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Category:CORRESPONDENCE-LETTERS
MONTHYEARDD-99-12, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 9910281999-10-28028 October 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 991028 ML20217N8261999-10-25025 October 1999 Discusses Errata Re 991021 Filing of Northeast Nuclear Energy Co Answer to Request for Hearing & Petition to Intervene B17901, Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)1999-10-18018 October 1999 Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6) B17886, Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 21999-10-18018 October 1999 Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 2 05000336/LER-1999-012, Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl B17900, Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 11999-10-14014 October 1999 Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 1 ML20217G9491999-10-14014 October 1999 Forwards Exemption from Requirements of 1-CFR50,App E, Section IV.F.2.c,re Conduct of full-participation Exercise in Sept 1999,at Plant,Units 1,2 & 3 ML20217D9671999-10-12012 October 1999 Forwards Copy of Transcript of Public Meeting Held by NRC Staff & NNECO on 990825 at Waterford,Connecticut on Decommissioning Program for Millstone,Unit 1.Without Encl ML20217D3011999-10-0707 October 1999 Forwards Request for Addl Info Re Util 990118 Request for Amend to License NPF-49 to Allow full-core Offloads to Spent Fuel Pool During Core Offloads to Spent Fuel Pool During Core Offload Events ML20217F0031999-10-0606 October 1999 Forwards Original Petition to Intervene Being Filed on Behalf of Clients,Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone,Iaw Provisions of 10CFR2.714 ML20217P1201999-10-0606 October 1999 Informs NRC of Proposed Acquisition of Parent Holding Company of Central Maine & Requests NRC Concurrence,Based on Threshold Review,That Proposed Acquisition Does Not,In Fact, Constitute Transfer Subject to 10CFR50.80 B17892, Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC1999-10-0505 October 1999 Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC ML20217B4711999-10-0404 October 1999 Informs That Staff Did Not Identify Any Safety Concerns Re Licensee Proposals to Modify Commitments Made for Action Items 4.2.1,4.2.2,4.5.1 & 4.5.2 of GL 83-28 by Providing Addl Justifications or Safety Bases for Changes ML20212K1241999-10-0101 October 1999 Responds to Recent Ltrs to Chairman Jackson,Commissioners & Wd Travers,Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performace of Millstone to Ensure That Public Health & Safety,Adequately Protected ML20212J3051999-10-0101 October 1999 Discusses GL 97-06 Re Degradation of SG Internals,Dtd 971230.GL Requested Each PWR Licensee to Submit Info That Will Enable NRC Staff to Verify Whether PWR SG Internals Comply & Conform to Current Licensing Basis for Facilities ML20212L2081999-10-0101 October 1999 Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance ML20212J9991999-10-0101 October 1999 Responds to Recent Ltr to President Clinton,H Clinton, Chairman Jackson &/Or Wd Travers Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performance of Plant to Ensure That Public Health & Safety Adequately Protected ML20212L1971999-10-0101 October 1999 Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety ML20212J2451999-10-0101 October 1999 Informs That Util 980807 & 990629 Responses to GL 98-01, Y2K Readiness of Computer Sys at NPPs Acceptable.Nrc Considers Subj GL to Be Closed for Units 2 &3 ML20212L1831999-10-0101 October 1999 Responds to Recent Ltr to Wd Travers Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Performance of Millstone to Ensure Adequate Protection to Public Health ML20212L2171999-10-0101 October 1999 Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island ML20217A9271999-09-30030 September 1999 Discusses Investigation Conducted at Millstone Nuclear Power Station by NRC OI Region I on 980319 to Determine If Contract Training Instructor Was Terminated for Raising Concerns About Quality of Training Matls ML20217B3221999-09-30030 September 1999 Refers to Investigation Rept 1-1997-035 Conducted at Millstone Nuclear Power Station by NRC Ofc of Investigation Field Ofc,Region I on 970915 to Determine Whether Former Health Physics Technician Discriminated Against ML20212J6621999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Units 2 & 3 on 990916.Identified Several Recent Instances in Which Condition Repts Were Not Initiated,Resulting in Untimely or Inadequate C/As.Historical Listing of Plant Issues Encl B17887, Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer1999-09-28028 September 1999 Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer ML20216J1341999-09-28028 September 1999 Ltr Contract:Task Order 49, Millstone Units 2 & 3 Employee Concerns Program Insp, Under Contract NRC-03-98-021 B17883, Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-62301999-09-27027 September 1999 Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-6230 B17890, Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-09-27027 September 1999 Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal B17888, Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 9909151999-09-24024 September 1999 Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 990915 B17884, Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-031999-09-24024 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-03 ML20212F4961999-09-20020 September 1999 Forwards Insp Repts 50-245/99-08,50-336/99-08 & 50-423/99-08 on 990615-0809.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs,Consistent with App C of Enforcement Policy 05000336/LER-1999-001, Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl B17867, Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports1999-09-17017 September 1999 Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports B17865, Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal1999-09-16016 September 1999 Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal B17876, Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant1999-09-16016 September 1999 Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant B17882, Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6) B17881, Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6) B17859, Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 9801281999-09-15015 September 1999 Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 980128 B17880, Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6) B17872, Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 11999-09-14014 September 1999 Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 1 ML20212A9011999-09-10010 September 1999 Forwards Environ Assessment & Finding of No Significant Impact Re Application for Exemption,Dtd 990803.Proposed Exemption Would Provide Relief from Requirement of 10CFR50 ML20212A3171999-09-10010 September 1999 Discusses Investigation Rept 1-1998-045 Conducted on 981112 to Determine If Former Senior Health Physics Technician Being Denied Employment at Millstone in Retaliation for Having Raised Safety Concerns in Past.Synopsis Encl B17838, Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls1999-09-10010 September 1999 Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls ML20212A7501999-09-10010 September 1999 Forwards Staff Requirements Memo Response,Dtd 990525,which Provides Actions NRC Plans for Continued Oversight of safety-conscious Work Environ & Employee Concerns Program ML20211J9291999-09-0303 September 1999 Forwards mark-ups & Retypes of Proposed Conforming License Changes Required in Connection with Transfers Being Sought in 990615 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests ML20211K5171999-09-0202 September 1999 Expresses Appreciation for Support Provided for NRC Public Meeting on 990825 05000336/LER-1999-010, Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 11999-09-0202 September 1999 Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 1 ML20216H0591999-09-0202 September 1999 Responds to Re Issues Submitted by Cullen on Behalf of Several Petitioners Concerning Offsite Emergency Prepardeness for Millstone Nuclear Power Station ML20211N9241999-09-0101 September 1999 Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures ML20211H0741999-08-30030 August 1999 Discusses GL 92-01,Rev 1, Rv Structural Integrity, Issued by NRC on 950519 & NNECO Responses for Millstone Unit 2 & 980715.