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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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- . 1 l NMM Rope Ferry Rd. (Route 156), Waterford, CT 06385
, Nuclear Energy mistone Nocien, Power station Northeast Nuclear Energy Company P.O. Box 128 Waterford, CT 06385-0128 (860) 447-1791 Fax (860) 444 4277 The Nonheast Utilitica System NOV I 2 1998 Docket No. 50-336 B17523 Re: 10CFR50.54(f)
GL 98-04 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 l
Millstone Nuclear Power Station, Unit No. 2
, Response to Generic Letter.98-04 Potential For Degradation of The Emergency Core Cooling System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Forelan Materiaiin Containment i
This letter provides Northeast Nuclear Energy Company's-(NNECO) response to - ;
p Generic Letter (GL) 98-04* regarding potential for degradation of the emergency core l cooling system after a loss-of-coolant accident because of construction and protective coating deficiencies and foreign material in containment.
I GL 98-04 requests that NNECO, within 120 days of the date of this generic letter, l submit a written response that includes the following information:
l (1) A summary description of the plant-specific program or programs implemented to r ensure that Service Level 1 protective coatings used inside the containment are L procured, applied, and maintained in compliance with applicable regulatory L requirements and the plant-specific licensing basis for the facility. Include a { ,j ,
i- discussion of how the plant-specific program meets the applicable criteria of 10 CFR Part 50, Appendix B, as well as information regarding any applicable ,
standards, plant-specific procedures, or other guidance used for: (a) controlling
.r C(f L
i.,.j' ~" j ') the procurement testing of protectiveof coatings coatings, andand paints preparaUon, (c) surface used at theapplication, facility, (b) the qual l
surveillance, and maintenance activities for protective coatings. Maintenance activities involve reworking degraded coatings, removing degraded coatings to !
h M GL 98-04, " Potential For Degradation of The Emergency Core Cooling System After a
. Loss-of-Cociant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment," dated July 14,1998.
9811190241 981112 ?
PDR ADOCK.05000336,
.P PDR g
l .
U.S. Nuclerr Rrgulatory Commission B17523/Page 2 l-
- sound coatings, correctly preparing the surfaces, applying new coatings, and
. verifying the quality of the coatings.
(2) Information demonstrating compliance with :t 3m (i) or item (ii):
1 (i) For plants with licensing-basis requirements for tracking the amount of l unqualified coatings inside the containment and for assessing the impact of
( potential coating debris on the operation of safety-related SSCs during a l postulated DB LOCA, the following information shall be provided to i demonstrate compliance: l (a) The date and findings of the last assessment of coatings, and the planned l- date of the next assessment of coatings.
l l (b)The limit for the amount of unqualified protective coatings allowed in the containment and how this limit is determined. Discuss any conservatism in the method used to determine this limit.
l-l (c) If a commercial-grade dedication program is being used at your facility for dedicating commercial-grade coatings for Service Level 1 applications inside the containment, discuss how the program adequately qualifies such a coating for Service Level 1 service. Identify which standards or other guidance are currently being used to dedicate containment coatings at your facility; or, (ii) For plants without the above licensing-basis requirements, information shall l be provided to demonstrate compliance with the requirements of 10 CFR 50.46b(5), "Long-term cooling" and une functional capability of the safety-related CSS as set fo;th in your licensing basis, if a licensee can demonstrate this compliance without quantifying the amount of unqualified coatings, this is acceptable. The following information shall be provided:
l (a)If commercial-grade coatings are being used at your facility for Service i
Level 1 applications, and such coatings are not dedicated or controlled under your Appendix B Quality Assurance Program, provide the regulatory and safety basis for not controlling these coatings in accordance with such a program. Additionally, explain why the facility's licensing basis does not require such a program.
- NNECO has reviewed the current licensing and design basis regarding programs for
{ ensuring that Service Level 1 protective coatings inside containment do not detach from their substrate during a DB LOCA and interfere with the operation of the
- Emergency Core Cooling System (ECCS) and the safety-related containment spray i
F
_ _ _ _ .m ._ _ . _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ . . .
' I U.S.' Nuclitr Rtguintory Commission l B17523/Page 3 system (CSS). Attachment 1 provides NNECO's response for the request of l information contained in GL 98-04. l l
There are no regulatory commitments contained within this letter. Should you have any !
