Investigation Conducted at Millstone Nuclear Power Station by NRC OI Region I on 980319 to Determine If Contract Training Instructor Was Terminated for Raising Concerns About Quality of Training Matls ML20217B3221999-09-30030 September 1999 Refers to Investigation Rept 1-1997-035 Conducted at Millstone Nuclear Power Station by NRC Ofc of Investigation Field Ofc,Region I on 970915 to Determine Whether Former Health Physics Technician Discriminated Against ML20212J6621999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Units 2 & 3 on 990916.Identified Several Recent Instances in Which Condition Repts Were Not Initiated,Resulting in Untimely or Inadequate C/As.Historical Listing of Plant Issues Encl B17887, Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer1999-09-28028 September 1999 Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer ML20216J1341999-09-28028 September 1999 Ltr Contract:Task Order 49, Millstone Units 2 & 3 Employee Concerns Program Insp, Under Contract NRC-03-98-021 B17883, Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-62301999-09-27027 September 1999 Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-6230 B17890, Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-09-27027 September 1999 Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal B17888, Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 9909151999-09-24024 September 1999 Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 990915 B17884, Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-031999-09-24024 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-03 ML20212F4961999-09-20020 September 1999 Forwards Insp Repts 50-245/99-08,50-336/99-08 & 50-423/99-08 on 990615-0809.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs,Consistent with App C of Enforcement Policy 05000336/LER-1999-001, Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl B17867, Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports1999-09-17017 September 1999 Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports B17865, Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal1999-09-16016 September 1999 Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal B17876, Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant1999-09-16016 September 1999 Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant B17882, Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6) B17881, Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6) B17859, Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 9801281999-09-15015 September 1999 Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 980128 B17880, Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6) B17872, Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 11999-09-14014 September 1999 Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 1 ML20212A9011999-09-10010 September 1999 Forwards Environ Assessment & Finding of No Significant Impact Re Application for Exemption,Dtd 990803.Proposed Exemption Would Provide Relief from Requirement of 10CFR50 ML20212A3171999-09-10010 September 1999 Discusses Investigation Rept 1-1998-045 Conducted on 981112 to Determine If Former Senior Health Physics Technician Being Denied Employment at Millstone in Retaliation for Having Raised Safety Concerns in Past.Synopsis Encl B17838, Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls1999-09-10010 September 1999 Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls ML20212A7501999-09-10010 September 1999 Forwards Staff Requirements Memo Response,Dtd 990525,which Provides Actions NRC Plans for Continued Oversight of safety-conscious Work Environ & Employee Concerns Program ML20211J9291999-09-0303 September 1999 Forwards mark-ups & Retypes of Proposed Conforming License Changes Required in Connection with Transfers Being Sought in 990615 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests ML20211K5171999-09-0202 September 1999 Expresses Appreciation for Support Provided for NRC Public Meeting on 990825 05000336/LER-1999-010, Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 11999-09-0202 September 1999 Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 1 ML20216H0591999-09-0202 September 1999 Responds to Re Issues Submitted by Cullen on Behalf of Several Petitioners Concerning Offsite Emergency Prepardeness for Millstone Nuclear Power Station ML20211N9241999-09-0101 September 1999 Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures ML20211H0741999-08-30030 August 1999 Discusses GL 92-01,Rev 1, Rv Structural Integrity, Issued by NRC on 950519 & NNECO Responses for Millstone Unit 2 & 980715.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 Based on Response Review 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217N8261999-10-25025 October 1999 Discusses Errata Re 991021 Filing of Northeast Nuclear Energy Co Answer to Request for Hearing & Petition to Intervene B17886, Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 21999-10-18018 October 1999 Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 2 B17901, Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)1999-10-18018 October 1999 Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6) 05000336/LER-1999-012, Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl B17900, Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 11999-10-14014 October 1999 Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 1 ML20217P1201999-10-0606 October 1999 Informs NRC of Proposed Acquisition of Parent Holding Company of Central Maine & Requests NRC Concurrence,Based on Threshold Review,That Proposed Acquisition