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 Based on Response Review 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217N8261999-10-25025 October 1999 Discusses Errata Re 991021 Filing of Northeast Nuclear Energy Co Answer to Request for Hearing & Petition to Intervene B17886, Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 21999-10-18018 October 1999 Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 2 B17901, Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)1999-10-18018 October 1999 Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6) 05000336/LER-1999-012, Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl B17900, Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 11999-10-14014 October 1999 Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 1 ML20217P1201999-10-0606 October 1999 Informs NRC of Proposed Acquisition of Parent Holding Company of Central Maine & Requests NRC Concurrence,Based on Threshold Review,That Proposed Acquisition Does Not,In Fact, Constitute Transfer Subject to 10CFR50.80 ML20217F0031999-10-0606 October 1999 Forwards Original Petition to Intervene Being Filed on Behalf of Clients,Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone,Iaw Provisions of 10CFR2.714 B17892, Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC1999-10-0505 October 1999 Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC B17887, Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer1999-09-28028 September 1999 Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer B17883, Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-62301999-09-27027 September 1999 Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-6230 B17890, Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-09-27027 September 1999 Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal B17884, Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-031999-09-24024 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-03 B17888, Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 9909151999-09-24024 September 1999 Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 990915 05000336/LER-1999-001, Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl B17867, Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports1999-09-17017 September 1999 Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports B17876, Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant1999-09-16016 September 1999 Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant B17865, Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal1999-09-16016 September 1999 Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal B17881, Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6) B17880, Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6) B17859, Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 9801281999-09-15015 September 1999 Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 980128 B17882, Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6) B17872, Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 11999-09-14014 September 1999 Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 1 B17838, Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls1999-09-10010 September 1999 Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls ML20211J9291999-09-0303 September 1999 Forwards mark-ups & Retypes of Proposed Conforming License Changes Required in Connection with Transfers Being Sought in 990615 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests 05000336/LER-1999-010, Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 11999-09-0202 September 1999 Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 1 ML20216H0591999-09-0202 September 1999 Responds to Re Issues Submitted by Cullen on Behalf of Several Petitioners Concerning Offsite Emergency Prepardeness for Millstone Nuclear Power Station ML20211N9241999-09-0101 September 1999 Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures B17851, Forwards Semiannual fitness-for-duty Program Performance Data for 990101-990630 for Millstone Nuclear Power Station, Units 1,2 & 3,IAW 10CFR26.71(d)1999-08-27027 August 1999 Forwards Semiannual fitness-for-duty Program Performance Data for 990101-990630 for Millstone Nuclear Power Station, Units 1,2 & 3,IAW 10CFR26.71(d) B17855, Forwards NRC Forms 398 & 396 in Support of License Renewal for SRO TE Grilley,SOP-4053-04.Encl Withheld,Per 10CFR2.7901999-08-17017 August 1999 Forwards NRC Forms 398 & 396 in Support of License Renewal for SRO TE Grilley,SOP-4053-04.Encl Withheld,Per 10CFR2.790 B17849, Forwards Second Quarter Backlog Performance Rept for 1999, Which Represents Fourth Rept on Mnps Performance Since Restart of Unit 3 & First Status Update for Unit 2.No Regulatory Commitments Are Contained in Ltr1999-08-16016 August 1999 Forwards Second Quarter Backlog Performance Rept for 1999, Which Represents Fourth Rept on Mnps Performance Since Restart of Unit 3 & First Status Update for Unit 2.No Regulatory Commitments Are Contained in Ltr B17854, Forwards Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2,per TS 6.9.1.7.Revised Repts for May & June Also Encl Which Reflect Correct Faulty Printometer Readings1999-08-14014 August 1999 Forwards Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2,per TS 6.9.1.7.Revised Repts for May & June Also Encl Which Reflect Correct Faulty Printometer Readings B17850, Forwards First Lhc Quarterly Assessment Rept for Assessment Performed 990621 to 990701.NNECO Taking Appropriate Actions to Address Observations in Rept1999-08-11011 August 1999 Forwards First Lhc Quarterly Assessment Rept for Assessment Performed 990621 to 990701.NNECO Taking Appropriate Actions to Address Observations in Rept B17837, Forwards COLR for Cycle 7, for Millstone Unit 3,IAW TS 6.9.1.6.Explanation of Changes to COLR Also Encl1999-08-0707 August 1999 Forwards COLR for Cycle 7, for Millstone Unit 3,IAW TS 6.9.1.6.Explanation of Changes to COLR Also Encl B17657, Requests Schedular Exemption from Emergency Plan Exercise Requirements of 10CFR50,App E,Part Iv,Section F,Paragraph 2.c.Requests That Nrc/Fema Evaluated Exercise Be Conducted in Mar 2000 Rather than Sept 19991999-08-0303 August 1999 Requests Schedular Exemption from Emergency Plan Exercise Requirements of 10CFR50,App E,Part Iv,Section F,Paragraph 2.c.Requests That Nrc/Fema Evaluated Exercise Be Conducted in Mar 2000 Rather than Sept 1999 B17845, Forwards Revised Commitment for Surveillance Scheduling & Tracking.Options for Surveillance Scheduling & Tracking Methodologies to Be Incorporated in Standardized Station Surveillance Program Are Currently Being Reconsidered1999-08-0202 August 1999 Forwards Revised Commitment for Surveillance Scheduling & Tracking.Options for Surveillance Scheduling & Tracking Methodologies to Be Incorporated in Standardized Station Surveillance Program Are Currently Being Reconsidered B17831, Informs NRC Staff That Change 3 to Rev 25 of Mnps Emergency Plan Was Implemented on 990715.Change Removes Facility Organizational Charts from Emergency Plan & Identifies Relocation to Nuqap1999-07-26026 July 1999 Informs NRC Staff That Change 3 to Rev 25 of Mnps Emergency Plan Was Implemented on 990715.Change Removes Facility Organizational Charts from Emergency Plan & Identifies Relocation to Nuqap B17834, Forwards Proprietary Revised NRC Form 398,which Certifies That SL Doboe Has Completed Eligibility Requirements for Sro,Per 10CFR55.31.Proprietary Info Withheld1999-07-20020 July 1999 Forwards Proprietary Revised NRC Form 398,which Certifies That SL Doboe Has Completed Eligibility Requirements for Sro,Per 10CFR55.31.Proprietary Info Withheld B17836, Forwards Revised NRC Form 396 & Supporting Physician Rept for Licensed Operator Restricted from Licensed Duties, Effective 990628,due to Medical Condition.Without Encl1999-07-20020 July 1999 Forwards Revised NRC Form 396 & Supporting Physician Rept for Licensed Operator Restricted from Licensed Duties, Effective 990628,due to Medical Condition.Without Encl B17811, Submits Response to NRC AL 99-02,requesting That Licensees Provide Numerical Estimates of Licensing Actions to Be Expected to Be Submitted in Fy 2000 & 20011999-07-20020 July 1999 Submits Response to NRC AL 99-02,requesting That Licensees Provide Numerical Estimates of Licensing Actions to Be Expected to Be Submitted in Fy 2000 & 2001 ML20210S9911999-07-18018 July 1999 Requests NRC Intervene for All Shareholders of New England Electric System & to Help with Merger with National Grid Group & That NRC Petition Security & Exchange Commission to Investigate Matter Relative to No Shareholder Options B17835, Forwards Rev 33 to Millstone Station Physical Security Plan, Per 10CFR50.54(p)(2).Licensee