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Category:CORRESPONDENCE-LETTERS
MONTHYEARDD-99-12, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 9910281999-10-28028 October 1999
Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 991028
ML20217N8261999-10-25025 October 1999
Discusses Errata Re 991021 Filing of Northeast Nuclear Energy Co Answer to Request for Hearing & Petition to Intervene
B17901, Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)1999-10-18018 October 1999
Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)
B17886, Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 21999-10-18018 October 1999
Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 2
05000336/LER-1999-012, Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl1999-10-15015 October 1999
Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl
B17900, Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 11999-10-14014 October 1999
Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 1
ML20217G9491999-10-14014 October 1999
Forwards Exemption from Requirements of 1-CFR50,App E, Section IV.F.2.c,re Conduct of full-participation Exercise in Sept 1999,at Plant,Units 1,2 & 3
ML20217D9671999-10-12012 October 1999
Forwards Copy of Transcript of Public Meeting Held by NRC Staff & NNECO on 990825 at Waterford,Connecticut on Decommissioning Program for Millstone,Unit 1.Without Encl
ML20217D3011999-10-0707 October 1999
Forwards Request for Addl Info Re Util 990118 Request for Amend to License NPF-49 to Allow full-core Offloads to Spent Fuel Pool During Core Offloads to Spent Fuel Pool During Core Offload Events
ML20217F0031999-10-0606 October 1999
Forwards Original Petition to Intervene Being Filed on Behalf of Clients,Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone,Iaw Provisions of 10CFR2.714
ML20217P1201999-10-0606 October 1999
Informs NRC of Proposed Acquisition of Parent Holding Company of Central Maine & Requests NRC Concurrence,Based on Threshold Review,That Proposed Acquisition Does Not,In Fact, Constitute Transfer Subject to 10CFR50.80
B17892, Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC1999-10-0505 October 1999
Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC
ML20217B4711999-10-0404 October 1999
Informs That Staff Did Not Identify Any Safety Concerns Re Licensee Proposals to Modify Commitments Made for Action Items 4.2.1,4.2.2,4.5.1 & 4.5.2 of GL 83-28 by Providing Addl Justifications or Safety Bases for Changes
ML20212K1241999-10-0101 October 1999
Responds to Recent Ltrs to Chairman Jackson,Commissioners & Wd Travers,Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performace of Millstone to Ensure That Public Health & Safety,Adequately Protected
ML20212J3051999-10-0101 October 1999
Discusses GL 97-06 Re Degradation of SG Internals,Dtd 971230.GL Requested Each PWR Licensee to Submit Info That Will Enable NRC Staff to Verify Whether PWR SG Internals Comply & Conform to Current Licensing Basis for Facilities
ML20212L2081999-10-0101 October 1999
Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance
ML20212J9991999-10-0101 October 1999
Responds to Recent Ltr to President Clinton,H Clinton, Chairman Jackson &/Or Wd Travers Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performance of Plant to Ensure That Public Health & Safety Adequately Protected
ML20212L1971999-10-0101 October 1999
Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety
ML20212J2451999-10-0101 October 1999
Informs That Util 980807 & 990629 Responses to GL 98-01, Y2K Readiness of Computer Sys at NPPs Acceptable.Nrc Considers Subj GL to Be Closed for Units 2 &3
ML20212L1831999-10-0101 October 1999
Responds to Recent Ltr to Wd Travers Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Performance of Millstone to Ensure Adequate Protection to Public Health
ML20212L2171999-10-0101 October 1999
Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island
ML20217A9271999-09-30030 September 1999
Discusses Investigation Conducted at Millstone Nuclear Power Station by NRC OI Region I on 980319 to Determine If Contract Training Instructor Was Terminated for Raising Concerns About Quality of Training Matls
ML20217B3221999-09-30030 September 1999
Refers to Investigation Rept 1-1997-035 Conducted at Millstone Nuclear Power Station by NRC Ofc of Investigation Field Ofc,Region I on 970915 to Determine Whether Former Health Physics Technician Discriminated Against
ML20212J6621999-09-30030 September 1999
Informs of Completion of mid-cycle PPR of Units 2 & 3 on 990916.Identified Several Recent Instances in Which Condition Repts Were Not Initiated,Resulting in Untimely or Inadequate C/As.Historical Listing of Plant Issues Encl
B17887, Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer1999-09-28028 September 1999
Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer
ML20216J1341999-09-28028 September 1999
Ltr Contract:Task Order 49, Millstone Units 2 & 3 Employee Concerns Program Insp, Under Contract NRC-03-98-021
B17883, Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-62301999-09-27027 September 1999
Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-6230
B17890, Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-09-27027 September 1999
Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal
B17888, Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 9909151999-09-24024 September 1999
Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 990915
B17884, Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-031999-09-24024 September 1999
Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-03
ML20212F4961999-09-20020 September 1999
Forwards Insp Repts 50-245/99-08,50-336/99-08 & 50-423/99-08 on 990615-0809.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs,Consistent with App C of Enforcement Policy
05000336/LER-1999-001, Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl1999-09-20020 September 1999
Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl
B17867, Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports1999-09-17017 September 1999
Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports
B17865, Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal1999-09-16016 September 1999
Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal
B17876, Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant1999-09-16016 September 1999
Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant
B17882, Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999
Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6)
B17881, Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999
Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6)
B17859, Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 9801281999-09-15015 September 1999
Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 980128
B17880, Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999
Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6)
B17872, Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 11999-09-14014 September 1999
Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 1
ML20212A9011999-09-10010 September 1999
Forwards Environ Assessment & Finding of No Significant Impact Re Application for Exemption,Dtd 990803.Proposed Exemption Would Provide Relief from Requirement of 10CFR50
ML20212A3171999-09-10010 September 1999
Discusses Investigation Rept 1-1998-045 Conducted on 981112 to Determine If Former Senior Health Physics Technician Being Denied Employment at Millstone in Retaliation for Having Raised Safety Concerns in Past.Synopsis Encl
B17838, Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls1999-09-10010 September 1999
Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls
ML20212A7501999-09-10010 September 1999
Forwards Staff Requirements Memo Response,Dtd 990525,which Provides Actions NRC Plans for Continued Oversight of safety-conscious Work Environ & Employee Concerns Program
ML20211J9291999-09-0303 September 1999
Forwards mark-ups & Retypes of Proposed Conforming License Changes Required in Connection with Transfers Being Sought in 990615 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests
ML20211K5171999-09-0202 September 1999
Expresses Appreciation for Support Provided for NRC Public Meeting on 990825
05000336/LER-1999-010, Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 11999-09-0202 September 1999
Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 1
ML20216H0591999-09-0202 September 1999
Responds to Re Issues Submitted by Cullen on Behalf of Several Petitioners Concerning Offsite Emergency Prepardeness for Millstone Nuclear Power Station
ML20211N9241999-09-0101 September 1999
Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures
ML20211H0741999-08-30030 August 1999
Discusses GL 92-01,Rev 1, Rv Structural Integrity, Issued by NRC on 950519 & NNECO Responses for Millstone Unit 2 & 980715.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 Based on Response Review
1999-09-30
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML20217N8261999-10-25025 October 1999
Discusses Errata Re 991021 Filing of Northeast Nuclear Energy Co Answer to Request for Hearing & Petition to Intervene
B17886, Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 21999-10-18018 October 1999
Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 2
B17901, Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)1999-10-18018 October 1999
Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)
05000336/LER-1999-012, Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl1999-10-15015 October 1999
Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl
B17900, Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 11999-10-14014 October 1999
Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 1
ML20217P1201999-10-0606 October 1999
Informs NRC of Proposed Acquisition of Parent Holding Company of Central Maine & Requests NRC Concurrence,Based on Threshold Review,That Proposed Acquisition Does Not,In Fact, Constitute Transfer Subject to 10CFR50.80
ML20217F0031999-10-0606 October 1999
Forwards Original Petition to Intervene Being Filed on Behalf of Clients,Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone,Iaw Provisions of 10CFR2.714
B17892, Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC1999-10-0505 October 1999
Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC
B17887, Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer1999-09-28028 September 1999
Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer
B17883, Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-62301999-09-27027 September 1999
Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-6230
B17890, Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-09-27027 September 1999
Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal
B17884, Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-031999-09-24024 September 1999
Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-03
B17888, Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 9909151999-09-24024 September 1999
Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 990915
05000336/LER-1999-001, Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl1999-09-20020 September 1999
Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl
B17867, Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports1999-09-17017 September 1999
Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports
B17876, Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant1999-09-16016 September 1999
Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant
B17865, Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal1999-09-16016 September 1999
Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal
B17881, Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999
Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6)
B17880, Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999
Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6)
B17859, Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 9801281999-09-15015 September 1999
Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 980128
B17882, Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999
Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6)
B17872, Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 11999-09-14014 September 1999
Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 1
B17838, Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls1999-09-10010 September 1999
Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls
ML20211J9291999-09-0303 September 1999
Forwards mark-ups & Retypes of Proposed Conforming License Changes Required in Connection with Transfers Being Sought in 990615 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests
05000336/LER-1999-010, Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 11999-09-0202 September 1999
Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 1
ML20216H0591999-09-0202 September 1999
Responds to Re Issues Submitted by Cullen on Behalf of Several Petitioners Concerning Offsite Emergency Prepardeness for Millstone Nuclear Power Station
ML20211N9241999-09-0101 September 1999
Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures
B17851, Forwards Semiannual fitness-for-duty Program Performance Data for 990101-990630 for Millstone Nuclear Power Station, Units 1,2 & 3,IAW 10CFR26.71(d)1999-08-27027 August 1999
Forwards Semiannual fitness-for-duty Program Performance Data for 990101-990630 for Millstone Nuclear Power Station, Units 1,2 & 3,IAW 10CFR26.71(d)
B17855, Forwards NRC Forms 398 & 396 in Support of License Renewal for SRO TE Grilley,SOP-4053-04.Encl Withheld,Per 10CFR2.7901999-08-17017 August 1999
Forwards NRC Forms 398 & 396 in Support of License Renewal for SRO TE Grilley,SOP-4053-04.Encl Withheld,Per 10CFR2.790
B17849, Forwards Second Quarter Backlog Performance Rept for 1999, Which Represents Fourth Rept on Mnps Performance Since Restart of Unit 3 & First Status Update for Unit 2.No Regulatory Commitments Are Contained in Ltr1999-08-16016 August 1999
Forwards Second Quarter Backlog Performance Rept for 1999, Which Represents Fourth Rept on Mnps Performance Since Restart of Unit 3 & First Status Update for Unit 2.No Regulatory Commitments Are Contained in Ltr
B17854, Forwards Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2,per TS 6.9.1.7.Revised Repts for May & June Also Encl Which Reflect Correct Faulty Printometer Readings1999-08-14014 August 1999
Forwards Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2,per TS 6.9.1.7.Revised Repts for May & June Also Encl Which Reflect Correct Faulty Printometer Readings
B17850, Forwards First Lhc Quarterly Assessment Rept for Assessment Performed 990621 to 990701.NNECO Taking Appropriate Actions to Address Observations in Rept1999-08-11011 August 1999
Forwards First Lhc Quarterly Assessment Rept for Assessment Performed 990621 to 990701.NNECO Taking Appropriate Actions to Address Observations in Rept
B17837, Forwards COLR for Cycle 7, for Millstone Unit 3,IAW TS 6.9.1.6.Explanation of Changes to COLR Also Encl1999-08-0707 August 1999
Forwards COLR for Cycle 7, for Millstone Unit 3,IAW TS 6.9.1.6.Explanation of Changes to COLR Also Encl
B17657, Requests Schedular Exemption from Emergency Plan Exercise Requirements of 10CFR50,App E,Part Iv,Section F,Paragraph 2.c.Requests That Nrc/Fema Evaluated Exercise Be Conducted in Mar 2000 Rather than Sept 19991999-08-0303 August 1999
Requests Schedular Exemption from Emergency Plan Exercise Requirements of 10CFR50,App E,Part Iv,Section F,Paragraph 2.c.Requests That Nrc/Fema Evaluated Exercise Be Conducted in Mar 2000 Rather than Sept 1999
B17845, Forwards Revised Commitment for Surveillance Scheduling & Tracking.Options for Surveillance Scheduling & Tracking Methodologies to Be Incorporated in Standardized Station Surveillance Program Are Currently Being Reconsidered1999-08-0202 August 1999
Forwards Revised Commitment for Surveillance Scheduling & Tracking.Options for Surveillance Scheduling & Tracking Methodologies to Be Incorporated in Standardized Station Surveillance Program Are Currently Being Reconsidered
B17831, Informs NRC Staff That Change 3 to Rev 25 of Mnps Emergency Plan Was Implemented on 990715.Change Removes Facility Organizational Charts from Emergency Plan & Identifies Relocation to Nuqap1999-07-26026 July 1999
Informs NRC Staff That Change 3 to Rev 25 of Mnps Emergency Plan Was Implemented on 990715.Change Removes Facility Organizational Charts from Emergency Plan & Identifies Relocation to Nuqap
B17834, Forwards Proprietary Revised NRC Form 398,which Certifies That SL Doboe Has Completed Eligibility Requirements for Sro,Per 10CFR55.31.Proprietary Info Withheld1999-07-20020 July 1999
Forwards Proprietary Revised NRC Form 398,which Certifies That SL Doboe Has Completed Eligibility Requirements for Sro,Per 10CFR55.31.Proprietary Info Withheld
B17836, Forwards Revised NRC Form 396 & Supporting Physician Rept for Licensed Operator Restricted from Licensed Duties, Effective 990628,due to Medical Condition.Without Encl1999-07-20020 July 1999
Forwards Revised NRC Form 396 & Supporting Physician Rept for Licensed Operator Restricted from Licensed Duties, Effective 990628,due to Medical Condition.Without Encl
B17811, Submits Response to NRC AL 99-02,requesting That Licensees Provide Numerical Estimates of Licensing Actions to Be Expected to Be Submitted in Fy 2000 & 20011999-07-20020 July 1999
Submits Response to NRC AL 99-02,requesting That Licensees Provide Numerical Estimates of Licensing Actions to Be Expected to Be Submitted in Fy 2000 & 2001
ML20210S9911999-07-18018 July 1999
Requests NRC Intervene for All Shareholders of New England Electric System & to Help with Merger with National Grid Group & That NRC Petition Security & Exchange Commission to Investigate Matter Relative to No Shareholder Options
B17835, Forwards Rev 33 to Millstone Station Physical Security Plan, Per 10CFR50.54(p)(2).Licensee Determined That Changes Do Not Decrease Effectiveness of Plan.Rev Withheld from Public Disclosure,Per 10CFR2.790(d)(1)1999-07-16016 July 1999
Forwards Rev 33 to Millstone Station Physical Security Plan, Per 10CFR50.54(p)(2).Licensee Determined That Changes Do Not Decrease Effectiveness of Plan.Rev Withheld from Public Disclosure,Per 10CFR2.790(d)(1)
B17818, Provides NRC Staff with Change to TS Bases Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only.Change Was Reviewed & Approved by Unit 3 Plant Operations Review Committee IAW Provisions of 10CFR50.591999-07-16016 July 1999
Provides NRC Staff with Change to TS Bases Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only.Change Was Reviewed & Approved by Unit 3 Plant Operations Review Committee IAW Provisions of 10CFR50.59
B17824, Forwards Monthly Oeprating Rept for June 1999 & Revised Monthly Operating Rept for May 1999 for Millstone Unit 21999-07-13013 July 1999
