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Category:CORRESPONDENCE-LETTERS
MONTHYEARDD-99-12, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 9910281999-10-28028 October 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 991028 ML20217N8261999-10-25025 October 1999 Discusses Errata Re 991021 Filing of Northeast Nuclear Energy Co Answer to Request for Hearing & Petition to Intervene B17901, Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)1999-10-18018 October 1999 Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6) B17886, Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 21999-10-18018 October 1999 Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 2 05000336/LER-1999-012, Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl B17900, Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 11999-10-14014 October 1999 Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 1 ML20217G9491999-10-14014 October 1999 Forwards Exemption from Requirements of 1-CFR50,App E, Section IV.F.2.c,re Conduct of full-participation Exercise in Sept 1999,at Plant,Units 1,2 & 3 ML20217D9671999-10-12012 October 1999 Forwards Copy of Transcript of Public Meeting Held by NRC Staff & NNECO on 990825 at Waterford,Connecticut on Decommissioning Program for Millstone,Unit 1.Without Encl ML20217D3011999-10-0707 October 1999 Forwards Request for Addl Info Re Util 990118 Request for Amend to License NPF-49 to Allow full-core Offloads to Spent Fuel Pool During Core Offloads to Spent Fuel Pool During Core Offload Events ML20217F0031999-10-0606 October 1999 Forwards Original Petition to Intervene Being Filed on Behalf of Clients,Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone,Iaw Provisions of 10CFR2.714 ML20217P1201999-10-0606 October 1999 Informs NRC of Proposed Acquisition of Parent Holding Company of Central Maine & Requests NRC Concurrence,Based on Threshold Review,That Proposed Acquisition Does Not,In Fact, Constitute Transfer Subject to 10CFR50.80 B17892, Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC1999-10-0505 October 1999 Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC ML20217B4711999-10-0404 October 1999 Informs That Staff Did Not Identify Any Safety Concerns Re Licensee Proposals to Modify Commitments Made for Action Items 4.2.1,4.2.2,4.5.1 & 4.5.2 of GL 83-28 by Providing Addl Justifications or Safety Bases for Changes ML20212K1241999-10-0101 October 1999 Responds to Recent Ltrs to Chairman Jackson,Commissioners & Wd Travers,Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performace of Millstone to Ensure That Public Health & Safety,Adequately Protected ML20212J3051999-10-0101 October 1999 Discusses GL 97-06 Re Degradation of SG Internals,Dtd 971230.GL Requested Each PWR Licensee to Submit Info That Will Enable NRC Staff to Verify Whether PWR SG Internals Comply & Conform to Current Licensing Basis for Facilities ML20212L2081999-10-0101 October 1999 Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance ML20212J9991999-10-0101 October 1999 Responds to Recent Ltr to President Clinton,H Clinton, Chairman Jackson &/Or Wd Travers Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performance of Plant to Ensure That Public Health & Safety Adequately Protected ML20212L1971999-10-0101 October 1999 Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety ML20212J2451999-10-0101 October 1999 Informs That Util 980807 & 990629 Responses to GL 98-01, Y2K Readiness of Computer Sys at NPPs Acceptable.Nrc Considers Subj GL to Be Closed for Units 2 &3 ML20212L1831999-10-0101 October 1999 Responds to Recent Ltr to Wd Travers Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Performance of Millstone to Ensure Adequate Protection to Public Health ML20212L2171999-10-0101 October 1999 Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island ML20217A9271999-09-30030 September 1999 Discusses Investigation Conducted at Millstone Nuclear Power Station by NRC OI Region I on 980319 to Determine If Contract Training Instructor Was Terminated for Raising Concerns About Quality of Training Matls ML20217B3221999-09-30030 September 1999 Refers to Investigation Rept 1-1997-035 Conducted at Millstone Nuclear Power Station by NRC Ofc of Investigation Field Ofc,Region I on 970915 to Determine Whether Former Health Physics Technician Discriminated Against ML20212J6621999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Units 2 & 3 on 990916.Identified Several Recent Instances in Which Condition Repts Were Not Initiated,Resulting in Untimely or Inadequate C/As.Historical Listing of Plant Issues Encl B17887, Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer1999-09-28028 September 1999 Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer ML20216J1341999-09-28028 September 1999 Ltr Contract:Task Order 49, Millstone Units 2 & 3 Employee Concerns Program Insp, Under Contract NRC-03-98-021 B17883, Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-62301999-09-27027 September 1999 Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-6230 B17890, Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-09-27027 September 1999 Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal B17888, Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 9909151999-09-24024 September 1999 Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 990915 B17884, Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-031999-09-24024 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-03 ML20212F4961999-09-20020 September 1999 Forwards Insp Repts 50-245/99-08,50-336/99-08 & 50-423/99-08 on 990615-0809.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs,Consistent with App C of Enforcement Policy 05000336/LER-1999-001, Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl B17867, Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports1999-09-17017 September 1999 Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports B17865, Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal1999-09-16016 September 1999 Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal B17876, Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant1999-09-16016 September 1999 Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant B17882, Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6) B17881, Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6) B17859, Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 9801281999-09-15015 September 1999 Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 980128 B17880, Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6) B17872, Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 11999-09-14014 September 1999 Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 1 ML20212A9011999-09-10010 September 1999 Forwards Environ Assessment & Finding of No Significant Impact Re Application for Exemption,Dtd 990803.Proposed Exemption Would Provide Relief from Requirement of 10CFR50 ML20212A3171999-09-10010 September 1999 Discusses Investigation Rept 1-1998-045 Conducted on 981112 to Determine If Former Senior Health Physics Technician Being Denied Employment at Millstone in Retaliation for Having Raised Safety Concerns in Past.Synopsis Encl B17838, Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls1999-09-10010 September 1999 Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls ML20212A7501999-09-10010 September 1999 Forwards Staff Requirements Memo Response,Dtd 990525,which Provides Actions NRC Plans for Continued Oversight of safety-conscious Work Environ & Employee Concerns Program ML20211J9291999-09-0303 September 1999 Forwards mark-ups & Retypes of Proposed Conforming License Changes Required in Connection with Transfers Being Sought in 990615 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests ML20211K5171999-09-0202 September 1999 Expresses Appreciation for Support Provided for NRC Public Meeting on 990825 05000336/LER-1999-010, Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 11999-09-0202 September 1999 Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 1 ML20216H0591999-09-0202 September 1999 Responds to Re Issues Submitted by Cullen on Behalf of Several Petitioners Concerning Offsite Emergency Prepardeness for Millstone Nuclear Power Station ML20211N9241999-09-0101 September 1999 Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures ML20211H0741999-08-30030 August 1999 Discusses GL 92-01,Rev 1, Rv Structural Integrity, Issued by NRC on 950519 & NNECO Responses for Millstone Unit 2 & 980715.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 Based on Response Review 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217N8261999-10-25025 October 1999 Discusses Errata Re 991021 Filing of Northeast Nuclear Energy Co Answer to Request for Hearing & Petition to Intervene B17886, Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 21999-10-18018 October 1999 Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 2 B17901, Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)1999-10-18018 October 1999 Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6) 05000336/LER-1999-012, Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl B17900, Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 11999-10-14014 October 1999 Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 1 ML20217P1201999-10-0606 October 1999 Informs NRC of Proposed Acquisition of Parent Holding Company of Central Maine & Requests NRC Concurrence,Based on Threshold Review,That Proposed Acquisition Does Not,In Fact, Constitute Transfer Subject to 10CFR50.80 ML20217F0031999-10-0606 October 1999 Forwards Original Petition to Intervene Being Filed on Behalf of Clients,Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone,Iaw Provisions of 10CFR2.714 B17892, Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC1999-10-0505 October 1999 Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC B17887, Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer1999-09-28028 September 1999 Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer B17883, Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-62301999-09-27027 September 1999 Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-6230 B17890, Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-09-27027 September 1999 Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal B17884, Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-031999-09-24024 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-03 B17888, Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 9909151999-09-24024 September 1999 Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 990915 05000336/LER-1999-001, Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl B17867, Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports1999-09-17017 September 1999 Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports B17876, Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant1999-09-16016 September 1999 Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant B17865, Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal1999-09-16016 September 1999 Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal B17881, Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6) B17880, Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6) B17859, Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 