Letter Sequence RAI |
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Results
Other: A04104, Forwards Overview Re Appeal for Requested Mod of Hydrogen Purge Sys Valves to Close on Radiation Signal,Per Generic Ltr 84-08 & NUREG-0737,Item II.E.4.2.7, Containment Venting at Power. Addl Info Re Leakage Testing Expected by 840730, B11269, Forwards Figure 3.1,per Re NUREG-0737,Item II.E.4.2.7, Containment Venting at Power, Providing Justification That Isolation Logic for Hydrogen Purge Valves Adequate, ML20078N847, ML20134A587, ML20134A599, ML20137A490, ML20137B423, ML20137B442
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MONTHYEARA03035, Forwards Response to NRC Request for Addl Info Re Operability of 6-inch Butterfly Containment Purge & Vent Valves.Based on Analyses,Adequate Justification Does Not Exist to Warrant Mods to Equipment1983-03-28028 March 1983 Forwards Response to NRC Request for Addl Info Re Operability of 6-inch Butterfly Containment Purge & Vent Valves.Based on Analyses,Adequate Justification Does Not Exist to Warrant Mods to Equipment Project stage: Request ML20078N8471983-10-27027 October 1983 Forwards Response to NRC 830902 Comments on Unresolved Items Re Containment Purge/Vent Review.No Addl Tech Specs or Equipment Mods Warranted.Operability Requirement Met W/Compliance W/Tmi Item II.E.4.2 Project stage: Other A03992, Requests Informal Appeal Meeting W/Nrc to Review Requested Mod of Hydrogen Purge Valves to Close on High Radiation Signal,Per Generic Ltr 84-08 & NUREG-0737,Item II.E.4.2.71984-05-15015 May 1984 Requests Informal Appeal Meeting W/Nrc to Review Requested Mod of Hydrogen Purge Valves to Close on High Radiation Signal,Per Generic Ltr 84-08 & NUREG-0737,Item II.E.4.2.7 Project stage: Meeting A04104, Forwards Overview Re Appeal for Requested Mod of Hydrogen Purge Sys Valves to Close on Radiation Signal,Per Generic Ltr 84-08 & NUREG-0737,Item II.E.4.2.7, Containment Venting at Power. Addl Info Re Leakage Testing Expected by 8407301984-07-11011 July 1984 Forwards Overview Re Appeal for Requested Mod of Hydrogen Purge Sys Valves to Close on Radiation Signal,Per Generic Ltr 84-08 & NUREG-0737,Item II.E.4.2.7, Containment Venting at Power. Addl Info Re Leakage Testing Expected by 840730 Project stage: Other B11269, Forwards Figure 3.1,per Re NUREG-0737,Item II.E.4.2.7, Containment Venting at Power, Providing Justification That Isolation Logic for Hydrogen Purge Valves Adequate1984-07-13013 July 1984 Forwards Figure 3.1,per Re NUREG-0737,Item II.E.4.2.7, Containment Venting at Power, Providing Justification That Isolation Logic for Hydrogen Purge Valves Adequate Project stage: Other B11271, Application for Amend to License DPR-65,revising Tech Specs Re Fire Protection Sys,Including Fire Detectors,Fire Water Pump Diesels,Spray/Sprinkler Sys,Hose Station & Penetration Fire Barriers.Fee Paid1985-05-28028 May 1985 Application for Amend to License DPR-65,revising Tech Specs Re Fire Protection Sys,Including Fire Detectors,Fire Water Pump Diesels,Spray/Sprinkler Sys,Hose Station & Penetration Fire Barriers.Fee Paid Project stage: Request ML20129A1511985-05-31031 May 1985 Proposed Tech Specs Re Fire Protection Sys,Including Fire Detectors,Fire Water Pump Diesels,Spray/Sprinkler Sys,Hose Station & Penetration Fire Barriers Project stage: Other B11598, Forwards Millstone Nuclear Power Station Unit 2 Inservice Insp & Testing Program, for Second 10-yr Insp Interval to Commence on 851226.Response Re Acceptability Requested by 8512261985-06-27027 June 1985 Forwards Millstone Nuclear Power Station Unit 2 Inservice Insp & Testing Program, for Second 10-yr Insp Interval to Commence on 851226.Response Re Acceptability Requested by 851226 Project stage: Request ML20126M2981985-07-24024 July 1985 Application for Amend to License DPR-65,revising Tech Specs to Expand Storage Capacity of Spent Fuel Pool from 667 to 1,112 Storage Locations by Reracking Spent Fuel Pool W/Combination of Poison & Nonpoison Racks.Fee Paid Project stage: Request B11549, Proposed Tech Spec Revs to Sections 5 & 3/4.9,expanding Storage Capacity of Spent Fuel Pool from 667 to 1,112 Storage Locations by Reracking Spent Fuel Pool W/Combination of Poison & Nonpoison Racks in Two Region Arrangement1985-07-24024 July 1985 Proposed Tech Spec Revs to Sections 5 & 3/4.9,expanding Storage Capacity of Spent Fuel Pool from 667 to 1,112 Storage Locations by Reracking Spent Fuel Pool W/Combination of Poison & Nonpoison Racks in Two Region Arrangement Project stage: Other ML20134N6051985-08-26026 August 1985 Forwards Auxiliary Sys Branch Request for Addl Info Re Util 850724 Request to Modify Tech Spec