Forwards Monthly Oeprating Rept for June 1999 & Revised Monthly Operating Rept for May 1999 for Millstone Unit 2
ML20212K1701999-07-13013 July 1999
Submits Concerns Re Millstone & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Should Provide Adequate Emergency Planning in Case of Radiological Accident
B17816, Provides Certification That M Lettrich,Has Completed Eligibility Requirements,Per 10CFR55.31 for Operator License.Util Requests That Licensing Action Be Taken for Named Individual1999-07-0101 July 1999
Provides Certification That M Lettrich,Has Completed Eligibility Requirements,Per 10CFR55.31 for Operator License.Util Requests That Licensing Action Be Taken for Named Individual
B17801, Forwards 10CFR50.59 Annual Rept for Period Jan-Dec 1998. Various Changes That Were Initiated in Previous Yrs & Completed in 1998,also Incorporated Into Annual Rept1999-06-30030 June 1999
Forwards 10CFR50.59 Annual Rept for Period Jan-Dec 1998. Various Changes That Were Initiated in Previous Yrs & Completed in 1998,also Incorporated Into Annual Rept
B17819, Forwards Rev 17 to FSAR & Addendum 6 to Annual Rept.Nneco Recently Completed Review of Unit 2 Design & Licensing Bases Which Resulted in Changes to FSAR Provided in Encl 1.Encl 2 Includes Info Covering Changes Not Included in1999-06-30030 June 1999
Forwards Rev 17 to FSAR & Addendum 6 to Annual Rept.Nneco Recently Completed Review of Unit 2 Design & Licensing Bases Which Resulted in Changes to FSAR Provided in Encl 1.Encl 2 Includes Info Covering Changes Not Included in
B17780, Forwards Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) TR, IAW 10CFR50.54(a)(3).Changes to TR Are Shown as Text in Bold Italics1999-06-30030 June 1999
Forwards Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) TR, IAW 10CFR50.54(a)(3).Changes to TR Are Shown as Text in Bold Italics
B17723, Responds to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for Units 2 & 3 Encl.Without Encl1999-06-29029 June 1999
Responds to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for Units 2 & 3 Encl.Without Encl
B17767, Forwards Rev 12 to FSAR & Addendum 3 to Annual Rept, for Millstone Unit 3,per 10CFR50.71(e) & 10CFR50.4(b)(6). No New Regulatory Commitments Contained in Ltr1999-06-29029 June 1999
Forwards Rev 12 to FSAR & Addendum 3 to Annual Rept, for Millstone Unit 3,per 10CFR50.71(e) & 10CFR50.4(b)(6). No New Regulatory Commitments Contained in Ltr
1999-09-03
[Table view]
Category:UTILITY TO NRC
MONTHYEARML20064A8071990-09-11011 September 1990
Forwards Core Operating Limits Rept for Four & Three Loop Operation,Per Tech Spec 6.9.1.6.d
A08900, Responds to Expressing NRC Views on Access to Util Internal or third-party Assessment Repts.Believes Internal Analysis to Support Amend of One of Util NRC OLs to Authorize Higher Power Level Is within NRC Purview & Access1990-09-11011 September 1990
Responds to Expressing NRC Views on Access to Util Internal or third-party Assessment Repts.Believes Internal Analysis to Support Amend of One of Util NRC OLs to Authorize Higher Power Level Is within NRC Purview & Access
B13628, Forwards Correction to Error Discovered in Util 900727 Response to Notice of Violation from Insp Rept 50-336/90-09. Statement Corrected to Read That Contract Personnel That Have long-term Assignments,Certified as Testing Personnel1990-09-0707 September 1990
Forwards Correction to Error Discovered in Util 900727 Response to Notice of Violation from Insp Rept 50-336/90-09. Statement Corrected to Read That Contract Personnel That Have long-term Assignments,Certified as Testing Personnel
B13624, Forwards Addl Info Re Relief Request from ASME Code Section XI Requirements for Temporary Repair to Piping Adjacent to Valve 2-SW-97A,per 900817 Telcon1990-09-0505 September 1990
Forwards Addl Info Re Relief Request from ASME Code Section XI Requirements for Temporary Repair to Piping Adjacent to Valve 2-SW-97A,per 900817 Telcon
A08977, Advises of Commitment to Install Hardened Wetwell Vent at Facility,In Response to NRC .Util Will Be Proceeding W/Initial Design & Engineering of Hardened Vent, to Support Installation During 1993 Refueling Outage1990-09-0404 September 1990
Advises of Commitment to Install Hardened Wetwell Vent at Facility,In Response to NRC .Util Will Be Proceeding W/Initial Design & Engineering of Hardened Vent, to Support Installation During 1993 Refueling Outage
B13596, Forwards Millstone Unit 3 Individual Plant Exam for Severe Accident Vulnerabilities, Per Generic Ltr 88-20.Rept Identified That No Major Severe Accident Vulnerabilities Requiring Corrective Action Needed1990-08-31031 August 1990
Forwards Millstone Unit 3 Individual Plant Exam for Severe Accident Vulnerabilities, Per Generic Ltr 88-20.Rept Identified That No Major Severe Accident Vulnerabilities Requiring Corrective Action Needed
B13626, Informs That Info Provided in Re safety-related Equipment Classification Programs Also Applicable for Unit 3 of Facility1990-08-31031 August 1990
Informs That Info Provided in Re safety-related Equipment Classification Programs Also Applicable for Unit 3 of Facility
B13618, Forwards Addl Info on Util 900815 Relief Request from ASME Code Section XI Requirements,Per 10CFR50.55a(g)(6)(i),for Repairs to Pipe 3SWP-006-050-031990-08-24024 August 1990
Forwards Addl Info on Util 900815 Relief Request from ASME Code Section XI Requirements,Per 10CFR50.55a(g)(6)(i),for Repairs to Pipe 3SWP-006-050-03
ML20059C2061990-08-23023 August 1990
Forwards Vols 1 & 2 to Semiannual Radioactive Effluents Release Rept Jan-June 1990, Per 10CFR50.36a.Rept Includes Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents
A08918, Responds to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-245/90-08.Mitigation of Civil Penalty Requested.Corrective Action:List of Procedural Changes Provided1990-08-22022 August 1990
Responds to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-245/90-08.Mitigation of Civil Penalty Requested.Corrective Action:List of Procedural Changes Provided
B13610, Requests Relief from ASME Boiler & Pressure Vessel Code Section XI Requirements Re Mods to Pipe 3SWP-006-050-03. Results of Insps & Required Repairs Will Determine Schedule for Future Insps1990-08-15015 August 1990
Requests Relief from ASME Boiler & Pressure Vessel Code Section XI Requirements Re Mods to Pipe 3SWP-006-050-03. Results of Insps & Required Repairs Will Determine Schedule for Future Insps
B13595, Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-13941990-08-14014 August 1990
Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-1394
B13607, Requests Relief from ASME Code Section XI to Reflect Mod to Piping Adjacent to Valve 2-SW-97A,in Response to Generic Ltr 90-051990-08-10010 August 1990
Requests Relief from ASME Code Section XI to Reflect Mod to Piping Adjacent to Valve 2-SW-97A,in Response to Generic Ltr 90-05
A08845, Responds to NRC Backfit Analyses of Hardened Wetwell Vent, Contained in .Benefit of Installing Hardened Wetwell Vent to Satisfy Basic Design Objective of Preventing core-melt Event Not Sufficient for Immediate Decision1990-08-0808 August 1990
Responds to NRC Backfit Analyses of Hardened Wetwell Vent, Contained in .Benefit of Installing Hardened Wetwell Vent to Satisfy Basic Design Objective of Preventing core-melt Event Not Sufficient for Immediate Decision
ML20058N2181990-08-0707 August 1990
Notification of Change in Senior Operator Status.Util Determined That Need to Maintain Senior OL of LS Allen No Longer Exists.Determination Effective 900719
ML20058M8321990-08-0707 August 1990
Discusses Spent Fuel Racks Poison Surveillance Coupon Boraflex Degradation.Visual Exam of Remaining Surveillance Coupons Revealed Similar Situation Existed in All Coupon Samples
B13590, Responds to NRC 900718 Request for Addl Info Re Util 900418 Request for Schedular Exemption from 10CFR50,App E,Section IV.F.3 to Allow Dec 1990 Full Participation Exercise to Be Exchanged W/Oct 1991 Partial Participation Exercise1990-08-0101 August 1990
Responds to NRC 900718 Request for Addl Info Re Util 900418 Request for Schedular Exemption from 10CFR50,App E,Section IV.F.3 to Allow Dec 1990 Full Participation Exercise to Be Exchanged W/Oct 1991 Partial Participation Exercise
A08881, Responds to NRC Re Violations Noted in Insp Rept 50-423/90-08.Corrective Action:Operators Directly Involved W/Event Removed from Licensed Duties & Counseled by Operations Manager on Causes of Event1990-07-31031 July 1990
Responds to NRC Re Violations Noted in Insp Rept 50-423/90-08.Corrective Action:Operators Directly Involved W/Event Removed from Licensed Duties & Counseled by Operations Manager on Causes of Event
B13594, Forwards Rev 13 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21(b) & 2.790(a))1990-07-30030 July 1990
Forwards Rev 13 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21(b) & 2.790(a))
ML20055J4621990-07-27027 July 1990
Advises That Need to Maintain OL or Senior OL for Listed Individuals No Longer Exists,Effective 900701
B13585, Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys1990-07-26026 July 1990
Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys
A08565, Responds to NRC 900302 Request for Addl Info Re LPCI Swing Bus Transfer Design & Single Failure Vulnerabilities1990-07-26026 July 1990
Responds to NRC 900302 Request for Addl Info Re LPCI Swing Bus Transfer Design & Single Failure Vulnerabilities