9801281999-09-15015 September 1999 Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 980128 B17882, Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6) B17872, Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 11999-09-14014 September 1999 Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 1 B17838, Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls1999-09-10010 September 1999 Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls ML20211J9291999-09-0303 September 1999 Forwards mark-ups & Retypes of Proposed Conforming License Changes Required in Connection with Transfers Being Sought in 990615 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests 05000336/LER-1999-010, Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 11999-09-0202 September 1999 Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 1 ML20216H0591999-09-0202 September 1999 Responds to Re Issues Submitted by Cullen on Behalf of Several Petitioners Concerning Offsite Emergency Prepardeness for Millstone Nuclear Power Station ML20211N9241999-09-0101 September 1999 Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures B17851, Forwards Semiannual fitness-for-duty Program Performance Data for 990101-990630 for Millstone Nuclear Power Station, Units 1,2 & 3,IAW 10CFR26.71(d)1999-08-27027 August 1999 Forwards Semiannual fitness-for-duty Program Performance Data for 990101-990630 for Millstone Nuclear Power Station, Units 1,2 & 3,IAW 10CFR26.71(d) B17855, Forwards NRC Forms 398 & 396 in Support of License Renewal for SRO TE Grilley,SOP-4053-04.Encl Withheld,Per 10CFR2.7901999-08-17017 August 1999 Forwards NRC Forms 398 & 396 in Support of License Renewal for SRO TE Grilley,SOP-4053-04.Encl Withheld,Per 10CFR2.790 B17849, Forwards Second Quarter Backlog Performance Rept for 1999, Which Represents Fourth Rept on Mnps Performance Since Restart of Unit 3 & First Status Update for Unit 2.No Regulatory Commitments Are Contained in Ltr1999-08-16016 August 1999 Forwards Second Quarter Backlog Performance Rept for 1999, Which Represents Fourth Rept on Mnps Performance Since Restart of Unit 3 & First Status Update for Unit 2.No Regulatory Commitments Are Contained in Ltr B17854, Forwards Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2,per TS 6.9.1.7.Revised Repts for May & June Also Encl Which Reflect Correct Faulty Printometer Readings1999-08-14014 August 1999 Forwards Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2,per TS 6.9.1.7.Revised Repts for May & June Also Encl Which Reflect Correct Faulty Printometer Readings B17850, Forwards First Lhc Quarterly Assessment Rept for Assessment Performed 990621 to 990701.NNECO Taking Appropriate Actions to Address Observations in Rept1999-08-11011 August 1999 Forwards First Lhc Quarterly Assessment Rept for Assessment Performed 990621 to 990701.NNECO Taking Appropriate Actions to Address Observations in Rept B17837, Forwards COLR for Cycle 7, for Millstone Unit 3,IAW TS 6.9.1.6.Explanation of Changes to COLR Also Encl1999-08-0707 August 1999 Forwards COLR for Cycle 7, for Millstone Unit 3,IAW TS 6.9.1.6.Explanation of Changes to COLR Also Encl B17657, Requests Schedular Exemption from Emergency Plan Exercise Requirements of 10CFR50,App E,Part Iv,Section F,Paragraph 2.c.Requests That Nrc/Fema Evaluated Exercise Be Conducted in Mar 2000 Rather than Sept 19991999-08-0303 August 1999 Requests Schedular Exemption from Emergency Plan Exercise Requirements of 10CFR50,App E,Part Iv,Section F,Paragraph 2.c.Requests That Nrc/Fema Evaluated Exercise Be Conducted in Mar 2000 Rather than Sept 1999 B17845, Forwards Revised Commitment for Surveillance Scheduling & Tracking.Options for Surveillance Scheduling & Tracking Methodologies to Be Incorporated in Standardized Station Surveillance Program Are Currently Being Reconsidered1999-08-0202 August 1999 Forwards Revised Commitment for Surveillance Scheduling & Tracking.Options for Surveillance Scheduling & Tracking Methodologies to Be Incorporated in Standardized Station Surveillance Program Are Currently Being Reconsidered B17831, Informs NRC Staff That Change 3 to Rev 25 of Mnps Emergency Plan Was Implemented on 990715.Change Removes Facility Organizational Charts from Emergency Plan & Identifies Relocation to Nuqap1999-07-26026 July 1999 Informs NRC Staff That Change 3 to Rev 25 of Mnps Emergency Plan Was Implemented on 990715.Change Removes Facility Organizational Charts from Emergency Plan & Identifies Relocation to Nuqap B17834, Forwards Proprietary Revised NRC Form 398,which Certifies That SL Doboe Has Completed Eligibility Requirements for Sro,Per 10CFR55.31.Proprietary Info Withheld1999-07-20020 July 1999 Forwards Proprietary Revised NRC Form 398,which Certifies That SL Doboe Has Completed Eligibility Requirements for Sro,Per 10CFR55.31.Proprietary Info Withheld B17836, Forwards Revised NRC Form 396 & Supporting Physician Rept for Licensed Operator Restricted from Licensed Duties, Effective 990628,due to Medical Condition.Without Encl1999-07-20020 July 1999 Forwards Revised NRC Form 396 & Supporting Physician Rept for Licensed Operator Restricted from Licensed Duties, Effective 990628,due to Medical Condition.Without Encl B17811, Submits Response to NRC AL 99-02,requesting That Licensees Provide Numerical Estimates of Licensing Actions to Be Expected to Be Submitted in Fy 2000 & 20011999-07-20020 July 1999 Submits Response to NRC AL 99-02,requesting That Licensees Provide Numerical Estimates of Licensing Actions to Be Expected to Be Submitted in Fy 2000 & 2001 ML20210S9911999-07-18018 July 1999 Requests NRC Intervene for All Shareholders of New England Electric System & to Help with Merger with National Grid Group & That NRC Petition Security & Exchange Commission to Investigate Matter Relative to No Shareholder Options B17835, Forwards Rev 33 to Millstone Station Physical Security Plan, Per 10CFR50.54(p)(2).Licensee Determined That Changes Do Not Decrease Effectiveness of Plan.Rev Withheld from Public Disclosure,Per 10CFR2.790(d)(1)1999-07-16016 July 1999 Forwards Rev 33 to Millstone Station Physical Security Plan, Per 10CFR50.54(p)(2).Licensee Determined That Changes Do Not Decrease Effectiveness of Plan.Rev Withheld from Public Disclosure,Per 10CFR2.790(d)(1) B17818, Provides NRC Staff with Change to TS Bases Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only.Change Was Reviewed & Approved by Unit 3 Plant Operations Review Committee IAW Provisions of 10CFR50.591999-07-16016 July 1999 Provides NRC Staff with Change to TS Bases Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only.Change Was Reviewed & Approved by Unit 3 Plant Operations Review Committee IAW Provisions of 10CFR50.59 B17824, Forwards Monthly Oeprating Rept for June 1999 & Revised Monthly Operating Rept for May 1999 for Millstone Unit 21999-07-13013 July 1999 Forwards Monthly Oeprating Rept for June 1999 & Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20212K1701999-07-13013 July 1999 Submits Concerns Re Millstone & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Should Provide Adequate Emergency Planning in Case of Radiological Accident B17816, Provides Certification That M Lettrich,Has Completed Eligibility Requirements,Per 10CFR55.31 for Operator License.Util Requests That Licensing Action Be Taken for Named Individual1999-07-0101 July 1999 Provides Certification That M Lettrich,Has Completed Eligibility Requirements,Per 10CFR55.31 for Operator License.Util Requests That Licensing Action Be Taken for Named Individual B17801, Forwards 10CFR50.59 Annual Rept for Period Jan-Dec 1998. Various Changes That Were Initiated in Previous Yrs & Completed in 1998,also Incorporated Into Annual Rept1999-06-30030 June 1999 Forwards 10CFR50.59 Annual Rept for Period Jan-Dec 1998. Various Changes That Were Initiated in Previous Yrs & Completed in 1998,also Incorporated Into Annual Rept B17819, Forwards Rev 17 to FSAR & Addendum 6 to Annual Rept.Nneco Recently Completed Review of Unit 2 Design & Licensing Bases Which Resulted in Changes to FSAR Provided in Encl 1.Encl 2 Includes Info Covering Changes Not Included in1999-06-30030 June 1999 Forwards Rev 17 to FSAR & Addendum 6 to Annual Rept.Nneco Recently Completed Review of Unit 2 Design & Licensing Bases Which Resulted in Changes to FSAR Provided in Encl 1.Encl 2 Includes Info Covering Changes Not Included in B17780, Forwards Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) TR, IAW 10CFR50.54(a)(3).Changes to TR Are Shown as Text in Bold Italics1999-06-30030 June 1999 Forwards Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) TR, IAW 10CFR50.54(a)(3).Changes to TR Are Shown as Text in Bold Italics B17723, Responds to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for Units 2 & 3 Encl.Without Encl1999-06-29029 June 1999 Responds to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for Units 2 & 3 Encl.Without Encl B17767, Forwards Rev 12 to FSAR & Addendum 3 to Annual Rept, for Millstone Unit 3,per 10CFR50.71(e) & 10CFR50.4(b)(6). No New Regulatory Commitments Contained in Ltr1999-06-29029 June 1999 Forwards Rev 12 to FSAR & Addendum 3 to Annual Rept, for Millstone Unit 3,per 10CFR50.71(e) & 10CFR50.4(b)(6). No New Regulatory Commitments Contained in Ltr 1999-09-03
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A8071990-09-11011 September 1990 Forwards Core Operating Limits Rept for Four & Three Loop Operation,Per Tech Spec 6.9.1.6.d A08900, Responds to Expressing NRC Views on Access to Util Internal or third-party Assessment Repts.Believes Internal Analysis to Support Amend of One of Util NRC OLs to Authorize Higher Power Level Is within NRC Purview & Access1990-09-11011 September 1990 Responds to Expressing NRC Views on Access to Util Internal or third-party Assessment Repts.Believes Internal Analysis to Support Amend of One of Util NRC OLs to Authorize Higher Power Level Is within NRC Purview & Access B13628, Forwards Correction to Error Discovered in Util 900727 Response to Notice of Violation from Insp Rept 50-336/90-09. Statement Corrected to Read That Contract Personnel That Have long-term Assignments,Certified as Testing Personnel1990-09-0707 September 1990 Forwards Correction to Error Discovered in Util 900727 Response to Notice of Violation from Insp Rept 50-336/90-09. Statement Corrected to Read That Contract Personnel That Have long-term Assignments,Certified as Testing Personnel B13624, Forwards Addl Info Re Relief Request from ASME Code Section XI Requirements for Temporary Repair to Piping Adjacent to Valve 2-SW-97A,per 900817 Telcon1990-09-0505 September 1990 Forwards Addl Info Re Relief Request from ASME Code Section XI Requirements for Temporary Repair to Piping Adjacent to Valve 2-SW-97A,per 900817 Telcon A08977, Advises of Commitment to Install Hardened Wetwell Vent at Facility,In Response to NRC .Util Will Be Proceeding W/Initial Design & Engineering of Hardened Vent, to Support Installation During 1993 Refueling Outage1990-09-0404 September 1990 Advises of Commitment to Install Hardened Wetwell Vent at Facility,In Response to NRC .Util Will Be Proceeding W/Initial Design & Engineering of Hardened Vent, to Support Installation During 1993 Refueling Outage B13596, Forwards Millstone Unit 3 Individual Plant Exam for Severe Accident Vulnerabilities, Per Generic Ltr 88-20.Rept