- questions regarding this submittal, please contact Mr. Ravi G. Joshi at (860) 440-2080.
~
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY 1
Martin L. Bowling, Jr. (/
Recovery Officer - Technical Services Swom to and subscribed before me this day o h .1998 A Public C
My Commission expires MY COMMISSION EXPIRES JUNE 30,2004 i
i Attachment cc: H. J. Miller, Region i Administrator D. G. Mcdonald, Jr., NRC Senior Project Manager, Millstone Unit No. 2 D. P. Beaulieu, Senior Resident inspector, Millstone Unit No. 2
' E. V. Imbro, Director, Millstone ICAVP inspections S. Dembek, NRC Project Manager, Millstone Unit No.1 l
i I
5~
Docket No. 50-336 !
, B17523 i
Attachment 1 l
Millstone Nuclear Power Station, Unit No. 2 Response to Generic Letter 98-04 Potential For Degradation of The Emergency Core Cooling System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and i l Foreign Materialin Containment !
. Requested Information l'
l I
November 1998
l 1
l U.S. Nucl=r Regulatory Commission l B17523/ Attachment 1/Page 1 Respon'se to Generic Letter 98-04 Requested Information
Introduction:
The NRC issued Generic Letter (GL) 98-04 to alert the addressees to the problems associated with the material condition of Service Level 1 protective coatings inside the containment and t - request information under 10 CFR 50.54(f) to evaluate the addressees' progranis for ensuring that Service Level 1 protective coatings inside containment do not detach from their substrate during a DB LOCA and interfere with the operation of the Emergency Core Cooling System (ECCS) and the safety-related containment spray system (CSS). The following is Northeast Nuclear Energy Company's (NNECO) response to the requested information.
Response to Questions:
Question (1)
A summary description of the plant-specific program or programs l implemented to ensure that Service Level 1 protective coatings used inside the containment are procured, applied, and maintained in compilance with applicable regulatory requirements and the plant-specific licensing basis for the facility. Include a discussion of how the plant-specific program meets the applicable criteria of 10 CFR Part 50, Appendix B, as well as information regarding any applicable standards, plant-specific procedures, or other guidance used for: (a) controlling the procurement of coatings and paints used at the facility,(b) the qualification testing of protective coatings, and (c) surface preparation, application, surveillance, and maintenance activities for protective coatings. Maintenance activities involve reworking deyaded coatings, removing degraded coatings to sound coatings, correctly preparing the ~" es, applying new coatings, and verifying the quality of the coatings.
RESPONSE to (1):
Northeast Nuclear Energy Company (NNECO) has implemented controls for the procurement, application, and maintenance of Service Level 1 protective coatings used inside the containment in a manner that is consistent with the licensing basis and regulatory requirements applicable to Millstone Nuclear Power Station, Unit No. 2 (MP2). The requirements of 10 CFR Part 50 Appendix B are implemented through specification of appropriate technical and quality requirements for the Service Level 1 coatings program which includes ongoing maintenance activities.
Currently, Millstone Unit No. 2 Service Level 1 maintenance coatings are subject to the requirements of Regulatory Guide 1.54. Service Level 1 applies to coatings used in the primary containment which are procured, applied and maintained by NNECO or 4 - _, , _
7
!' U.S. Nucicer R:gulatory Commission
' B17523/ Attachment 1/Page 2 their contractor. Maintenance coating materials are required to be tested to withstand Millstone Unit No. 2 design basis loss of coolant accident (DBA-LOCA) conditions.
Current requirements for coating materials and their application comply with Regulatory Guide 1.54 with the following clarifications and exceptions as stated in FSAR Section 5.9.3.7:
- 1) Compliance with Regulatory Guide 1.54 will not be invoked for equipment of a miscellaneous nature and insulated surfaces. It is impractical to impose Regulatory Guide requirements on the standard shop process used in painting valve bodies, handwheels, electrical cabinetry, control panels, loud speakers, emergency light cases, and other miscellaneous equipment. Wrapped or rigid insulation captures and retains any coating which may come off equipment surfaces, thereby preventing the coating material from reaching and blocking sump drains or interrupting water flow in the containment recirculation system.