B13592, Requests Extension to Respond to NRC Backfit Analyses of Hardened Wetwell Vent1990-07-24024 July 1990
Requests Extension to Respond to NRC Backfit Analyses of Hardened Wetwell Vent
ML20063P9791990-07-23023 July 1990
Notification of Change in SL Jackson Status Effective 900701,due to Permanent Reassignment within Util
B13563, Discusses Util Comprehensive Review of Options Re Degraded Grid Undervoltage Protection.Confirms Previous Conclusion That Splitting Loss of Normal Power Logic Would Have Overall Adverse Impact on Plant Safety1990-07-20020 July 1990
Discusses Util Comprehensive Review of Options Re Degraded Grid Undervoltage Protection.Confirms Previous Conclusion That Splitting Loss of Normal Power Logic Would Have Overall Adverse Impact on Plant Safety
B13566, Advises That Util Has Reasonable Assurance That Safety Relief Valves Operable & Will Perform as Expected Until Next Outage1990-07-20020 July 1990
Advises That Util Has Reasonable Assurance That Safety Relief Valves Operable & Will Perform as Expected Until Next Outage
B13588, Corrects 900703 Submittal of Results of Second in-cycle Insp of Steam Generators.All Tubes W/Cracks Stacked & Plugged1990-07-18018 July 1990
Corrects 900703 Submittal of Results of Second in-cycle Insp of Steam Generators.All Tubes W/Cracks Stacked & Plugged
A08822, Submits Addl Info Requested Re Util Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls. Charpy Impact Use Values for Welds Provided in Evaluation of Irradiated Capsule W-971990-07-18018 July 1990
Submits Addl Info Requested Re Util Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls. Charpy Impact Use Values for Welds Provided in Evaluation of Irradiated Capsule W-97
ML20055G5331990-07-18018 July 1990
Forwards Decommissioning Financial Assurance Certification Rept
B13587, Requests Temporary Waiver of Compliance from Tech Spec 3.5.F.2 Re Emergency Diesel Generator (EDG) Limiting Condition for Operation.Waiver Would Extend Available Time to Repair Damaged Electrical Components1990-07-16016 July 1990
Requests Temporary Waiver of Compliance from Tech Spec 3.5.F.2 Re Emergency Diesel Generator (EDG) Limiting Condition for Operation.Waiver Would Extend Available Time to Repair Damaged Electrical Components
ML20055D3461990-07-0303 July 1990
Responds to NRC Bulletin 90-001 Re Loss of Fill Oil Transmitters Mfg by Rosemount.Operability Determinations Performed & Documented for All Rosemount 1153 & 1154 Transmitters at Facility
B13545, Forwards Rev 3 to Updated FSAR for Millstone Unit 31990-06-29029 June 1990
Forwards Rev 3 to Updated FSAR for Millstone Unit 3
ML20055D7191990-06-29029 June 1990
Amends 900604 Rev 13 to QA Program
ML20055D3481990-06-29029 June 1990
Forwards Addl Info Re Facility Crdr & Isap,Including Justification for Human Engineering Discrepancies Dispositioned for No Corrective Action
B13531, Forwards Rev 8 to Updated FSAR for Millstone Unit 21990-06-29029 June 1990
Forwards Rev 8 to Updated FSAR for Millstone Unit 2
B13550, Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl1990-06-27027 June 1990
Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl
B13499, Forwards Corrected Tech Specs Page 3/4 9-1 for Incorporation Into Proposed Amend 36 to License DPR-21 Re Auxiliary Electrical Sys1990-06-26026 June 1990
Forwards Corrected Tech Specs Page 3/4 9-1 for Incorporation Into Proposed Amend 36 to License DPR-21 Re Auxiliary Electrical Sys
ML20043F8721990-06-11011 June 1990
Corrects Name of Vendor Supplying Replacement Plug Valves, Per Util 900511 Ltr.Replacement Bolts,Not Valves,Purchased from Cardinal Industrial Products Corp
ML20043H0161990-06-0808 June 1990
Requests Exemption from App J to 10CFR50 for 12 Valves in Reactor Bldg Closed Cooling Water Sys.Valves Not within Definition of Containment Isolation Valves in App J & Not Required to Be Tested
ML20043E8831990-06-0505 June 1990
Requests NRC Authorization to Use Plugs Fabricated of nickel-chromium-iron Uns N-06690 Matl Alloy 690 to Plug Tubes in Steam Generators of Plant
ML20043D0451990-05-30030 May 1990
Discusses Proposed Rev to Tech Specs Re Facility ESF Actuation Sys Instrumentation Trip Setpoint,Per 900330 Ltr
ML20042H0311990-05-0909 May 1990
Discusses Steam Generator Safety Assessment.Concludes That Continued Operation Through Remainder of Current Cycle 10 Fully Justified
ML20042F0941990-04-30030 April 1990
Provides Addl Info Re Environ Impact of 900226 Application for Amend to License NPF-49,revising Tech Specs to Allow Containment Pressure to Increase to 14 Psia During Modes 1-4,per NRC Request
ML20042F0661990-04-30030 April 1990
Responds to NRC 900404 Ltr Re Violations Noted in Safety Insp Rept 50-336/90-01 on 900120-0305.Corrective Action:Ler 90-004 Submitted on 900430 to Document Condition Prohibited by Plant Tech Specs
ML20042E8331990-04-27027 April 1990
Forwards Annual Environ Protection Plan Operating Rept for 1989, & Monitoring Marine Environ of Long Island Sound at Millstone Nuclear Power Station Annual Rept 1989.
ML20012E2681990-03-23023 March 1990
Responds to NRC 900226 Ltr Re Violations Noted in Insp Rept 50-423/89-23.Corrective Actions:Requirement to Review All Changes on Safety Sys for Potential Operating Procedure Changes Stressed to Operations & Engineering Personnel
ML20012C3141990-03-13013 March 1990
Forwards Info Re Insp of Facility Emergency Operating Procedures,Per 900119 Ltr
ML20012B4111990-03-0202 March 1990
Provides Addl Info Requested to Clarify Changes Proposed to Tech Spec Action Statements for Inoperable Accumulator
B13453, Advises That Mods to Steam Generator Blowdown Sample Sys Completed,Per Violations Noted in Insp Rept 50-423/89-14 & Salp.Sys Will Be Evaluated for Next 2 Wks to Ensure Blowdown Radiation Monitor Operating Reliably1990-02-26026 February 1990
Advises That Mods to Steam Generator Blowdown Sample Sys Completed,Per Violations Noted in Insp Rept 50-423/89-14 & Salp.Sys Will Be Evaluated for Next 2 Wks to Ensure Blowdown Radiation Monitor Operating Reliably
ML20011F7541990-02-26026 February 1990
Notifies That Jh Parillo Reassigned & No Longer in Need of License SOP-10263-2 as of 900219
1990-09-07
[Table view] |
Text
-
c :
IMHtTHI!AST IFFII.FFIIES 1
L L
@@((hf[.5 J M:"2' 0;2,g;;7 November 1,1985
$aN?NNECWmHH Docket No. 50-423 B-11851 Director of Nuclear Reactor Regulation Mr. B. 3. Youngblood, Chief Licensing Branch No. I Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Reference:
(1) B. 3. Youngblood Letter to 3. F. Opeka, Final Draft Technical Specifications, dated October 18,1985 (2) 3. F. Opeka letter to B. 3. Youngblood, Comments on Final Draft Technical Specifications, dated November 1,1985
Dear Mr. Youngblood:
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 FINAL DRAFT TECHNICAL SPECIFICATIONS Reference (1) transmitted Final Draft Technical Specifications for Millstone Unit No.
3 and requested comments from NNECO. Reference (2) provided comments based on our review of Reference (1). Attached are additional changes to three tables in the Final Draft Technical Specifications. These changes are necessary to reflect the as-built plant configuration for these components.
The items in Enclosure I consist of additions and deletions to Technical Specification ,
Table 3.8-1, Containment Penetration Conductor Overcurrent Protective Devices. '
The items in Enclosure 2 consist of additions and deletions to Technical Specification Table 3.8-2a, Motor-Operated Valves Thermal Overload Protection With Bypass Devices Bypt.ssed Only Under Accident Conditions. The items in Enclosure 3 consist of additions and deletions to Technical Specification Table 3.8-2b, Motor-Operated Valves Thermal Overload Protection Not Bypassed.
If there are any questions, please contact me as soon as possible.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY et. al.
BY NORTHEAST NUCLEAR ENERGY COMPANY Their Agent
- 3. F% Qpeka (/
0t Senior Vice President F pdoinnS$1d? '
i A
l
O STATE OF CONNECTICUT )
) ss. Waterford COUNTY OF NEW LONDON )
Then personally appeared before me 3. F. Opeka, who being duly sworn, did state that he is Senior Vice President of Northeast Nuclear Energy Company, an Applicant herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Applicants herein and that the statements contained in said information are true and correct to the best of his knowledge and belief. '
67 tlc d &' QV Notary Public /
s t
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+
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ENCLOSURE 1 i
i i
i l
ENCLOSURE 1 Additions to Technical Specification Table 3.8.-l Containmen+ Penetration Conductor Overcurrent Protective Devices 3-CDS-AOV 45A Chilled Water Isolation Valve 3CDS-AOV 46A Chilled Water Isolation Valve 3DAS-3B01 Aerated Drains Junction Box
, 3PGS-PNLD Primary Grade Water 3MHR-CRN-3A Material Handling Cranes in Containment 3MHR-CRN-3B Material Handling Cranes in Containment 3MHR-CRN-3C Material Handling Cranes in Containment 3MHR-CRN-3D Material Handling Cranes in Containment 3MHR-CRN-4 Material Handling Cranes in Containment 3MHR-CRN-5 Material Handling Cranes in Containment 3HVU&CTV 39A, B Containment Structure Ventilation System 3HVU-FN IB Containment Structure Ventilation System
FINAL DRAFT TABLE 3.8-1 OCT 16 fc85 CONTAINMENT PENETRATION CONOUCTOR ,
OVERCURRENT PROTECTIVE DEVICES J Device Ni-her OESE S_ystem Powered Qfoca't 3RCS-HTR-24 Reactor Coolant System !