Identified That No Major Severe Accident Vulnerabilities Requiring Corrective Action Needed1990-08-31031 August 1990 Forwards Millstone Unit 3 Individual Plant Exam for Severe Accident Vulnerabilities, Per Generic Ltr 88-20.Rept Identified That No Major Severe Accident Vulnerabilities Requiring Corrective Action Needed B13626, Informs That Info Provided in Re safety-related Equipment Classification Programs Also Applicable for Unit 3 of Facility1990-08-31031 August 1990 Informs That Info Provided in Re safety-related Equipment Classification Programs Also Applicable for Unit 3 of Facility B13618, Forwards Addl Info on Util 900815 Relief Request from ASME Code Section XI Requirements,Per 10CFR50.55a(g)(6)(i),for Repairs to Pipe 3SWP-006-050-031990-08-24024 August 1990 Forwards Addl Info on Util 900815 Relief Request from ASME Code Section XI Requirements,Per 10CFR50.55a(g)(6)(i),for Repairs to Pipe 3SWP-006-050-03 ML20059C2061990-08-23023 August 1990 Forwards Vols 1 & 2 to Semiannual Radioactive Effluents Release Rept Jan-June 1990, Per 10CFR50.36a.Rept Includes Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents A08918, Responds to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-245/90-08.Mitigation of Civil Penalty Requested.Corrective Action:List of Procedural Changes Provided1990-08-22022 August 1990 Responds to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-245/90-08.Mitigation of Civil Penalty Requested.Corrective Action:List of Procedural Changes Provided B13610, Requests Relief from ASME Boiler & Pressure Vessel Code Section XI Requirements Re Mods to Pipe 3SWP-006-050-03. Results of Insps & Required Repairs Will Determine Schedule for Future Insps1990-08-15015 August 1990 Requests Relief from ASME Boiler & Pressure Vessel Code Section XI Requirements Re Mods to Pipe 3SWP-006-050-03. Results of Insps & Required Repairs Will Determine Schedule for Future Insps B13595, Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-13941990-08-14014 August 1990 Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-1394 B13607, Requests Relief from ASME Code Section XI to Reflect Mod to Piping Adjacent to Valve 2-SW-97A,in Response to Generic Ltr 90-051990-08-10010 August 1990 Requests Relief from ASME Code Section XI to Reflect Mod to Piping Adjacent to Valve 2-SW-97A,in Response to Generic Ltr 90-05 A08845, Responds to NRC Backfit Analyses of Hardened Wetwell Vent, Contained in .Benefit of Installing Hardened Wetwell Vent to Satisfy Basic Design Objective of Preventing core-melt Event Not Sufficient for Immediate Decision1990-08-0808 August 1990 Responds to NRC Backfit Analyses of Hardened Wetwell Vent, Contained in .Benefit of Installing Hardened Wetwell Vent to Satisfy Basic Design Objective of Preventing core-melt Event Not Sufficient for Immediate Decision ML20058N2181990-08-0707 August 1990 Notification of Change in Senior Operator Status.Util Determined That Need to Maintain Senior OL of LS Allen No Longer Exists.Determination Effective 900719 ML20058M8321990-08-0707 August 1990 Discusses Spent Fuel Racks Poison Surveillance Coupon Boraflex Degradation.Visual Exam of Remaining Surveillance Coupons Revealed Similar Situation Existed in All Coupon Samples B13590, Responds to NRC 900718 Request for Addl Info Re Util 900418 Request for Schedular Exemption from 10CFR50,App E,Section IV.F.3 to Allow Dec 1990 Full Participation Exercise to Be Exchanged W/Oct 1991 Partial Participation Exercise1990-08-0101 August 1990 Responds to NRC 900718 Request for Addl Info Re Util 900418 Request for Schedular Exemption from 10CFR50,App E,Section IV.F.3 to Allow Dec 1990 Full Participation Exercise to Be Exchanged W/Oct 1991 Partial Participation Exercise A08881, Responds to NRC Re Violations Noted in Insp Rept 50-423/90-08.Corrective Action:Operators Directly Involved W/Event Removed from Licensed Duties & Counseled by Operations Manager on Causes of Event1990-07-31031 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-423/90-08.Corrective Action:Operators Directly Involved W/Event Removed from Licensed Duties & Counseled by Operations Manager on Causes of Event B13594, Forwards Rev 13 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21(b) & 2.790(a))1990-07-30030 July 1990 Forwards Rev 13 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21(b) & 2.790(a)) ML20055J4621990-07-27027 July 1990 Advises That Need to Maintain OL or Senior OL for Listed Individuals No Longer Exists,Effective 900701 B13585, Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys1990-07-26026 July 1990 Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys A08565, Responds to NRC 900302 Request for Addl Info Re LPCI Swing Bus Transfer Design & Single Failure Vulnerabilities1990-07-26026 July 1990 Responds to NRC 900302 Request for Addl Info Re LPCI Swing Bus Transfer Design & Single Failure Vulnerabilities B13592, Requests Extension to Respond to NRC Backfit Analyses of Hardened Wetwell Vent1990-07-24024 July 1990 Requests Extension to Respond to NRC Backfit Analyses of Hardened Wetwell Vent ML20063P9791990-07-23023 July 1990 Notification of Change in SL Jackson Status Effective 900701,due to Permanent Reassignment within Util B13563, Discusses Util Comprehensive Review of Options Re Degraded Grid Undervoltage Protection.Confirms Previous Conclusion That Splitting Loss of Normal Power Logic Would Have Overall Adverse Impact on Plant Safety1990-07-20020 July 1990 Discusses Util Comprehensive Review of Options Re Degraded Grid Undervoltage Protection.Confirms Previous Conclusion That Splitting Loss of Normal Power Logic Would Have Overall Adverse Impact on Plant Safety B13566, Advises That Util Has Reasonable Assurance That Safety Relief Valves Operable & Will Perform as Expected Until Next Outage1990-07-20020 July 1990 Advises That Util Has Reasonable Assurance That Safety Relief Valves Operable & Will Perform as Expected Until Next Outage B13588, Corrects 900703 Submittal of Results of Second in-cycle Insp of Steam Generators.All Tubes W/Cracks Stacked & Plugged1990-07-18018 July 1990 Corrects 900703 Submittal of Results of Second in-cycle Insp of Steam Generators.All Tubes W/Cracks Stacked & Plugged A08822, Submits Addl Info Requested Re Util Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls. Charpy Impact Use Values for Welds Provided in Evaluation of Irradiated Capsule W-971990-07-18018 July 1990 Submits Addl Info Requested Re Util Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls. Charpy Impact Use Values for Welds Provided in Evaluation of Irradiated Capsule W-97 ML20055G5331990-07-18018 July 1990 Forwards Decommissioning Financial Assurance Certification Rept B13587, Requests Temporary Waiver of Compliance from Tech Spec 3.5.F.2 Re Emergency Diesel Generator (EDG) Limiting Condition for Operation.Waiver Would Extend Available Time to Repair Damaged Electrical Components1990-07-16016 July 1990 Requests Temporary Waiver of Compliance from Tech Spec 3.5.F.2 Re Emergency Diesel Generator (EDG) Limiting Condition for Operation.Waiver Would Extend Available Time to Repair Damaged Electrical Components ML20055D3461990-07-0303 July 1990 Responds to NRC Bulletin 90-001 Re Loss of Fill Oil Transmitters Mfg by Rosemount.Operability Determinations Performed & Documented for All Rosemount 1153 & 1154 Transmitters at Facility B13545, Forwards Rev 3 to Updated FSAR for Millstone Unit 31990-06-29029 June 1990 Forwards Rev 3 to Updated FSAR for Millstone Unit 3 ML20055D7191990-06-29029 June 1990 Amends 900604 Rev 13 to QA Program ML20055D3481990-06-29029 June 1990 Forwards Addl Info Re Facility Crdr & Isap,Including Justification for Human Engineering Discrepancies Dispositioned for No Corrective Action B13531, Forwards Rev 8 to Updated FSAR for Millstone Unit 21990-06-29029 June 1990 Forwards Rev 8 to Updated FSAR for Millstone Unit 2 B13550, Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl1990-06-27027 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl B13499, Forwards Corrected Tech Specs Page 3/4 9-1 for Incorporation Into Proposed Amend 36 to License DPR-21 Re Auxiliary Electrical Sys1990-06-26026 June 1990 Forwards Corrected Tech Specs Page 3/4 9-1 for Incorporation Into Proposed Amend 36 to License DPR-21 Re Auxiliary Electrical Sys ML20043F8721990-06-11011 June 1990 Corrects Name of Vendor Supplying Replacement Plug Valves, Per Util 900511 Ltr.Replacement Bolts,Not Valves,Purchased from Cardinal Industrial Products Corp ML20043H0161990-06-0808 June 1990 Requests Exemption from App J to 10CFR50 for 12 Valves in Reactor Bldg Closed Cooling Water Sys.Valves Not within Definition of Containment Isolation Valves in App J & Not Required to Be Tested ML20043E8831990-06-0505 June 1990 Requests NRC Authorization to Use Plugs Fabricated of nickel-chromium-iron Uns N-06690 Matl Alloy 690 to Plug Tubes in Steam Generators of Plant ML20043D0451990-05-30030 May 1990 Discusses Proposed Rev to Tech Specs Re Facility ESF Actuation Sys Instrumentation Trip Setpoint,Per 900330 Ltr ML20042H0311990-05-0909 May 1990 Discusses Steam Generator Safety Assessment.Concludes That Continued Operation Through Remainder of Current Cycle 10 Fully Justified ML20042F0941990-04-30030 April 1990 Provides Addl Info Re Environ Impact of 900226 Application for Amend to License NPF-49,revising Tech Specs to Allow Containment Pressure to Increase to 14 Psia During Modes 1-4,per NRC Request ML20042F0661990-04-30030 April 1990 Responds to NRC 900404 Ltr Re Violations Noted in Safety Insp Rept 50-336/90-01 on 900120-0305.Corrective Action:Ler 90-004 Submitted on 900430 to Document Condition Prohibited by Plant Tech Specs ML20042E8331990-04-27027 April 1990 Forwards Annual Environ Protection Plan Operating Rept for 1989, & Monitoring Marine Environ of Long Island Sound at Millstone Nuclear Power Station Annual Rept 1989. ML20012E2681990-03-23023 March 1990 Responds to NRC 900226 Ltr Re Violations Noted in Insp Rept 50-423/89-23.Corrective Actions:Requirement to Review All Changes on Safety Sys for Potential Operating Procedure Changes Stressed to Operations & Engineering Personnel ML20012C3141990-03-13013 March 1990 Forwards Info Re Insp of Facility Emergency Operating Procedures,Per 900119 Ltr ML20012B4111990-03-0202 March 1990 Provides Addl Info Requested to Clarify Changes Proposed to Tech Spec Action Statements for Inoperable Accumulator B13453, Advises That Mods to Steam Generator Blowdown Sample Sys Completed,Per Violations Noted in Insp Rept 50-423/89-14 & Salp.Sys Will Be Evaluated for Next 2 Wks to Ensure Blowdown Radiation Monitor Operating Reliably1990-02-26026 February 1990 Advises That Mods to Steam Generator Blowdown Sample Sys Completed,Per Violations Noted in Insp Rept 50-423/89-14 & Salp.Sys Will Be Evaluated for Next 2 Wks to Ensure Blowdown Radiation Monitor Operating Reliably ML20011F7541990-02-26026 February 1990 Notifies That Jh Parillo Reassigned & No Longer in Need of License SOP-10263-2 as of 900219 1990-09-07
[Table view] |
Text
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March 30, 1979 Docket No. 50-336 Director of Nuclear Reactor Regulation Attu: Mr. R. Reid, Chief Operating Reactors Branch #4 U. S. Nuclear Regulatory Commission Washington, D. C. 20555
References:
(1) W. G. Counsil letter to R. Reid dated February 12, 1979.