Concerning Expansion of Spent Fuel Storage Capacity.Response Requested within 15 Days Project stage: RAI ML20135G1691985-09-0505 September 1985 Forwards Request for Addl Info Re Spent Fuel Storage Capacity Expansion,To Complete Review of 850724 Request to Modify Tech Specs.Info Requested within 15 Days of Ltr Receipt Project stage: RAI B11712, Forwards Response to 850826 Request for Addl Info Re Util 850724 Proposed Change to Tech Spec Mods for Spent Fuel Storage Pool Capacity1985-09-16016 September 1985 Forwards Response to 850826 Request for Addl Info Re Util 850724 Proposed Change to Tech Spec Mods for Spent Fuel Storage Pool Capacity Project stage: Request ML20133F2641985-10-0101 October 1985 Proposed Rev to Tech Spec 3/4.7.10,adding Continuous or Hourly Fire Watch Patrol Until Temporary or Inoperable Fire Barrier Permanently Repaired Project stage: Other B11733, Rev to 850528 Application to Amend License DPR-65,adding Continuous or Hourly Fire Watch Patrol Until Temporary or Inoperable Fire Barrier Permanently Repaired.Determinations Re 10CFR50,App R Still Applicable1985-10-0101 October 1985 Rev to 850528 Application to Amend License DPR-65,adding Continuous or Hourly Fire Watch Patrol Until Temporary or Inoperable Fire Barrier Permanently Repaired.Determinations Re 10CFR50,App R Still Applicable Project stage: Request ML20133E7071985-10-0303 October 1985 Forwards Structural & Geotechnical Engineering Branch Request for Addl Info to Complete Review of 850724 Application to Modify Tech Specs Re Spent Fuel Storage Capacity Expansion Project stage: RAI B11777, Forwards Response to Request for Addl Info Re 850724 Application to Revise Tech Specs on Spent Fuel Storage Capacity1985-10-17017 October 1985 Forwards Response to Request for Addl Info Re 850724 Application to Revise Tech Specs on Spent Fuel Storage Capacity Project stage: Request B11827, Forwards Addl Info Requested in Oct 1985 Re Util Request to Modify Tech Specs Concerning Spent Fuel Storage Capacity1985-10-28028 October 1985 Forwards Addl Info Requested in Oct 1985 Re Util Request to Modify Tech Specs Concerning Spent Fuel Storage Capacity Project stage: Other ML20134A5871985-10-29029 October 1985 Forwards Notice of Consideration of Issuance of Amend to License DPR-65 & Proposed NSHC Determination & Opportunity for Hearing Re 850724 Application to Expand Spent Fuel Pool Storage Capacity Project stage: Other ML20134A5991985-10-29029 October 1985 Notice of Consideration of Issuance of Amend to License DPR-65 & Proposed NSHC Determination & Opportunity for Hearing.Amend Authorizes Licensee to Increase Spent Fuel Pool Storage Capacity from 667 to 1,112 Storage Locations Project stage: Other B11889, Forwards Confirmation of Resolution to Request for Addl Info Re Application for Increased Spent Fuel Storage Capacity Based on Series of Telcons1985-11-25025 November 1985 Forwards Confirmation of Resolution to Request for Addl Info Re Application for Increased Spent Fuel Storage Capacity Based on Series of Telcons Project stage: Request B11766, Submits Isap Topic 1.11, Post-Accident Hydrogen Monitor Per 850517 Commitment.Installation of Redundant Containment Hydrogen Monitor Unnecessary.Addl Info Will Be Provided by 8601311985-11-25025 November 1985 Submits Isap Topic 1.11, Post-Accident Hydrogen Monitor Per 850517 Commitment.Installation of Redundant Containment Hydrogen Monitor Unnecessary.Addl Info Will Be Provided by 860131 Project stage: Request B11893, Forwards Review of Spent Fuel Storage Capacity Expansion Request,Containing Proposed Mod to Tech Spec Re Decay Time Requirement,In Response to NRC 850826 Request for Addl Info1985-11-27027 November 1985 Forwards Review of Spent Fuel Storage Capacity Expansion Request,Containing Proposed Mod to Tech Spec Re Decay Time Requirement,In Response to NRC 850826 Request for Addl Info Project stage: Request B11910, Responds to Request for Addl Info Re Spent Fuel Storage Capacity.Analysis Showing That Adjacent Modules Do Not Contact During Seismic Event Inadvertently Omitted from1985-12-0303 December 1985 Responds to Request for Addl Info Re Spent Fuel Storage Capacity.Analysis Showing That Adjacent Modules Do Not Contact During Seismic Event Inadvertently Omitted from Project stage: Request ML20137B4421985-12-16016 December 1985 Environ Assessment & Finding of No Significant Impact Supporting Amend to License DPR-65,authorizing Increase of Spent Fuel Pool Storage Capacity Project stage: Other B11916, Provides Supplemental Relief Request Info Re Inservice Insp & Testing Program.Main Feed Sys Check Valves 2-FW-5A & 2-FW-5B Cannot Be Tested Per ASME Boiler & Pressure Vessel Code.Periodic