3RCS-HTR-51 Reactor Coolant System 3RCS-HTR-52 Reactor Coolant Systes , !
3RCS-HTR-29 Reactor Coolant System 3RCS-HTR-57 Reactor Coolant System 3RCS-HTR-58 Reactor Coolant System 3RCS-HTR-34 Reactor Coolant System 3RCS-HTR-63 Reactor Coolant System 3RCS-HTR-64 hteactorCoolantSystem 3RCS-HTR-39 Reactor Coolant System 3RCS-HTR-69 Reactor Coolant System ,
3RCS-HTR-70 Reactor Coolant System 3RCS-HTR-44 Reactor Coolant System 3RCS-HTR-75 Reactor Coolant System 3RCS-HTR-76 Reactor Coolant System 3RCS-HTR-23 Reactor Coolant System 3RCS-HTR-49 Reactor Coolant System 3RCS-HTR-50 Reactor Coolant System 3RCS-HTR-28 Reactor Coolant System 3RCS-HTR-55 Reactor Coolant System 3RCS-HTR-56 Reactor Coolant System 3RCS-HTR-35 Reactor Coolant System 3RCS-HTR-61 Reactor Coolant System j
MILLSTONE - UNIT 3 3/4 8-20
_~ _ . _
. FINAL DRAFT j TABLE 3.8-1 (Cont) OCT 161985 j CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES ;
l
'Javice Number System Powered p ,, g d Location]
- 3RHS*MV87028 Residual Heat Removal System 3RHS*MV8702C Residual Heat Removal System 3SIL*MV88088 Low Pressure Safety Injection System 3SIL*MV88080 Low Pressure Safety Injection System 3RHS*MV8701A Residual Heat Removal System 3RHS*MV8701C Residual Heat Removal System 3SIL*MV8808A Low Pressure Safety Injection System 3SIL*MV8808C Low Pressure Safety Injection System 3CCP*A0V1788 Reactor Plant Component Cooling Water System 3CCP"A0V1798 Reactor Plant Component Cooling Water System 3CCP*A0V1808 Reactor Plant Component Cooling Water System 3CCP"MOV488 Reactor Plant Component Cooling Water System ,
3CDS*CTV408 Chilled Water System 3CDS*SOV918 Chilled Water System hM~
(3IAS*MOV72 InNrumentAirS 3HVU*CTV33A & 8 Containment Structure Ventilation System 3RCS*FIS4188 Reactor Coolant System 3RCS*FIS4288 Reactor Coolant System 3RCS*FIS4388 Reactor Coolant System 3RCS*HCV4428 Reactor Coolant System 3RCS*FIS4488 Reactor Coolant System 3RCS*MV80018 Reactor Coolant System 3RCS*MV8001D Reactor Coolant System
-]
MILLSTONE - UNIT 3 3/4 8-22
- - --, - - , + - . , - . - - - - - - - - - - - - - , - . . , - - - - -,--,--<-,,-,-e, ,- > ~ . . - ~ ,
FINAL DRAFT l
. TABLE 3.8-1 (Cont) -
CONTAINMENT PE'NETRATION CONDUCTOR
( OVERCURRENT PROTECTIVE DE' VICES I Device Number M g/2Ehb9 ciniPl.~ocatieN 3CDS*SOV91A System Powered Chilled Water System g8 w'i old -
h3HVU*CTV33A&B Containment Structure Ventilation System 3RCS*FIS4188 Reactor Coolant System 3RCS*FIS4388 Reactor Coolant System __
3RCS*MV8001A Reactor Coolant System 3RCS*MV8001C Reactor Coolant System 3RCS*MV8002A Reactor Coolant System 3RCS*MV8002C Reactor Coolant System 3RCS*MV8003A Reactor Coolant System 3RCS*MV8003C Reactor Coolant System 3SIL*SVS875E Low Pressure Safety Injection System 3SIL*SV8875G Low Pressure Safety Injection System 3CCP*A0V1780 Reactor Plant Component Cooling Water System 3CCP*MOV222 Reactor Plant Component Cooling Water System -
3CCP*MOV223 Reactor Plant Component Cooling Water System 3CCP"MOV224 Reactor Plant Component Cooling Water System 3CCP"MOV225 Reactor Plant Component Cooling Water System 3CHS*MV8112 Chemical and Volume Control System
! 3CHS*AV8147 Chemical and Volume Control System 3CHS*AV8149A Chemical and Volume Control System 3CHS*AV81498 Chemical and Volume Control System 3CHS*AV8149C Chemical and Volume Contral System 3CHS*CVS160 Chemical and Volume Control System 3GSN*CTV105 Mitrogen Supply Systa:a
{
MILLSTONE - UNIT 3 3/4 8-25 ,
~
' FINAL DRAFT TABLE 3.8-1 (Cont) OCT 161o85 CONTAINMENT PENETRATION CONDUCTOR
( OVERCURRENT PROTECTIVE DEVICES Device _ Number g T6 cation T DESystem M Powered 3RHS*MV8701C Residual Heat Removal System 3RMS*RM41 Radiation Monitoring System 3SIL*SV8875A Low Pressure Safety Injection System 3SIL*SV8875C Low Pressure Safety Injection System
- 3SIL*CV8890A Low Pressure Safety Injection System 3SIL*HCV943A Low Pressure Safety Injection System 3SIL*MV8808A Low Pressure Safety Infection System 3SIL*MV8808C Low Pressure Safety Injection System SIS Valve Ann Safety Injection System 3CDS-A0V53A Chilled Water System
( 3PGS-LV49 Primary Grade Water System High Pressure Safety Injectirn System 3SIH*AV8889A
- SV8875A Low Pressure Safety Injection System 3SIL*AV8877A Low Pressure Safety Injection System g 3SIL*AV8879A Low Pressure Safety Injection. System p Low fressure Safety Injection System ggd O 3SIL*AV88898 3SIL*AV8872A Low Pressure Safety Injection System kb
- SV8875C Low Pressure Safety Injection Sys 3SIL*AV8877C Low Pressure Safety Injection System 3SIL*AV8879C Low Pressure Safety Injection System 3SIL*AV8872C Low Pressure Safety Injection System 3CHS*AV8141A Chemical and Volume Control System 3CHS*AV8141C Chemical and Volume Control System C
MILLSTONE-t[ NIT 3 3/4 8-29
- i I
FINAL DRAFT TABLE 3.8-1 (Cont) OCT 161585 CONTAINMENT PENETRATION CONDUCTOR
( OVERCUhRENT PROTECTIVE DEVICES esfid l'ocatig%M DeviceJ umber System Powere'd 3SSR*SOV31A Reactor Plant Samp1'ing Systes 3SSR*SOV28C Reactor Plant Sampling System 3SSR*SOV31C Reactor Plant Sampling System 3J8-C025 Junction Box HTR-11, 12, 35 Pressurizer Heater System HTR-15, 16, 40 Pressurizer Heater System HTR-19, 20, 45 Pressurizer Heater System 3JB-0026 Junction Box HTR-3, 4, 25 Pressurizer Heater System HTR-7, 8, 30 Pressurizer Heater System 3JB-0025 Junction Box HTR-13, 14, 37 Pressurizer Heater System
( HTR-17, 18, 42 Pressurizer Heater System 3JB-0026 Junction Box ,
HTR-1, 2, 22 Pressurizer Heater System HTR-5, 6, 27 Pressurizer Heater System HTR-9, 10, 32 Pressurizer Heater System 5Houth 6e
- 7. (p) 3HVU-F Containment Structure Ventilation System 3DGS-P1A Reactor Plant Gaseous Drains System 3DGS-P1B Reactor Plant Gaseous Drains System 3DGS-P3A Reactor Plant Gaseous Drains System 30GS-P3B Reactor Plant Gaseous Drains System 3LAR-PNL3RC10 Lighting in Reactor Building System 3LAR-PNL3RC2P Lighting in Reactor Building System
~
3JRB-EL Reactor Building Superstructure Loads .