(2) W. G. Counsil letter to R. Reid dated March 22, 1979.
(3) W. G. Counsil letter to R. Reid dated January 27, 1979.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Large Break LOCA ECCS Performance Results In Reference (1), Northeast Nuclear Energy Company (NNECO) provided the results of the non-LOCA safety analyses necessary to support Cycle 3 operation at 2700 MWt. The large break LOCA/ECCS performance analysis has now been completed and the results are provided as Attachment 1. These results have not as yet been QA-verified by Combustion Engineering, the NSSS and fuel supplier. This verification is expected on or about April 10, 1979 and you will be notified promptly when this process has been completed. Non-QA results of the small break LOCA analysis were provided in Reference (2).
No te t ha t thr. large break analysis assumes 500 plugged steam generator tubes per steam generator. This is less than the number currently plugged, which is 350 and 412 in Steam Generators 1 and 2, respectively.
NNECO las reviewed these results pursuant to the requirements of 10CFR170 and has determined that no additional fee is required. The basis for this determination is provided in Reference (3).
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
/ / ONAU W'. G. Counsil Vice President Attachment 7 9 0 4 0 9 015ct
7 k DOCKET No. 50-336 ATTAClfMENT 1 MILLSTONE NUCLEAR POWER S'IATION, UNIT NO. 2 LARGE BREAK LOCA ECCS PERFORMANCE RESULTS MARCH, 1979
- r. p Millstone Unit 2 Cycle 3 Large Break LOCA ECCS Performance Results 1.0 Introduction and Summary The large break loss-of-coolant accident ECCS performance evaluation for Millstone 2, cycle 3, presented herein demonstrates appropriate conformance with the Acceptance Criteria for LigFt-Water-Cooled Reactors as presented in 10CFR50.46 0) .
The evaluation demonstrates acceptable ECCS perfomance for Millstone 2 during cycle 3 at a reactor power level of 2754 Mwt and a peak linear heat generation rate (PLHGR) of 15.6 kw/f t. The method of analysis and results are presented in the following sections.
2.0 Method of Analysis The calculations performed for this evaluation used Combustion Engineering's Large Break Evaluation Model which is described in References 2 through 8 Blowdown, refill /reflood, and temperature calculations were performed to incorporate the cycle 3 fuel characteristics and reactor power level of 2754 fint into the ECCS performance evaluation. The blowdown hydraulic calculations were performed with the CEFLASH-4A(4) code while the refill /
reflood hydraulic calculations were performed with the COMPERC-II(5) code.
The hot rod clad temperature and clad oxidation calculations were performed with the STRIKIN-II(6) and PARCH (0} codes. Core wide clad oxidation calculations were also performed in this analysis.
The ECCS analysis assumptions are the same as those stated in Reference 9 The core and system parameters which differ from the previous analysis (9 I are shown in Table Al which is consistent with the PLHGR of 15.6 kw/ft.
The containment parameters pertinent to this analysis are listed in Table A2.
v .
In general, all possible break locations are considered in a LOCA analysis. However, it was demonstrated in Reference 2 that ruptures in the cold leg pump discharge location produce the highest clad temperatures.
This is due to the minimization of core flow for this break location.
Since core flow is a function of the break size, the Millstone Unit 2, cycle 3, large break calculations have been performed for the cold leg pump discharge breaks for both guillotine and slot breaks over a range of break sizes from 5.89 ft2 to twice the flow area of the cold leg.
3.0 Resul ts_
Included in the cycle 3 core are 72 partially depleted and 72 undepleted stable high density fuel assemblies (Batches D and E), and 73 unstable high density, partially depleted fuel assemblies (Batches B and C).
Burnup dependent calculations for the various fuel types were performed with the FATES (7) and STRIKIN-II(0) codes. The results demonstrated that the most limiting fuel rod during cycle 3 operation is a rod in one of the partially depleted batch B assemblies retained from cycle 2.
For the limiting batch B assembly rod, clad rupture was predicted to occur during the blowdown period. Clad rupture during blowdown leads to the highest clad temperatures because of a degradation in the cooling of the fuel rod during the blowdown period and a decrease in the effectiveness of rod-to-rod thermal radiation during the reflood period, as well as increased clad oxidation. In this analysis blowdown rupture for the limiting batch B fuel was first predicted to occur toward the end of the third fuel cycle. Earlier in the cycle at the time of minimum fuel-clad gap conductance, when the fuel stored energy is at-a maximum, the fuel pin pressure was not high enough to cause rupture during blowdown. For this reason the highest clad temperatures were not predicted at the time of minimum gap conductance, but at the time when the fuel pin pressure first became high enough to cause blowdown
s .,
rupture. The spectrum of break sizes was therefore analyzed at a burnup of 49,988 MWD /MTU, the time-in-life when blowdown rupture first occurred, to maximize the initial stored energy in the fuel rod. However, for the 0.6 x DES /PD* and 0.6 x DEG/PD** breaks, blowdown rupture did not occur even at the very end of the fuel cycle when the fuel-clad gap pressure was highest. Therefore, these two breaks were analyzed at the time-in-life of minimum gap conductance (6582 MWD /MTU).
The break spectrum analysis described in Section 2.0 was performed for the limiting B assembly rod. It was determinee from this analysis that the peak linear heat generation rate (PLHGR) for the B assembly rod is 15.6 kw/ft.
The 0.8 DEG/PD break produced the highest clad temperature of 2081 F.
The highest local clad oxidation percentage was less than 16.0%. The 0.8 DEG/PD also resulted in the highest core wide clad oxidation which was less than 0.727%. The PLHGR of 15.6 kw/f t is therefore demonstrated to be an acceptable limit for cycle 3 operation.
The rupture strain model employed in the performance of this analysis is currently being reviewed by the NRC. Potential changes to the strain model, which could result following the NRC review, are not expected to impact the results and conclusions of the analyses presented in this report.
- DES /PD = Double-Ended Slot at Pump Discharge
- DEG/PD = Double-Ended Guillotine at Pump Discharge
The times of interest for each of the breaks are presented in Table A3.
The new rupture ti..es are included in Table A4, which contains a sunnary of the peak clad temperatures and oxidation percentages for the break spectrum. Table A5 contains a list of the pertinent variables plotted for each break in this analysis. Table A6 contains a list of additional parameters plotted for the 0.8 DEG/PD break. Mass and energy release to the containment during blowdown is presented in Table A7 for the worst break.
Also presented in this table is the steam expulsion data during reflood.
Figure A7 shows the peak clad temperature plotted versus break size and type, demonstrating that the worst break is the 0.8 DEG/PD rupture. The ECC water spillage and containment spray flow rates are presented graphically in Figure A8.
4.0 Conclusion The results of the ECCS perfonr.ance evaluation for Millstone 2, cycle 3 demonstrate conformance with the Acceptance Criteria for Light-Water-Cooled Reactors as presented in 10CFR50.46 0) . The results of the analysis identified the peak clad temperature of 2081 F, a peak local clad oxidation percentage of <l6.0%. The peak core wide clad oxidation percentage was calculated to be less than 0.727%. Therefore, it can be concluded that operation of Millstone 2 at a reactor power level of 2754 Mwt and a PLHGR of 15.6 kw/ft is acceptable for cycle 3.
5.0 Computer Code Version Identification The following code versions were used in this analysis:
CEFLASH-4A Version 76041 COMPERC-II Version 75097 STRIKIN-II Version 77036 PARCH Version 77004 IL
6.0 References
- 1. Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Cooled liuclear Power Reactors, Federal Register, Vol. 39,fio. 3 -
Friday, January 4, 1974.
- 2. CEf1PD-132, " Calculative Methods for the CE Large Break LOCA Evaluation Model", August 1974 (Proprietary).
CEf1PD-132, Supplement 1, "Updcted Calculative Methods for the CE Large Break LOCA Evaluation Model", December 1974 (Proprietary).
- 3. CEf1PD-132, Supplement 2, " Calculational Methods for the CE Large Break LOCA Evaluation Model", July 1975 (Proprietary).
- 4. CEf1PD-133, "CEFLASH-4A, A FORTRAft IV Digital Computer Program for Reactor Blowdown ',.alysis", April 1974 (Proprietary).
CEf1PD-133, Supplement 2, "CEFLASH-4A, A FORTRAfi IV Digital Computer Program for Reactor Blowdown Analysis (Modification)", Dc ember 1974 (Proprie tary) .
- 5. CEf1PD-134, "COMPERC-II, A Program for Emergency Refill-Reflood of the Core", April 1974 (Proprietary).
CEf1PD-134, Supplement 1, "COMPERC-II, A Program for Emergency Refill-Reflood of the Core (Modification)", December 1974 (Proprietary).
- 6. CEf1PD-135, "STRIKIfi, A Cylindrical Geometry Fuel Rod Heat Transfer Program, April 1974 (Proprietary).
CEf1PD-135, Supplement 2 "STRIKIft-II, A Cylindrical Geometry Fuel Rod Heat Transfer Program (Modification)", February 1975.
e ,
CENPD-135, Supplement 4, "STRIKIN-II, A Cylindrical Geometry Fuel Rod Heat Transfer Program", August 1976 (Proprietary).
CENPD-135, Supplement 5-P, "STRIKIN-II, A Cylincrical Geometry Fuel Rod Heat Transfer Program", April, 1977 (Proprietary).
- 7. CENPD-139, "CE Fue 2 valuation Model", July 1974 (Proprietary).
8 CENPD-138, and Supplement 1 " PARCH, A FORTRAN IV Digital Program to Evaluate Pool Boiling, Axial Rod and Coolant Heatup",
February, 1975.