Valve Disassembly Suggested1985-12-16016 December 1985 Provides Supplemental Relief Request Info Re Inservice Insp & Testing Program.Main Feed Sys Check Valves 2-FW-5A & 2-FW-5B Cannot Be Tested Per ASME Boiler & Pressure Vessel Code.Periodic Valve Disassembly Suggested Project stage: Supplement ML20137B4231985-12-16016 December 1985 Forwards Environ Assessment & Finding of No Significant Impact Re 850724 Request for Amend to License DPR-65 Concerning Spent Fuel Pool Expansion Project stage: Other ML20137B4321985-12-16016 December 1985 Notice of Environ Assessment & Finding of No Significant Impact Re Issuance of Amend to License DPR-65,changing Tech Specs to Increase Storage Capacity of Spent Fuel Pool Project stage: Approval ML20137A4901985-12-31031 December 1985 Forwards Addl Info Demonstrating Compliance w/NUREG-0737, Item II.E.4.2.7 Re Containment Venting Through Hydrogen Purge Valves,Per 840425,0902 & 1211 Requests Project stage: Other ML20141F8781986-01-0303 January 1986 Advises That Review Underway of Proposed Inservice Insp & Testing Program,Submitted on 850627.Proposal Would Increase Program Beyond Current Tech Spec Requirements.Final Approval of Submission Will Be Granted Upon Completion of Review Project stage: Other ML20214N7971987-05-27027 May 1987 Forwards Request for Addl Info for Review of 850627 Submittal Re Inservice Testing at Facility.Addl Info Should Be Submitted within 60 Days of Ltr Receipt Project stage: RAI A06539, Ack Receipt of Encl NRC Invoices for Costs Incurred in Review of Util Submittals for Plants.Fee Will Be Sent to J Rodriquez,Per 10CFR50,55 & 1701987-05-29029 May 1987 Ack Receipt of Encl NRC Invoices for Costs Incurred in Review of Util Submittals for Plants.Fee Will Be Sent to J Rodriquez,Per 10CFR50,55 & 170 Project stage: Other ML20195G5271987-10-0202 October 1987 Technical Evaluation Rept:Millstone Nuclear Power Station, Unit 1,Post-Fire Shutdown Evaluation,App R Project stage: Other A06958, Confirms 880515 Revised Due Date for Util Response to NRC Request for Addl Info Re Inservice Insp Program,Per Telcons W/Facility Project Manager1988-01-0808 January 1988 Confirms 880515 Revised Due Date for Util Response to NRC Request for Addl Info Re Inservice Insp Program,Per Telcons W/Facility Project Manager Project stage: Request ML20151M0621988-04-14014 April 1988 Advises That Revised post-fire Safe Shutdown Methodology Conforms W/Requirements of Sections III.G.3. & Iii.L of App R,10CFR50 & Acceptable,Per .Technical Evaluation Rept SAIC-87/3084 Encl Project stage: Other ML20154E9881988-05-12012 May 1988 Fowards Addl Info Re Inservice Insp Program,Per 880212 Request.Attachment 1 Consists of Util Response to Questions Posed in NRC & Attachment 2 Consists of Revised Program Sections Project stage: Other ML20150C7151988-06-28028 June 1988 Forwards Request for Addl Info Re Pump & Valve Inservice Testing Program.Response Requested within 60 Days of Receipt of Ltr Project stage: RAI 1985-12-31
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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:NRC TO UTILITY
MONTHYEARML20062F4991990-11-16016 November 1990 Forwards List of Unimplemented GSIs at Facilities,Per Generic Ltr 90-04.Timely Completion Requested ML20062G2441990-11-16016 November 1990 Forwards Combined Insp Repts 50-245/90-23,50-336/90-25 & 50-423/90-23 on 901001-05.No Violations Noted ML20217A6661990-11-15015 November 1990 Requests Addl Info Concerning Boraflex Degradation in Millstone 2 Spent Fuel Pool Storage Racks to Support Review of Util 901001 Submittal.Info Re Gamma Doses to Boraflex Matl During Blackness Testing & Storage Patterns Requested ML20058J1111990-11-14014 November 1990 Forwards Safety Insp Rept 50-423/90-19 on 900905-1015 & Notice of Violation ML20217A2021990-11-0909 November 1990 Forwards Insp Repts 50-213/90-83,50-245/90-82 & 50-336/90-82 & 50-423/90-83 on 900924-28.No Violations Noted ML20217A0821990-11-0505 November 1990 Forwards Safety Insp Rept 50-336/90-18 on 900822-1001 & Notices of Violation & Deviation ML20058F7061990-11-0101 November 1990 Forwards Amend 47 to License DPR-21 & Safety Evaluation. Amend Deletes Requirement That Combined Time Interval for Any Three Consecutive Surveillance Intervals Not to Exceed 3.25 from Tech Spec 1.0.X ML20062D5441990-10-30030 October 1990 Confirms 901018 Telcon Re Possible Unanalyzed Condition Re Repairs for Steam Generator Tube Plugs in Mar 1989 ML20058C3761990-10-30030 October 1990 Ack Receipt of & Payment of Civil Penalty in Amount of $25,000 for Violations Re Main Steam Line High Flow Setpoints & Gas Turbine Generator Surveillance Testing ML20058G3421990-10-29029 