- 2) Quality Assurance Program recommendations stated in Regulatory Guide 1.54 for the major equipmant and structures are followed except that inspection will be in accordance with action 10 of ANSI N5.12-1974 in lieu of Section 7 of ANSI N5.9 as referenced in Section 6.2.4 of ANSI N101.4.
- 3) Each coating was tested in accordance with ASTM D3911, " Evaluating Coatings Used in Light-Water Nuclear Power Plants at Simulated Design Basis f.ccident (DBA) Conditions." Prior to exposure to DBA conditions, each coating was irradiated to an accumulated dose in accordance with ASTM D4082, "Effect of Gamma Radiation on Coatings for Use in Light-Water Nuclear Power Plants."
During original construction, MP2 was not licensed to Regulatory Guide 1.54.
However, MP2 was committed to ANSI N101.2 for use in the selection and evaluation of coatings for Service Level 1 areas. Per FSAR Section 5.9.3.6, containment coating materials for original construction have been tested by their manufacturers under simulated operating and incident conditions and certified to fully comply with the requirements of ANSI N101.2 (1972).
Adequate assurance that the applicable requirements for the procurement, application, inspection, and maintenance are implemented is currently provided by procedures and programmatic controls, approved under the NNECO Quality Assurance program. A Service Level 1 specification and procedures for MP2 provide technical, quality and procedural requirements for the application of protective coatings inside containment.
NNECO is evaluating the guidance provided in EPRI TR-109937 " Guideline on Nuclear Safety-Related Coatings" and, as appropriate, improvements to our existing programs and procedures for Service Level 1 coatings will be made.
(a) Procurement of Service Leve! 1 coatings used for new applications or repair / replacement activities are procured from vendor (s) with a quality assurance program meeting the applicable requirements of 10 CFR Part 50 Appendix B. The
l
U.S. ' Nuclear Regulatory Commission j B17523/ Attachment 1/Page 3 applicable technical and quality requirements that the vendor is required to meet
- are specified by NNECO in procurement documents. Acceptance activities are i conducted in accordance with procedures that are consistent with ANSI N45.2 1 requirements. This specification of technical and quality requirements combined with appropriate acceptance activities provides assurance that the coatings
- received meet the requirements of the procurement documents. l t
j (b)The qualification testing cf Service Level 1 coatings used for new applications or i repair / replacement activities inside containment meets the applicable requirements
)
contained in the standards and regulatory commitments referenced above. These l coatings have been evaluated to meet the applicable standards and regulatory requirements previously referenced.
l (c) The surface preparation and application of Service Level 1 coatings for both new l
^
applications or repair / replacement activities inside containment meet the applicable portions of the standards and regulatory commitments referenced above. The i technical and quality requirements for application of protective coatings to exposed 3
surfaces of steel, concrete, and equipment within Primary Containment areas at Millstone Unit No. 2 are established by an approved Service Level 1 coatings specification and procedures. Documentation is consistent with the applicable requirements.
NNECO maintains coatings in accordance with its overall maintenance program for MP2. Repairs of coatings in accordance with approved procedures are performed in conjunction with miscellaneous inspection, maintenance and modification activities.
As a result of miscellaneous activities inside containment, any other localized areas of degraded coatings can be identified. Those costed areas would then be evaluated and scheduled for repair or replacement, as necessary. NNECO is evaluating the guidance provided in EPRI TR-109937, " Guidance on Nuclear Safety-Related Coatings," for l performing condition assessments of containment coatings.
)
i I
Question (2) information demonstrating compliance with item (i) or item (ii):
i (i) For plants with licensing-basis requirements for tracking the amount of l unqualified coatings inside the containment and for assessing the impact of potential coating debris on the operation of safety-related SSCs during a postulated design basis LOCA, the following information shall be provided to demonstrate compliance:
(a) The date and findings of the last assessment of coatings, and the ;
planned date of the next assessment of coatings.
ki _ _ _ . _ _ . . _ , . - _ _ __. ~
I
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U.S. Nuct:cr Regulatory Commission B17523/ Attachment 1/Page 4 l (b) The limit for the amount of unqualified protective coatings allowed in the containment and how this limit is determined. Discuss any conservatism in the method used to determine this limit.