Does Not,In Fact, Constitute Transfer Subject to 10CFR50.80 ML20217F0031999-10-0606 October 1999 Forwards Original Petition to Intervene Being Filed on Behalf of Clients,Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone,Iaw Provisions of 10CFR2.714 B17892, Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC1999-10-0505 October 1999 Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC B17887, Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer1999-09-28028 September 1999 Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer B17883, Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-62301999-09-27027 September 1999 Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-6230 B17890, Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-09-27027 September 1999 Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal B17884, Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-031999-09-24024 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-03 B17888, Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 9909151999-09-24024 September 1999 Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 990915 05000336/LER-1999-001, Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl B17867, Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports1999-09-17017 September 1999 Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports B17876, Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant1999-09-16016 September 1999 Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant B17865, Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal1999-09-16016 September 1999 Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal B17881, Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6) B17880, Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6) B17859, Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 9801281999-09-15015 September 1999 Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 980128 B17882, Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6) B17872, Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 11999-09-14014 September 1999 Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 1 B17838, Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls1999-09-10010 September 1999 Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls ML20211J9291999-09-0303 September 1999 Forwards mark-ups & Retypes of Proposed Conforming License Changes Required in Connection with Transfers Being Sought in 990615 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests 05000336/LER-1999-010, Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 11999-09-0202 September 1999 Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 1 ML20216H0591999-09-0202 September 1999 Responds to Re Issues Submitted by Cullen on Behalf of Several Petitioners Concerning Offsite Emergency Prepardeness for Millstone Nuclear Power Station ML20211N9241999-09-0101 September 1999 Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures B17851, Forwards Semiannual fitness-for-duty Program Performance Data for 990101-990630 for Millstone Nuclear Power Station, Units 1,2 & 3,IAW 10CFR26.71(d)1999-08-27027 August 1999 Forwards Semiannual fitness-for-duty Program Performance Data for 990101-990630 for Millstone Nuclear Power Station, Units 1,2 & 3,IAW 10CFR26.71(d) B17855, Forwards NRC Forms 398 & 396 in Support of License Renewal for SRO TE Grilley,SOP-4053-04.Encl Withheld,Per 10CFR2.7901999-08-17017 August 1999 Forwards NRC Forms 398 & 396 in Support of License Renewal for SRO TE Grilley,SOP-4053-04.Encl Withheld,Per 10CFR2.790 B17849, Forwards Second Quarter Backlog Performance Rept for 1999, Which Represents Fourth Rept on Mnps Performance Since Restart of Unit 3 & First Status Update for Unit 2.No Regulatory Commitments Are Contained in Ltr1999-08-16016 August 1999 Forwards Second Quarter Backlog Performance Rept for 1999, Which Represents Fourth Rept on Mnps Performance Since Restart of Unit 3 & First Status Update for Unit 2.No Regulatory Commitments Are Contained in Ltr B17854, Forwards Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2,per TS 6.9.1.7.Revised Repts for May & June Also Encl Which Reflect Correct Faulty Printometer Readings1999-08-14014 August 1999 Forwards Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2,per TS 6.9.1.7.Revised Repts for May & June Also Encl Which Reflect Correct Faulty Printometer Readings B17850, Forwards First Lhc Quarterly Assessment Rept for Assessment Performed 990621 to 990701.NNECO Taking Appropriate Actions to Address Observations in Rept1999-08-11011 August 1999 Forwards First Lhc Quarterly Assessment Rept for Assessment Performed 990621 to 990701.NNECO Taking Appropriate Actions to Address Observations in Rept B17837, Forwards COLR for Cycle 7, for Millstone Unit 3,IAW TS 6.9.1.6.Explanation of Changes to COLR Also Encl1999-08-0707 August 1999 Forwards COLR for Cycle 7, for Millstone Unit 3,IAW TS 6.9.1.6.Explanation of Changes to COLR Also Encl B17657, Requests Schedular Exemption from Emergency Plan Exercise Requirements of 10CFR50,App E,Part Iv,Section F,Paragraph 2.c.Requests That Nrc/Fema Evaluated Exercise Be Conducted in Mar 2000 Rather than Sept 19991999-08-0303 August 1999 Requests Schedular Exemption from Emergency Plan Exercise Requirements of 10CFR50,App E,Part Iv,Section F,Paragraph 2.c.Requests That Nrc/Fema Evaluated Exercise Be Conducted in Mar 2000 Rather than Sept 1999 B17845, Forwards Revised Commitment for Surveillance Scheduling & Tracking.Options for Surveillance Scheduling & Tracking Methodologies to Be Incorporated in Standardized