Determined That Changes Do Not Decrease Effectiveness of Plan.Rev Withheld from Public Disclosure,Per 10CFR2.790(d)(1)1999-07-16016 July 1999 Forwards Rev 33 to Millstone Station Physical Security Plan, Per 10CFR50.54(p)(2).Licensee Determined That Changes Do Not Decrease Effectiveness of Plan.Rev Withheld from Public Disclosure,Per 10CFR2.790(d)(1) B17818, Provides NRC Staff with Change to TS Bases Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only.Change Was Reviewed & Approved by Unit 3 Plant Operations Review Committee IAW Provisions of 10CFR50.591999-07-16016 July 1999 Provides NRC Staff with Change to TS Bases Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only.Change Was Reviewed & Approved by Unit 3 Plant Operations Review Committee IAW Provisions of 10CFR50.59 B17824, Forwards Monthly Oeprating Rept for June 1999 & Revised Monthly Operating Rept for May 1999 for Millstone Unit 21999-07-13013 July 1999 Forwards Monthly Oeprating Rept for June 1999 & Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20212K1701999-07-13013 July 1999 Submits Concerns Re Millstone & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Should Provide Adequate Emergency Planning in Case of Radiological Accident B17816, Provides Certification That M Lettrich,Has Completed Eligibility Requirements,Per 10CFR55.31 for Operator License.Util Requests That Licensing Action Be Taken for Named Individual1999-07-0101 July 1999 Provides Certification That M Lettrich,Has Completed Eligibility Requirements,Per 10CFR55.31 for Operator License.Util Requests That Licensing Action Be Taken for Named Individual B17801, Forwards 10CFR50.59 Annual Rept for Period Jan-Dec 1998. Various Changes That Were Initiated in Previous Yrs & Completed in 1998,also Incorporated Into Annual Rept1999-06-30030 June 1999 Forwards 10CFR50.59 Annual Rept for Period Jan-Dec 1998. Various Changes That Were Initiated in Previous Yrs & Completed in 1998,also Incorporated Into Annual Rept B17819, Forwards Rev 17 to FSAR & Addendum 6 to Annual Rept.Nneco Recently Completed Review of Unit 2 Design & Licensing Bases Which Resulted in Changes to FSAR Provided in Encl 1.Encl 2 Includes Info Covering Changes Not Included in1999-06-30030 June 1999 Forwards Rev 17 to FSAR & Addendum 6 to Annual Rept.Nneco Recently Completed Review of Unit 2 Design & Licensing Bases Which Resulted in Changes to FSAR Provided in Encl 1.Encl 2 Includes Info Covering Changes Not Included in B17780, Forwards Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) TR, IAW 10CFR50.54(a)(3).Changes to TR Are Shown as Text in Bold Italics1999-06-30030 June 1999 Forwards Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) TR, IAW 10CFR50.54(a)(3).Changes to TR Are Shown as Text in Bold Italics B17723, Responds to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for Units 2 & 3 Encl.Without Encl1999-06-29029 June 1999 Responds to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for Units 2 & 3 Encl.Without Encl B17767, Forwards Rev 12 to FSAR & Addendum 3 to Annual Rept, for Millstone Unit 3,per 10CFR50.71(e) & 10CFR50.4(b)(6). No New Regulatory Commitments Contained in Ltr1999-06-29029 June 1999 Forwards Rev 12 to FSAR & Addendum 3 to Annual Rept, for Millstone Unit 3,per 10CFR50.71(e) & 10CFR50.4(b)(6). No New Regulatory Commitments Contained in Ltr 1999-09-03
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A8071990-09-11011 September 1990 Forwards Core Operating Limits Rept for Four & Three Loop Operation,Per Tech Spec 6.9.1.6.d A08900, Responds to Expressing NRC Views on Access to Util Internal or third-party Assessment Repts.Believes Internal Analysis to Support Amend of One of Util NRC OLs to Authorize Higher Power Level Is within NRC Purview & Access1990-09-11011 September 1990 Responds to Expressing NRC Views on Access to Util Internal or third-party Assessment Repts.Believes Internal Analysis to Support Amend of One of Util NRC OLs to Authorize Higher Power Level Is within NRC Purview & Access B13628, Forwards Correction to Error Discovered in Util 900727 Response to Notice of Violation from Insp Rept 50-336/90-09. Statement Corrected to Read That Contract Personnel That Have long-term Assignments,Certified as Testing Personnel1990-09-0707 September 1990 Forwards Correction to Error Discovered in Util 900727 Response to Notice of Violation from Insp Rept 50-336/90-09. Statement Corrected to Read That Contract Personnel That Have long-term Assignments,Certified as Testing Personnel B13624, Forwards Addl Info Re Relief Request from ASME Code Section XI Requirements for Temporary Repair to Piping Adjacent to Valve 2-SW-97A,per 900817 Telcon1990-09-0505 September 1990 Forwards Addl Info Re Relief Request from ASME Code Section XI Requirements for Temporary Repair to Piping Adjacent to Valve 2-SW-97A,per 900817 Telcon A08977, Advises of Commitment to Install Hardened Wetwell Vent at Facility,In Response to NRC .Util Will Be Proceeding W/Initial Design & Engineering of Hardened Vent, to Support Installation During 1993 Refueling Outage1990-09-0404 September 1990 Advises of Commitment to Install Hardened Wetwell Vent at Facility,In Response to NRC .Util Will Be Proceeding W/Initial Design & Engineering of Hardened Vent, to Support Installation During 1993 Refueling Outage B13626, Informs That Info Provided in Re safety-related Equipment Classification Programs Also Applicable for Unit 3 of Facility1990-08-31031 August 1990 Informs That Info Provided in Re safety-related Equipment Classification Programs Also Applicable for Unit 3 of Facility B13596, Forwards Millstone Unit 3 Individual Plant Exam for Severe Accident Vulnerabilities, Per Generic Ltr 88-20.Rept Identified That No Major Severe Accident Vulnerabilities Requiring Corrective Action Needed1990-08-31031 August 1990 Forwards Millstone Unit 3 Individual Plant Exam for Severe Accident Vulnerabilities, Per Generic Ltr 88-20.Rept Identified That No Major Severe Accident Vulnerabilities Requiring Corrective Action Needed B13618, Forwards Addl Info on Util 900815 Relief Request from ASME Code Section XI Requirements,Per 10CFR50.55a(g)(6)(i),for Repairs to Pipe 3SWP-006-050-031990-08-24024 August 1990 Forwards Addl Info on Util 900815 Relief Request from ASME Code Section XI Requirements,Per 10CFR50.55a(g)(6)(i),for Repairs to Pipe 3SWP-006-050-03 ML20059C2061990-08-23023 August 1990 Forwards Vols 1 & 2 to Semiannual Radioactive Effluents Release Rept Jan-June 1990, Per 10CFR50.36a.Rept Includes Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents A08918, Responds to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-245/90-08.Mitigation of Civil Penalty Requested.Corrective Action:List of Procedural Changes Provided1990-08-22022 August 1990 Responds to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-245/90-08.Mitigation of Civil Penalty Requested.Corrective Action:List of Procedural Changes Provided B13610, Requests Relief from ASME Boiler & Pressure Vessel Code Section XI Requirements Re Mods to Pipe 3SWP-006-050-03. Results of Insps & Required Repairs Will Determine Schedule for Future Insps1990-08-15015 August 1990 Requests Relief from ASME Boiler & Pressure Vessel Code Section XI Requirements Re Mods to Pipe 3SWP-006-050-03. Results of Insps & Required Repairs Will Determine Schedule for Future Insps B13595, Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-13941990-08-14014 August 1990 Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-1394 B13607, Requests Relief from ASME Code Section XI to Reflect Mod to Piping Adjacent to Valve 2-SW-97A,in Response to Generic Ltr 90-051990-08-10010 August 1990 Requests Relief from ASME Code Section XI to Reflect Mod to Piping Adjacent to Valve 2-SW-97A,in Response to Generic Ltr 90-05 A08845, Responds to NRC Backfit Analyses of Hardened Wetwell Vent, Contained in .Benefit of Installing Hardened Wetwell Vent to Satisfy Basic Design Objective of Preventing core-melt Event Not Sufficient for Immediate Decision1990-08-0808 August 1990 Responds to NRC Backfit Analyses of Hardened Wetwell Vent, Contained in .Benefit of Installing Hardened Wetwell Vent to Satisfy Basic Design Objective of Preventing core-melt Event Not Sufficient for Immediate Decision ML20058N2181990-08-0707 August 1990 Notification of Change in Senior Operator Status.Util Determined That Need to Maintain Senior OL of LS Allen No Longer Exists.Determination Effective 900719 ML20058M8321990-08-0707 August 1990 Discusses Spent Fuel Racks Poison Surveillance Coupon Boraflex Degradation.Visual Exam of Remaining Surveillance Coupons