October 1990 Forwards Exam Rept 50-245/90-10OL Administered During Wk of 900827 ML20058E5871990-10-26026 October 1990 Discusses Programmed Enhancements for Generic Ltr 88-17, Loss of Dhr ML20058E6201990-10-26026 October 1990 Forwards Safety Insp Repts 50-245/90-19,50-336/90-21 & 50-423/90-17 on 900904-07.No Violations Noted ML20058E0931990-10-25025 October 1990 Advises That Schedule for Installation of Alternate Ac Acceptable,Per 900925 Response to Station Blackout Rule ML20058G6121990-10-25025 October 1990 Advises That 900926 Response to Station Blackout Evaluation Acceptable,Based on Installation of Alternate Ac Prior to Startup ML20062C7041990-10-24024 October 1990 Forwards Environ Assessment & Finding of No Significant Impact Re 900418 Request from Section IV.F.3 of App E to 10CFR50,Section IV.F.3 ML20058D5601990-10-24024 October 1990 Forwards Team Insps 50-213/90-82,50-245/90-81,50-336/90-81 & 50-423/90-82 on 901001-12 ML20058G0151990-10-23023 October 1990 Forwards Exemption to 10CFR50,App E,Section IV.F.3 Re Conduct of Full Participation Emergency Exercise,Per 900418 & 0801 Ltrs ML20058B3181990-10-17017 October 1990 Ack Receipt of Forwarding Payment of Civil Penalty in Amount of $50,000.Penalty Not Mitigated IR 05000336/19900271990-10-17017 October 1990 Forwards Operator Exam Rept 50-336/90-27OL on 901003.Exam Results:Operator Passed Retake Exam ML20058A9791990-10-17017 October 1990 Forwards Insp Rept 50-336/90-19 on 900910-14.No Violations Noted ML20058E0661990-10-16016 October 1990 Forwards SE Granting 900926 Request for Relief from ASME Code Inservice Insp Requirements to Repair Svc Water Sys ML20062B8751990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20062B8831990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20059N4061990-10-0303 October 1990 Forwards Safety Evaluation Accepting pressure-temp Limits Re Generic Ltr 88-11.Current pressure-temp Limits for Heatup, Cooldown,Leak Test & Criticality of RCS Acceptable ML20059N9681990-10-0303 October 1990 Forwards Partially Withheld Safeguards Insp Repts 50-245/90-16,50-336/90-17 & 50-423/90-16 on 900827-31 & Notice of Violation ML20059N3291990-10-0202 October 1990 Forwards Response to Comments Contained in Util Re Installation of Hardened Wetwell Vent IR 05000336/19900091990-10-0101 October 1990 Ack Receipt of 900727 & 0907 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-336/90-09. Actions Will Be Examined During Future Insps ML20059M1471990-09-27027 September 1990 Ack Receipt of & Payment of Civil Penalty in Amount of $50,000 Proposed by NRC .Corrective Actions Will Be Examined During Future Insps ML20059M0471990-09-14014 September 1990 Advises That NRC Does Not See Need for Formal Relief from ASME Code Section XI to Repair Leak in Svc Water Piping ML20059J8621990-09-12012 September 1990 Grants 900911 Request for Temporary Waiver of Compliance from Tech Spec Table 3.2.2 Re Containment Spray Interlock ML20059J7621990-09-12012 September 1990 Forwards Amend 45 to License DPR-21 & Safety Evaluation. Amend Changes Tech Spec Section 3/4.5.C by Adding Operability & Surveillance Requirements for Mods Made to Tie Breakers 14A to 14G ML20059F3301990-08-29029 August 1990 Forwards Safety Evaluation Accepting Util 890417,0530 & 900330 Responses Concerning Method of Dealing W/Station Blackout Provided Util Make Mods,Procedure Changes & Calculations Discussed.Technical Evaluation Rept Also Encl ML20059C8261990-08-28028 August 1990 Forwards Safety Insp Repts 50-245/90-11,50-336/90-12 & 50-423/90-09 on 900611-15 & 25-29.No Violations Noted ML20059D7281990-08-27027 August 1990 Requests Listed Ref Matls Needed for Senior Reactor Operator Licensing Exams Scheduled for Wk of 901112.Completed License Applications Required 30 Days Before Exam Date ML20059E2201990-08-24024 August 1990 Forwards Radiological Controls Insp Repts 50-245/90-14, 50-336/90-15 & 50-423/90-13 on 900723-27.One Noncited Violation Identified ML20059D7341990-08-23023 August 1990 Forwards Safety Insp Rept 50-423/90-10 on 900612-0723 & Notice of Violation.Util Should Respond to Violation Re Inaccurate Statement in LER 90-013 Concerning Rev of Procedure by Following Instructions in Encl App a ML20059J8481990-08-16016 August 1990 Forwards Training Effectiveness Team Insp Rept 50-423/90-06 on 900604-08.Training Programs Well Implemented & Personnel Effectively Trained.Few Weaknesses Identified ML20058M7711990-08-0909 August 1990 Requests Addl Info Re License Amend Application Under Generic Ltr 87-09 for Facility.Affirms That Remedial Measures Prescribed for Affected Action Statements Consistent W/Updated SAR & Supporting Safety Analysis ML20056A9451990-08-0707 