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Results
Other: ML20062G381, ML20062G387, ML20064C234, ML20064D492, ML20064E453, ML20064H429, ML20076A802, ML20076A836, ML20076A843, ML20076A904, ML20076A952, ML20076B087, ML20076B088, ML20076B089, ML20244A548, ML20244A585
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MONTHYEARML20236C3041976-09-14014 September 1976 Notification of 760928 Meeting W/Util in Bethesda,Md to Discuss Util Concepts for Proposed Neutron Shield for Plant. Summary of Neutron Streaming Problem Encl Project stage: Meeting ML20064C2341978-10-11011 October 1978 Forwards Proposed Tech Specs to Require Diesel Generator Start Time of Less than or Equal to 20 Project stage: Other ML20064D4921978-11-0101 November 1978 Presents Details of Stretch Power Effort in Advance of Execution to Enable Facility to Operate at 2,700 Mwt Following Second Refueling Outage Project stage: Other ML20064E4531978-11-18018 November 1978 Forwards Sys Description for Reactor Coolant Pump Shaft Speed Trip Function Being Installed by Util to Replace Steam Generator Differential Pressure Sys.Believes Proposal Is Exempt from Amend Fee Project stage: Other ML20062G3871978-12-14014 December 1978 Sleeved Guide Tube Inspec Prog, CEN-104(N)-NP.Describes Inspec Prog to Show Performance Re Wear.Edited to Delete Info W/Held from Pub Disclosure IAW 10CFR2.790 Project stage: Other ML20064H4291978-12-15015 December 1978 Appl to Amend Oper Lic DPR-65 by Increasing Maximum Allowable Thermal Output of Subj Facil Over 2700MWt to Commence W/Cycle 3 on 790515.W/att Environ Impact Appraisal, Eval of Radiological Consequences & Site Meteorology Project stage: Other ML20062G3811978-12-18018 December 1978 Forwards non-proprietary Version of Sleeved CEA Guide Tube Inspec Prog,CEN-104(N)-NP,relating to Amend 38 to DPR-65. IAW 10CFR2.790.W/encl Affidavit Project stage: Other ML20244A5481979-03-23023 March 1979 Provides Trip Setpoint for Proposed Tech Spec Revision to Incorporate Reactor Coolant Pump Speed Sensing Sys as Addition to Reactor Protection Sys Project stage: Other ML20076A8021979-04-0606 April 1979 in Answer to IE Bulletin 79-01,environmentally Qualified stem-mounted Limit Switches W/Appropriate Documentation Can Be Procured.Util Will Replace Switches W/Qualified Switches Prior to Start of Cycle 3 Operation Scheduled for May 1979 Project stage: Other ML20244A5851979-04-12012 April 1979 Forwards Info Re Proposed Revisions to Tech Specs to Reflect Installation of Reactor Coolant Pump Speed Sensing Sys to Provide Protection for 4-pump Loss of Flow Event Project stage: Other ML20076A8431979-04-13013 April 1979 Steam Generator Insp Project stage: Other ML20076A8361979-04-13013 April 1979 Eddy Current Test Has Been Performed.No Tube Defects Discovered & No Corrective Action Based on Tube Defects Required.Preliminary Analysis of Results of Insp Indicates Denting Rate Has Been Reduced Project stage: Other ML20076A9041979-04-18018 April 1979 Responds to IE Bulletin 79-01.One Solenoid Installed on safety-related Valve in Plant Containment Has Not Been Qualified for Svc in LOCA Environ.Solenoid Will Be Replaced Before Start of Cycle 3 Operation Project stage: Other ML20076A9551979-04-26026 April 1979 Responds to NRC 780419 Request for Insulation Resistance Tests.Forwards Electrical Penetration Testing Evaluation. Modified Conductor Configuration Is Acceptable for Cycle 3 Operation Project stage: Request ML20076A9521979-04-26026 April 1979 Discusses Guide Tube Insp Program.Pull Tests Performed on 35 Sleeves.Evaluation of Data Indicates Sleeves Are Functioning as Expected Project stage: Other ML20244A6131979-05-0303 May 1979 Forwards Responses to Request for Addl Info Re Cycle 3 Safety Analysis.Nonproprietary Rept Encl.Proprietary Version Withheld (Ref 10CFR2.790) Project stage: Request ML20076B0871979-05-0808 May 1979 Notifies That stem-mounted Limit Switches on Valves SI-614, SI-624,SI-634 & SI-644 Will Not Be Replaced;Valves Do Not Perform safety-related Function Project stage: Other ML20076B0881979-05-11011 May 1979 Discusses Results of Six Tasks Which Utilized Adlpipe Computer Program for Reanalysis of Piping Sys.Mods Involved Minor Changes to Small Portions of Existing Sys Project stage: Other ML20076B0891979-05-17017 May 1979 Forwards Addl Info Re Performance of Control Element Assembly Guide Tubed Sleeves,In Response to Project stage: Other 1979-04-12
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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] |
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May 3, 1979 Docket No. 50-336 Director of Nuclear Reactor Regulation Attn: Mr. R.'Reid, Chief Operating Reactors Branch #4 U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Reference:
(1) W. G. Counsil letter to R. Reid, dated February 12, 1979.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Additional Information Concerning Cycle 3 Safety Analyses During the pit.st zeveral weeks, our respective Staffs have been discussing the material presente.d in Reference (1) supporting Cycle 3 operation. The most recent set of questions was supplied in an undocketed fashion; nonetheless, formal responses are provided as Attachment 1.
