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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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Northeast 1 7 seiden swo Bew 06037 h Utilities System Nonheon vuuue. senw company P.O. Box 270 llanford, CT 06141-0270 i
(203) 665-5000 APR I 61996 Docket No. 50-423 B15648 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 3 Revised Source Term Time-of-Release Proposal Millstone Unit No. 3 is one of five pilot plants in the NEI/NRC initiative to develop industry guidelines for the implementation of the Revised Source Term (RST) for design basis radiological calculations. The Millstone Unit No. 3 license amendment request which will implement the time-of-release aspects of the RST is currently being finalized. However, Northeast Utilities believes it is beneficial to submit the initial dose calculation at this time for NRC review. This calculation is being submitted as part of the pilot plant application phase of the RST implementation project. We believe this approach is beneficial for the following reasons:
- The TACT III calculation of the public dose provides the source term and release assumptions that will be used in the '
habitability calculations for the control rooms and Technical Support Center. If the NRC has comments or recommended changes on the manner in which the RST timing assumptions were implemented in this calculation, it will affect the source term assumptions used in the habitability calculations.
Hence, timely NRC feedback is desired on this initial calculation before the other calculations are finalized and submitted with the future licensing amendment request.
- It will be one to two more months before all assessments and internal reviews of the Millstone Unit No. 3 license amendment request are complete. If our calculation was not. submitted until that time, it would delay any assessment of the timing-only application of the new source term. Since there are other plants interested in applying a timing-only option, any delay on our part would also delay all other interested utilities. The calculation provides all the necessary information for understanding how the RST is being applied on a timing-only basis. Hence, the NRC review will provide most of the assessment necessary to allow other applications of the RST timing-only option to begin.
9604220349 960416 PDR ADOCK 05000423 P PDR n., . m llool 220099 g
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! U.S. Nuclear Regulatory Commission B15648/Page 2 Attachment 1 presents a method of RST timing implementation that falls within the methods and philosophy proposed in NEI's Draft
- Framework Document for RST application. It is Northeast Utilities' perspective that the timing application method provided in l Attachment 1 is the optimum method for timing applications in that i it is simplistic, technically justifiable, and generically
- applicable. Simplistic and generic applicability are important in
] the minimization of NRC and utility resources for the review of j subsequent submittals using a time only approach.
l The calculations of the public dose at the Exclusion Area Boundary .
i and the Low Population Zone for the proposed application are !
3 complete and are included in Attachment 2. These calculations
! incorporate the revised source term timing assumptions and the j i proposed secondary containment drawdown times. The calculations I were performed using the TACT III code.
1 i Attachment 3 provides the preliminary results of supplemental I analyses for comparative purposes. These analyses are variations ,
. of the Attachment 2 analysis, presented to illustrate the effects l
- of the RST versus the current source term, separating out the I i effects of the change in drawdown time. The NRC requested this i type of comparison at the January 23, 1996, meeting with NEI.
Based on the above, we are requesting NRC review of Attachments 1 and 2. NRC approval will not be requested until the Millstone Unit No. 3 license application is submitted. However, we would appreciate feedback on the attached in a timely manner to help support justification of the other evaluations which must be performed and internally approved. We look forward to the opportunity to discuss this with you. If you have any questions please contact Mr. W. J. Temple at (860) 437-5904. If you desire, we would be pleased to meet with your Staff to discuss this matter. ,
1 very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY s_. l -
F. R. Dacimo Vice President - Nuclear Operationu Attachments cc: See Page 3
U.S. Nuclear Regulatory Commission B15648/Page 3 cc: T. T. Martin, Region I Administrator V. L. Rootley, NRC Project Manager, Millstone Unit No. 3 A. C. Carne, Senior Resident Inspector, Millstone Unit No. 3 l
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Docket No. 50-423 B15648 Attachment 1 Millstone Nuclear Power Station, Unit No. 3 Basic Assumptions of the Millstone 3 Pilot Plant Application April 1996
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l Basic Assumptions of the Millstone 3 Pilot Plant Application: Proposed Timing Extension of the TID-14844 Source Term l
The NEI/EPRI Source Term Task Force has prepared a Generic Framework for Application of Revised Source Term To Operating Plants IRef. 21 which outlines methods in which the new source term can be applied to existing light water reactor designs. Northeast Utilities (NU) is a supporter and active participant in this effort, and the Millstone 3 plant has been selected for pilot application.
l l The Millstone 3 pilot application will be a " timing only" type application. It is the intent here to apprise the NRC staff of some of the basic assumptions that NU believes l
l appropriate to use for this application. For convenience, and to distinguish them from other possible timing only proposals, we call these assumptions the " timing extension of the TID-14844 Source Term"(tex Source). The rationale behind the selection of these assumptions is also provided. In conjunction with the draft of the framework document l and task force discussions with the staff, we believe that this letter will provide adequate
- information for the staff to reach some preliminary conclusions as to the reasonableness of the assumptions. It is intended that the assumptions be generic enough that other NU !
nuclear units, and possibly other industry units, can use them for additional timing only applications.