Station Surveillance Program Are Currently Being Reconsidered1999-08-0202 August 1999 Forwards Revised Commitment for Surveillance Scheduling & Tracking.Options for Surveillance Scheduling & Tracking Methodologies to Be Incorporated in Standardized Station Surveillance Program Are Currently Being Reconsidered B17831, Informs NRC Staff That Change 3 to Rev 25 of Mnps Emergency Plan Was Implemented on 990715.Change Removes Facility Organizational Charts from Emergency Plan & Identifies Relocation to Nuqap1999-07-26026 July 1999 Informs NRC Staff That Change 3 to Rev 25 of Mnps Emergency Plan Was Implemented on 990715.Change Removes Facility Organizational Charts from Emergency Plan & Identifies Relocation to Nuqap B17834, Forwards Proprietary Revised NRC Form 398,which Certifies That SL Doboe Has Completed Eligibility Requirements for Sro,Per 10CFR55.31.Proprietary Info Withheld1999-07-20020 July 1999 Forwards Proprietary Revised NRC Form 398,which Certifies That SL Doboe Has Completed Eligibility Requirements for Sro,Per 10CFR55.31.Proprietary Info Withheld B17836, Forwards Revised NRC Form 396 & Supporting Physician Rept for Licensed Operator Restricted from Licensed Duties, Effective 990628,due to Medical Condition.Without Encl1999-07-20020 July 1999 Forwards Revised NRC Form 396 & Supporting Physician Rept for Licensed Operator Restricted from Licensed Duties, Effective 990628,due to Medical Condition.Without Encl B17811, Submits Response to NRC AL 99-02,requesting That Licensees Provide Numerical Estimates of Licensing Actions to Be Expected to Be Submitted in Fy 2000 & 20011999-07-20020 July 1999 Submits Response to NRC AL 99-02,requesting That Licensees Provide Numerical Estimates of Licensing Actions to Be Expected to Be Submitted in Fy 2000 & 2001 ML20210S9911999-07-18018 July 1999 Requests NRC Intervene for All Shareholders of New England Electric System & to Help with Merger with National Grid Group & That NRC Petition Security & Exchange Commission to Investigate Matter Relative to No Shareholder Options B17835, Forwards Rev 33 to Millstone Station Physical Security Plan, Per 10CFR50.54(p)(2).Licensee Determined That Changes Do Not Decrease Effectiveness of Plan.Rev Withheld from Public Disclosure,Per 10CFR2.790(d)(1)1999-07-16016 July 1999 Forwards Rev 33 to Millstone Station Physical Security Plan, Per 10CFR50.54(p)(2).Licensee Determined That Changes Do Not Decrease Effectiveness of Plan.Rev Withheld from Public Disclosure,Per 10CFR2.790(d)(1) B17818, Provides NRC Staff with Change to TS Bases Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only.Change Was Reviewed & Approved by Unit 3 Plant Operations Review Committee IAW Provisions of 10CFR50.591999-07-16016 July 1999 Provides NRC Staff with Change to TS Bases Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only.Change Was Reviewed & Approved by Unit 3 Plant Operations Review Committee IAW Provisions of 10CFR50.59 B17824, Forwards Monthly Oeprating Rept for June 1999 & Revised Monthly Operating Rept for May 1999 for Millstone Unit 21999-07-13013 July 1999 Forwards Monthly Oeprating Rept for June 1999 & Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20212K1701999-07-13013 July 1999 Submits Concerns Re Millstone & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Should Provide Adequate Emergency Planning in Case of Radiological Accident B17816, Provides Certification That M Lettrich,Has Completed Eligibility Requirements,Per 10CFR55.31 for Operator License.Util Requests That Licensing Action Be Taken for Named Individual1999-07-0101 July 1999 Provides Certification That M Lettrich,Has Completed Eligibility Requirements,Per 10CFR55.31 for Operator License.Util Requests That Licensing Action Be Taken for Named Individual B17801, Forwards 10CFR50.59 Annual Rept for Period Jan-Dec 1998. Various Changes That Were Initiated in Previous Yrs & Completed in 1998,also Incorporated Into Annual Rept1999-06-30030 June 1999 Forwards 10CFR50.59 Annual Rept for Period Jan-Dec 1998. Various Changes That Were Initiated in Previous Yrs & Completed in 1998,also Incorporated Into Annual Rept B17819, Forwards Rev 17 to FSAR & Addendum 6 to Annual Rept.Nneco Recently Completed Review of Unit 2 Design & Licensing Bases Which Resulted in Changes to FSAR Provided in Encl 1.Encl 2 Includes Info Covering Changes Not Included in1999-06-30030 June 1999 Forwards Rev 17 to FSAR & Addendum 6 to Annual Rept.Nneco Recently Completed Review of Unit 2 Design & Licensing Bases Which Resulted in Changes to FSAR Provided in Encl 1.Encl 2 Includes Info Covering Changes Not Included in B17780, Forwards Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) TR, IAW 10CFR50.54(a)(3).Changes to TR Are Shown as Text in Bold Italics1999-06-30030 June 1999 Forwards Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) TR, IAW 10CFR50.54(a)(3).Changes to TR Are Shown as Text in Bold Italics B17723, Responds to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for Units 2 & 3 Encl.Without Encl1999-06-29029 June 1999 Responds to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for Units 2 & 3 Encl.Without Encl B17767, Forwards Rev 12 to FSAR & Addendum 3 to Annual Rept, for Millstone Unit 3,per 10CFR50.71(e) & 10CFR50.4(b)(6). No New Regulatory Commitments Contained in Ltr1999-06-29029 June 1999 Forwards Rev 12 to FSAR & Addendum 3 to Annual Rept, for Millstone Unit 3,per 10CFR50.71(e) & 10CFR50.4(b)(6). No New Regulatory Commitments Contained in Ltr 1999-09-03
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J,AM 05 ' 89 11:35 HRC MILLSTONF 0 0FFICE P02 i .