The response to Question 2.2 contains material proprietary to Combustion Engineering. Accordingly, the response is provided as CEN-110(N)-P. Due to the proprietary nature of the material contained in CEN-110(N)-P, Northeast Nuclear Energy Company (NNECO) requests that the document be withheld from public disclosure in accordance with the provisions of 10CFR2.790 and that this material be safeguarded. The reasons for the classification of this material as proprietary are delineated in the attached affidavit provided by Combustion Engineering.
In light of the proximity of the scheduled start of Cycle 3 operation for Millstone Unit No. 2, your prompt and favorable disposition of the attached responses would be greatly appreciated.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
/-
W. G. Counsil Vice President g h
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. DOCKET NO. 50;336 l
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1 ATTACHMENT 1 MILLSTONE NUCLEAR POWER STATION, UNIT No. 2 ADDITIONAL INFORMATION CONCERNING CYCLE 3 SAFETY ANALYSES e
MAY, 1979
. o AFFIDAVIT PURSUANT TO 10 CFR 2.790 Combustion Engineering, Inc. )
State of Connecticut )
County of Hartford ) SS.:
1, A. E. Scherer depose and say that I am the Manager, Licensing of Combustion Engineering, Inc., duly authorized to make this affidavit, and
'have reviewed or caused to have reviewed the information which is identified as proprietary and referenced in the paragraph immediately below. I am submitting this affidavit in conformance with the provisions of 10 CFR 2.790 of the Commission's regulations and in conjunction with the application of Northeast Nuclear Energy Company for withholding this information.
The information for which proprietary treatment is sought is contained in the following document:
CEN-110(N)-P, Response to NRC Question 2.2 On The Millstone Unit No. 2 Cycle 3 Reload Application. Docket No. 50-336 May 2, 1979.
This document has been appropriately designated as proprietary.
I have personal knowledge of the criteria and procedures utilized by Combustion Engineering in designating information as a trade secret, privileged or as confidential commercial or financial information.
Pursuant to the provisions of paragraph (b) (4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration {
by the Commission in determining whether the information sought to be withheld from public disclosure, included in the above referenced document, should be withheld.
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- 1. The information sought to.be' withheld from public disclosure is results.of analyses in support of setpoint methodology which is owned and
-has been held in confidence by Combustion Engineering.
- 2. The information consists of test data or other similar data concerning a process, method or component, the application of which results in a substantial competitive advantage to Combustion Engineering.
- 3. The information is of a type customarily held in confidence by Combustion Engineering and not customarily disclosed to the public.
Combustion Engineering has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when_and whether to hold certain types of information in confidence. The details of the aforementioned system were provided to the Nuclear Regulatory Commission via letter DP-537 from F.M. Stern to Frank Schroeder dated December 2,1974. This system was applied in determining that the subject ecuments herein are proprietary.
- 4. The information is being transmitted to the Commission in confidence under the provisions of 10 CFR 2.790 with the understanding that it is to be received in confidence by the Commission.
- 5. The information, to the best of my knowledge and belief, is not available in public sources, and any disclosure to third parties has been made pursuant to regulatory provisions or proprietary agreements which l provide for maintenance of the infonnation in confidence.