(c) N a commercial-grade dedication program is being used at your facility for dedicating commercial-grade coatings for Service Level 1 l applications inside the containment, discuss how the program l adequately qualifies such a coating for Service Level' 1 service. Identify l which standards or other guidance are currently being used to
- dedicate containment coatings at your facility; or, l RESPONSE to 2 (1)
1 This item is not applicable for Millstone Unit No. 2. A response to item (ii) is provided below.
l First part of 2 (ii)
(ii) For plants without the above licensing-basis requirements, information shall be provided to demonstrate compliance with the requirements of 10CFR50.46b(5), "Long-term cooling" and the functional capability of the safety-related CSS as set forth in your licensing basis. If a licensee can demonstrate this compliance without quantifying the amount of l unqualified coatings, this is acceptable.
RESPONSE to first part of 2 (ii):
The following description and referenced materials provides the licensing basis for Millstone Unit No. 2 relative to conformance with 10 CFR 50.46(b)(5), "Long-term Cooling," specifically with regard to MP2's ability to provide extended decay heat removal including related assumptions for debris that could block containment emergency sump screens:
, Millstone Unit No. 2 FSAR Section 6.1, " Engineered Safety Features System" describes the licensing basis for systems that provide containment heat removal, including assumptions for the design of the containment sump. The specific sections of the FSAR which address emergency core cooling are Section 6.2, " Refueling Water i Storage Tank and Containment Sump," Section 6.3, " Safety injection System," and i
Section 6.4, " Containment Spray System." These sections provide the design bases including functional requirements, applicable design criteria and a system description.
l The Emergency Core Cooling System (ECCS) provides borated water to cool the i reactor core following a major Loss of Coolant Accident (LOCA). It consists of three 4
U.S. Nuclecr Regulatory Commission B17523/ Attachment 1/Page 5 subsystems that maintain the reactor core in a cool conditior' The three subsystems are the Safety injection (SI) system, the Containment Spray (CS), and Shut-down I
Cooling (SDC).
The SI system injects borated water into the reactor coolant system to cool the reactor core following a major loss of coolant accident. The injection system also provides continuous long-term cooling of the core by recirculation of borated water from the containment sump.
The Refueling Water Storage Tank (RWST) is the water source for cooling the core at the onset of a LOCA. When the RWST reaches its low setpoint, recirculation from the containment sump begins to maintain long term cooling.
l The CS system removes heat by spraying cool borated water through the containment atmosphere. The sprayed heated water is then collected in the containment sump and cooled by the reactor bui! ding closed cooling water system through the SDC heat exchangers and recirculated through spray nozzles into the containment atmosphere.
The SDC heat exchangers and the low pressure safety injection pumps are used during plant operations to remove core decay heat and primary coolant system sensible heat.
Following cooldown they are used to maintain a constant primary coolant system temperature while the plant is at cold shutdown.
Containment Sump The containment sumps are located at the bottom of the containment building at elevation (-)22'-6" and are provided with enclosures around the recirculation pump suction pipes. The borated water from the safely injection, containment spray system and reactor coolant system is collected and subsequently recirculated to the pump's suction. Two 24 inch containment recirculation pipes are provided from the sump to the suction of the Si and CS pumps. The sump screen enclosure is a screen assembly constructed of a stainless steel frame and galv7nized grating to which a stainless steel wire cloth is attached. The screen assembly is divided into two sections separated by mesh and grating. It is sized such that any particle that penetrates the screen is capable of passing through the engineered safety features' components. A failure of one side would not negate the operation of the remaining assembly.
Due to the low-face velocity across the sump screen, loose objects generated by a pipe break will either settle on the sump screen prior to sump operation or not be affected by sump operation. Loose objects most likely to block the sump screen would be sections of pipe insulation dislodged by a LOCA. The insulation debris generated from a LOCA in the steam generator cubicle (worse case) is assumed to be fine
, fragments. For design basis with one LPSI pump failing to trip on initiation of l recirculation switchover, insulation can be transported to and adhere on the sump 1
l l
l
U.S. Nuclur Regulatory Commission B17523/ Attachment 1/Page 6 screen. However, if no LPSI pump is operated in the recirculation mode, no insulation is expected to build up on the screens because of the low transport velocity.
Regulatory Guide 1,82 Millstone Unit No. 2 sump design has been reviewed against the guidance of Regulatory Guide 1.82 (RG 1.82). Although not a design basis / licensing basis requirement for MP2, engineering reviewed Regulatory Guide 1.82, " Water Source for Long Term Recirculation Cooling Following a Loss-of Cooling Accident," to compare MP2's present design with the latest requirements, in 1996, the existing sump screen was redesigned using RG 1.82 as guidance.