3MHR-CRN2 Material Handling Crane in Reactor Buf1 ding 3CVS*MOV25 Containment Vacuus System l
MILLSTONE - UNIT 3 3/4 8-31 l
l i .
. FINAL DRAFT TABLE 3.8-1 (Cont) OCT 16 IS85 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES Device Number MSystem Powered I
3RCS-FIS417, 427, Reactor Coolant System 437, 447 ,
i 3RCS-TBP18-4 Reactor Coolant System 3RCS-PS492 Reactor Coolant System 3RCS-TBPID-4 Reactor Coolant System 3RCS-PS494 Reactor Coolant System 3HVU-PNL-01A Containment Structure Ventilation System 3HVU-PNL-01B Containment Structure Ventilation System 3SSR*SOV248 Reactor Plant Sampling System 3SSR*SOV288 Reactor Plant Sampling System 3SSR"SOV318 Reactor Plant Sampling System 3SSR*SOV280 Reactor Plant Sampling System ,
3SSR*SOV31D Reactor Plant Sampling System 3LAR-XLR1 Lighting in Reactor Building System 3LAR-XLR2 Lighting in Reactor Building System 3LAR-XLR3 Lighting in Reactor Building System 3LAR-XLR4 Lighting in Reactor B Jilding System Reactor Coolant Syst b
h*HIA
[HTR-23,44,50 Pressurizer' Heater System 06LSTE ggoJA ON
- AM
- HTR-28,55,56 Pressurizer Heater System HTR-33,61,62 Pressurizer Heater System g Zo , 21 HTR-38,67,68 Pressurizer Heater System HTR-43,73,74 "ressurizer Heater Systejm
% tainment Structure Ventilation System 3HVU-FN2A 3HV N2B Containment Structure Ventilation System o
S9ovuo SE+-
.)
HILLSTONE - UNIT 3 3/4 8-34
. FINAL DRAFT l
TABLE 3.8-1 (Cont) OCT 161o85 l
e CONTAINMENT PENETRATION CONDUCTOR l DVERCURRENT PROTECTIVE DEVICES i
Device _ Number 0 ESystem N Powered g n Flocation ]
Reactor Coolant System
[ 3RCS*H18 f -
O g g -dAu2sAbi P u 6-20,2i HTR-24,51,52 Pressurizer Heater System 3RCS-HIE Reactor Coolant System HTR-3,4,25 Pressurizer Heater System Reactor Coolant System y D 6 6 hkS-H1 3J8-0025 Junction Box HTR-22, 47, 48 Pressurizer Heater System HTR-26, 53, 54 Pressurizer Heater System HTR-31, 59, 60 Pressurizer Heater System 3J8-0026 Junction Box
'HTR-36, 65, 56 Pressurizer Heater System HTR-41, 71, 72 Pressurizer Heater System HTR-46, 77, 78 Pressurizer Heater System i 30AS-P1 Reactor Plant Aerated Drains System
(
3DAS-P10 Reactor Plant Aerated Drains System 3RCS-TBP18-2 Reketor Coolant System ,
3RCS-TBPID-2 Reactor Coolant System 3RDI-CABA Reactor Rod Drive Instrumentation System 3RDI-CA88 Reactor Rod Drive Instrumentation System Neutron Monitoring Traverse Incore Probe System 3NMT-TB1 3RCS-P131 Reactor Coolant System 3RCS-PID1 Reactor Coolant System 30AS-P28 Reactor Plant Aerated Drains System 3RCS*MV80018 Reactor Coolant System 3RCS*MV8001D Reactor Coolant System ,
3RCS*MV80028 Reactor Coolant System I
l I 3RCS*MV80020 Reactor Coolant System MILLSTONE - UNIT 3 3/4 8-35
. FINAL DRAFT TABLE 3.8-1 (Cont)
OCT 161995 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES
(
Device Number gEI.
System Powered pdL'ocati 3DGS-LS31 Reactor Plant Gaseous Drains System 3HVU-PNL-FLT-1B - Containment Structure Ventilation System 3IAC-PNLC1B ContainmentInstrumentNirSystem 3IAC-DRY 1 Containment Instrument Air System 3RCS-PS492 Reactor Coulant System 3RCS-PS494 Reactor Coolant System 3RCS*MV80018 Reactor Coolant System 3RCS W 8002B Reactor Coolant System D3 SM S*MV80038 Reactor Coolant Syst E.- ~3b 3RCS*MV9001D Reactor Coolant System 3RCS*MV8002D Reactor Coolant System 3RCS*MV8003D Reactor Coolant System 3IAC-PNLCIA Containment Instrument Air System 3IAC-PNLC18 Containment Instrument Air System 3HVU-FS34A,8,C Containment 5tructure Ventilation System 3HVU-PDIS20A, 21A, Containment Structure Ventilation System 22A, 23A 3HVU-PDIS 2CB, Containment Structure Ventilation System 218, 218, 23B 35SP*S0VIA Plant Sampling System 3 SSP *SOV2A Plant Sampling Systee 3 SSP *SOV1B Plant Sampling System 3 SSP *SOV28 Plant Sampling System .
3 SSP *SOVIC Plant Sampling System ,
3 SSP *SOVID Plant Sampling System
(
MILLSTONE - UNIT 3 3/4 8-37
. FINAL DRAFT TABLE 3.8-1 (Cont) OCT 161985 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES ,
Device N nd ocation QfSystem N Powered 3RCS*MV8003A Reactor Coolant System !
3RCS*MV8003C ' Reactor Coolant System b3CCP*MOV226 Reactor Plant Component Cooling Water System DOI 3CCP*MOV227 Reactor Plant Component Cooling Water System bM p od 3CCP*MOV228 Reactor Plant Component Cooling Water System $ Ms E 3CCP*MOV229 Reactor Plant Component Cooling Water System 3CCP"MOV488 Reactor Plant Component Cooling Water System CMS *MOV24 ContainmentAtmosphereMonitoringSyst[
. 3IAS*MOV72 Instrument Air System g- 3\
3RCS*MV8000A Reactor Coolant System 3CCP*MOV222 Reactor Plant Component Cooling Water System 3CCP*MOV223 Reactor Plant Component Cooling Water System ggTt' " '
3CCP*MOV224 , Reactor Plant Component Cooling Water System ALfl6ADi 3CCP*MOV225 Reactor Plant Component Cooling Water System fl9W$ g 3CCP"MOV48A Reactor Plant Component Cooling Water System g -7.3 3CHS*MV8112 Chemical and Volume Coatrol, System 3RCS*MV8098 Reactor Coolant System 3RCS*MV80008 Reactor Coolant System 3RHS*MV87028 Residual Heat Removal Syste" SE - PIL8 Residual Heat Removal System ) O 3RHS*MV8702C 3SIL*MV88088 Low Pressure Safety Injection System [A66-3SIL*MV8808D Low Pressure Safety Injection System 3RHS*MV8701A Residual Heat Removal System 39.HS*MV8701C Residual Heat Removal System ,
l MILLSTONE - UNIT 3 3/4 8-40
. - - - - - - - _ _ _ - . - .__ _ _ . _ . _ _ _ , _i___-._____ __ _ _ . _ . -
. RNA1. DRAFT TABLE 3.8-1 (Cont) OCT 16 loS5 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES
, (
S m Powered g6M 3SIL*MV8808A Low Pressure Safety Injection System M Low Pressure Safety Injection System 3SIL*MV8808C ContainmentStructureVentilationSysteym Osg[g4 sa (3HVU*FN2B 3JB*0024 Junction Box I
HTR-24, 51, 52 HTR-29, 57, 58 Pressurizer Heater System Pressurizer Heater System 06gg-M g g-zo
$M\
HTR-34, 63, 54 HTR-39, 69, 70 Pressurizer Heater System Pres:urizer Heater System Q
HTR-44, 75, 76 Pressurizer Heater System ,
- HTR-23,44,50 Pressurizer Heater System ,
HTR-28,55,56 Pressurizar Heater System HTR-33,61,62 Pressurizer Heater System 7 OMTE~<W HTR-38,67,68 Pressurizer Heater System @M b ~
)
(
HTR-43,73,74 Pressurizer Heater System /
k' - .