- 6. Public disclosure of the information is likely to cause substantial !
harm to the competitive position of Combustion Engineering because: l
- a. A similar product is manufactured and sold by major pressurized water reactors competitors of Combustion Engineering.
- b. Development of this information by C-E required hundreds of man-hours of effort and tens of thousands of dollars. To the best of my knowledge and belief a competitor would have to undergo similar expense in generating ~ equivalent information.
- c. In order to acquire such information, a competitor would also require considerable time and inconvenience related to obtaining access to computer facilities and conducting extensive computer programs.
- d. The information required significant effort and expense to obtain the licensing approvals necessary for application of the information.
Avoidance of this expense would decrease a competitor's cost in applying the information and marketing the product to which the information is applicable,
- e. The infonnation consists of supporting data for analyses, the application of which provides a competitive economic advantage. The availability of such information to competitors would enable them to modify their product to better compete with Combustion Engineering, tr.ke marketing or other actions to improve their product's position or impair the position of Combustion Engineering's product, and avoid developing similar data and analyses in support of their processes, methods or apparatus,
- f. In pricing Combustion Engineering's products and services, significant research, development, engineering, analytical, manufacturing, licensing, quality assurance and other costs and expenses must be included.
i The ability of Combustion Engineering's competitors to utilize such information without similar expenditure of resources may enable them to sell at prices l
reflecting signi.'icantly lower costs.
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- g. Use of the information by competitors in the international !
marketplace would increase their ability to market nuclear steam supply systems by reducing the costs associated with their technology development.
1 In addition, disclosure would have an adverse economic impact on Combustion Engineering's potential for obtaining or maintaining foreign licensees.
Further the deponent sayeth not.
1 - ~s> w ~
AT E Ta6eFer Manager, Licensing Sworn to before me this 2nd day of Ma , 1979 W eden'?/Glfff/0 otary Public P USA G. WAICUNAS. NOTARY PUBUC State of Connecticut No (4492 Commlaston Expires March 31,1983 I
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-Question 2.1: Questions on, the AT' Power Calculator Time Delay Compensation L . Circuit ~(TDCC)
L L a. ' You'have' stated'that the TDCC circuitry can be'(and is):
bypassed if the RTD time constant is less than or equal
% to.eight seconds. Justify this statement. Is this result .
' Cycle 3 specific, Millstone 2 specific, or CE Generic?
- b. is there an adjustment of the TM-LP coefficient's to account for the bypassing'of the TDCC?
- c. Some transients which affect the'TDCC coefficients are not reanalyzed in Cycle 3. e.g., Excess Load (Complete list appears in 'CENPD-199 Table 5-2). Could their reanalysis change your conclusion on the.TDCC?
Response:-
o . .
2.1 44 The aT Power calculator (ATPC) circuitry as stated in CENPD-199, consists of two components,: the ' static portion, and the dynamic portion. The dynamic portion ("a" and."F equipment coefficients) modulates the static portion of the signal.in the ATPC during a transient. For Millstone 2. Cycle 3, the analysis justified zeroing out the dynamic coefficients-in the ATPC for a - ,
RTD time constantd8. seconds.' However, the circuitry was not bypassed as implied in'the question. This procedure is specific to~ Millstone-2 Cycle 3 and not generic to all . plants that CE reloads, 2.1.b.
The QR1 function, which augments the power reading, is boosted to compensate for ~ zeroing out the dynamic portion of. the ATPC in order to produce a conservative-power reading, if necessary. This is, in fact, what was done for . Cycle 3. It should be noted that the AT dynamic compensation is not " bypassed" per se, only the coefficients are set to zero.
2 .1. c .
As stated in CENPD-199, all- those events listed in Table 5-2 depend on the ATPC for a conservative power input to the RPS. Of all those events, the excess load and CEA withdrawal produce the greatest cooldown and heatup of the NSSS, respectively. If the AT Power reading for those' events is conservative, then the AT Power will be conservative for all other events which are not as fast (e.g. , loss of load). For Cycle 3, these two transients were re-analyzed to determine that input to the ATPC would produce
- conservative power readings. Although this seems to contradict the statement made in the reload license submittal on the Excess Load Event,~our meaning'then was that the Excess Load Event was not re-analyzed
.as in the FSAR. Instead, we ensured that the inputs to the TM/LP trip system were conservative to avoid violation of a 1.19 CE-1 DNBR for the Excess Load Event. Further discussion is provided in response to question 2.3.
y
(Section 7.1.4 Excess Load Event)
You state "The Excess Load Incident analysis presented in the FSAR for 2560 MWT operation conservatively bounds Cycle 3 operation at
' 2700 MWT." This is not at all obvious, and may, in fact, be incorrect. In the FSAR analysis, the minimum W-3 DNBR reached was 1.80.