August 1990 Forwards Insp Rept 50-423/90-80 on 900416-25.Weaknesses Identified ML20058N0581990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Other Power Reactor Licenses in Region 1 Encouraged to Start Similar Initiative to Provide for Sharing of Info & Experiences Involving Engineering & Solutions of Problems Common to All ML20058M5361990-08-0606 August 1990 Forwards Review of Westinghouse Rept WCAP-12277, Westinghouse Owners Group Bounding Evaluation for Pressurizer Surge Line Thermal Stratification, Per NRC Bulletin 88-011 ML20056A6901990-08-0101 August 1990 Forwards Insp Rept 50-336/90-11 on 900530-0711.No Violations Noted ML20058L3331990-07-25025 July 1990 Forwards Safety Insp Repts 50-245/90-13,50-336/90-13 & 50-423/90-11 on 900609-13.No Violations or Deviations Noted ML20055J2121990-07-25025 July 1990 Advises That Review of Cen 387-P, C-E Owners Group Pressurizer Surge Line Flow Stratification Evaluation, Concludes Adequate Bases Not Provided That Facility Meets All Appropriate Code Limits for 40-yr Plant Life ML20056A3551990-07-24024 July 1990 Forwards Requalification Exam 50-336/90-10OL-RQ on 900618-22 IR 05000245/19900081990-07-23023 July 1990 Discusses Insp Rept 50-245/90-08 on 900510-25 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty. Violation Occurred on 900507 When Stated Cask Arriving at Barnwell,Sc Found to Contain Contaminated Water ML20055H3621990-07-23023 July 1990 Grants Temporary Waiver of Compliance Re Facility Tech Spec 3.6.6.1, Supplemental Leak Collection & Release Sys 1990-09-27
[Table view] Category:OUTGOING CORRESPONDENCE
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 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 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 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 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 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 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 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 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 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 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 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 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 ML20216J1341999-09-28028 September 1999 Ltr Contract:Task Order 49, Millstone Units 2 & 3 Employee Concerns Program Insp, Under Contract NRC-03-98-021 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 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 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 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 ML20211K5171999-09-0202 September 1999 Expresses Appreciation for Support Provided for NRC Public Meeting on 990825 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 ML20211H9971999-08-27027 August 1999 Forwards Insp Rept 50-423/99-07 on 990614-0715.Violations of NRC Requirements Occurred Re Adequacy of C/As for Organizational Changes & Being Treated as NCVs DD-99-09, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-09) Expired.Commission Declined Any Review & Decision Became Final on 990823.With Certificate of Svc.Served on 9908261999-08-26026 August 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-09) Expired.Commission Declined Any Review & Decision Became Final on 990823.With Certificate of Svc.Served on 990826 ML20211F5841999-08-23023 August 1999 Discusses Proposed Rev 21 to Northeast Utils Quality Assurance Program TR for NRC Review & Approval,Iaw 10CFR50.54 ML20211D5701999-08-20020 August 1999 Informs That in May 1999,Northeast Nuclear Energy Co, Restarted Millstone Nuclear Power Station,Unit 2.Licensee Has Been Tasked Charter with Listed Specific Responsibilities ML20211C4621999-08-18018 August 1999 Discusses Rev to TS Bases Sections 3/4.5.2 & 3/4.5.3, Emergency Core Cooling Sys Subsystems ML20210S9611999-08-13013 August 1999 Informs That NRC Received Encl Ltr from Pb Johnston Expressing Concern About Certain Impacts on Shareholders of New England Electric Sys with Respect to Nees Proposed Merger with Natl Grid Group ML20210S9511999-08-13013 August 1999 Responds to to Collins Expressing Concerns with Certain Terms of Proposed Merger Between New England Electric Sys & National Grid Group.Nrc Has No Authority to Interject Itself in Nees Merger with National Grid Group ML20210N4921999-08-0909 August 1999 Ack Receipt of 990331 Electronic Transfer of $88,000 for Civil Penalty,Proposed on 990309.Corrective Actions Will Be Examined During Future Insp ML20210C0751999-07-21021 July 1999 Forwards 990721 Notice of Public Meeting Re post-shutdown