9 Letter, D. C. Switzer (NNECO) to R. Reid (NRC) Docket No. 50-336, March 3, 1978.
TABLE Al Millstone Unit II Cycle III Core Parameters Quanti ty Value 2754 Mwt Core Power Level (102% of Nominal)
Average Linear lieat Rate (102% of Dominal) 6.396 kw/ft Peak Linear lleat Generation Rate (PLitGR) 15.6 kw/ft Core Inlet Temperature 551 F 0
Core Outlet Temperature 602 F 6
SystemFlowRate(total) 138.9x10 lbm/hr 6
Core Flow Rate 133.8x10 lbm/hr 2
Gap Conductance at PLliGR* 2000 BTU /hr-f t - F Fuel Centerline Temperature at PLilGR* 3484 F U
Fuel Average Temperature at PLilGR* 2082 F Hot Rod Gas Pressure
- 1971 psia flot Rod Burnup* 49988 MWD /MTU 1393 BTU /hr-ft 2_op Gap Conductance at PLHGR**
Fuel Centerline Temperature at PLHGR** 3685 F Fuel Average Temperature at PLilGR** 2304 F Hot Rod Gas Pressure ** 1392 psia Hot Rod Burnup** 6582 MWD /MTU
- At Time-In-Life Of Maximum Gap Pressure
- At Time-in-Life Of Minimum Gap Conductance
- e Table A2 Millstanc Unit 2 Containrent Physical Parameters 6 3 1.938 x 10 gt Net Free Volume
. Containment Initial Conditions: . ,
100%
Humidity
"~
Containment Temperature 60 F Enclosure Building Tecperature 60 F Ground Temperature 40 F 14.7 psia Initial Pressure Initial Time for:
26 seconds Spray Flow 0.0 seconds Fans (3)
. 14.0 seconds Additional Fan .
Containment Spray Water:
50 F Temperature 3300 gpm Flow Rate (Total, 2 pumps)
Fan Cooling Capacity (Per Fan)
Vapor Temperature ( F) Capacity (BTU /Sec) 60 0.0 145 3360.0 165 5280.0 300 28800.0 350 32400.0 Containment Heat Absorbing Surfaces
- 1. Surface Areas and Thicknesses
- a. Shell and doec - 71,870 Ft (one side exposed to contain=ent accosphere)
(1) Paint - 0.003 In. '
(2) Carbon steel - OI25 r In. .
(one side exposed to enclosure buildirg atmosphere)
(3) Concrete - 3.0 Ft.
. s Table A 2 (con't)
Hillstone Unit 2 Cont aintien t Physical Parameters
- b. U.tlined Concrete - 62,800 Ft (1) Concrete - 2.0 Ft. (onc side exposed to containment atmosphere, one side insulated) ,
- c. Galvanized Steel - 120,100 Ft (1) Zine - 0.0036 In. (one side exposed to containment atmosphere)
(2) Carbon steci - 0.20 In. (ona side insulated)
- d. Painted Thin Steel - 56,850 Ft (1) Paint - 0.003 In. (onc side exposed to containment atmosphere)
(2) Carbon steel - 0.2 In. (onc side insulated)
- c. Painted Steel - 32,600 Ft -
(1) Paint - 0.003 In. (one side exposed to containment atmosphere)
..(2) Carbon steel - 0.26 In. (onc side insulated)
- f. Painted Steel - 22,425 Ft (1) Paint - 0.003 In. (onc side exposed to containment atmosphere)
(2) Carbon steel - 0.86 In. (one side insulated)
- g. Painted Thick Steel - 4,250 Ft (1) Paint - 0.003 In. (one side exposed to containment atmosphere)
(2) Carbon steel - 2.94 In. (one side insulated)
- h. Containment Penetration Area - 3,000 Ft (1) Paint - 0.003 In. (one side exposed to containment atmosphere)
(2) Carbon steel - 0.75 In.
(3) Concrete - 3.75 Ft. (one side exposed to enclosure building atmosphere)
- i. Stain 1 css Steel Lined Concrete - 8,340 Ft (1) Stainless steel - 0.25 In. (one side exposed to containment atmosphere)
(2) Concrete - 2.0 Ft. (one side insulated)
l Tabic A 2 (Con ' t)
!!illstone t' nit 2 Containment Physical Parameters
- j. Base Slab - 11,130 Ft (1) Concretc - 8.0 Ft. (one side exposed to containment sump, one side exposed to ground) ,
- k. Neutron Shield - 1400 Ft (1) Stainless Steel - 0.024 Ft (both sides exposed to containment atmosphere)
- 2. Thermeti Properties llcat Capacity Materfal Conductivitg (BTU /hr-ft- F ) (BTU /ft3_op)
- a. Concretc 2.0 36
- b. Carbon Steel 35.0 55
- c. Stainless Steel 10.0 62
- d. Paint 1.5 32
- c. Zinc 70.0 45
- 3. IIcat Transfer Coefficients
- a. ' Containment atmosphere to sump - 500 BTU /hr-ft - F
- b. Sump to base slab - 50 BTU /hr-ft -F
- c. Containment structure to enclosure building atmosphere - 5.0 BTU /hr-ft - F
TABLE A3 MILLSTONE UNIT 2 CYCLE 3 TIMES OF INTEREST (SECONDS)
START OF TIME OF ANNULUS CONTACT TIME SAFETY BREAK SAFETY INJECTION DOWNFLOW TIME " -CTION TANKS EMPTY 1.0 DES /PD 16.1 19.1 33.2 60.7 0.8 DES /PD 16.7 19.8 33.9 61.3 0.6 DES /PD 18.3 21.4 35.5 63.0 1.0 DEG/PD 16.0 19.0 33.1 60.5 0.8 DEG/PD 16.8 19.8 33.9 61.3 0.6 DEG/PD 18.9 22.0 36.1 63.5
TABLE A4 Millstone Unit 2 Cycle 3 Hot Rod Rupture Peak Local Core-Wide Break Peak Clad Temperature (UF) Time (sec) Clad 0xidation (%) Clad 0xidation (%)
2079 9.68 <16.0 <.704 1.0 x DES /PD 2077 9.46 <16.0 < 695 0.8 x DES /PD 28.05 8.61 - ,96 0.6 x DES /PD* 1950 1.0 x DEG/PD 2080 9.40 <16.0 <.720 2081 9.64 <16.0 <.727 0.8 x DEG/PD 1948 32.17 8.44 <.446 0.6 x DEG/PD*
6.
- Analyzed at time of minimum gap conductance
I Table A5 Variables Plotted as a Function of Time for Each large Break in the Spectrum Figure yariable _ Designation
~ '
.A.
~
Core Po.ier .
Pressure in Center !!ot Assembly liode B Leak Flo'./ C~
!!at Assembly Flow (below hot spot) -
D.1 lbtAssemblyFlo.i(abovehotspot) ,
D.2' Ifot Assembly Quality ,
E .
Containc.cnt Pressure -
F l' ass Added to Core During P,eflood G Peak Clad Tempcrature - , !!
s -
4 e
e e e a
e 4
e e
9 e
Table A6 Additional Variables Plotted as a function of Time for the large Break Having the Highest Clad Temperature Figure Va riables _ .,
Desionation
~ ~
L . -
Mid Annulus Flow f Qualities Above.and Below the Core J Core Pressure Drop K Safety Injection Tank Flow into Intact Discharae Legs L Water Level in Downccmer During Reflood 11 Hot Spot Gap Conductance H Peak Local Clad 0xidation- 0 Clad Tenperature, Centerline Fuel Temocrature, Average F'uel Temperature and Coolant Temperature for Hottest flode P Hot Spot Heat Transfer Coefficient Q Containment Temperature R Sump Temperature S Hot Rod' Internal Gas Pressure ,
T Core Bulk Channel Flow Rate U a
h
laDie A/
MILLST0fiE UflIT 2 CYCLE 3 BLOWDOWil AND REFLOOD MASS Af1D EliERGY RELEASE DA'la 0.8 DEG/PD h . _ , - . . _ _ _. I _ _ _ _ _ ___
" _ _I=f~ ------ =I
=m-I
- ,- - , - = ---
IflTEGRAL OF
,=
M^b
. _ . _ _ _5_ } S$d. .__{RG{RELEASEI__INTEGRALOF Ef MASS FLOW EllERGY RELEASE _
SEC LBfGSEC BTV/SEC LBli BTU i l
, E l I l l i .
l i
Mo !
ao i aoi i
j ao i
!. do l c !
l A c<S- l2 998 W /c4i%35.2 r/O !!1 tL M x /o' '
- / J& # x /6 6 1 i .
' i
!6:/d l9./30 LF.9&f'; Id.3<// k' /o' O.7.20 l V. Ar 14 3/.z 3.97aN , dVB s/s # 7s/
V..a l u 9s s.od ws u+)l y ,
2d ! 7, /J8 L5. EEd A ?d.2 9dS</x so ' l ,
I I l p.3S d.949 J,788 ' 2. 44 7 l A3'A2 u /s 7 l YsWS d' BS-;/ 3746 3, AS7 l l ld.suo s.7so e/sf lV.sso A 7/9 l \
baso I i
\
O..80 &.7fo 3. 96 4 SSV& 3.s23 I ;
Q -
A 60 ,h. 73 4 . \3.sB 7 1
- s. 297; Y 1
L3 7/.2 i
' A '/O ed. 40 / 3.dd f fM /0 J20' l/:80 ld'Ys.2 , 3.293 A .rs& el /o f J. dPB- ,
i I ! ! ! ;
J. 2o Gn.7,ys; 'J. 880 / </)8 ' l 2 Bao l l
- J. s6 4 238 J17c A d.28 I5. 9.2 h Y !
l l i i 3.00 ' /' d54 L2.4 W A 8/9 '
9,900.k'/O I I
j l i J. '/'O l4347 LP. '/JJ A 99.9 lAO98 2 /0 0 !
f I !
3.80 l 4 /06 , l729.2;
. J./4 9 ; A / 9.2 , ,
,V90 J.746 l i I
.2. /2r l l..Voh J
- /.3n 3.~.2 o 3.2 73 ;
l A 904 l 2.dBf A v'8S 4.60 2.95 7 i A 799 l 2.933 l/. 43 / '
d.!O '2.g7/l
! ! ! I A 744 l 2.40 l / & 6 9 'l 3./S8'l i .