Revealed Similar Situation Existed in All Coupon Samples B13590, Responds to NRC 900718 Request for Addl Info Re Util 900418 Request for Schedular Exemption from 10CFR50,App E,Section IV.F.3 to Allow Dec 1990 Full Participation Exercise to Be Exchanged W/Oct 1991 Partial Participation Exercise1990-08-0101 August 1990 Responds to NRC 900718 Request for Addl Info Re Util 900418 Request for Schedular Exemption from 10CFR50,App E,Section IV.F.3 to Allow Dec 1990 Full Participation Exercise to Be Exchanged W/Oct 1991 Partial Participation Exercise A08881, Responds to NRC Re Violations Noted in Insp Rept 50-423/90-08.Corrective Action:Operators Directly Involved W/Event Removed from Licensed Duties & Counseled by Operations Manager on Causes of Event1990-07-31031 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-423/90-08.Corrective Action:Operators Directly Involved W/Event Removed from Licensed Duties & Counseled by Operations Manager on Causes of Event B13594, Forwards Rev 13 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21(b) & 2.790(a))1990-07-30030 July 1990 Forwards Rev 13 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21(b) & 2.790(a)) ML20055J4621990-07-27027 July 1990 Advises That Need to Maintain OL or Senior OL for Listed Individuals No Longer Exists,Effective 900701 A08565, Responds to NRC 900302 Request for Addl Info Re LPCI Swing Bus Transfer Design & Single Failure Vulnerabilities1990-07-26026 July 1990 Responds to NRC 900302 Request for Addl Info Re LPCI Swing Bus Transfer Design & Single Failure Vulnerabilities B13585, Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys1990-07-26026 July 1990 Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys B13592, Requests Extension to Respond to NRC Backfit Analyses of Hardened Wetwell Vent1990-07-24024 July 1990 Requests Extension to Respond to NRC Backfit Analyses of Hardened Wetwell Vent ML20063P9791990-07-23023 July 1990 Notification of Change in SL Jackson Status Effective 900701,due to Permanent Reassignment within Util B13566, Advises That Util Has Reasonable Assurance That Safety Relief Valves Operable & Will Perform as Expected Until Next Outage1990-07-20020 July 1990 Advises That Util Has Reasonable Assurance That Safety Relief Valves Operable & Will Perform as Expected Until Next Outage B13563, Discusses Util Comprehensive Review of Options Re Degraded Grid Undervoltage Protection.Confirms Previous Conclusion That Splitting Loss of Normal Power Logic Would Have Overall Adverse Impact on Plant Safety1990-07-20020 July 1990 Discusses Util Comprehensive Review of Options Re Degraded Grid Undervoltage Protection.Confirms Previous Conclusion That Splitting Loss of Normal Power Logic Would Have Overall Adverse Impact on Plant Safety ML20055G5331990-07-18018 July 1990 Forwards Decommissioning Financial Assurance Certification Rept A08822, Submits Addl Info Requested Re Util Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls. Charpy Impact Use Values for Welds Provided in Evaluation of Irradiated Capsule W-971990-07-18018 July 1990 Submits Addl Info Requested Re Util Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls. Charpy Impact Use Values for Welds Provided in Evaluation of Irradiated Capsule W-97 B13588, Corrects 900703 Submittal of Results of Second in-cycle Insp of Steam Generators.All Tubes W/Cracks Stacked & Plugged1990-07-18018 July 1990 Corrects 900703 Submittal of Results of Second in-cycle Insp of Steam Generators.All Tubes W/Cracks Stacked & Plugged B13587, Requests Temporary Waiver of Compliance from Tech Spec 3.5.F.2 Re Emergency Diesel Generator (EDG) Limiting Condition for Operation.Waiver Would Extend Available Time to Repair Damaged Electrical Components1990-07-16016 July 1990 Requests Temporary Waiver of Compliance from Tech Spec 3.5.F.2 Re Emergency Diesel Generator (EDG) Limiting Condition for Operation.Waiver Would Extend Available Time to Repair Damaged Electrical Components ML20055D3461990-07-0303 July 1990 Responds to NRC Bulletin 90-001 Re Loss of Fill Oil Transmitters Mfg by Rosemount.Operability Determinations Performed & Documented for All Rosemount 1153 & 1154 Transmitters at Facility ML20055D3481990-06-29029 June 1990 Forwards Addl Info Re Facility Crdr & Isap,Including Justification for Human Engineering Discrepancies Dispositioned for No Corrective Action ML20055D7191990-06-29029 June 1990 Amends 900604 Rev 13 to QA Program B13545, Forwards Rev 3 to Updated FSAR for Millstone Unit 31990-06-29029 June 1990 Forwards Rev 3 to Updated FSAR for Millstone Unit 3 B13550, Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl1990-06-27027 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl B13499, Forwards Corrected Tech Specs Page 3/4 9-1 for Incorporation Into Proposed Amend 36 to License DPR-21 Re Auxiliary Electrical Sys1990-06-26026 June 1990 Forwards Corrected Tech Specs Page 3/4 9-1 for Incorporation Into Proposed Amend 36 to License DPR-21 Re Auxiliary Electrical Sys ML20043F8721990-06-11011 June 1990 Corrects Name of Vendor Supplying Replacement Plug Valves, Per Util 900511 Ltr.Replacement Bolts,Not Valves,Purchased from Cardinal Industrial Products Corp ML20043H0161990-06-0808 June 1990 Requests Exemption from App J to 10CFR50 for 12 Valves in Reactor Bldg Closed Cooling Water Sys.Valves Not within Definition of Containment Isolation Valves in App J & Not Required to Be Tested ML20043E8831990-06-0505 June 1990 Requests NRC Authorization to Use Plugs Fabricated of nickel-chromium-iron Uns N-06690 Matl Alloy 690 to Plug Tubes in Steam Generators of Plant ML20043D0451990-05-30030 May 1990 Discusses Proposed Rev to Tech Specs Re Facility ESF Actuation Sys Instrumentation Trip Setpoint,Per 900330 Ltr ML20042H0311990-05-0909 May 1990 Discusses Steam Generator Safety Assessment.Concludes That Continued Operation Through Remainder of Current Cycle 10 Fully Justified ML20042F0941990-04-30030 April 1990 Provides Addl Info Re Environ Impact of 900226 Application for Amend to License NPF-49,revising Tech Specs to Allow Containment Pressure to Increase to 14 Psia During Modes 1-4,per NRC Request ML20042F0661990-04-30030 April 1990 Responds to NRC 900404 Ltr Re Violations Noted in Safety Insp Rept 50-336/90-01 on 900120-0305.Corrective Action:Ler 90-004 Submitted on 900430 to Document Condition Prohibited by Plant Tech Specs ML20042E8331990-04-27027 April 1990 Forwards Annual Environ Protection Plan Operating Rept for 1989, & Monitoring Marine Environ of Long Island Sound at Millstone Nuclear Power Station Annual Rept 1989. ML20012E2681990-03-23023 March 1990 Responds to NRC 900226 Ltr Re Violations Noted in Insp Rept 50-423/89-23.Corrective Actions:Requirement to Review All Changes on Safety Sys for Potential Operating Procedure Changes Stressed to Operations & Engineering Personnel ML20012C3141990-03-13013 March 1990 Forwards Info Re Insp of Facility Emergency Operating Procedures,Per 900119 Ltr ML20012B4111990-03-0202 March 1990 Provides Addl Info Requested to Clarify Changes Proposed to Tech Spec Action Statements for Inoperable Accumulator B13453, Advises That Mods to Steam Generator Blowdown Sample Sys Completed,Per Violations Noted in Insp Rept 50-423/89-14 & Salp.Sys Will Be Evaluated for Next 2 Wks to Ensure Blowdown Radiation Monitor Operating Reliably1990-02-26026 February 1990 Advises That Mods to Steam Generator Blowdown Sample Sys Completed,Per Violations Noted in Insp Rept 50-423/89-14 & Salp.Sys Will Be Evaluated for Next 2 Wks to Ensure Blowdown Radiation Monitor Operating Reliably ML20011F7541990-02-26026 February 1990 Notifies That Jh Parillo Reassigned & No Longer in Need of License SOP-10263-2 as of 900219 ML20006G1581990-02-21021 February 1990 Forwards Response to & Comments on Initial SALP Rept 50-423/88-99 for Period 880601 - 891015.Procedures Revised to Permit Operators to Adjust Area Monitors to Reduce Nuisance Alarms 1990-09-07
[Table view] |
Text
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,,,, umou sa., as m. cww General Offices
- Seiden Street, Berlin, Connecticut 9 meia .=amn atomc (*= P.O. BOX 270 m.ou weuoma c""" HAnTFORD, CONNECTICUT 06141-0270 k k ] C $,,",I',C.~', (203) 66s-5000
{l' October 7,1987 Docket No. 50-423 B12700 Re: 10CFR51
. U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555
References:
- 1. Millstone Nuclear Power Station Unit No. 3 Environmental Report, Operating License Stage, Vol. 2, Section 5.1.3.3, October 29,1982.
- 2. Final Environmental Statement related to the operation of Millstone Nuclear Power Station, Unit No. 3, U. S. Nuclear Regulatory Commission, December 1984.