Decommissioning Activities Rept ML20210A9681999-07-14014 July 1999 Responds to Re Changes to Millstone Physical Security Plan Identified as Rev 32,submitted Per Provisions of 10CFR50.54(p).No NRC Approval Is Required,Based on Util Determination That Revs Do Not Decrease Plan Effectiveness ML20209E7341999-07-12012 July 1999 Discusses Util Responses to GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. Responses Acceptable.Info Revised in Reactor Vessel Integrity Database (Rvid) & Is Releasing as Rvid Version 2 ML20209G2921999-07-0909 July 1999 Forwards Insp Repts 50-336/99-06 & 50-423/99-06 on 990420-0614.Ten Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy DD-96-23, Informs That on 961226,NRC Issued Partial Director'S Decision DD-96-23,in Response to Petition Submitted,Per 10CFR2.206,on 9508211999-07-0101 July 1999 Informs That on 961226,NRC Issued Partial Director'S Decision DD-96-23,in Response to Petition Submitted,Per 10CFR2.206,on 950821 ML20196J2111999-06-30030 June 1999 Forwards SE Concluding Licensee USI A-46 Implementation Program Meets Purpose & Intent of Criteria in Generic Implementation Procedure for Seismic Verification of NPP Equipment, Rev 2 ML20196J5031999-06-30030 June 1999 Responds to 990414 Petition,Submitted Per 10CFR2.206 to Nrc. NRC Solicited Support from FEMA to Ensure That Appropriate Response to Enhancements Identified to Offsite EP in Event of Radiological Emergency at Millstone,Developed ML20196J1131999-06-29029 June 1999 Forwards Notice of Receipt & Availability for Comment of Post-Shutdown Decommissioning Activities Rept, Re .Notice Provided for Public Comments to Be Submitted within 30 Days of Notice Date ML20196G9531999-06-24024 June 1999 Discusses Changes Provided by NNECO on 990504 to TS Bases Sections 3/4.7.7 & 3/4.7.8.Returns TS Bases to NNECO to Be Inserted in TS to Ensure That NRC Staff & NNECO Have Identical TS Bases Pages ML20212H9661999-06-21021 June 1999 Confirms 990611 & 14 Telcons with M Selden,In Which Beckman & Assocs,Inc Was Advised to Stop Work Under Mod 4 to Task Order 005,under Contract NRC-03-98-021 ML20212H6661999-06-15015 June 1999 Forwards RAI Re 990315 Application Request for Approval of Proposed Indirect Transfer of Seabrook Station,Unit 1 License & Proposed Indirect Transfer of Millstone,Unit 3 License to Extent Held by Nepco ML20212J0751999-06-15015 June 1999 Forwards Notice of Withdrawal of Amend Request for Allowed Outage Time Extensions for Emergency Diesel Generators & Low Pressure Safety Injection Trains of Emergency Core Cooling Sys ML20195J3121999-06-15015 June 1999 Expresses Concern Re M Casey 990523 Column, Gaffes Turn Into Cash at NRC, & Disagrees with New London Day Earlier Editorial Criticism of NRC Investigations of Harassment & Intimidation of Employees at Millstone NPPs ML20195K0601999-06-15015 June 1999 Forwards Request for Addl Info Re fire-related IPEEE Analysis,Per GL 88-20 ML20195J4761999-06-10010 June 1999 Forwards Insp Rept 50-336/98-219 on 981214-18,990126-29 0208-19 & 0301-05.Four Violations Identified & Being Treated as Noncited Violations ML20195J0321999-06-10010 June 1999 Expresses Appreciation for Serving as Moderator for 990209 Public Meeting at Waterword,Ct.Questions Raised by Interested Members of Public & NRC Responses Encl.Staff Reply to Blanch Also Encl ML20196J5091999-06-0404 June 1999 Requests Assistance to Review Petition Submitted Under 10CFR2.206 of NRC Rules.Petition Concerns EP Issues for Millstone Nuclear Power Station ML20207G1121999-06-0303 June 1999 Forwards Insp Repts 50-245/99-05,50-336/99-05 & 50-423/99-05 on 990302-0419.No Violations Noted.Closure of 15 Significant Items List (SIL) Issues at Unit 2 Signifies Completion of Insp for Entire Unit 2 SIL ML20207G6271999-06-0303 June 1999 Forwards Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Replace Specific Titles in Section 6.0 of TSs for All Three Millstone Units with Generic Titles 1999-09-30
[Table view] |
Text
_ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
October 3,1985 DISTRIBUTION:
Docket No. 50-336 SMRT7TEF Gray File NRC PDR L PDR ORB 43 RDG Mr. John F. Opeka, Senior Vice President OELD Nuclear Engineering and Operations EJordan Northeast Nuclear Energy Company BGrimes P. O. Box 270 JPartlow Hartford, Connecticut 06141-0270 00sborne PMKreutzer
Dear Mr. Opeka:
ACRS 10
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON SPENT FUEL STORAGE CAPACITY EXPANSION FOR MILLSTONE UNIT 2 To complete our review of your request dated July 24, 1985 to modify your Technical Specification concerning the spent fuel storage capacity at Millstone Unit 2, we will need responses to the questions in the enclosure.