'l f T _. ,
December 30, 1988 ,
Mr. Peter Habinghorst Resident Inspector Nuclear Regulatory Commission i Millstone Unit 2 Waterford, CT 22, 1988, we, ,j As a follow-up to our meetings of December ,
the undersigned, would like to state for the record our concerns, and provide you with additional data detailing a chronic history of procedural non-compliance on the part of Millstone Unit 2 and its management.
As an initial response we would like to comment on Nr.
McCabe's letters to us regarding problems presented to him for resolution. It appears that Mr. McCabe was unable to -
resist the easy and preferred answers provided by the company, and in so doing cast aside or neglected other answers more worthy of consideratior.. Furthermore, the NBC's failure to follow-up on documented charges S, Labor of employee harassment (independent o' the U.
Department) suggests that power _not individual rights count.
This f ailure furthe. gives unwarpnted status to the belief
" lowly" individuals :uch 3s 56'tig should surrender to what is most powerful, and in so do that make the worship of vulgar success look principled even at-the expense of public safety.
Mr. McCabe's condescending attitude, his poor choice of words and indeed his arrogant portrayal of the nim's actions serves to enforce our.long held belief that an i enforcetaent entropy or an. evaporation of tha will to enforce required nuclear and safety procedures with regard to N.U. exists on the part of the N'.R.C. Most of his responses.can-best be described as having.gone neutral if indeed not benign. Most of his narrative is merely publia-relations clap-trap, sprinkled at times with sanctimonious comment.
In fact, based on the information supplied, his explanation and justification must have required a breathtaking leap of /
illogicality. Further, his amateurish attempt at intinidation by stating. he- would make' available to the )y
' - -~~~"aie=+4^n. ia i tactic.unworthv.of a high / t 9210230254'9203ES PDA FOIA CUILD92-162 PDR-.
- 2ed-444 do>J !
JAH '05 'S9 11:35 HRC MILLSTONE OFFICE P03 Page Two December 30, 1988 An example of such ramblings are his comments on the comolaint of procedural non-compliance regarding excessive overtime. He stated that no safety violations occurred.
Rm:3meer the comp 1= int was on excessive overtime--not safety violations. At best such ";ogic" (or lack of it) constitutes a non sequitur but in layman's language it is akin to saying that milk cows in Wasconsin are supplying tainted milk due to excessive pesticides in tne tood supply ,
but that is acceptatle because the aristocra / in Genoa, Italy are all driving their Ferrari's in a safe manner.
In addition to the items we discussed mt cur December 22 meeting we are providing you with addit'ional data suggesting procedural non-compliance. We are also providing a minimal amount of manufacturer's data suggesting that our claims are founded on facts. We are prepared to supply other data which you may require, and we will continue to supply you instances of non-compliance until we are satisfied that the NRC actions will lead to i parmanent and satisf actory solution.
Examples of non-compliance:
Tolerances on rad monitors 2404 AR 2404 A0 2401 J i
2404 BA 2401 E ACP 1. 14 Ground Cart Procedure l Rad Menitor Horns Lack of UCRs on deficiencies CTMT Rad Mon Test Switches Overt!me.Non-Compliance Acoustic Valve Monitor Calib Acoustic Valve Mon. Testing
- Acoustic Valve Hon. Amp Repl SPM 2401E/T-88-2 RCP Oil Level Problems RCP Alarm Set Points RCP RTD's RCP Diff. Temp.