- .2.453 / 483 3.362 V889
hI 8.40 l !
I i
'.J. 2 ?'& l lA37/ l3.ss/ , J.so3 Y .30 .2. $ d .2- / .238 . -
Y -
3 7.2d' .) /08 l 1 l l l a/0 O A 8/6b'/d W /. /.2 / A' /O Y
- 3. 280 K /0 5 J. 203 a' /C
Table A7 (cont'd)
Q.
I
= ._ . - - - - = - - - - _ _
_ -.=T.
i IflTEGRAL OF IflTEGRAL OF l TIME g MASS FLOW ENERG{ RELEASE _ MASS FLOW....___..ENERGYyELEASE_
I LBM I B"U SEC LBM/SEC !
BTV)SEC l l l l
\ //. O / 434 x /o # 9 6;S B.< <s ' lM D-W/x /O 2.3c 7 a /0 8 l l l l
' /2. 0 2 784xl /d 3 7 460l 4 AS& l
- l. 2.392 ;
- /3. O t
?. /2 9 d. 4 / / -4.254 /. 44/
h/d.0 ad9'/ 3 67/ M360 2. d ?d
./d& 3.BS.Z 4386 4346 .2,J 7Y
/d o 2.83 9 3.9'3o 9'379 J. &/3 V ayo.7
/ 7. O J./81 .2. s ,g Q.s4
/8. O A 390 ,p /0 42/9 44.2.2 J.sdf
/2O f 23/ W /0# A/df Jc /0 ' 4 Y 3' 3 2d79
,/98 d./ N X/O ' 9.d.2 8 X /O S 4 WJ9 x /0 # ,2, dSd ,.g /C E
!
- TIME OF AfifiULUS DOWriFLOW
! 1 l i . -START lOF REFLOOD (VALUES BELOW ARE FOR STEAM I ;
4, . , ss so ser v i .
- s6s a I
so 6. o 4 439\ sssp
- 93. 9 l I I L53. 9 sio 6. O MVJ9 ! Ls.sf4 i l 43.9 2./ssz.m i
J a. me /s' d4& i 2 493l i
I i
$J. 9 J. //7 U" 8s47 :
WWd6:
i O.22/' i :
j h5< f ./$b .2.$3 b h? .2. /Yf , l
. i ,
fd. f &fS i
?Y$l :
(kW0f: J fl7, l i
/'s3.f N624 h.7/8 i i
4429l ;
Y Bod i l I i t [2.d83 '
f2/ ' O.83d! '
l
@.; /JJ.9 2.62f6jl/'VJ. f L?. !o.ro v/ l l - l lJ.so&'!
l 9/.z l, l j'd 3. 9 ,2 c o r Y 2.4.?4l l Mn&'
i V 's.rs<? V ;
h]. f 0. E i E /$ . $)$ .X /db bY /0 3.8/l /$
Table A7 (cont'd) g y.~,-- ,- y s_ _ '
IllTEGRAL OF IllTEGP,AL OF
- TIME MASS FLOW EllERGY RELEASE ' .. ASS FLOW _ _ . EliERGY RELEASE .
SEC tDr)SEC BTU)SEC I LBM ! BkV j l I
, Jo3 9 2.co/ x / c = s . 6 2 /:x / or .y' 73.2 x /s' !s. ors !x /s a;
! i I
l l ! I JJ3 9 J.62'/ fdf/ W 7f.2 l [3 / ?.2 l ;
i 2+67 9! 2o35 l 7.ss4
.- +t8/3 &l/7f I h/3 9 2.dV.2 3.JXf f853 3229 IJ23 9 2,s'/3 J.476 -9'899' 3.28z 303,9 2o3.z 2.JJ.2 '/93s" 3 33&
!3?3 9 ls.ds3 s. 7s3 # 9 74 339o 3+G.9 2dd7 2. 70 8 56/7 . 'AJ JJ3. 9 s.scri e
sJ9/ 1sd9 l3. 9'98 VB3,9 J.s74 J. 7/ 9 &/60 3. s S z-0l '//3 9 L2s7 z V ,.,7x , \l x,szlV , ,. s s ,' V ;
I WJ3. 9 J.676 x /s 2 t
J. //2 x /oS &Jsb /o3 488 x /o " i i I
l 0 -
i~
l
..+.e ~ ~ . . . -
, - ~ . - - . . - - .
FICURE A-1/.
MhLST0:4E U;4lT 2 CYCLE 3 1.0 x DOUBLE ELIDED SLOT BREAK IN PUMP DISCilARGE LEG CORE P0llER l
1.2001 ,
1.0000 -
i
.8000 ,
i 03 5
" i k .6000 e
.4000
.2000 -
0.00000 o o o o a 8 8 8 8 8 8 9 8 9 9 3 o -< <a m n to.
TIME, SECONDS
FIGURE A-1B HILLSTONE UillT 2 CYCLE 3 1.0 x DOUBLE ErlDED SLOT BREAK Id PUMP DISCl!ARGE LEG PRESSURE Ill CEllTER fl0T ASSEMBLY WODE 2.4 .0-2000.0 1600.0 E
- 1200.0 E
E 800.0 400.0 0.0 o o c c 8 8 8 8 8 8 9 9 a a
Ja Jm Jm o to TIME, SECONDS
FIGURE A-1C llILLST0ilE UillT 2 CYCLE 3 1.0 x DOUBLE EilDED SLOT BREAK IN PUf1P DISCHARGE LEG LEAK FLOW 120000.
100000.
80000.
O C
5 N 60000.
Ei 5
d 40000.
N 20000, s 0
5 E S $ Z 0 TIME, SECONDS
FIGURE A-1D.1 tilLLST0iiE UillT 2 CYCLE 3 1.0 x DOUBLE EiiDED SLOT BREAK Ii1 PUMP DISCilARGE LEG FLOW Ill ll0T ASSEMBLY-PATH 16, BELOW li0T SPOT 30.000 20.000 ,
1
}
10.000 'l, "
W -
2 I
N 0.000 !
-10.000 i V
-20.000
-30.000 o o o a 8 8 8 8 8 8 5 5 $ $ $ $
TIME, SECONDS
FIGURE A-1D.2 HILLST0ilE UNIT 2 CYCLE 3 1.0 x DOUBLE EilDED SLOT BREAK Iil PUMP DISCHARGE LEG FL0ll IN HOT ASSEMBLY-PATH 17, AB0VE HOT SPOT 30.000 y i
1 l
20.000 I
't I
10.000 f3 l s
O.000
= a e -10.000
\e y
r
-20.000 l
-30.000 b b 5 E S 0 2 0 TIME, SECONDS
FIGUI!E A-lE lilLLST0i1E U:llT 2 CYCLE 3 1.0 x DOUBLE EilDED SLOT BREAK lil PUilP DISCHARGE LEG HOT ASSEilBLY OUALITY fl0DE 13, BELOW HOT SPOT
N0DE 114, AT HOT SPOT
- - - N0DE 15, AB0VE HOT SPOT 1.0000 , f
.8000
\l V '
[iI 1 \\ j i
- I Il //
, 'l I
ll
- i es
, \' / f
/
.6000 j i t f b i I /
E I '
/ ~' './
8 l '
.4000 J ' I.
\ \!'
I h
.2000 E l
D I
0.0000 a a a a 8 8 8 8 8 8 2 3 5 $ $ $
TIME, SECONDS
FIGURE A-1F MILLSTCl1E UrlIT 2 CYCLE 3 1.0 x DOUBLE EilDED SLOT BREAK lil PUMP DISCilARGE LEG C0i1TAliiMEi1T PRESSURE 60.000 50.000 40.000 d 30.000 8
23 o"_
20.000 10.000 0.000 a a o a a 8 9 9 9 9 9 J 8 Z (v) 8
+
o c- .-4 oJ TIME AFTER RUPTURE, SECONDS
FIGURE A-16 filLLST0flE UillT 2 CYCLE 3 1.0 x DOUBLE Ei1DED SLOT BREAK Irl PUI1P DISCHARGE LEG MASS ADDED TO CORE DURIilG REFLOOD 1
90000.
75000.
y ~ 60000.
u3 8
S 45000. /
S 8
30000. '
15000. .
0.
o g g g g 8 9 a a a J J 8 "; ;5 s
TIME AFTER C0f1 TACT, SECONDS
FIGURE A-lH NILLST0:1E U: LIT 2 CYCLE 3 1.0 x DOUBLE ElDED SLOT BREAK Ill PUilP DISCHARGE LEG PEAK CLAD TEMPERATURE 2200 x
2000 '
\
N 1800 1600
- - 1400 -,
E" 25 E 1200 '
g .
1000 800 600 400 0 140 280 420 560 700 840 9E:
TIME, SEC0llDS
FIGURE A-2A NILLSTONE UillT 2 CYCLE 3 0.8 x DOUBLE EilDED SLOT BREAK IN PUMP DISCliARGE LEG CORE POWER 1.2001 1.0000
.8000 83 i5 o_
p .6000 t5 r
.4000 l
.2000
\
a a 0.00000 o a o 8 8 8 8 8 8 9 9 9 9 9 9 + r>
a <a c>
o TIME, SECONDS
FIGURE A-2B MILLSTONE UillT 2 CYCLE 3 0.8 x DOUBLE EilDED SLOT BREAK lil PUI4P DISCilARGE LEG PRESSURE Ii1 CEilTER l10T ASSEMBLY l'10DE 2400.0 2000.0 1600.0 1 E
E 1200.0 0
E 800.0 x 400.0 3 0.0 a o a a S S S -
S S S 2 3 $ $ 5 $
TIME, SEC0t1DS.
FIGURE A-2C MILLSTOWE Ui1IT 2 CYCLE 3 0.8 x DOUBLE EilDED SLOT BREAK Iil PUMP DISCHARGE LEG LEAK FLOW 120000.
100000.
80000.
Ed l' R
S j 60000.
E cd 40000.