We request that you provide this infonnation by October 18, 1985, in order to maintain schedules. An advance copy of the enclosure has previously been provided to your staff.
The information requested in this letter affects fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely,
/s/
Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing
Enclosure:
As stated cc w/ enclosure:
See next page ORB #3 DL ORB # :D 0 j' L
,Plfreb)tzer 00s e:dd J6udher "10/ /85 10/f/85 10/1 /85 7
8510090507 851003 PDR ADOCK 05000336 P PDR
l l
Mr. John F. Opeka Millstone Nuclear Power Station Northeast Nuclear Energy Company Unit No. 2 cc:
Gerald Garfield, Esq. Mr. Wayne D. Romberg Day, Berry & Howard Superintendent Counselors at Law Millstone Nuclear Power Station City Place P. O. Box 128 Hartford, Connecticut 06103-3499 Waterford, Connecticut 06385 Regional Administrator, Region I Mr. Edward J. Mroczka U.S. Nuclear Regulatory Commission Vice President, Nuclear Operations Office of Executive Director for Northeast Nuclear Energy Company Operations P. O. Box 270 631 Park Avenue Hartford, Connecticut 06141-0270 King of Prussia, Pennsylvania 19406 Pr. Charles Brinkman, Manager Washington Nuclear Operations C-E Power Systems i Combustion Engineering, Inc.
7910 Woodmont Avenue I Bethesda, Maryland 20814 Mr. Lawrence Bettencourt, First Selectman
-Town of Waterford Hall of Records - 200 Boston Post Road Waterford, Connecticut 06385 Northeast Utilities Service Company ATTN: Mr. Richard R. Laudenat, Manager
' Generation Facilities Licensing Post Office Box 270 Hartford, Connecticut 06141-0270 Kevin McCarthy, Director Radia' tion Control Unit Department of Environmental Protection State Office Building Hartford, Connecticut 06106 Mr. John Shedlosky Resident Inspector / Millstone Box 811 Niantic, Connecticut 06357 Office of Policy & Management ATTN: Under Secretary Energy Division
, 80 Washington Street i Hartford, Connecticut 06106 i !
i t
- - --- -- ,- .. --- ,- ,--n- ,a-,,.,, . . , . - _ . _ - - - - - - - . - - - - . - . - - - -
a ENCLOSURE RAI FOR MILLSTONE - 2 SFP STRUCTURAL AND GE0 TECHNICAL ENGINEERING BRANCH
Reference:
Letter from J. F. Opeka of Northeast Utilities to E. J. Butcher of NRC, " Millstone Nuclear Power Station, Unit No. 2. Proposed Change to Technical Specifications, Modifications to Spent Fuel Storage Pool", dated July 24, 1985.
- 1. With respect to seismic loadings on the spent fuel rack modules:
- a. Identify which rack modules were analyzed.
- b. Provide a description of how the horizontal earthquake acceleration (time history) was oriented relative to the long and short cross-sectional dimensions of the rack modules in the non-linear displace-ment analysis,
- c. Describe what constitutes the worst case (identifying the factors by which the worst case was identified) and how it was considered.
- 2. Reference 4-2 was cited on page 22 of the Licensee's report (see above reference) in lieu of any description of the non-linear analysis model:
- a. Provide the relationship of this reference to the analysis performed for the Licensee's report,
- b. Describe how the analysis for the Licensee's report differed from that presented in the referenced technical paper,
- c. Provide a copy of the reference to expedite the review.
- 3. Provide a full description of the mathematical model used for the non-linear rack module analysis.
1
- 4. In addition to not providing the mathematical model for the non-linear dynamic displacement analysis, the Licensee did not indicate the relation-ship of the rack module analyzed to its adjacent rack modules. The fol-
.i lowing information is required:
- a. Describe and justify how in-phase and/or out-of-phase motion with
- adjacent rack modules was considered and implemented,
- b. Describe fully how hydrodynamic coupling to adjacent rack modules was considered and justify the use of the theoretical basis employed.