For Cycle 3, the Core Power, Pressure, Temperature, Flow, and Radial Peaking Factor has changed from the values used in the FSAR analysis. The changes in all these parameters is roughly equivalent to a change in W-3 DNBR of -0.43. Thus, in a first approximation, it appears that if the FSAR analysis were performed with Cycle 3 parameters, the minimum W-3 DNBR reached would be roughly 1.80-0.43=1.37.
In view of the potential inaccuracy in the computation of the DNBR=1.37 value, there appears to be considerable likelihood that if the FSAR ar.alysis were performed using Cycle 3 parameters, the results woulc show a minimum W-3 DNBR less than the allowed limit of 1.30. In view of this, a reanalysis of the Excess Load event seems appropriate. Either provide such reanalysis or else provide justification for not performing this analysis.
Response
2.3 The criteria for the Excess Load event is a minimum 1.19 (CE-1) DNBR. As stated in the FSAR, the high power . trip, low steam generator pressure trip, low steam generator water level trip, or the Thermal its SAFDL.
Margin / Low Pressure trip will prevent the DNBR from going below To verify that the DNBR for the Excess Load is >1.19 (CE-1),
an explicit minimum DNBR can be generated (as in the FSAR) or all the inputs to the TM/LP trip can be demonstrated to be conservative for this event.
For MP-2, Cycle 3, the latter approach was utilized. If the combination of the power input, temperature input, and the bias term (y) in the TM/LP is conservative for this event, a TM/LP trip will prevent a CE-1 DNBR below 1.19.
j For Cycle 3, our evaluations showed that all the inputs to the TM/LP will be conservative for Excess Load.
To address your specific concern that the DNBR might go below a 1.19 DNBR (CE-1), an explicit case was' rbn. The analysis of the full power Excess o
Load event, performed in the same manner as the FSAR initiated at the proposed Cycle 3 Tech Spec LCOs, results in a minimum DNBR of 1.43 (CE-1).
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q t Question 2.4i (Section 7.2.1, Loss of RCS. Flow Event) j
. The change'i.nianalytical methodology required to accomodate. the RCP !
speed trip is;not delineated inL the Rel oad Application. . From avail-able information, we. surmise the following paragraph explainsJthe change'in methodology. Please advise.us,if.there are any errors in.
our. understanding.
For both past analyses and the present analysis, ~the time-dependent core and individual loop flows and steam generator pressure drops
~
.'are determined by using the C0AST program (described'in CENPD-98).
which solves the conservation equations for mass' flow and momentum.
The general forcing. functions for the fluid momentum equations consist of.the pump torque values. from the manufacturer's four quadrant curves, wherein' the torque is related to the ' pump angular velocity and discharge rate. The output of C0AST includes the time dependence of both the RCS flow and the RCP speed. In. the Four Pump Loss of Flow analysis, .
tne trip is assumed to occur at a pump speed of 839 rpm rather than the a specified flow, as has been the case in past analyses. In either case, C0AST' predicts a trip time. The only change in the analytical =
method required to accommodate the RCP speed sensing system is the-determination of the trip time from~ the RCP speed curve rather than the RCS flow curve'.
Response
2.4
.There has not been any change in analytical methodology to accommodate the
-RCP Speed Sensing System. In the reload license application, it is assumed that this system dll atsure a reactor trip at a- flow rate greater than or equal to 91.5% of minimum guaranteed flow, ;ith a trip signal delay time ..
for the speed sensing system of 0.45 seconds. These were the values: assumed I in the analyses 'of the 4-pump Loss-of-Flow. The values are consistent with previously submitted Technical Specification changes.
The conversion from percent flow to rpm was made subsequent to completion of the 4-pump Loss-of-Flow analysis so that the appropriate value (029 rpm) could be provided for Technical Specifications.