N 20000, s N
!S $
5 S Q Z E TIME, SECONDS
FIGURE A-2D.1 MILLST0rlE UillT 2 CYCLE 3 0.8 x DOUBLE EilDED SLOT BREAK Iii PUMP DISCilARGE LEG FLOW Ii1 Il0T ASSEMBLY-PATil 16, BEL 0\l ll0T SPOT 30.000 l l
20.000 i i
I
' I 10.000 d
, 0.000
= 'N of b -10.000 j
-20.000
-30.000 o o a o 8 8 8 8 8 8 2 3 5 5 5 $
TIME, SECONDS
FIGURE A-20.2 MILLST0;4E UiilT 2 CYCLE 3 0,8 x DOUBLE EWDED SLOT BREAK Iil PURP DISCHARGE LEG FLOW Ill HOT ASSEilBLY-PATH 17, AB0VE HOT SPOT 30.000 ll 20.000 i
i 10.000 f lIl hw R tl 0
N 0.000 fi
=
\ /b
-10.000 j,A[
-20.000
-30.000 a o a c 8 8 8 8 8 8 o $ $ $ $
TIME, SECONDS
FIGURE A-2E MILLST0i1E UtilT 2 CYCLE 3 0.8 x DOUBLE EiiDED SLOT BREAK Ii1 PUMP DISCHARGE LEG HOT ASSEMBLY QUALITY ,
N0DE 13, BELOW HOT SPOT
N0DE 14, AT HOT SPOT
- - N0DE 15, AB0VE H0T SP0T i 1.0000 i ', i
. l!
i I l 0 l 1.
l
' 'Il r j ii t
. .8000 .
iy vv i I is t t I I i
[ /
I ll; fx l /
.6000 ;
s, c -s v /
C l \s'
- /
C25 I I s *-
./
f
.4000 ; i-I \l#
I i ,
i !
.2000 I I . l l
0.0000 o o o a 8 8 8 8 8 8 b b b b b b TIME, SECONDS
FIGURE A-2F MILLST0ilE UilIT 2 CYCLE 3 0.8 x DOUBLE Ei10ED SLOT BREAK IN PUMP DISCHARGE LEG C0itTAlr1MEi1T PRESSURE 60.000 .
50.000 40.000 E
$ 30.000 is 20.000 10.000 0.000 a a o a o 8 9 9 9 9 9 J 8 Z 8 o m a cu m +
TIME AFTER RUPTURE, SECONDS
FIGURE A-2G filLLST0ilE U;11T 2 CYCLE 3 0.8 x DOUBLE EdDED SLOT BREAK lii PUMP DISCHARGE LEG flASS ADDED TO CORE DURIi16 REFLOOD I
l 90000.
75000.
b
~ !
60000. 1 en iS O 45000.
R i S
8 30000. '
l g i n i i
15000.
o 8 k k k k 5 8 Z 8 w a =
15000. .
e = = =
8 9 J J J J J 8 % Z W TIME AFTER CONTACT, SECONDS
FIGURE A-4H HILLST0,iE UillT 2 CYCLE 3 1.0 x DOUBLE EilDED GUILLOTI:lE BREAK I;l PUMP DISCHARGE LEG PEAK CLAD TEMPERATURE 2200 2000 N
N N
1800 1600 g- 14 0 0 -
0 0
g1200 ,
?
3 1000 800 600 400 0 140 280 420 560 700 840 98:
TIME, SEC0i1DS
FIGURE A-5A IllLLSTONE UNIT 2 CYCLE 3 0.8 x DOUBLE ENDED GUILLOTIllE BREAK IN PUflP DISCHARGE LEG CORE POWER 1.2001 1,0000 4
.8000 ,
6 -
B-
.G000 d
ts n
.4000 -
l I
k
.2000 j i
I 0.00000 o a o o o l
S S S S S S 8 8 8 8 8 o a w n 4 m flME, SECONDS
FIGURE A-5B HILLSTONE UilIT 2 CYCLE 3 0.8 x DOUBLE EllDED GUILLOTli1E BREAK lil PUMP DISCHARGE LEG PP,tSSURE Ill CEllTER HOT ASSEMBLY il0DE 2400.0 - - - - - - - - -
2000.0 1600.0 -- - --l- --
5 E
d 1200.0 0
E 800.0 --
1-400.0 - - - -
0.0 o g --- - ---- 5 a 8 8 8 8 8 8 2 3 $ $ $ $
TIME, SECONDS
FIGURE A-5C flILLST0i1E UillT 2 CYCLE 3 0.8 x DOUBLE EiiDED GUILLOTIi1E' BREAK lit PUMP DISCHARGE LEG LEAK FLOW PUMP SIDE REACTOR VESSEL SIDE j 120000.
100000.
80000.
U.
s B
N 60000.
5 '
E cd 40000. "' s
\s
's .
20000.
V 'x he_.
O. O c a o 8 8 8 8 8 8 Ja Ja Jw Jw o to TIME, SECONDS
FIGURE A-5D.1 MILLSTONE UillT 2 CYCLE 3 0.8 x DOUBLE ENDED GUILLOTINE BREAK lil PUMP DISCllARGE LEG FLOW Iil [10T ASSEflBLY-PATil 16, BEL 0ll HOT SPOT i
30.000 ,
l l
20.000
\l 10.000 R
5 0 000 '
% / -
-10.000
-20.000
-30.000 a a a g 8 8 8 8 8 8 8 8 a a a a w
o m a a a TIME, SECONDS
FIGURE A-5D,2 MILLST0r!E UillT 2 CYCLE 3 0.8 x DOUBLE EiiDED GUILLOTIi1E BREAK lil PUMP DISCllARGE LEG FLOW Ii1 HOT ASSEMBLY-PATH 17, AB0VE HOT SPOT 30.000 20.000 l i
4l 10.000 b
N 0.000
\
25 5
a hf d
-10.000
-20.000 j i
-30.000 a o a a 8 8 8 8 8.
8.
0 0 J J S Q Z U TIME, SECONDS
FIGURE A-5E (11LLST0ilE UillT 2 CYCLE 3 0,8 x DOUBLE EilDED GUILLOTIilE BREAK lil PUMP DISCHARGE LEG HOT ASSEllBLY QUALITY N0DE 13, BELOW HOT SPOT
N0DE 14, AT HOT SPOT
- N0DE 15, ABOVE HOT SPOT 1.0000 , , ,
i i ,
!i
' /!,
l
) i lI
!, Ii , ,
I /
.8000 Jl' l. 7 i-Ji ,
e' /
- i N ,' /
( s t' %- j I' ' '
.6000 7 ij b ['
I
)
/
y ; r, '
/
@ f I '
.4000 f \/
I
)
i
.2.000 ','
l)
?)
0.0000 o o a o 8 8 8 8 8 8" 9 9 Ja a Jw w o in TIME, SECONDS 8
FIGURE A-5F filLLST0i1E UillT 2 CYCLE 3 0.8 x DOUBLE EllDED GUILL0TIllE BREAK Ill PullP DISCliARGE LEG C0l1 Tali 1MEllT PRESSURE 60.000 50.000 40.000 Q 30.000 8
0 E
20.000 10.000 a 8 k k k k 3 5 8 8 8 8 o w a w m +
TIME AFTER RUPTURE, SECONDS
FIGURE A-5G MILLST0i1E UillT 2 CYCLE 3 0.8 x DOUBLE ENDED GUILLOTlilE BREAK Ill PUMP DISCHARGE LEG MASS ADDED TO CORE DURIi1G REFLOOD 90000.
75000.
$ 60000.
u3 -
b S 45000. !
S 8
g 30000. '
TIME (SEC) REFLOOD RATE 0.00-8.000 3.32 IN/SEC j 8.00-77.00 1.25 IN/SEC i 77.0-400.0 0.75 IN/SEC 15000. _
- 0. c c c c c
d 8 Z 8 o w a co m +
TIME AFTER CONTACT, SECONDS
1-lbukt /\ ' 11 HILLSTO.4E U!11T 2 CYCLE 3 0,0 x DOUBLE EilDED GUILLOTI.lE BREAK I.1 PUr.P DISCllARGE LEG PEAK CLAD TEP.PERATURE 2200 . -
2000 '[f' ,
N
~ N l ~
/ '%
i
~
~, '
x 1800 I,' ~~ _ ,
G '
l 1600 ,'
s PEAK CLAD TEMPERATURE fl0DE u_ ---- - RUPTURE il0DE 1400 o '
!d '
s ,l 25 ',
y 1200 h,+
$ il 11
]
O l'
ll 1000 *i l.
l.
It i.
800 t, -
l .
i f
600 400 0 140 280 420 560 700 840 98 TIME, SEC0 lids
FIGURE A-51 MILLSTONE UNIT 2 CYCLE 3 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG MID ANNULUS FLOW 15000. .
10000.
5000.
tu R
u2 b l ac
-5000.
-10000. gv
-15000. O o o a 8 8 8 8 8 8 1 5 $ b b b TIME, SECONDS
FIGURE A-5J MILLSTONE UtilT 2 CYCLE 3 0.8 x DOUBLE ENDED GUILLOTIf1E BREAK IN PUMP DISCilARGE LEG QUALITIES AB0VE Af1D BELOW THE CORE ABOVE THE CORE BELOW TiiE CORE 1.0000 , , ; ",; ,, ; , ,- ,, j e l,5, , f"
,' 1;l
.8000 ,
i s
1
.6000 ,' ,
g '
3 .
s' 1
.4000 Iji l .
y
/ ', ,
, i ,
.2000 '
,,/
s,
,s 0.0000 a a a a 8 8 8 8 8 8 b 5 b b b b TIME, SECONDS
s .
FIGURE A-5K MILLSTONE UNIT 2 CYCLE 3 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG CORE PRESSURE DROP 30.000 20 000 10.000 l,
G a_.
e :
I J l ,
O )\ 11 I \N f
[]
9 ny
=
iTI
" l
-10.000
-20.000 a a
-30.000 o a 8
8 8 8 8 8
2 3 TIME, SECONDS
FIGURE A-5L MILLST0llE UNIT 2 CYCLE 3 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG SAFETY INJECTIf4E FLOW If1TO INTACT DISCHARGE LEGS 7000 , , i l
l t
6000 - -
g 5000 - -
a a
4000 f
u_
5 p
u y
3000 - -
C
-t 2000 - -
1000 - -
0 ' ' ' '
0 20 40 60 80 100 TIME, SECONDS
FIGURE A-5M MILLST0f1E UNIT 2 CYCLE 3 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG WATER LEVEL IN DOWNCOMER DURING REFInon 18.000
( :- _ -:: _= - - -
12.000 ib ici 9.000 es .