Gentlemen:
Millstone Nuclear Power Station,~ Unit No. 3 Unit No. 3 Environmental Report - Operating License Stage In Reference (1), Northeast Nuclear Energy Company (NNECO) described three methods of assessing three-unit impact of the Millstone Nuclear Power Station (MNPS) on the winter flounder. These findings were included in Reference (2) by the NRC. The first two involve so-called " equivalent-adult" calculations and the third is a deterministic impact assessment model developed specifically for the {
determination of MNPS impacts.
During recent discussions between NNECO and te Connecticut Department of l Environmental Protection Marine Fisheries Office, the latter noted an apparent ;
error in a mortality coefficient used in the second of the two equivalent-adult i methods. The purpose of this letter is to correct that error using the proper j mortality coefficient with more current data than available at the time i References (1) and (2) were completed. The revised calculations are included in Attachment 1. An evaluation of the equivalent-adult method of impact assessment is also included (Appendix to Attachment 1) to provide a perspective on its reliability.
NNECO believes that the deterministic model used in References 1 and 2 I provides the best and most appropriate measure of impact and the conclusions reached on the basis of this model remain in effect. A conservative potential f
reduction of 5' to 6% in Niantic River winter flounder population size was projected to occur af ter 35 years of three-unit MNPS operation, followed by a recovery to within 1% of the equilibrium population level af ter an additional 65 l years.
8710140194 871007 g Ogl PDR ADOCK 05000423
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, , . B12700/Page 2 4 4. i October 7,1987-9, w > -
. , +" If 6 you~ havej any questions .concerning this submittal, please call Mr. Paul M. .
- 4. /, . , '
, = 3acobson, Manager, Northeast Utilities Environmental Laboratory, at (203) 444-4239.
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'Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY j /
f1 ,
EMpr~oczka (/
p; (, Senior Vice President
-cc:- Mr. Charles Fredette 6 *
. Department of Environmental Protection
< , . Water Compliance Unit
'122 Washington Street
- Hartford, CT
,4
. Mr. Eric Smith .
Department of Environmental Protection
-Marine Fisheries' Office
- ,,
- Waterford, CT 06385 Mi. Richard Barlow,' Director .
Water Compliance Unit 71 '.. '
' Department of Environmental Protection 4
165 Capitol Avenue
, ,, Hartford, Connecticut 06115
> Mr. Stanley J. Modzelesky s
- Administrative Assistant Connecticut Siting Council
' l Central Park Plaza New Britain, Connecticut 06051 W. T. Russell, Region I Administrator R. L. Ferguson, NRC Project Manager, Millstone Unit No. 3
- > .W. 3. Raymond, Resident inspector, Millstone Unit No. 3-
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t Docket No. 50-423 B12700
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9 Attachment 1 Millstone Unit No. 3 Equivalent - Adult Revised Calculation October,1987 i
4 l Docket No. 50-423 k'
B12700 Attachment 1 Millstone Unit No. 3 Equivalent - Adult Revised Calculation
,\
October,1987
1 y-EQUIVALENT-ADULT REVISED CALCULATION-f E
The potential impact of 3 unit operation at Millstone Nuclear Power Station (MNPS) on the Niantic River winter Counder population was' assessed by three methods in the " Millstone Nuclear Power Station Unit 3 Environment Report Operating Iicense Stage" (NUSCo 1983; pages 5.149 through 5.1-63) submitted to the Nuclear Regulatory Commission in 1983. The three assessment methods were:
the equivalent-adult method of Ilorst (1975), a modified equivalent adult method (Goodyear 1978), and a detenninistic model involving both hydrodynamic and population projcetion submodels (lless et al.
1975). -The second of these methods was the direct conversion of larval entrainment to equivalent adults using the length frequency distribution of entrained larvac classified into 0.5-mm size classes.- The estimated natural larval mortality per 0.5 mm of length increment was applied to each size-class to detennine equivalent juvenile loss due to entrainmenti After estimating the equivalent. juveniles entrained, juvenile and adult mortality rates from the literature were used to calculate the equivalent age 4 adult loss. In doing so, the juvenile monthly mortality rate of 0.30 (Pearcy 1962) was mistakenly used as
. a survival rate in the calculations resulting in the underestimation of the equivalent-adults.
The present document presents the results of a new assessment of larval entrainment using the same
~ method with updated larval entrainment data (1976-85) and recent mortality estimates directly derived from our data on the Niantic River winter flounder population. The equivalent adult method of impact assessment and its assumptions are also discussed in light of what we now know about the local winter flounder population. The methods and infornmtion used for the revised calculation are provided in an appendix.
I,ife table of the Niantic River winter floimder population Ikjuivalent-adult calculations require mortality rates for various life history stages. The most recent estimates of these rates for the Niantic River winter flounder are given in Tabic 1. Mortality rates that were directly derived from our data on the Niantic River population include mortality from hatching through stage 3 larvac (3 mm through 7 mm), juvenile mortality during the first 150 days (May through September), and annual mortality rates of age 2 and 3 fish. The methods and data used I
.a Table 1. Curre.it life table for Niantic River winter flounder population.
Mortality Rates Stage or I) oration Cumulative Percent (7.) (7) Cumulative Age-class (dnys) days I)nily I)aily Total Total Mort.
I gg 15 15 - -
1.628" h
I.nrval stnFen 1.2, & 3 55 70 4,59 .047 2.5R3 G1 (3 to 7 mm) 1,arval singe 4 10 R0 3.25 .033' O.330 (7 to 9 mm) h Juvenile i 150 230 1.9 .019 2.R 50 d
Juvenile il 135 365 1.2 .012 1.639 9.030 Age 1 365 -
.53 .005 1.930' h
Age 2 365 -
.20 .002 0.725 h
Ae3F 365 --
.20 .002 0.725 12.410 Total mortality (7.) from egg to nge 4 = 12.41 , , , ,
2 Mnximum nilowable (7) for n vinble population: -log, ; = 12.41 J.
Menn fecundity (/) - 490,l00 eggi per female I
- lislimnted as the difl'erence between 7, = 12.41 nnd the total (7) from hatching to age 4 h
lislimated from our datn on the Ninntic Itiver winter flounder (see Appendix)
- I!stimnted by linent interpolation between the daily (/rs corresponding in stage 3 and juvenile 1.
d I:stinmted by linent interpolation between the dnity (7)'s corresponding to juvenile I and age 1.
- I)erived by llean et al. (1975)
I Fstimated fiom our data (see Appendix Tnble 2) 2
to estimate these rates are provided in the Appendix. Rates that were estimated by linear interpolation between the daily instantaneous mortality (7.) of the preceding and sueeceding life-history stages were stage 4 larvae (7 to 9 mm) and juveniles during their last 135 days of development. The annual mortality rate of age i fish was from liess et al. (1975). Total mortality from spawning to the age where the fecundily is equivalent to the mean population fecundity (f) must not exceed the instantaneous mortality calculHed as: , , , ,
2 Zt " " IDEE :-
J.
for the population to remain viable (llorst 1975). Therefore egg mortality rate or hatching success was estimated as the difference between the maximum allowable total mortality of 7, = 12.41 (Table
- 1) and the total mortality from hatching through age 3 adults. Ilceause the estirnated population mean fecundity of 490,l00 eggs per female spawner corresponds to the mean fecundity of a 4.3 year ohl fish .i (see Appendix Table 2), choosing age 3 fish as the cut off point in the life table was conservative.
Equivalent-adult calculation for 3-unit entrainment The average annual entrainment of larval winter flounder under 3-unit operation was estimated as 175 million distributed according to the length-frequency distribution shown in Table 2. Supporting .
i information on entrainment estimation, entrainment mortality, and length-frequency distribution are j provided in the Appendix. lintrainment loss in Table 2 represents larval mortality due to entrainment.
This mortality was estimated as 100% for larvac in the 3.0. to 7.0-mm size classes (stages I, 2, and
- 3) and as 20% for the 7.5- to 9.0-mm size-classes (stage 4). 1.arval instantaneous mortalities per unit time (Table 1) were converted to the following mortalities per 0.5 mm of length increment: 0.287 for the 3.0- to 7.0-mm size-classes and 0.0825 for the 7.5- to 9.0-mm size-classes. The application of these mortality rates to the 175 million entrained larvac results in an equivalent loss of 40.686 million of i newly recruited juveniles, which in turn are equivalent to 456,980 age 1, 66,330 age 2, 32,123 age 3, or 15,559 age 4 fish.