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a a Question 2.5-(Section 7.2.1, Loss of. RCS Flo'w Event) li F
. a. LIn Principle, the Required Over-Power Margin (ROPM) is determined by the most limiting of the Four Pump loss of Flow, the Two Pump '
Loss of Flow, the CEA Drop, and the Malfunction of One Steam Generator events. Was the R0PM, in fact, computed for all these or was.it only computed.for the Four Pump Loss of Flow Event?.
- b. 1he-ROPM is used' to compute the DNBR LC0 ASI Tent'. This being.
'.the case, these transient (s) should be examined for a variety '
of Powers and ASI, and possibly other parameters such as Axial Shape, Rod Insertion, and Burnup. Enumerate the parameters that are varied for each. transient analyzed. and indicate the range and number of values. assumed for these parameters.
- c. Are the analyses of the four transients under consideration which are reported in' the Reload Application performed assuming the DNBR LCO ASI Tent determined from the limiting R0PM7
- d. In the analyses of these four transients which are reported in the Reload Appl.ication, how are the initial conditions for the ;
transients determined? In particular, do the initial conditions assumed produce the' minimum DNBR,i.e. , are the DNBR reported for these transients on the reload application the. minimum possible DNBR? !
i
Response
2.5.a The R0PM was computed for all of the se transients.
2.5.b .
Complete discussions for these transients are provided in Sections .
7.0 &8.0 of CENPD-199-P. As indicated in the report, sensitivity studies were made to determine the sensitivity of these transients to variations in different parameters. Results of these studies and l the parameters considered are reported in CENPD-199-P.
2.5.c :
Descriptions of methodologies for these four transients are provided in CENPD-199-P. The most limiting Required Overpower Margin's (ROPM) of all of these transients form the bases for the DNB LCO ASI Tent.
Therefore, for any of the* e transients starting from within the LCO, the minimum CE-1 DNBR will automatically be at or higher than 1.19.
2.5.d The selection of initial conditions for these transients is discussed in i CENPD-199-P. These initial conditions produce'the minimum DNBR and in those instances where the minimum DNBR is quoted in the license submittal, these are, in fact, the most limiting values one wodd see when the transient is initiated from within the DNBR LC0 limits.
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Question 2.6 (Section 7.2.5, Loss of Load to One SG)
~ '
. What is the peak KW/ft predicted for this transient?
Response
2.6 The initial PLHR assumed for this analysis was~16 kw/ft. The 16 kw/ft value is the maximum allowable initial PLHR for non-LOCA transients.
The maximum predicted PLHR during Loss of Load to one steam generator (based in this initial.PLHR) is 19.0 kw/ft. Since for Millstone Unit No. 2 cycle 3 the maximum allowable PLHR is 15.6 kw/ft, the predicted maximum is less than 19.0 kw/ft.
(
Question 2.7: (Section 7.3.3, Steam Generator Tube Rupture Event)
The sequence of events delineated in Table 7.3.3-2 do not appear )
to correlate with the pressure plot of Figure 7.3.3-5. Explain what causes each pressure change in Figure 7.3.3-5 and explain how these pressure changes are related to the events of Table l 7.3.3-2. I
Response
2.7 Table 7.3.3-2 in the license submittal lists the times when the dump valves and the bypass valves initially open and finally close. In between the initial opening and final closing of the bypass valves',
predictions indicate that these valves reopen and close a couple of times. The attached table gives the detailed opening and closing of the valves.
The following is a descriptive sequence of events:
Time (Sec) Event
- 1) 825.6 The first decrease in pressure is caused by opening of the dump and bypass valves on turbine trip. The turbine admiss son valve also starts closing at this time.
- 2) 830.0 The pressure then starts to increase because of the turbine admission valve closure since the dump and bypass valves are unable to handle the full load rejection initially.
- 3) 839.0 The pressure decreases when the steam dump and bypass are able to keep pace with the load rejection. At this time, the capacity of the valves are greater than the steam flow.
- 4) 882.0 The pressure then increases when the steam dump and bypass valves close. The closure of the valves is caused by the primary Tave dropping below the closing setpoint of the dumps and the secondary pressure being below the closing setpoint of the bypass valves.
l l 5) 898.4 When the pressure again exceeds the opening pressure
- setpoint of the bypass valves, the bypass valves reopen, causing the pressure to decrease once again.
- 6) 913.2 The pressure then decreases below the bypass pressure setpoint and the bypass valves finally close.