CE
=c -
6.000 3.000 -
o 8" 8
3 m
Z m
8 o m .
TIME AFTER .C0t1 TACT, SECONDS
FIGURE A-Sil MILLST0flE UtilT 2 CYCLE 3 0,8 x DOUBLE ENDED GUILLOTIllE BREAK If4 PUFiP DISCliARGE H OT GAP CONDU UA E 900 800 700 u-c 600 a / ~
R E 500 / '
~ ~
m /
!5 5 '
$ 400 g
8 300 200 100 0
0 140 280 420 560 700 840 98 TIllE, SEC0f1DS
FibOHL A-bu MILLST0f1E UtilT 2 CYCLE 3 0.8 x DOUBLE Ef1DED GUILLOTIfiE BREAK Ill PUMP DISCHARGE PEAK LOCAL CLAD OXIDATI0ff 18
~~
1G 1 ,-
14 -
/
/
/
/
12 /
/
h PEAK CLAD TEMPERATURE liODE we
,' -- -- - RUPTURE fiODE
!$ 10 ,
5 I s '
- /
A 8 ' /
3"
/
i o
6 l
l t
4 j I
I I
2 '
O O 140 280 420 560 700 840 98L TIME, SEC0i1DS
FIGURE A-SP MILLST0tlE UtilT 2 CYCLE 3 0.8 x DOUBLE ENDED GUILLOTlilE BREAK lil PUMP DISCllARGE CLAD TEf1PERATURE, CErlTERLit1E FUEL TEf1PERATURE, AVERAGE FUELTEllPERATUREATIDC00LAtlTTEMPERATUREFORll0TTEST[10DE 4000 3500 3000 2500 FUEL C flTERLIr1E au o]
N g 2000 7 x_w%
g _ _
AVERAGE FUEL CLAD 1500 h
1000 C00LAt1T
\
500
\ \
0 -
0 140 280 420 560 700 840 98C TIME, SEC0tiDS
MILLST0llE UNIT 2 CYCLE 3 0.8 x DOUBLE EllDED GUILLOTIflE BREAK lli PU:lP DISCl1ARGE s 110T SPOT llEAT TRAt1SFER COEFFICIEilT 450 400 350 LL.
1 L1 J- 300 R
R m
P_5 0 s
LL d
8 g 200 Yi ik Q 150 W
100 t
50 0
0 140 280 420 560 700 840 98 TIME, SEC0 fids
FIGURE A-5R fin ' STONE UNIT 2 CYCLE 3 0.8 x DOUBLE ENDEL GUILLOTINE BREAK Ill PUMP DISCHARGE LEG LONTAINMENT TEMPERATURE 300.0 250.0 200.0 u
E 150.0 25 E
5 100.0 50.0 0.0 0 80 160 240 320 400 TIME, SECONDS
FIGURE A-5S MILLSTONE UtilT 2 CYCLE 3 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG SUMP TEMPERATURE 300.0 250.0 200.0 ['
O id y 150.0 5
100.0 50.0 0.0 0 80 160 240 320 400 TIME, SECONDS
FIGURE A-ST MILLSTONE Uf1IT 2 CYCLE 3 0.8 x DOUBLE ENDED GUILLOTINE BREAK Irl PUMP DISCHARGE LEG HOT R0D INTERNAL GAS PRESSURE 2000.0 N -P INITIAL = 1970.6 PSIA I I 1600.0 - - RUPTURE = 9.63 SEC
$ 1200.0 s
la
$ 800.0 400.0 0.0 --
0 20 40 60 80 100 TIME, SECONDS
FIGURE A-5U MILLSTONE UNIT 2 CYCLE 3 0,8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE CORE BULK CHANNEL FLOW RATE i
CORE INLET i
CORE EXIT !
30000.. - --
l p
20000.
I
('
10000. ;, - - - - - - - ---
o : i, W :(
s ! '.'
"M-y f w-5 d
-10000. --- -- - - - - ----
BULK CHANNEL REPRESENTS 98%
OF TOTAL CORE FLOW AREA
-20000.
-30000. O o o o 8 8 8 8 8 8 o
5 e
Ja Je Jm o
TIME, SECONDS
FIGURE A-6A iilLLST0ilE UillT 2 CYCLE 3 0.6 x DOUBLE EllDED GUILLOTIi1E BREAK Ill PUf1P DISCllARGE LEG CORE POWER 1.2001 1.0000
.8000 03 5
I .6000 R
.4000 t
.2000 0.0000o o o o o a 8 8 8 8 8 8 9 9 9 9 9 9 o a <u m + to TIME, SEC0tiDS
FIGURE A-6B HILLST0i1E UillT 2 CYCLE 3 0.6 x DOUBLE EllDED GUILLOTlilE BREAK I;1 PUI1P DISCHARGE LEG PRESSURE Ill CEilTER HOT ASSEMBLY N0DE 2400.0 2000.0
. 1600.0
<c -
E 1200.0 -
!O E
800.0 400.0
\
\
0.0 c o a o k k k k k k 5 5 S Q Z 0 TIME, SEC0f1DS
FIGURE A-6C MILLST0ilE UillT 2 CYCLE 3 0.6 x DOUBLE EilDED GUILLOTlilE BREAK lil PUMP DISCHARGE LEG LEAK FLOW PUMP SIDE i
- - - - REACTOR VESSEL SIDE 120000. ;
100000.
80000. ~
Ed R
N 60000.
s -
E if 40000.
's
\
20000. - .
s
~
'4 %___
0.
!5 !E S $ Z 0 TIME, SEC0flDS
FIGURE A-6D.1 fllLLST0ilE UilIT 2 CYCLE 3 0,6 x DOUBLE EilDED GUILLOTliiE BREAK IN PUMP DISCHARGE LEG FLOW lli HOT ASSEMBLY-PATH 16, BELOW HOT SPOT 30.000 20,,000 j 10.000 -
o d I s" i s 0.000 '
N l /W
= , il/
d -10.000
-20.000
-30.000 o o a o 8 8 8 8 8 8" 9 9 Ja Ja J w cu o m TIME, SECONDS
FI31RE A-6D.2 MILLSTONE Ui1IT 2 CYCLE 3 0.6 x DOUBLE EilDED GUILLOTINE BREAK Ill t' IMP DISCHARGE LEG FLOW Itr HOT ASSEl1BLY-PATil 17, AB0VF r;~ SPOT 30.000 20.000 10.000 ,
0.000
~
id
\/ b/ )
-10,,000
-20.000
-30.000 o a a a 8 8 8 8, 8 8 3 3 $ $ 5 $
TIME, SECONDS
FIGURE A-6E MILLST0ilE UdIT 2 CYCLE 3 0.6 x DOUBLE EilDED GUILLOTIi1E BREAK lil PUMP DISCHARGE LEG HOT-ASSEilBLY QUALITY I
N0DE 13, BELOW HOT SPOT j
N0DE 114, AT HOT SPOT
- - N0DE 15, AB0VE HOT SPOT 1.0000 , , si 1 f
,'i ,\
Il, \, ,! I' i ,
ll
!l i ', '
/I l
.8000 !( ii l
i' I l'* '
r Ii !
l*' n , 'n, ~
,~
l
.6000 Y . l
>- \ l 's *
/
C I,, h jl ;
'n' 7
$ In >
8 4 i r.s.-
I '
.4000 i I
\.t' l _
i l
.2000 l l}
0.0000 o o o a 8 8 8 8 8 8 3 3 $ $ $ $
TIME, SECONDS 4
FIGURE A-GF MILLSTO,1E Ui1IT 2 CYCLE 3 0.6 x DOUBLE EilDED GUILLOTlilE BREAK lti PUMP DIScilARGE LEG C0flTAINMEitT PRESSURE 60.000 50.000 40.000 W 30.000 u
a.
2.0.000 10.000 0 8 5 8 S Z 8 o m a w m
- TIME AFTER RUPTURE, SECONDS
FIGURE A-6G MILLST0;1E U:11T 2 CYCLE 3 0.6 x "OUBLE EilDED GUILLOTli1E BREAK lil PUMP DISCHARGE LEG MASS ADDED TO CORE DURI!!G REFLOOD 90000.
75000, y 60000.
el S
S 45000. '
S 8
g 30000.
15000. .
1 o
5 8 Z 8 e m a w m +
TIME AFTER CONTACT, SECONDS
t e FIGURE A-6H illLLSTONE U,;1T 2 CYCLE 3 0.6 > DOUBLE EllDED GUILL.0TIllE BREAK IW PUilP DISCHARGE LEG PEAK CLAD TEliPERATURE 2000. .
1800'
\ '
N
/
/ N 1600,
[y
^/ s s- 1400.
82
@1200.
b 3
" 1000, 800, 600.
400.
0 140 280 420 560 700 840 980 Ill1E, SECONDS
FIGURE A-7 MILLSTONE UNIT 2 CYCLE 3 PEAK CLAD TEMPERATURE vs BREAK AREA 2200. , , , , , , ,
O DISCHARGE LEG SLOTS AT 15.6 KW/FT o DISCHARGE LEG GUILLOTINES AT 15.6 KW/FT 2120. -
pg._ _ _ _ _ g a ,
d 2040. -
e
~
iE' i e
si '
5 i b 1960. -
a b
DISCHARGE LEG BREAKS _
1880. _
0.6 DE 0.8 DE 1.0 DE 1800.
0 2 4 6 8 10 12 14 16 BREAK AREA, FT2
FIGURE A-3 MILLSTONE UNIT 2 CYCLE 3 COMBItiED SPRAY Af4D SPILLAGE INTO CONTAINMENT 15000 , , , , , , i i 14000 -
13000 = 1 TANK SPILLING DIRECTLY INTO 12000 \ CONTAINMENT -
11000 -
_ 1. N -
s g 9000 x -
sg 8000 -
7000 g
f 6000 \ : EFFECTIVE ANNULUS SPILLAGE -
m 5000 x EFFECTIVE
\\ \ PUMP SPILLAGE 4000 -
\ x ~ - ~ ~ ;~ ~ ~ - -
llll \/ ///
SPRAY FLOW
//
~
e \
0 40 80 120 160 200 240 280 320 360 400 TIME AFTER BREAK, SEC