NU recognizes that the staff needs a complete submittal to make a full detennination as to the acceptability of the timing extension proposal. With this letter we seek only to receive a preliminary indication of reasonabiness, prior to expending the significant resources required for a full licensing submittal.
Background
l Prior to the initiation of the NEI/EPRI effort, Northeast Utilities made a presentation to the ACRS which resulted in the following ACRS recommendation to the Commission:
l Information provided to the Committee suggests that the use of realistic timing .
! assumptionsfor radionuclide releases to the containment during accidents can lead to safety improvements in existing plants. We urge that the risk implications be evaluated and consideration be given to allowing current licensees the option ofusing the timing assumptions in the proposed source terms without performing a complete source terin reanalysis. (Ref. l}
The information presented here is the basis of the Millstone 3 pilot application for implementing the ACRS recommendation. The assumptions here are an implementation of and consistent with the Generic Framework for Application of Revised Source Term To Operating Plants, and much background information is covered there. Some i
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information is repeated here to provide a complete picture to those readers unfamiliar with the draft document.
l Current Source Term Timing Issues The present DB source term, TID-14844 as refined by Regulatory Guides 1.3 and 1.4, calls for instantaneous release of the source. This non-mechanistic assumption presumably was made with conservative intent given a sparsity of knowledge of source term mechanics. In practice, this assumption often causes designs and practices that are less than ideal in terms of safety and cost-benefit when applied to mechanistic design requirements. Some examples will illustrate this point.
Example 1: The control room at Millstone Unit 3 has a one-hour supply of pressurized air to maintain positive pressure post-accident. To meet the GDC19 limits with the current DB instantaneous plume the pressurized air system auto-initiates one minute following a safety injection signal. Unless the operator takes manual action the air supply is exhausted in one hour. Source term knowledge reflected in NUREG-1465 clearly shows that it is preferable to l have that system available for as much of the the major release period as l
possible, which would not start until at least t = 30 minutes. In addition, the 1 minute auto-initiation requirement increases the complexity of testing and maintaining the system.
l Example 2: This example deals with the loading of emergency diesel generators. Some systems are loaded onto diesel generators very early on the presumption that
! the source term is released at t=0. Consequently, the diesels are challenged unnecessarily early in an accident sequence. This early loading also adds maintenance and testing complexity and expense without a resultant safety benefit.
There are many other examples that exist, including containment spray start time and MOV closure time requirements, in which unrealistic timing assumptions result in non-conservative operational practices, An additional realistic safety consequence of these difficulties is increased worker exposure resulting from extended maintenance outages.
Timing Extension as an Option NUREG-1465 is generally recognized as the source tenn most reflective of current research and as providing a safe basis for licensing plants. It is also recognized that re-licensing all existing plants to NUREG-1465 is not cost-beneficial nor necessary for safety. The current TID-14844 source term remains a valid design basis; however, as noted above it suffers from deficiencies. The framework document [Ref. 2] notes that
! one of the ways to capture some of the benefits of the ofimproved source term knowledge is to implement a " timing only proposal."
The " timing extension"is a timing only proposal which is an extension of the current TID-14844 source term using more realistic release timing. The timing extension option l
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I is designed to be quickly applicable, that is, easily applied to existing plants and readily recognized as acceptable by regulators. It allows some of the benefits of new source term knowledge to be captured, but not as many of the possible benefits that would come with using some of the other, more complete approaches described in the framework document. It is recognized that the benefits captured using the timing extension may in i
many cases come at the cost of calculated off-site doses that are higher than those achievable with the full NUREG-1465 analysis.
The timing extension of the current source term has some significant benefits:
- Philosophically a direct extension of existing design basis, therefore easily understood.
- Modifies the current unrealistic timing assumption which is in some cases excessivley conservative, in others unconservative.
- Generic and universally applicable with one set of assumptions at all sites.
- Can be analyzed with existing codes and methods.
- Timing of the release is conservative with respect to NUREG-1465, i.e., all the activity for the major release period is completely released at the beginning of the period instead of gradually during the period.
- It is relatively inexpensive to apply to existing plants.
Timing Extension Defined The timing extemion of the TID-14844 source term changes the timing of the release.