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- SEQUENCE OF EVENTS FOR '
-THE STEAM GENERATOR TUBE RUPTURE INCIDENT Time (Sec) Event Setpoint or Value 0.0 Tube Rupture Occurs 825.2 Pressurizer Empties --
825.2 Low Pressurizer Pressure Trip Condition 1728 psia l 825.6 Dump Valves Open --
825.6 Bypass Valves Open --
826.6 CEAs Begin to Drop into Core --
830.0 Turbine Valve Closes --
8 39.0 Maximum Steam Generator Pressure 901.4 psia i 882.0 Dump Valves Close --
882.0 Bypass Valves Close --
898.4 Bypass Valves Reopen. --
913.2 Bypass Valves Reclose --
1800.0 Operator Initiates Appropriate Action and --
Begins Cooldown to 300 F l
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, CEN-110(.N) + NP RESPONSE TO N.R.C. QUESTION 2.2 ON THE MILLSTONE UNIT NO. 2 CYCLE 3 RELOAD APPLICATION, DOCKET NO 50-336 MAY 2, 1979 i
Combustion Engineering, Inc.
Nuclear Power Systems /\
yY Windsor, Connecticut
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d LEGAL NOTICE
.THIS REPORT WAS PREPARED AS AN ACCOUNT OF WORK SPONSORED BY. COMBUSTION ENGINEERING, INC. NEITHER COMBUSTION ENGINEERING -
NOR ANY PERSON ACTING ON ITS BEHALF:
A. MAKES ANY WARRANTY OR REPRESENTATION, EXPRESS OR IMPLIED INCLUDING THE WARRANTIES OF FITNESS FOR A PARTICULAR PURPOSE OR MERCHANTABILITY, . WITH RESPECT TO THE ACCURACY, j COMPLETENESS, OR USEFULNESS OF THE INFORMATION CONTAINED IN THIS ;
. REPORT, OR THAT THE USE OF ANY INFORMATION, APPARATUS, METHOD, OR PROCESS DISCLOSED IN THIS REPORT MAY NOT INFRlNGE PRIVATELY OWNED RIGHTS;OR B. ASSUMES ANY LIABILITIES WITH RESPECT TO THE USE OF,OR FOR DAMAGES RESULTING FROM THE USE OF, ANY INFORMATION, APPARATUS, METHOD OR PROCESS DISCLOSED IN THIS REPORT. -
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_ , Response to URC Question 2.2 on the Millstone Unit 2 Reload Application Question 2.2: (Section 7.1.1, CEA Withdrawal Event)
The Time deley Adjustment Bias (TAB) for the TM-LP parameter is, in principle,. determined by the transient, for which DNBR suffers the greatest degradation af ter core ' conditions have -
reached the TM-LP setp'oint. All potentially limiting transients should be considered in computing the TAB. (The loss of Flow, Seized Rotor, CEA Drop, CEA Ejection, Steam Line Rupture, and Malfunction of One Steam Generator Events do not require the TM-LP trip, and hence, are excluded from consideration in the determination of the TAB.) Ordinarily, the limiting transient is either CEA Withdrawal or RCS Depressurization. However, all transients (except those noted above) should be examined to ascertain that they are, in fact, not more limiting than those two.
For those other' transients, it is ordinarily not necessary to compute the TAB, but only to demonstrate that they produce substantially slower degradation in DNBR that the two limiting transients. Provide answers to the three following questions.
- a. Was the comparison of' speed of degradation described above performed? If so, what transients were considered?
- b. If this comparisoa was performed, what is your criterion for a saying that one transient produces substantially slower DNBR f degradation than another transient?
i c. The iiransient'with the fastest degradation in DNBR does not i necessarily produce the limiting TAB because the shap of the turnaround in DNBR vs Time curve is a function of the particular
~
L l transient being analyzed. (This is why both CEA Withdrawal and
- RCS Depressurization are normally both analyzed, and not simply j the one with the fastest degradation in DNBR.) Explain how the i criterion of questions b above is justified in view of i
'the above consideration. Do this in numerical terms to demon-strate the confidence we can put on your criterion.
Response: .
2.2.a -
)
As stated in section 5.6.1 of CENPD-199-P, and as indicated in Table 1-3 l of the same report., [r 1
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! 2.2.b The purpose of the bias factor is to accommodate the trip delays for the most
( severe transients for which protection is provided by the TM/LP tri,p.
The transients with [
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