1 i l
\
\
I
Table 2. Estimated winter flounder entrainment anIl equivalent juvenile recruits.
Number l'ntrainment Total Z to - Juvenile Sire- entrained loss juvenile equivalents
'6 class (x 10 ') (x 10 ) recruitment (x .10 ')
3.0 15.312 15.312 2.913 0.832 3.5 13.971. I3.971 2.626 0.794 4.0 12.R26 12.826 2.339 1.237 4.5 14.415 14.415 2.052 1.85; 5.0 . 19.817 19.817 1.765 3.392 5.5 19.604 19.604 1.47R 4.472 6.0 21.l l0 21.110 1.191 6.416 6.5 22.013 22.013 0.904. R.9I 4 7.0 17.661 17.661 0.617 9 529 7.5 11.039 2.208 0.330 1,587 8.0 6.440 1.288 0.24R 1.006 R.5 2.926 0.5R5 0.165 0.496
! 9.0 0.866 0.173 0.083 0.159 l
l 40.686 "
" Juvenile recruits are equivalent to: 456,980 age 1, 66,330 nye 2, 32,125 nFe 3, and 15,559 #Fe 4 lish.
l l
l 4
L__________. s
4 t
L Discussion The assessment method known as equivalent-adult (llorst 1975) providos " worst case' approximated projections of adult fish lost as a result of larval mortality caused by entrainment. The method uses the probability of natural survival of the larvae to extrapolate the number of ' equivalent" adults that the entrained larvae could have contributed to the spawning stock. The three major assumptions of this methodology are that the population is at equilibrium, that recruitment is strictly proportional to the parent stock, and that the probability of natural survival for the entrained larvae is known. A discussion of how well the equivalent-adult method and its assumptions apply to assessing larval
~
entrainment at MNPS follows.
The direct extrapolation of equivalent adult fish from the annual estimates of larvae entrained at MNPS leads to unreasonable predictions of adult fish losses because the assumptions for such extrapolation do not apply to the Niantic Iliver winter flounder. I;irst of all, the method must assume that larvac in the vicinity of the plant intakes (in Niantic Ilay) cither wouhl be able to find their way into the Niantic itiver or would survive to become adults at the same rate as larvac in the Niantic Iliver. The fate of larvae found in the northern portion of Niantic Ilay (likely to be susceptible to entrainment),
was investigated by liess et al. (1975) using a model of tidal circulation and larval dispersal. They found that only 25% of the initial numbers were left after only four tidal cycles and that the loss was due to tidal flushing offshore in a net castward movement through Twotree Island Channel. This compares to 85% of the larvae in the Niantic River remaining there after four tidal cycles. Thm findings suggest that, relative to the Niantic River, the Niantic Ilay has poor larval retention characteristics, g likely resulting in a high loss of larvae from the llay. Although it could be argued that hydrodynamic (
modeling may not apply well to all larval stages, liess et at (1975) validated the model predictions through dye studies and the model assumptions should at least apply to early larvae (stages I and 2),
which account for an average 33% of the total annual entrainment at MNPS. 1. ate larvae (stages 3 and 4) exhibit a diel behavior (NUSCo 1987) which could make them less susceptible to tidal Gushing.
Ilowever, substantial numbers of these larvae may still drift offshore during the time they are in the water column at night. It would also seem reasonable to expect substantially lower survival rates in the flay for late stage larvae that are not flushed ofTshore and for emly juvenile fish than in the Niantie Itiver nursery area. Therefore, the direct extrapolation from entrained larvae to equivalent aduhs, couhl
'W 5
4
L , .'
]
he used to assess entrainment at MNPS only after adjusting total entrainment for potential losses duc -
to flushing out of the Ilay and to higher natural mortality for the larvae remaining there. 3 The estimated 92 million stage 3 larvae (56% of 175 million) entrained annually under 3-unit operation is equivalent throagh backcalculation to about 3 billion spawed eggs. This production requires about 6,200 adult females. Although it seems possible that some of the entrained larvae might have been spawned in areas west of Niantic Ilay, the above number of 6,200 required spawners is not large 1 i enough to invalidate the assumption of the Niantic iliver as the major source of entrained stage 3 larvae at MNPS. This is not inconsistent with the findings of Iless et al. (1975), who indicated that reganlless nf plant operation, almut 4% of the larvac hatched in the river were flushed out of the system in each tidal cycle. Over 80 tidal cycles (about 40 days, the approximate development time from hatching through stage 2), as much as 96.18% of the initial larval production could become available for entrainment or lost ofTshore.
Although not as critical for extremely conservative impact assessments, the assumptions of equilibrium population and recruitment proportional to parent stock are not met either. There is new evidence suggesting that recruitment of Niantic River winter flounder (Fig.1) is very sensitive to water temper-atures following spawning (February and March), and that recruitment rates are also negatively alTeeted by large parent stocks which produce large initial numbers of larvac. This infonnation was acquired recently through the analysis of possible stock-recruitment relationships and it further supports our contention that equivalent adult calculations will not provide valid assessments of larval entrainment at M NPS.
In summary, two equivalent-adult methods and a population and hydrodynamics modeling approach were used in NUSCo (1983) to assess the impact of larval entrainment on the Niantic Iliver winter flounder. An examination of the assumptions inherent of the equivalent-adult methodology suggests that direct extrapolation from total numbers of entrained larvae to adult fish is not appropriate for estimating impacts at MNPS. The most problematic features of the method are that it i: mores the larval dispersion patterns from Niantic Ilay and that it assumes equal probabilities of survival for larvae ,
in the Ilay and in the Niantic Iliver nursery area. Ily contrast, the impact assessment model developed by the University of Ithode Island (lless et al. 1975) accounts for the different larval retention characteristics of the llay and the Itiver and simulates larval losses with and without plant operation ;
6 I
i
\
25-R = 4.058
D , -~~~
's, ,'
l ca, s ,
N 16- /
I h /
p ,'
- A s (5 l [ j / 's *&,, #4 s / ,
- 4,,, 's 0, 10* j ,s** ,5 m m, * %
~
% 0, 9
e x l/ ,-
l' +c;. . ~.
.;%;r:s,or 's
. tha[o~v,,~ ,-
I r
/e/ ,
/ e,,s.~,,,m~~ s,~%e , ,%o,fe S. ! , . ,~,'
,t,/ ,',' . potor,'~ ,,, ,
t
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~_
l 0 ,' , , , _ , , ,
o S 10 15 20 25 30 35 40 PARENT STOCK INDEX l'igure I, Prr timinary stock-recruitment relationship for the Niantic River winter ununder population from 1979 through 19R6 data.
' 7
e to produce more realistic impact estimates. This modeling approach was independently reviewed by flatelle Nonhwest I.,boratories (Thomas et al.1978) and found adequate for the problem at hand given the model assumptions and information available at the time. NUSCO believes that the projections of this model, which included the cumulative impact of entrainment losses over the expected
- lifetime of MNPS, continue to be the most reliable assessment. Ilecause the error in the equivalent-adult calculations had no efTect on the impact projections from the model (5-6% reduction in population size after 35 years of plant operation), the conclusions reached in the Environmental Report (NtJSCo 1983) remain unchanged.
A stochastic impact assessment model including the latest information available on the stock-recruitment relationship of the Niantic River winter flounder is currently under development by NtJSCO. This model will be coupled with a Probabilistic Risk Analysis submodel to assess the effect of environmental variability on the model impact projections over the lifetime of MNPS. The model will also simulate j the dynamics of the winter flounder population under various regimes of postulated annual larval losses due to entrainment. The determination of larval mortality rates, which require reliable larval aging methods, continue to be an important research goal at NtJSCO. In addition, we have plans for investigating the feasibility of using new methods for larval stock identification and for assessing the successful metamorphosis and viability of winter flounder larvac in the Niantic Ilay.