RCP Undersped Input to RPS RCP Level Transmitters Incorrect Prints Rad Monitor Key Switches H2 Analyzer Problems Diesel Gen Flow Switch Rad Mon SJAE RPS lifted lead problems Functional Tests on R.M.
Lack of procedur(s-Asbestos Lack of Procedures-PCB's Lack of Documentation on l Key Checkout NRC's failure to address discrimination l
- jai 05L*89-11836 i'RCJMILLSTONEl0FFICE PO4'
.:n
. . n
-._'. i Page Three December-30,-1988 ,
Overhaul of B&D car fans without procedure Hearing replacement on Rod Drive.MG without procedure NU's internal report on Ground Cart incident stating root cause as failure to follow procedure
- overhaul of "A" Car ran planned this outage--still no
L approved procedure .
Lack of separate ground oon "C" Inst. Air Comp.-in violation of_SP-EE-076, page 3, Item 6.1.25 Lack of approved (PORC) procedure for cathodic protection surveillance Lack of asbestos and PCB procedures plant-wide Company doesEnot__ follow time constraints of.theirLown '
orievance. procedure Use of~EMT for CKTS other than lighting in violation- -
of SP-EE-076 Electricians have consistently noted problems ~with- -
spare station battery such.as cracked cell',' severe discoloration of cell interconnecting bars and material oozing:from cell posts--no' action on theipart of the; company we continue to disoose of' emergency-light battery-acid by pouring same into floor drain-ofECPF. This is11n-violation of company procedure and environmental guidelines Many of the 270lJ series surveillance forms are outdated, incorrect or both TCB 7 has not worked properly-in over 5 years.- During _;~
high risk testing requires manual closing Many in-plant electrical panels do-not agree with-existing; prints. This- is;due to many changes and : PDCR-I not being recorded at_ time of change.
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JAll105 '89 112 36 11RC MILLST011E OFFICE P05 b
I Page Four December 30, 1988 ,
In closing we would like to state that we are prepared to .
supply any documentation you require and are willing to discuss any and all matters regarding these complaints at ,
your convanience, e t
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,w i t922.2%_.:Q; 5 1SUFERINTENDENT . . __ J ;2 4 '-
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_EFFEwT1- CATE SCRC MTE..Ms..
.)RM *APFROVEDtEf STATir g
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PDCR' EVALUATION FORM 1
ds NUMBER MP2-64-040 TITLE Aux Bldo Soece Htr X-162 Misc Lichtin2.
For Maint Hot Weld /Mechine Shop _
SYSTEM 2331 ORIGINATOR
- 1. DESCRIPTION OF CHANGEt This change involves the relocation of space heater X-162.and relocation /elimina*. ion of several area lighting fi:ttures ' to f acilitate the addition of a Hot Machine / Weld Shop at El. 08*-6" of them Auxiliary Building near the Seal Rebuild and No::le Dam Repair Room.
Technical detsils addressing installation of tne Hot Machine / Weld Sho; and associated auniliaries (including power requirements. ventilation and HEPA, drainage, fire protection, instrument air, radiological concerns, etc.) will be documented in a Plant Design Change Recore (PDCR).
i PEASON FQP CHANGE:
L The drain line for scace heater X-160 15 presently _ routed thru tne area where the Hot Machine /Wela Shop is going to be buil t - (Jus t east of the Spent Fuel Fool Area). Additonally. . airflow from the' space hes.er will be partially blockad by the shoc. Thus, relocation of the scace heatar is recuired.
Four arer lighting tintures are located less than 12' ecove the *!cce in tre area. Tha shop will be greater than 12' tall in these areas anc as sach tne lighting fintures require ralocation or removal.
- 2. EVALUATION IF ANY ANSWER TO OUESTIONS 2.1 THROUGH 2.c Is 'vE5". lHEN m FULn is REQUIRED FOR THE CHANGE.
2.1 Does tne change affect the' system /ccmponent cesign function or reduce its design margin?-
Yes :o Y Scses:
This change does not af f ect any system / component design function or recuce its design margin.
Both the supolv and return lines'from the heater will be shortened by.over OS' to accomodate'tne new location of the space highe' heater. The supply line will be routec at an elevation 4" than the present highest point in the line. This-increase ~1n j/j sepolu line elevation is considered insignificant anc.will not affect any original design flow margin 2.