The net release f ractions remain the same as the current design basis, e.g.,100% noble gases,50% iodines to the containment atmosphere and 1% of the solids to the coolant.
l The timing changes from one puff release at t=0 to two puff releases, the first a release of I the gap activity at t=30 seconds for PWR's (t=1 min for BWR's) post-accident, the second a puff release at t=30 minutes which releases the rest of the activity specified by the current source term. The first release is the gap phase release, using the timing identified in NUREG-1465. The proposed gap release fractions are 5% of the noble gases and iodines, consistent with NUREG-1465 as developed in the framework document (Ref. 2, Section 4 and Appendix B). The puff (" degraded fuel") release would consist of the current DB source term release less the already released 5% gap activity,i.e.,95% of the noble gases and 45% of the iodines.
Other aspects of the current design basis remain unchanged. The release form remains that specified in Reg. Guides 1.3 and 1.4. The dose calculation periods remain 0-2 hr for the EAB (the X/Q used for the degraded phase would the 0-2 hr X/Q) and 30 days for the LPZ. Credit for plateout ofiodines and sprays would remain as specified in SRP 6.5.2, Rev.2.
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Table I TID-14844 Timing Extension Source Term Releases Time of Release l (Releases are instantaneous puffs)
Long Term Cooling Long Term Cooling l Maintained Not Maintained l PWR BWR PWR BWR Coolant activity t=0 0 0 0 l Gap release: 5% noble gas 30 secs 1 min 0 0 (airborne) + 5% iodine (airborne)
Degraded core: 95% noble gas 30 mins 30 mins NA NA j (airborne) + 45% iodine (airborne) + 1% solids
! (liquid)
- Conclusions and Recommendations l Both existing source terms, NUREG-1465 and TID-14844, are of comparable magnitude to the proposed timing extension to TID-14844. Although details can be important, note that the differences between the source terms (e.g.,using the integrated release to containment as a measure, all are within a factor of 2) are greatly overshadowed by factor-of-10 conservatisms in other design basis analysis assumptions, such as meteorololgy. Especially note that the differences between the TID-14844 and the timing extended source term are very small. (For further discussion of this see the "
Attachment:
l Questions Related To The Timing Extended Source Term.") Using the timing extended l source term one can gain mechanistic safety and cost benefits that far outweigh any possible differences in the magnitude of the release. The same safety systems will be required but will be operated in a more mechanistic, safe, and cost-beneficial manner.
For example, control room bottled air sources can be conserved by starting them when they are most likely to be needed, when there is significant fuel failure, rather than at t -
0.
l It is for these reasons that we request that the timing extension to TID-14844 be given i preliminary approval as a source term for the NEI/ NU-Millstone 3 pilot plant project. As i discussed in the Oct 12,1995 NEI/NRC Revised Source Term meeting, it is hoped that this piece of the pilot proposal can be reviewed in parallel with the Generic Framework for Application of Revised Source Term 7; Operating Plants, and that preliminary approval can be granted in a short time.
f References l
- 1. Letter dated Sept. 20,1994, W. J. Lindblad, Vice-Chairman ACRS, to Ivan Selin, Chairman USNRC," Proposed Final Version of NUREG-1465, ' Accident Source Terms for Light-Water Nuclear Power Plants'"
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Attachment:
Questions Related To The Timing Extended Source Term During the development of the timing extended source term proposal some issues arose.
l These are presented below in a question and answer format.
Is this approach consistent with the Generic Framework for Acolication of Revised Source Term to Operatina Plants (Draft)? j l
j The framework document permits many approaches to applying the revised source l term. This timing extension is one example, using methods from the framework
! document.
How do we know that the timing extension is conservative?
Conservatism is difficult to define, and can be excessive. Also, there are now two l
, benchmarks to compare against: the TID-14844 and the NUREG-1465 source l l
terms, both of which are recognized as safe and acceptable bases for plant design.
As previously noted, the Reg. Guides 1.3 and 1.4 " conservative" assumption of instantaneous releases actually results in non-conservative plant designs. The timing extended source is very comparable to the other source terms.
l
[ A sometimes used measure of comparision is time integrated releases into l containment. How does the timing extended option compare?
As one might intuitively presume, the timing extension is a balance between the TID-14844 and the NUREG-1465 source terms. Note that the time-integrated i
release into containment is not the only or even the best measure of safety.
However, as one measure of reasonableness it is shown below that the timing extended time-integrated containment release is comparable to the NUREG-1465 and the TID-14844 sources.
Gap Activity For purposes of comparison one can arbitrarily divide the TlD-14844 source term into a gap release and a degraded core release, both occuring at t = 0. The gap fractions are taken to be 5% noble gas and 5% iodine. Doing so makes it easy to compare both the gap release and the more significant degraded core releases.
The timing extended source term uses the magnitude and start time of the NUREG-1465 gap release phase. The gap releases are seen to be similar for all three of the source terms. A relatively insignificant difference between the timing extended source and NUREG-1465 is that the gap release is a puff release instead l of the gradual release as specified in NUREG-1465. Given the relative magnitude i
of the gap activity versus the degraded core releases, the differences can be considered negligible.