REFERENCES CITED I
Goodyear, P.C. 1978. lintrainment impact estimates using the equivalent adult approach. I J.S .
1:ish and Wddlife Service, FWS/OllS 78/65/ July 197814 p.
liess, K.W., M.P. Sissenwine, and S.II. Saila. 1975. Simulating the impact of entrainment of winter I
flounder larvac. Pages 1-30 in S.II. S,ila, ed. Fisheries and energy production: a symposium.
Irxington Ilooks, D.C. IIcath and Co., Irxington, M A.
Ilorst, J.T. 1975. The assessment of impact due to entrainment of ichthyoplankton. Pages 105-118 I in S.II. Saila, ed. Fisheries and energy production: a symposium. lxxington Ilooks, D.C. IIcath and Co., lexington, MA.
8 l
8i' t 8 i
I Northeast Utilities Service Company 1983. Millstone Nuclear Power Station Unit 3 environmental report. ~ Operating license stage. Vol. 1-4.
1987. Monitoring the mariste environment of long Island Sound at Millstone Nuclear l'ower Station, Waterford, Connecticut. Summary of studies prior to Unit 3 operation.
Pearcy, W.G. 1962. Ecology of an estuarine population of winter flounder Pseudor/curonectes americanus (Walbaum). Ilull. Ilingham Oceanogr. Coll. 18(1):1-78.
Thomas, .I.M., J.A. Mahaffey, K.L Gore, and D.G. Watson. 1978. Statistical methods used to assess biological impact at nuclear power plants. J. Environ. Mgt. 7:269-290. 1 i
I l
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I 4
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9 1
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APPENDIX i
Larval mortality rates .
Mortality rates of larval winter flounder were estimated from data collected in the Niantic River.
Starting in 1983, three stations in the River were sampled twice weekly during the occurrence of winter flounder larvac. Data frort 1983 were excluded as smaller larvac were undersampled because of net extrusion (N11SCo 1987). Examination of the length-frequency distribution of farvac collected in the River (three stations combined) showed that larvae in the 3.0-mm size class were most frequently collected (Appendix Itig. I). Mean length at hatching for laboratory reared larvac was 2.94 tr.m (SE= 0.017; n = 160) (NUSCo 1987). Therefore, the number of larvac in the 3.0-mm and smaller-size classes were used as an abundance index of newly hatched larvac. The rapid decline in the frequency of larvae in the 3.5. and 4.0 mm size-classes was attributed to both natural mortality and tidal flushing from the River. Tidal studies conducted in the Niantic River suggested that older larvac (stages 3 and
- 4) utilize vertical migration in relation to tidal How to enter the river and those within the river use a similar behavior to remain there (NUSCo 1987). The increasing frequency of larvae in the 6.0- to 7.0-mm size-classes can be at least partially attributed to this behavior. The number of larvae in the 7 mm size class was used as an abundance index of laivac nearing the end of stage 3 development.
Survival rate from hatching through stage 3 was estimated as the ratio of the abundance index of the 7.0-mm si7c-class larvae to the abimdance ndex of the 3.0 mm and smaller size-classes larvae.
2 The abundance of young larvac in the River is reduced due to tidal flushing to the ik.f. Although fless et al (1975) estimated the loss of larvae from the entire river as 4% per tidal cycle, they also ;
determined that the loss from the lower portion of the river was about 28% per tidal cycle. Therefore, the 6aily abundance estimates of larvac in the 3.0-mm and smaller size-classes at the station located in I the lower portion of the River were increased by a factor of 1.93 to compensate for the 28% decline l per tidal cycle with two cycles per day. The abundance index for newly hatched larvae, after adjustment j for tidal Gushing, and for larvac in the 7.0 mm si7e class were calculated by summing the mean weekly abundance (three stations combined) during each larval season. Total larval mortality through stage 3 in 1984,19RS, and 1986 ranged frmn 84.59% to 96.91% (Appendix Table 1). These total mortality rates represent a mean instantaneous rate (Z) of 2.583. Since estimated developmental time from j hatching throue.h stage 3 was 55 days, the daily instantaneous mortality was estimated as Z = 0.047. I j 10 l
I f
l- ------------- _ i
Y NIANTIC RIVER 1984 20' Y . '
5 o
i-b : o U- . A 10- "
, y)4
. . 7 o.,
2.0
,_ 5.
2.5 30 3.5-
_e __
4.0 4.5 50 5.5 60 2_
5.5 7.0 7.5 80 8.5 N90 LENGTH (MM) 40-NIANTIC RIVER 1985
<! 30-g s ,
Q 20-M : ..,
d . t 10-
,1ggji 20 2.5 30 35 ELEEEEEbEBL_
4,0 4.5 50 b.S 60 6.b 7.0 7,5 80 85 90 1.ENGTH (MM)
Appendix 17igure 1. l.cngth-frequency distribution by 0.5-men sire classes collected in the Niantic River (<tations combined)in 1984 through 1986.
I1 .
i, .
t h
l l
NIANTIC RIVER 1986 !
30-r 20*
Y
,e i b
o '
i 1 - i 10- , L gf l b< . ..
n 2.0 2.5 30 35 4. 0 4.5 50 5.5 60 6.5 7.0 7.5 B.0 8.5 90 y LENGTH (MM) i 1
1 Appendix Figure 1. Cont.
12
4 L\
F Appendix larval winter flounder abundance indices from the Niantic River and estimated Table i rnortality rates from haiching to 7 ram.
Abundance Index Newly 7.0-mm Year hatched size-class Mortality (%) Z 1984 7,005 635 90.94 2.401 1985 13,733 424 96.91 3.478 , . ,
1986 2,459 379 84.59 1.870 ..
mean = 2.583 }.
I 1
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l
l These larval mortality rates are only preliminary estimates until additional aging information is available
. and new simulation studies are conducted to better estimate tidal flushing rates. Previous attempts to age larvac by examining otoliths with a light microscope weic not successful, but an improved technique i
developed at 11niversity of Rhode Island '(Dr. A. Durbin, personal communication) may allow the use of otoliths to age winter flounder larvac.
Post-larval mortality rates Survival rate of metamorphosed young-of-the-year winter flounder from May through September was determined using catch curves with estimated abundance at a station in the lower Niantic River during 1983,1984, and 1985 (Appendix Fig. 2). Monthly survival rate estimates ranged from 0.552 to 0.569 during those three years. The mean of the monthly instantaneous mortality rates was used to estimate i the average daily mortality of Z = 0.019 for the ISO-day period covered by the catch curves. !
Annual survival rate of age I winter flounder was derived by liess et al. (1975) as Si 2 0.1454, which i
corresponds to an instantaneous mortality rate of Z = 1.93. We have used this estimate in all our j calculations because the catch data of Niantic River age i flounder are not adequate for mortality estimation purposes (NtJSCo 1987).
Survival rate of adult (age 2+) Niantic River winter flounder was estimated using two catch curves with age and abundance data taken during the years 1978-79 and 198183 (Appendix Fig. 3). Neither catch curve included data from 1980 because of inconsistencies found during their analysis (NtJSCo 1987). The mean of the two annual instantaneous mortality rates was Z = 0.725, which was equivalent to m annual survival rate of 0.484. This estimate included both natural and fishing mortalities.
i Population nican fecundity i
A length-fecundity relationship for winter flounder was determined in 1977 using 48 females taken in i the Niantic River. This relationship was expressed as:
2 11ccundity = 0.08238 (length in em)* (r = 0.81) l l
l l
14 l
7; j_ ' 's
! a
- - 1983 - LR r --
E ~4-3 2
z
e o 3- i m
- c. * .;
$ Z = 0.137 2 *
$ S (weekly) = 0.872
$ S (monthly) = 0.552 5 r2= 0.60 1-MAY JUNE JULY AUGUST SEPTEMBER 1984 - LR Gr 4-2a w
Z = 0.132 *
$ 2 *
$ S (weekly) = 0.876 , , {
[5 S (rnenthly) == 0.564 r2 = 0.79
- 1-MAY JUNE JULY AUGUST SEPTEMBER Appendix Figure 2. Mortality determined by catch curve for Niantic River young winter flounder from 19R3 through 1980.
l l
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15 l
\
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G 4-x W
2 W
x a
k 3'
C y x
6 Z = 0.120 ,
S (weekly) = 0.878 l
5 S (menthly) = 0.569
-E r2= 0.23 ,
1-MAY JUNE JULY AUGUST Sr r idASER i 1
Appendix l'igure 2. Cont.