SF 35" y Re ! . 'M
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... - -., - ... - - . -. . . - ~. - . . .. . . - -- -
The design funwtion of the space' heater-w. 1 not.be.aficctec bv this change. The heater will continue to provide heet for this-
+ area.
s The lighting f i::tures -tha t are being removed will no longer be required since they are located'directlyOne above the shop and.the of the-lights to be shop will have independant lighting.
removed prov' des operational emergency lighting (not requiredLby.
Appendin "R'). Moving this light is not required due to the
_The-presence of other emergency lighting in the immediate area.
lighting fintures which are being relocated will provide - lighting The design function of the area along the east side of the shop.
lighting is not affected by this change.
The relocated lights are suoclied from circuits L50-30 and L91-10. Circuits LOO-CO and DO21-8 supply power to the two lights being removed. The change results in the load on panel DO21 being reo-ced by 130 watts and the load on panel L30 being recuced by 300 watts. Thus this change coes not decrease any design margins associated with the power supply circuits.
2.2 Does the change affect pipe lascing, floor loading, hanger loading. ctress calculationa, or seismic calculations which result in structural modifications being required?
'n N o _ __
eesse:
The cmange coes rot-affect pace leading. ficor loading, hanger Ic4cinc, stress calculaticns, er seismic calculations which
?sult :n structural mcoificacicns being requirec.
Scace neater anc picing succort cesigns are shown on Sketch 4 Design of lighting f i:: tu re supports will be a ccmbination of l
r engle iron / rod supports.similar to existing lighting supports.
It is notea that the supcly and return lines from X-iso are "non-OA' anc are not requirec t: function following a seismic event. Also, tnere are no ac]acent- GA Category 1 components whi:n could be affected by failure of the piping or hangers.
2.0 Dees the change require a cnange to any environmental
-lifications (e.g., operability time, aging, temperature, pressure, relative humidity, raclation, spray submergence); or t
does it result in a different normal or accident environment?
Yes Ne X Bases:
The change does not require any changes to environmental cualifications (e.g.. operability time, aging, temperature.
pressure relative humidity, radiation, spray sucmergenceit nor L
coes it result in a different normal or accident environment.
?o rc e hester piping will'not be routed to any different area than it is at present and tnus will not result in e different normal v acciaent ensironment.
SF 039 Rev. 03
. Liggting cn3ne will - nsve no s f f ec t cn a 'tronments!
l cualifications.
- 2.4 *Does the c hange adver'sely affect any system / component pressure, temperature, fluid chemistry. voltage. current, or material compatibility?
Yes No X Pasis Relocating the space heater will result in a shorter run of supply and drain lines and thus will not adversely affect the auxiliary steam pressure.
As described in Section 2.1 above, the lighting changes do not edversely affect and voltage or current requirements associated with powar supply circuits.
The change does not adversely affect any system / component temperature, fluid chemistry, or material compatibility.
2.5 Does the change adversely affect any element in the fire protectien/ Append 1r "R" program or in the Security Plan?
Yes No Y Bases:
The change cars not adversely affect any element in the fire protection /Accend1: "R" program or in the Security Plan.
Automatic 2moke detectcrs are located in the area. however the scace heater will not be located any clcser to cetectors than it c u r r e n t l', is and thus will not adverselv affect their operation.
One of the lign s to be removec is an ocerational emergency lign (not Append 1: 'R'). The remaining lights being affectec by tnis change are alsc non Appendi: 'R'.
2.6 Does the change create cr increase the potential levels of oftsite radiation or airoorne radioactivity or adversely 3ffect ALAFA goals? ,
Yes No i Bases:
The relocation of the space heater anc relocation / removal of lighting fi::tures coes not increase the potential of offsite radiation or airborne radioactivity or adversely affect ALARA goals.
2.7 Could the change be unsafe or have the potential to create an unreviewed safety question in that it would:
a.
Affect the operability of anv plant system or equipment as defined in Tecn Specs?
yes No X i J59 Rev. 03 Pace 3 of
r -
- s
'Si' l$pMINISTikTIVE IMPAL T :
Reference.
Required Completed Number S.1 PMMS Update. No S.2 -Procedure Update No S.O DSR/DCR ,
Yes 5.4 AWO Number Yes 5.5 MEPL Update No S.6 FSAR Update No S.7 I9I Program Update No ,
i S.8 Other No ,
i (See Instruction 6.2.6) ~!
Send a copy of this PDCR l S.9 Evaluation Form to the Director l of Nuclear Training. l
- 6. CLO9ECUT 1
' Unit Engineering Supervisor Date !
I l
l 1
t .