W 3HVU-FN2A Containment Structure Ventilation Syst D6L6IE
' swA o9 P6.B-3HVU-FN1B Containment Structure Ventilation System p 3HVU-FNIA Containment Structure Ventilation System 3HVU-FNIC Containment Structure Ventilation System 3HVU-FLT1B Containment Structure Ventilation System i
3HVU-FN38 Containment Structure Ventilation System-3IAC-C18 Containment Instrus.ent Air System 3 POP-JB3R1 Power Outlets General .)urpose 3 Phase System 3MHR-CRN1 Material Handling Crane in Reactor Building 3RCS-PIC Reactor Coolant System 3RCS-P18 Reactor Coolant System 3RCS-PIA Reactor Coolant System
(
MILLSTONE - UNIT 3 3/4 8-41
i w a ._
4 C
ENCLOSURE 2
(
l i
l l
4 e
h
. .,_ -""w~ - , ,,,, ~ **'m-,,-, _ , ' _ '"*N,..
th ea_gg oar m 8:Ne*
. TABLE 3.8-2e ,
OCT 1619eS MOTOR-OPERATED VALVES iMERMAL OVERLOAD PROTECT 10'i h5TH'IVFA55DEVICT'SBYPASSEDONLYUNDERACCIDENTCONDfTIONS' pg4 & SA G C* M cEnr~ eAJ G u s R fy a r= r**.r AF8ECTED NM .
VALVE NUMBER 3CCP*MOV45A Containment Isolation Valve 3CCP*MOV458 Containment Isolation Valve 3CCP"MOV48A Containment Isolation Valve 3CCP*MOV488 Containment Isolation Yalve .
3CCP*MOV4SA Containment Isolation Valve 3CCP*MOV498 Containment Isolation Valve 3CCP"MOV222 Containment Air Recircula' tion Cooling Coil Supply 3CCP"MOV223 Containment Air Recirculation Cooling coil Supply 3CCP*M0V224 Containment Air Recirculation Cooling coil Supply 3CCP*MCY225 Containment Air Recirculation Cooling coil Supply 3CCP"M0V226 Containment Air Recirculation Cooling coil Supply 3CCP*MOV227 Containment Air Recirculation Cooling coil Supply 3CCP*MOV228 Containment Air Recirculation Cooling coil Supply 3CCP*M0V229 Conte,inment Air Recirculation Cooling coil Supply 3CHS*LCY1128 Volume Control Tank Outlet Isolation 3CHS*LCV112C Volume Control Tank Outlet Isolation
- 3 CMS *LCV112D Volume Control Tank Outlet Isolation 3 CMS *LCY112E Volume Control Tank Outlet Isolation 3 CMS *MV8100 Reactor Coolant Psamp Seal Water Isolation j Boric Acid Filter to Charging Pump Isolationh M -
g g __ M_ *MV8104 3CHS*MV8105 Charging Pump to Reactor Coolant Isolation 3CHS*MV8106 Charging Pump to Reactor Coolant Isolation Reactor Coolant Pump Seal Water Isolation T aata .
f3CHS*MV8109A Odth Reactor Coolant Pump Seal Water Isolation Y-3CHS*MV81098 MILLSTONE - UNIT 3 3/4 8-44
._--_.....n,.,,,,,_. , , _,n_, ..-_ . , , _ . , _ . ..._,.,,n ,,_n ._,a._.,,.__ , . , , . , , , , _ . ,
~
. Ho05 5' Mar Avid /9#ASSED To FINAL DRMT n6e 3.6 - 2 b
. DCT 161985 TABl23.h2a(Continued)
_ MOTOR-OPERATED VALVES THERMAt_ OVERLOAD PROTECTION WITH BYPASS DEVICE 54YPA55ED ONLY UNDER ACCIDENT CONDITIONS
_ A oneTE SYSTEM (5)
VALVE NUMBER AFFEC1ED 3CHS*MV8109C Reactor Coolant Pump Seal Water Isolation pg d'c,^
OstErs q 3CHS*MV81090 Reactor Coolant Pump Seal Water Isolation b
3CHS*MV8110 Charging Pump Miniflow Isola. tion 3CHS*MV8111A Charging Pump Miniflow I6olation
- 3CHS W 81118 Charging Pump Isolation 3CHS*MV8111C Charging Pump Isolation 3CHS W 8112 Reactor Coolant Pump Seal Water Isolatish f3CHS*MV8116 Charging Header Isolation f 3CHS*MV8438A Charging Header Isolation 3CHS*MV84388 Charging Header Isolnion 3'CHSW8438C - Charging Header Isolation Charging Pump Suction Isolation !
3CHS*MV8468A f
i bP*"'
. 3CHS W 84688 Charging, Pump Suction Isolation 3CHS*Mv8507A Boric Acid Gravity Feed {
3CHS*MV85073 Boric Acid Gravity Feed 3 5 % 85 Sharging ump Minif1 Control &
06L6E "i u/
j- CHS W 5118 Chargi Pump Min flow Cont 1 ]
Charging Pump Miniflow Control N 3CHS*MV8512A 3CHS W 85128 Charging Pump Miniflow Control ,
3 CMS *MOV24 Containment Atmosphere Monitoring Inside Containment Isolation 3FWA*MOV35A Staan Genarator Auxiliary Feedwater Pump Isolatio 3FWA*MOV358 Steam Generator Auxiliary Feedwater Pump Isolation ,
Steam Generator Auxiliary Feedwater Pump Isolation 6 3FWA*MOV35C l Steam Generator Auxiliary Feedwater Pump Isolatio 5FWA*MOV350 MILLSTONE - UNIT 3 3/4 8-45 l -
1 . - _ - _ - . . -
M00E g t4or A0To /$#AssED To TA SLE 3.6 lb ,
FINAL ORAFT ;
~
TABLE 3.C (Continued) DCT 161 5 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION ITH BYPASS DEVICES)YPASSED ONLY UNDER ACCIDENT CONDITIONS A DEWTE SYSTEM (S)
VALVE NUMBER AFFECTED 3RCS*MV8000A Pressurizer Relief Isolation ,
3RCS*MV80008 Pressurizer Relief Isolation g
%L6T6. 3RCSW8098 Reactor to Excess' Letdown Isolation /
3RHS*FCV610 Residual Heat Removal Pump Miniflow RHS*FCV6u Residual Heat Removal Pump Miniflow 3RHS W 8701A Residual Heat System Inlet Isolation .
3RHS W 87018 Residual Heat System Inlet Isolation W 8701C Residual Heat System Inlet Isolation} uoh NN gg
- 3RHS*MV8702A Residual Heat System Inlet Isolation 3RMS*MV87028 Residual Heat System Inlet Isolation RHS*MV8702C Residual Heat System Inlet IsolatioW3 ,
'3RHS*MV8716A Residual He d System Conn Isolation' h.3 l
3RHS*MV87168 Residual Heat System Conn Isolation W l 3RSS*MOV20A Containment Recirculation Spray Header Isolation 3RSS*MOV208 Containment Recirculation Spray Header Isolation 3RSS*MOV20C Containment Lecirculation Spray Header Isolation 3RSS*M0V200 Containment Recirculation Spray Header Isolation
~
3RSS*MOV23A Containment Recirculation Pump Suction j 3RSS*MOV238 Containment Recirculation Pump suction 3RSS*MOV23C Containment Recirculation Pump Suction 3RSS*MOV2?D Containment Recirculation Pump Suction 6cnuinment Recirculation Pump Miniflow D 6tEiE - -a
!3RSS*MOV38A ~ ~' &
3RS$*MOV388 Containment Recirculation Pump Miniflow i t @
MILLSTONE - UNIT 3 3/4 8-46
, , , - _ _ . . . _ , , _ _ ,,,__ ,ey .., _. , __ _ _ ,.-,,-_,,,,,_,_,_..,m , . . , __, . _ . . . . , , _ . , , _ _ , , - _ _ . _ _ _ , , _
Mode M NOT- ADTD 61/A%ED 70 FINAL. DRAFT
. TA6LE. L 6 -Ib ' ,
16 ISS5
- . TABLE.3.8-2e (Continued)
MOTOR-OPERATIA VALVES THERMAL OVERLOAD PROTECTION
@ITH8YPASSDEV1tESTYPASSEDONLYUNDERACCIDENTCONDITION
~
~ - Ogtgre -
l SYSTEM (5)
VALVE NUMBER AFFECTED 3RSS*MV8837A Recirculation Spray System to Residual Heat N Re System Cross Connection 3RSS*MV88378 - Recirculation Spray System to Residual Heat Removal hF D6L6TE " system Cross Connection 3RSS*MV8838A Recirculation Spray System to Residual Heat Removal.