- c. Describe how the gap between adjacent rack modules was apportioned to each rack module and list the values for the racks analyzed, q d. Provide numerical comparisons of rack displacements (at the top of the
( rack if that is the point of maximum displacement) to the apportioned clearance,
- e. Where references are cited, please provide a copy of each reference
! with the response to expedite the review.
j 5. With respect to the modeling of impact between the fuel assembly and a rack cell in the non-linear dynamic analysis:
! a. Provide the data and structural premise upon which impact stiffness was based.
- b. Provide the value of impact damping used, if greater than the nominal structural damping used in the analysis, and provide documentation just-
, ifying that damping value.
j 6. The Licensee did not indicate what range of friction coefficnet values was used in the non-linear displacement analysis between the rack mounting feet and the pool floor liner:
- a. Provide the range of friction coefficient used and describe the proced-ures used to determine the friction coefficient that produces the maxi-mum rack displacement.
I 1
4
__ _-._..,_% . - _ , , ______ ._ ,% _,.y,, , . _.-,, -, _ _ , , , . -- - , - . . - ,., - , - . . - _ , - -
- b. Justify and document the validity of the range of friction coefficient used.
- 7. The Licensee did not indicate how the results from the non-linear dis-placement analysis was introduced to the stress analysis model,
- a. Provide full description of the load selection process and how the vertical and lateral dynamic loads on each rack mounting foot, as well as rack dead weight, are considered during rack lift-off in the stress analysis model.
- 8. Non-linear analyses, especially those involving impact of bodies as occurs between the fuel assemblies and the rack module, and between the rack mounting feet and the pool floor during lift-off, generally require add-itional procedures such as repeated solutions using a range of integration time steps to assure that the solution is both stable and fully converged.
This is important because integration procedures that have yielded a valid solution do not necessarily remain stable for all solutions. The Licensee made no mention of this important point.
- a. Provide a description of the methods used to assure that a valid solution of the non-linear analysis was reached for all cases in-vestigated.
- 9. At the bottom of page 22 of the Licensee's report, the Licensee stated that "The component stress on each element resulting from the application of each directional load is combined by the square root sum of the squares method".
No computed stresses or allowable stresses were provided:
a ihe Licensee should document how the stresses, thus calculated, repre-sent the worst case.
- b. The Licensee should provide a table of calculated maximum stresses, allowable stresses, and design margins.
1 i
4 j c. The Licensee should indicate that the stresses are compared to stress l allowables in accordance with the NRC's "O T Position for Review and Acceptance of Spent Fuel Storage and Handling Applications" (shown l by the Licensee as Reference 4-1) instead of "by the rules of the
- ASME....". (Note the last paragraph on Page 22 of the Licensee's i Report).
- 10. With respect to fuel handling accidents as addressed by the Licensee on page 23 of the report
, a. Provide analysis and justification as to why a spent fuel assembly falling through a rack cell and impacting the bottom of the cell "will not affect the primary function of the racks....".
j b. Provide the approach, the assumptions, the data employed, and the j results of analysis performed to assure that a fuel assembly dropped I through a rack storage cell will not penetrate the bottom of the rack 1
) module, or, if it does penetrate the bottom of the rack module, that I it will not damage the pool liner,
- c. For the case of a crane uplift accident, provide the method of analysis
- employed, and the criteria by which the results were judged to be l acceptable, including identification and documentation of the allow- ,
able stresses.
l
- 11. With respect to the pool structure, the Licensee provided virtually no information attesting to the adequacy of the Licensee's anal)tical pro-cedures, the analysis results or the selection of allowable stresses.
Instead, the Licensee provided only a brief abstract indicating that analysis involving multiple load cases was performed, that concrete sections were checked against the latest revision of the American Concrete Institute Requirements for Nuclear Safety Related Structures - ACI-349-80, j and that the analysis demonstrated the adequacy of the spent fuel pool
! and auxiliary building to accomodate the loads associated with the 4
i !
i I
t increased pool storage capacity. However, none of these procedures or results were provided.
Accordingly, the Licensee is requested to provide a description of all analytical procedures, including assumptions, limitations, justification and documentation of the methods applicability, source and validity of acceptance criteria, and the comparison of results to allowable values.
As a minimum, the information should include the following:
- a. Provide sketches and drawings of the portions of the pool and auxiliary building structures to be modeled.
i b. Provide a description of the mathematical model employed, including assumptions and limitations of the model,
- c. Describe and list the load cases used as well as the justification for these load cases.
- d. Describe how the dynamic interaction between the pool structure and
! the rack modules was considered, including the value of any associated l dynamic amplification factors. Include all assumptions made regarding i the summation and phase of all rack loads.
j e. Provide analysis of the adequace of the pool floor and liner under the l local maximum rack module dynamic mounting foot loads.
! f. Provide identification of the most critical regions of the pool l structure. List the stresses (thermal, deadweight, seismic and rack I dynamic loads) and their comparison to allowable values, where the source and justification of the use of that allowable is also docu-j mented.
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