SF 359 Rev. 03 Page 5 of S
- - - . = . - - -
e
- b. Result in any- plant syntom _ oparation which would deviate
f rom th3 way that th2 Syntom-op2 rat 3D 00 doccribOd in design documents?.
Yes No X If the answer to a or b is yes, then a Safety. Evaluation IAW L
NEO 3.12 (Reference 3.2.2) is required. PORC/SORC_ review is required prior to implementation.
- c. If the answe,r to a or b is yes, is an Integrated Safety Evaluation required?
Yes No X CONCLUS IONS :
- a. If any question 2.1 through 2.6 is answered YES, then PDCR is required. Indicate "NA" for Sections 0.0, 4.0, and 5.0, then closecut this evaluation.
- b. If all questions 0.1 througn 2.5 are answered NO, then no PDCR is recuired. However, if a Safety Evaluation (question 2.7) is reautred, then submit evaluation to FORC/SORC orier to implementation.
3.0 PETEST REOUIREMENTSt.
a) Space Heater Supply / Return Line Modifications :
Inservice Leak Test of Pioe Joints Acceptance Criteria: No Visible Leakage, b) Electrical Lighting Modifications:
Acceptance Criteria: ' Verif y - lights f unction properly.
Evaluation Ccmoleteo B ngineer
.['/Z[99
' Date IL (See NEO S.OS; -!
7'//~UT I Desion Verifice tien Date !-
(See NEO'5.05) dngineer t
' d Frior to PORC/SORC Approval Yes No I mo l emen ta tion A 7 O $1
=;pproved Ev Date Unit Engineering Supervisor
- 4. PORC/SORC APPROVAlt No .'
~
l' /Y OPOP /E" Mtg. '
Date SF 359 Rev.-05 Fage 4 of S
e ATTACHMENT TO.
EECH EVAL 4ATION HP2-89-040 DESIGN INPUTS:
- 1. NUSCO Drawing No. 25203-24087, Sheet 039, Rev. 0; " Auxiliary Steam Condensate to Condensate Recovery Tank T-78".
- 2. NUSCO Drawing No. 25203-24087, Sheet 040, Rev. 0; " Low Pressure Auxiliary Steam from PCV-8417".
3.
NUSCO Drawing No. 25203-24087, Sheet 041, Rev. 0; " Auxiliary Steam Condensate to Condensate Recovery Tank T-78".
- 4. NUSCO Drawing No. 25203-35019, " Lighting Grounding and Comm. ,
Auxiliary Building at El. 36*-6"
- 5. NUSCO Drawing No. 25203-35038, Sheets 18 and 17; " Lighting Panel Schedules for L-29 and L-30"
- 8. Generation Engineering Specification SP-ME-688, " Millstone Unit 2 Piping Class Sheets.
- 7. Power Piping Code. ANSI /ASME B31.1, 1971 Ed.
- 8. NUSCO Memo, W .R. Rotherf orth to T. A. Moore dated 7/11/88.
DETAILED DESIGN:
- 1. Gener21 El. 38*-6" of A Maintenance Hot Weld /east Machine Shop will be erected atof the Spent Fuel Pool Area a the Auxiliary Building, This change Seal Rebuild and Nozzle Dam Repair Room (See Sketch 1).
involves the relocation of space heater X-162, the relocation of two removal of two lighting fixtures in the lighting fixtures and the area to allow the necessary clearances required for erection of the shop.
Technical details addressing installation of the Hot Weld / Machine Shop and associated auxiliaries (including power requirement =,
ventilation, HEPA, drainage, fire protection, instrument air, radiological concerns, etc.) will be documented in a Plant Design Change Record (PDCR).
- 2. Space Henter_
Auxiliary Building Area Space Heater X-182 requires
~
relocation Sketches 1 thruto 3 installation of the Hot Machine / Weld Shop.
identify the piping change to lines 1"-HBD-153 (steam supply)These and allow 2 " -H B O - 144 (condensate return) necessary to relocate X-182.
to accomodate the new location of lines will be shortened by over 25'The supply line will be routed at an elevation the space heater.
only 4" higher than the present highest point in the line. This increase in elevation is insignificant and will not adversely affect auxiliary steam suppl! pressure.
f Page 1 of 3
9 Space. heater and pipe support modifications are shown on Sketch 4.
- Attachment of these supports to-the structural steel in the overhead is justified in accordance with Design Input No. 8, (attached).
Power supply cabling and conduit for this space heater will be field routed from its present location.