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4 Degraded Core Activity
- The significant differences between NUREG-1465, TID-14844, and the timing extended sources exist in the degraded fuel release.
The noble gas portion of the timing extended degraded fuel release is of the same magnitude (95% after gap activity) as the TID-14844 and corresponding NUREG-1465 early in-vessel release. The difference here is that the timing extended 1
source is a puff release at t = 30 minutes. As shown in Table II, the timing extended term is " conservative" with repect to NUREG-1465 and slightly less
" conservative" than the TID-14844 time integrated noble gas source in containment.
- The iodines are also different in timing. The timing extended source is a puff at t=30 minutes of 45% of the core inventory.' The NUREG-1465 release is 35%
(=40% - 5% gap) for PWR's and 25% (=30% - 5%) for BWR's at a constant release rate. Using the development of Appendix A [Ref. 2], and examining the more conservative case of the PWR, one can express the iodine release for the l PWR NUREG-1465 as 35%*Mc, released at rate 35%*McfI'. For the simple case of no mechanistic removal (i.e., no sprays) and credit for 50% iodine instantaneous plateout, Table III shows that the timing extended time integrated releases are between the TID-14844 and the NUREG-1465 values. Note that the timing extended releases would have an even greater margin over the case of NUREG-1465 BWR's.
l l
Sprays complicate the analysis for iodines. Essentially when early releases take ;
place there is more material available for a longer time for removal, which somewhat offsets the earlier release time. (This argument is more completely i presented in Ref 2.) As sprays become more effective the NUREG-1465 source produces relatively larger values of integrated releases when compared to TID-14844. For the same conditions the timing extended source approximates the TID-14844 value.
Wouldn't the use of the full (including chemical form) NUREG-1465 source be more beneficial?
In most cases it is thought that one would calculate lower offsite doses. However, the benefit that we are seeking through the use of the timing extended source is quickly applicable realistic mechanistic design requirements, recognizing the cost of this may come in terms of dose. Also, implementing a full NUREG 1465 analysis may be cost prohibitive.
' Note that the NRC has recently indicated to NU that, contrary to SRP 6.5.2, Rev. 2, it cannot be assumed that both instantaneous plateout and spray removal be credited, but only one or the other. An earlier revision of this proposal incorporated iodine instantaneous plateout in containtnent as part of the proposal.
Here it is treated as one option.
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Table II Comparison of tex Degraded Core Noble Gas Releases Mc is the Mass Noble Gas Core Inventory 2
TID-14844 tex TID NUREG-1465 PWR Timing Time of Release 0 0.5 hrs 0.5 - 2 hrs, constant 3
Mass Released Noble Gas (less 5% gap) 95%
- Mc 95%*Mc 0-2hr Ctmt Integrated Release 95%Mc* 2 hrs 95%Mc* 1.5 hrs 95%Mc
Relative Integrated Releases 1.35 1 0.5 2
Timing Extended TID-14844 source term.
3 The TID-14844 source term is arbitrarily divided into a gap phase release and a degraded core release, all at t=0. This provides a common baseline for comparision.
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Table III Comparison of tex Degraded Core Iodine Releases Mc is the Mass Iodine Core Inventory 4
TID-14844 tex TID NUREG-1465 PWR Timing Time of Release 0, puff 0.5 hrs, puff 0.5 - 2 hrs, constant s
Mass Released lodine (less 5% gap) 45%
- Mc 35%*Mc Effective Total Mass Release 22.5%Mc 22.5%*Mc 35%*Mc No Mechanistic Removal Instantaneous Plateout 50% 50% 0 0-2hr Integrated Release to Ctmt 22.5%Mc* 2 hrs 22.5%Mc* 1.5 hrs 35%Me
Relative Integrated Releases 1.3 1 .8 i Spray Removal - Constant lambda's Mass in Containment, f(t) (t = t - 45%Mc
- 0.5 hrs for t >= 0.5) (1 - e*')
Integrated Release to Ctmt, f(t) (45%Me /1)(l- e*') (45%Mc / A)(l- e*') (35%Mc/T/A ) *
(T + (e '-1)/A) 0-2hr Relative Intecrated Release Case A = 1 1.1 1 0.5 Case A = 3 1.0 1 0.5 Case A = 5 1.0 1 0.6 Case A = 10 1.0 1 0.7 Case A = 20 1.0 1 0.8 4
Timing Extended TID-14844 source term.
' He TID-14844 source term is arbitrarily divided into a gap phase release and a degraded core release, all at t=0. His provides a common baseline for comparision.
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- 2. Generic Framework for Application of Revised Source Term to Operatinct Plants (Draft), EPRI Report TR-105909, Project 4080-2, November 1995.
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