Generic Letter 97-04 Response in response to Generic Letter 97-04, dated January 5,1998, NNECO provided a review of the current design-basis analysis used to determine the available Net Positive Suction Head (NPSH) for the ECCS and containment heat removal pumps of MP2. A description of the methodology used to calculate head loss associated with the containment sump screen was provided. This included analysis of factors such as tho amount of insulation debris, sump screen area and sump water approach velocities to estimate the pressure drop across the sump screen mesh. Based on this review, NNECO concluded that:
. The head loss associated with the containment sump screen has been adequately calculated.
. The Millstone Unit No. 2 most recent ECCS analysis is different from the analysis reviewed and approved by the NRC for which a safety evaluation was issued.
. The NPSH analysis for the containment spray pumps is the same as the analysis reviewed and approved by the NRC for which a safety evaluation was issued.
. Containment overpressure was not credited in any ECCS NPSH calculation.
. The available NPSH for the HPSI pumps, in the recirculation mode, meets the required NPSH.
. Further analysis is required to confirm that there is adequate NPSH for the Containment Spray pumps.
NNECO committed to provide a written response, prior to the restart of MP2, to provide the results of the updated analyses of NPSH for the CS pumps.
In a response to a Request for Additionci information, dated June 18,1998, NNECO provided the supplemental information relating to the original response to Generic Letter 97-04 regarding NPSH for emergency core cooling and containment heat removal pumps. This included an updatec analysis of NPSH icr the Containment
' Spray Pumps. The analysis shows adequate NPSH margin and meets the Millstone
. 1
. 1 1
U.S. Nucigar Rngulatory Commission l 817523/ Attachment 1/Page 7 j (Jnit No. 2 Licensing Basis. The NRC, in a letter dated July 7,1998, indicated that the I
, staff had reviewed the response provided by NNECO under GL 97-04 and concluded !
- that the requested information had been provided. The staff considers GL 97-04 l
. closed for MP2. !
Summary:
Although the response to GL 97-04 provides the basis for current compliance with NPSH margin and long term cooling capability, NNECO recognizes the potential need to address the combination of fiber and unqualified coating debris. Since MP2 has no current licensing basis requirements to track amounts of unqualified coatings, NNECO is assessing the status of current coating systems inside containment to confirm their identification and also to establish the present condition of these coating systems as I applied. NNECO is also evaluating the potential impact that quantities of unqualified
) coating and insulation debris may have on containment sump screen head loss. This will address the effect that unqualified coating debris may have on overall sump l performance and therefore long-term cooling capability.
References:
)
- 1. Millstono 2, FSAR, Chapter 6.2, " Refueling Water Storage Tank and Containment Sump."
- 2. Millstone 2, FSAR, Chapter 6.3, " Safety injection System."
- 3. Millstone 2, FSAR, Chapter 6.4, " Containment Spray System."
- 4. M. L. Bowling to Nuclear Regulatory Commission, " Millstone Power Station, Unit No. 2, 90 Day Response to Generic Letter 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat removal Pumps," dated January 5,1998.
- 5. M. L. Bowling to Nuclear Regulatory Commission, " Millstone Power Station, Unit j No. 2, 90 Day Response to Generic Letter 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat removal 1 Pumps, Response to Request for Additional Information," dated June 18,1998.
- 6. Safety Evaluation of the Millstone Nuclear Power Station Unit No. 2, Docket No.
50-336, dated May 10,1974.
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U.S. Nuclar Regulatory Commission
- 817523/ Attachment 1/Page 8
- Second part of 2 (ii)
The following information shall be provided:
, (a) If commercial-grade coatings are being used at your facility for Service Level 1 applications, and such coatings are not dedicated or controlled under your Appendix B Quality Assurance Program, provide the regulatory
, and safety basis for not controlling these coatings in accordance with such
, a program. - Additionally, explain why the facility's licensing basis does not 4
require such a program.
RESPONSE to second part of 2 (ii)::
1 NNECO does not currently employ commercial grade dedication for Service Level 1 coatings used inside containment at Millstone Unit No. 2.
4