- 3. Lichtina ',
Two overhead lights in the area require relocation and two others will be removed to allow construction of the new Shop. The lighting fixtures that are being removed are no longer required since they are located directly above the shop and the shop will have independant lighting. One of the lights to be removed provides operational emergency lighting (not Appendix 'R'). Hoving this light is not required due to the presence of other emergency lighting in the immediate area. The lighting fixtures which are being relocated will provide lighting along the east side of the shop. Sketch 5 identifies the modifications necessary for the lighting change.
The relocated lights are supplied from circuits L30-30 and L81-10.
Circuits L30-30 and D021-8 supply power to the two lights being removed. The change results in the load on panel D021 being reduced by 150 watts and the load on panel L30-30 being reduced by 300 watts.
Technical justification f or modification to the lighting fixtures _is attached (See Memo K. Wallace to R. Bates, dtd. 3/29/89).
- 4. Imolementstica Two seperate AWO's will be written to perform this change; one each for the-space heater modifications and lighting changes.
All welding of pipe and hangers shall be _ in accordance with the Northeast Utilities Welding Manual. Visual inspection of pipe welds shall be performed in accordance with NNECO Procedure GWS-004 with acceptance criteria in accorcance with ANSI B31.1, parar 2ph 136.4.2.
All support welds shall be visually inspected per GWS-004, with acceptance criteria in accordance Attachment 3.2 of GWS-004.
Any conduit supports requiring attachment to building concrete will be done in accordance with MP 2721X.
All electrical work shall be done in accordance with applicable plant procedures.
Space heater piping shall be re-insulated in accordance with approved materials.
Page 2 of 3
s
_7, Docunentatina.
Drawing Change' Requests (DCR's) 9111 be developed as required to-incorporate piping and electrical changes as required of this PDCE, Page 3 of 3
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- es? PMMS WORK ORDER S Y S T E M <. =
= == s e san senessoassemassess e ss e m e P1MS ID: M2 O2 FHV MTR DRV FOO 1 WORK. ORDER..... -M2 89 08707 i LOCAL ID: F20M i WO TYPE.....: CM- I L SYS t- 2314F. l PRIORITY.......: 3 1 DG: AB' 1 LEAD DEPT......: MNTC 1.
OM a ' NEAR D/G DAY-TK ROOM i UNT STATUS-REOD: U -i cLEV: 0038 FT 06 IN 'l SCHD STRT DATE: 08 / $4 / 89 i TROUBLE REPORT NO.: 03M2192337 1 DES COMP DATE:.08 / 11 / 89 I EQUIPMENT DESCRIPTION: ==========...............s==....
FUEL HANDLING BUILDING HSV UNIT FAN MOTOR ( 3-EELTS-S/C-TT572054)
PROBLEM DESCRIPTION: MOTOR SMOKED, BREAKER TRIPPED.
PR465218 SUSPECTED MOTOR EEARING SPENT.
CAUSE:
ORIGINATOR : DATE: 03 / 03 / 39 DEPT: OPS.
SUPV APPROVAL : DATE: 08 / 03 / $9 WO TAG HUNG: Y o************** *******#*******************************u*********************
OC REQD : N CAT I N CONVEX-CLR N PART SHEET N TAG REQD : YES EEQ : N GUARD REQD: N TANK ENTRY: N-RWP REQD : N FPOA : N LLRT REQD N TOOL LIST: N ALARA REV: N RWOA : N ISI REQD : N FIRE WATCH N PROCCDURES CAUTIONS CAUTION NOTES 2710F -
. VAL CD-245 TASK DEPT ACT ACT REWORK ' N DESCRIPTION -MEN HRS INVOLVES PDCR N REPAIR ELEC ___ ___
PDCR NO. ___ - ___
RESP ENGR ___ ___
APPL CODE: ___ ___.
P.O. NO.: ___ ___.
JOB 1) INVESTIGATE AND REPAIR AS NECESSARY DESCRIPTION AU CCC ACC SU C CMS W.O. ACT RE AC%
ACCOUNTS: -
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WORK DIRECTE EY: __
ASST DEPT NOTIFIED: JOB SbPERVIS 31J FERR -
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DEPARTMENT APPROVAL: .. DATE: __./ __,-/ __
TAG CLEARANCE NO: ________________ COPY OF TAGGING-ATTACHED: ________
t 20 ENTERED: __
~ APPL TECH SPEC NO: __________ TIME PERMITTED: _ _ _ _ _ _ _ _ . _ _ _ _
AUTHORIZED BY OPS: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ , _
TIME: ______
DATE: __,/ __ / _ _ .
.