16
ed 1978 -79 8*
7- ,N ,
6*
n =
5 ca - 5' 1
o .
bC
~
4~
- Z = 0.657 I S = 0.518 l 3- A = 0.482 r2= 0.96 2-3 4 5 6 7 8 9 10 AGE 1981-83 10' 9- .
a
- g. .
7-2 "
$ 6-s ,
=
z T._ 5-Z = 0.793 4- S = 0.453 A = 0.547 3' r2 , o,91 2-4 5 6 7 8 9 10 3
AGE Appendix l'i Fure 3. Mortality determined by catch curve for Ninntic River adult winter flounder from 1978 79 and 19RI-83.
17
Population mean fecundity was calculated for Niantic River winter flounder as shown in Appendix Table 2. Annual survival rates for adult flounder were applied to an arbitrary initial number of 1,000 age 1 Osh to obtain the age-distribution for the population at equilibrium. The survival rate of 0.1454 (lless et al.1975) was used through age'l to obtain numbers in age 2 and the annual rate of 0.484 given above was applied to obtain numbers of fish in age classes 3 through 12. Age I and 2 females j were not mature and thus did not produce any eggs. Ilased on length-frequency distributions, an estimated 50% of age 3, 80% of age 4, and all older females were mature. The length-fecundity relationship given above was used with mean lengths-at age for females to estimate mean fecundity by age. Fgg production for each age-class was then determined by multiplying the age-specific fecundity value by the number of reproductive fish in cach age-class. Appendix Table 2 shows that about one-half of the eggs are produced by age 4 and 5 females and another one-quarter by fish 6 and 7 years old. The population mean fecundity of 490,100 was determined by dividing total egg production by the number of mature fish. This fecundity is equivalent to that of a 4.3 year old female fish.
)
Entrainment estimation IIntrainment estimates are based on sampics collected at discharges of MNPS Units 1 and 2 (18 samples per week in 1975-82 and 8 samples per week in 1983-85). Generally, winter flounder larvac are entrained from late February through the end of .fune with greatest densities from mid April through May. The entrainment estimates were obtained by multiplying the median entrainment density per unit volume during the larval entrainment season times the total water volume passed through MNPS during the same period. The larval entrainment season was defined as the period corresponding to 95% of the annual cumulative abundance which was determined by excluding the sampling dates that provided the first and last 2.5% of the cumulative entrainment over the entire entrainment period.
Restricting the season in this manner reduced the number of zero-valued data points in the tails of the time series of data used in the median calculations. The median of the data distribution was used instead of the arithmetic mean because the data were highly skewed and the mean wouhl not adequately describe central tendency. A nonparametric method (Snedecor and Cochran 1980) was used to construct 95% confidence intervals for cach median density and corresponding entrainment estimate. )
t l
Annual entrainment estimates are available from 1975 through 1985 (Appendix Table 3) during the operational period of Units I and 2. The average annual entrainment estimate during this period was IR l
Appendix Table 2. Niantic River winter flounder mean fecundily calculation.
Population I) distribution Distribution of Percent b h age Fraction of mature Fecundity egg production Contribution (eggs x 10') (eggs x 10*)
Age distribution" mature Osh by age-class I 1000.00 0.0 0.0 0.0 0.0 0.0 2 145.15 0.0 0.0 0.0 0.0 0.0 3 70.30 0.50 35.15 173.1 6,084.5 13.17 4 34.05 0.80 27.24 413.9 11,274.6 24.40 5 16.49 1.0 16.49 673.2 11,101.1 24.03 6 7.99 1.0 7.99 880.6 7.036.0 15.23 7 3.87 1.0 3.87 1,216.6 4,708.2 10.19 8 1.87 1.0 1.87 1,507.4 2,818.8 6.10 9 0.907 1.0 0.907 1,849.6 1,677.6 3.63 10 0.439 1.0 0.439 1,908.8 83A.0 1.81 11 0.213 1.0 0.213 2,052.5 437.2 0.95 12 0.103 I.0 0.103 2,160.2 222.5 ( 48 1 l 94.27 46,198.5 100.0 3
Population Mean Fecundity = 46,198.4 x 10 - 94.27 = 490,100 eggs per female spawner .
'For equilibrium population and the annual survival rates from the life table.
l bl )crived from our data.
l l
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f 19
Appendix Yearly median densitics (n per 500 m 3) of winter flounder larvac in entrainment Table 3. samples during their season of occurrence and annual entrainment estimates with 95% confidence intervals for MNPS Units 1 and 2 from 1976 through 1985.
l l Year Median 95% Cl II, stimate (x106 ) a 95% CI (x10 6) 1976 158.0 114.2-185.I 95.5 69.0-111.9 1977 68.3 54.5-96.3 30.9 24.7-43.6 I978 86.6 65.0-106.4 58.4 43.8-71.7 1979 90.3 69.7-108.4 36.6 28.2-43.9 1980 201.5 163.6-234.6 140.I i 13.7-163. I 198l 139.2 99.3-182.6 47.6 33.9-62.4 1982 183.5 147.5-215.I 137.1 I I0.3- 160.7 1983 244.4 'I58.1-314.8 172.9 111.9 222.6 1984 185.5 107.5-226.2 90.0 52.2-109.8 1985 107.1 78.8-149.5 65.9 48.5-92.1
- 1'he average entrainment for the 10 year period was 87.5 million larvac.
20
87.5 million winter flounder larvac. To assess the potential impact of three-unit operation, this estimate was doubled to 175 million because the water passed through Unit 3 is about the same as the combined volumes used by Units 1 and 2.
I!ntrainment data collected from 1983 through 1985 were examined for developmental stage composition and length-frequency distribution by 0.5-mm size-classes (Appendix Fig. 4). The percentages of larvac entrained were: 2% for stage 1, 31% for stage 2, 56% for stage 3, and 11% for stage 4. Almost 70% of the entrained larvac were in the 5-mm and larger size-classes. A comparison of developmental stage and size-class showed that stage I and 2 larvac were primarily in the 3.0- to 4.5-mm size classes, stage 3 in the 5.0 to 7.0-mm size-classes, and stage 4 in the 7.5-mm and larger size-classes.
i Winter flounder entrainment mortality studies were conducted in 1983 on larvae that had passed through i the plant (Nt1SCo 1987). No stage I larvac were collected during the study. All stage 2 and 3 larvat j were dead at the time of collection or within a 24-hour latent mortality period. Of the 24 stage 4 i larvac collected 19 (79%) survived a 96-hour latent mortality period. Therefore, when assessing the impact of winter flounder entrainment 100% mortality was assumed for all stage 1, 2, and 3 larvac, but only 20% mortality for stage 4 larvae, APPENDIX REFERENCES CITED Iless, K.W., M.P. Sissenwine, and S.II. Saila. 1975. Simulating the impact of entrainment of winter flounder larvac, Pages 1-30 i_n S.B. Saila, ed. Fisheries and energy production: a symposium. D.C.
IIcath and Co., icxington, MA.
Northeast titilities Service Company. 1983. Millstone Nuclear Power Station Unit 3 environmental report. Operating license stage. Vol. 1-4.
Snedecor, G.W., and W.C. Cochran. 1980. Statistical methods (7th Edition). The Iowa State University Press, Ames, I A. 507 pp.
21
m;;[
13' 12' E
b /
3 . .,
10-9-
g 8'
@ 7-g 5, ;d
,,#j 8-2 L E- wn.
3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 ' 7.0 7.5 8.0 8.5 9.0 LENGTH (MM)
STAGE. 1 2 3 4 Appendix Figure 4. percernge of winter flounder larvae entrained in each 0.5-mm size-class by developmental stage in 1983 thtough 1985.
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1 22
___ _ _ _ _ _ . _ _