System Cross Connection 3RSS*MV88388 Recirculation Spray System to Residual Heat Removat System Cross Connection -
j y 3SIH*MV8801A Charging Pump to Cold Leg Isolation 3SIH*MVB8018 Charging Pump to Cold Leg Isolation M 3SIH*MV8802A Safety Injection Pump to Hot Leg Isolation 3SIH*MV8806 Refueling Water Storage Tank to Safety Injection Isolation 3SIH*MV8807A Safety Injection High & Connection to Low Pressu Safety Injection J (Acrt \
3SIH*MV8813 High Pnssure Safety Injection Pump Miniflow huto 3 6 T, 351H*MVLT High Pressure Safety Injection Pump Miniflow g
I 'MV8821A safety Injection Pump Discharge Isolatio hgcao 3SIH'MV88218 Safety Injection Pump Discharge Isolation 3SIH*MV8835 JIH Supply to LPSI 3SIH*MV8920 High Pressure Safety Injection Pump Miniflow DI 3SIH*MV8923'A Safety Injection Pump Suction 3SIH*MV89238 SafetyInjectionPumpsuction 3SIH*MV8924 Safety Injection / Charging Suetion Cross Connection l 3SIL*MV8804A Residual Heat Removal Pump to Charging Pump 351L*MV88048 Residual Heat Removal Pump to Charging Pump i
% L #aA,7 94;-RP4(-~*b + " P"r" f)gg -* sre<w W 90o 76 S*h 4 T seed.- ut MILLSTONE - UNIT 3 3/4 e-C ffu s
Mo0E pg, Nor ALTio IMPAssED TO RNA1. DEFT
. TA4tE 3.6- 2.b
,, ,,., TABLE 3.8-2a (Continued) OCT 181085 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION GITH B9AST DEVIcEhBYPA55ED ONLY UNDER ACCIDENT CONDITIONS SvISTSF AFFECTED VALVE NUMBER 3SIL*MV8808A Accumulation Isolation 3SIL*MV88088 Accumulation Isolation .-
3SIL*MV8808C Accumulation Isolation 3SIL*MV88080 Accumulation Isolation
'3SIL*MV8809A Residual Heat Removal Cold Leg Isolation' 351L*MV88098 Residual Heat Removal Cold Leg Isolation 3SIL*MV8812A Refueling Water Storage Tank to Residual Heat Removah PW I 3SIL*MV88128 Refueling Water Storage Tank to Residual Heat Removal Pump d
DF A PT5--* 3SIL*MV8840 Residual Heat Removal Hot Leg Isolation hFj
~
35WP"MOV24A Service Water Backwash j35WP*MOV248 Service Water Backwash 35WP*MOV24C Service Water Backwash SWP*MOV240 Service Water Backwash 35WP"MOV50A Reactor Plant Component Cooling Water Heat Exchanger 35WP*M0V508 Reactor Plant Component Cooling Water Heat Exchanger 35WP"MOV54A Containment Recirculation Cooler Service Water Outlet 35WP*M0V548 Containment Recirculation Cooler Service Water Outlet 35WP*MOV54C Containment Recirculation Cooler Service Water Outlet ,
35WP*M0Y540 Containment Recirculation Cooler Service Water Outlet 35WP*MOV57A Containment Recirculation Cooler Service Water Outlet N-35WP"MOV578 Containment Recirculation Cooler Service Water Outlet *A OFAETE ~~ Containment Recirculation Cooler Service Water Outlet 35WP"MOV57C 35WP*MOV57D Containment Recirculation Cooler Service Water Outletj 3.Trygggggot g Se % h h m kr 4 M hy Da W h/*
D6L2TS- Ji4 T *5 MILL 5TUMc
~
N00F, ALL hkTr- AUTO dy/ASSQ 70
%E 3,6 - 2 b ,
FINAL DRMT TABLE 3.8-2a (Continued) DCT 161923 "0TO F OPERATl0 VALVES THERMAL OVERLOAD PROTECTION H BYPASS DEVICE 5) BYPASSED ONLY UNDER ACCIDENT CONDITIONS SYS VALVE NUMBER AFFECTED 35WP*MOV71A Turbine Plant Component Cooling Water Heat Exchanger 35WP"MOV718 Turbine Plant Component Cooling Water Heat Exchanger 35WP"MOV102A service Water Pump Discharge .
n m A.,I 35WP*M0Y1028 Service Water Pump Discharge syd & 4 Service Water Pump Discharge Aef h eae 64 PASSED 3SWP*MOV102C 35WP"MOV102D Service Water Pump DischargeA w
Circulating Water Pump Bearing Lube Water Supply 35WP*MOV115A 35WP*M0Y1158 Circulation Water Pump Bearing Lube Water Supply 35WP"MOV130A Motor Control Center and Rod Control Service Water Isolation -
35WP*MOV1308 Motor Control Center and Rod Control Service Water Isolation
$e35 N
- r - W" gTAS+non2. C.o ~ wet gp p
- I w.s-i.s I
o .
e MILLSTONE - UNIT 3 3/4 8-49 l
1 .
1
O ENCLOSURE 3
mlALDRMT
- OCT 1 6 1o35 TABLE 3.8-2b
. MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION NOT BYPASSED SYSTEM (5)
VALVE NUMBER AFFECTED Containment Atmosphere Honitoring Isolatiod-M N 13CVS*MOV25 Steam Generator Feedwater Pump Isolation b 3FWS*MOV35A Steam Generator Feedwater Pump Isolatier.
~MM Ctwrva i;.ds D6LM"3FWS*MOV358 .
, Steam Generator Feedwater Pump Isolation
- 3FWS*M0V35C
31E*M0V72 Containment open Pressure Tap Isolation
- TM T.E-2 8 3LMS*MOV40A Containment Open Pressure Tap Isolation 3LMS*MOV408 1
Containment Open Pressure Tap Isolation 3U45*MOV40C Containment Open Pressure Tap Isolation 3LMS*MOV400 Steam Generator Auxiliary Feedwater Pump Steam Supply 3M55"MOV17A Non-Return Steam Generator Auxiliary Feedwater Pump Steam Supply 3M55*MOV178 Non-Return Steam Generator Auxiliary Feedwater Pump Steam Supply 3 MSS *MOV170 Non-Return
' 3M55*M0V18A
- Main Stream Pressure Relief Isolation no %( t= 2 Main Stream Pressure Relief Isolation g y ,
3 MSS *MOV188 3M55*MOV28C Main Stream Pressure Relief Isolation @ 4s -
. N"-' " p/ -
.3 MSS *l#V180 Main Stream Pressure Relief Isolation Qgg _ =.
Main Stream Pressure Relief 8ypass M 3M55*MOV74A Main Stream Pressure Relief typass l 3M55*MOV748 Main Stream Pressur8 Relief 8ypass 3 MSS *MOV74C Main Stream Pressure Relief Sypass 3MS3*MOV74D Refueling Watsr Chemical Addition Tank Discharge l 3QSS*MOV29A 1
3/4 8-51 MILLSTONE - UNIT 3
,._.,---_,--,,--,-.w_,._ . _., _ . , - , , - , , . , _ . , . -.,.,.-.-y - , _ , _ _ _ _ ~ _ , _c.--_.m_, _o , ,_ _ _ . _ . -., ,_... . , . _ . _ _ , . , ,,.-=,,%__,w-,----
. . FINAL. DRAFT TABLE 3.8-2b (Contir.ved) OCT 16 toB5 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION NOT SYPASSED SYSTEM (5)
VALVE NUMBER ,AFFECTED 3Q55*MDV298 Refueling Water Chemical Addition Tank Discharge 3Q55*MOY34A . Quench Spray Isolation 3Q55*MOV348 Quench Spray Isolation 3Q55*MOV44A Quench Spray pump Discharge] " s a W (
Deu m A 55*MOV445 Quench Spray pump Discharge j bleactor Coolant Loop Stop (Hot) l f3RCS*MV8001A ~
nos. Cl.,u I6 H0 'S ,
3RCS*MV8001C Reactor Coolant Loop Stop (Hot)
. 3RCS*MV8001D Reactor Coolant Loop Stop (Not) 3RCS*MV8003A Reactor Coolant Bypass Lag Stop l 3RCS*MV80038 Reactor Coolant Bypass Leg 5 top 3RCS*MV8003C Resctor Coolant Bypass Leg Stop
. 3RC5"MV80030 Reactor Coolant Sypass Leg Stop 3RCS*MV8002A' Reactor Coolant Loop Stop (Cold) 3RCS*MV80028 Reactor Coolant Loop Stop (Cold) 3RCS*MV8002C Reactor Coolant Loop Stop (Cold) 3RCS*MV80020 Reactor Coolant Loop Stop (Cold) l o ,
ADD " Mcr A0To &lPAssED" VALVES Fracm TA6LE 3 . 8 - Z ot.
e e
MILLSTONE - UNIT 3 ,
3/4 8-52
- - -_ .._ ,._ . . _ . - . .
