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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20205L1831986-03-13013 March 1986 Comments on Proposed Rule 10CFR9.Rule Opposed Due to Opinion That Broad New Class of Secret Sessions or Meetings W/O Transcripts Will Be Created ML20151R5611986-01-30030 January 1986 Summarizes 851216 Mgt Meeting at Oak Ridge Operations Ofc to Review & Inspect Redress & Reclamation of Crbr Site.Drawings Reviewed,Discussions Held & Tour of Site Performed.Site Restoration Concluded to Be as Described in Plans & Specs ML20138Q8301985-12-0303 December 1985 Further Response to FOIA Request for Records Re Voluntary or Required Redress of Sites Where Const Was Terminated, Including Crbr & Legal Analysis.Forwards App E Documents.App D & E Documents Available in Pdr.Photographs Also Available ML20128B2801985-06-27027 June 1985 Updates DOE .Bids for Redress of Crbr Site Opened on 850604.Contract Awarded to Beaver Excavating Co,Canton, Oh,On 850613.Contractor Scheduled to Complete Site Redress on or Before 851216 ML20133C7371985-06-14014 June 1985 Further Response to FOIA Request for Documents Re Site Redress Where Plant Const Begun,Including Clinch River Facility & NRC Legal Analysis Re Redress.Forwards App B Documents.App C Document Withheld (Ref FOIA Exemption 5) ML20128R0001985-06-0606 June 1985 Partial Response to FOIA Request for Records Re Desirability of Voluntary or Required Redress of Nuclear Plant Sites Where Work Undertaken But Const No Longer Contemplated. Forwards Documents Listed in App a ML20133C6881985-05-0808 May 1985 FOIA Request for Documents Re Redress of Sites Where Nuclear Plant Const Begun & NRC Legal Analysis of Need for Site Redress W/ or W/O Current CP & LWA ML20107M8141984-11-0707 November 1984 Clarifies & Reaffirms Util Commitments Re Redress of Site in Accordance W/Util 840305 Final Site Redress Plan & NRC 840606 Approval of Plan ML20107H8031984-11-0606 November 1984 Reaffirms Commitments to Redress Site in Accordance W/ 840305 Final Site Redress Plan & NRC 840606 Approval Ltr. Related Correspondence ML20140C6121984-06-18018 June 1984 Advises That Time for Commission to Review ALAB-761 Expired. Commission Declined Review.Decision Became Final Agency Action on 840611.Served on 840618 ML20087B4361984-03-0808 March 1984 Confirms That ASLB Intends to Vacate Notice of 840314 Conference & Reschedule Later Date Due to Delay in Funding for Review of Redress Plan & Possible Lack of Availability of One ASLB Member.Certificate of Svc Encl ML20086T4631984-03-0505 March 1984 Forwards Site Redress Plan. Minor Clarifications & Corrections to Draft Plan Submitted 840227 Made in Response to NRC Comments ML20087A4141984-03-0202 March 1984 Forwards Page 15 Inadvertently Omitted from 840227 Transmittal of Draft Crbr Plant Redress Plan.Related Correspondence ML20080T9331984-03-0101 March 1984 Forwards Page 15 of Crbr Program Redress Plan,Inadvertently Omitted from 840227 Transmittal.Certificate of Svc Encl ML20128R0161984-02-29029 February 1984 Expresses Thanks for 840222 Review of Site Redress Planning. Concurs W/Conceptual Approach & 1-yr Period for Development of Final Site Redress Plan & Investigation of Potential Use of Site.Ml Lacy Encl ML20080S6661984-02-27027 February 1984 Forwards Draft Site Redress Plan,In Response to N Grace 831208 Request.Plan Will Be Finalized for Submission on 840302,following Receipt of Comments ML20079F9411984-01-13013 January 1984 Informs of Receipt & Storage,Through S&W Engineering,Of Spent Fuel Transfer Port Assembly Large Shield Plug.Due to Failure of Congress to Appropriate Addl Funding,Doe No Longer Seeking CP & Is Closing All Licensing Activities ML20083G3551984-01-10010 January 1984 Advises That Svc of DOE & Project Mgt Corp 831227 Notification Re Project Termination Affected Again on All Parties on Attached Svc List ML20083H2331983-11-15015 November 1983 Summarizes Current Status of SER Open Items Re Structural Response During Faulted Conditions & Beyond Dbas.Program Lacks Planned Analytical Support.Models to Support Experimental Efforts Should Be Developed ML20081B9721983-10-24024 October 1983 Summarizes 831004 Meeting W/Nrc,Acrs & Lnr Assoc Re Mgt of Crbr PRA Program.Viewgraphs & List of Meeting Attendees Encl ML20078A7571983-09-0707 September 1983 Forwards Evaluation Repts of Faults 1,2 & 3 Discovered on Site During Foundation Excavation.Faults Not Capable within Meaning of App a to 10CFR100.W/seven Photographs ML20076A8171983-08-17017 August 1983 Confirms Redirection for Shipping Applicant Voluminous Exhibits.Certificate of Svc Encl ML20076A7761983-08-17017 August 1983 Advises That Author Will Present Oral Argument on Behalf of Applicants & Forwards Motion Requesting Argument Be Rescheduled for 830928 ML20077J0781983-08-11011 August 1983 Forwards Pages from Transcript of Crbr CP 830810 Hearings Per ASLB Direction.Certificate of Svc Encl ML20081A5601983-08-11011 August 1983 Summarizes 830808 Informal Meeting on Contract Re PRA Review of Crbr (Task 4) & NRC Concerns Associated W/Technology for Energy Corp Deliverables Schedule ML20076H8811983-08-0909 August 1983 Expresses Appreciation for NRC Presentation on 10CFR21 & 10CFR50.55(e) Requirements.Info Should Be Most Useful to Personnel Involved in Project in Following Requirements ML20024E0391983-08-0505 August 1983 Forwards Errata Sheets for Applicant Prepared Testimony. Certificate of Svc Encl.Related Correspondence ML20077D1321983-07-25025 July 1983 Advises of Omission in Applicant 830722 Response Re CP Evidentiary Hearings.Hearings Did Not Commence on 830718 But Were Postponed Per 830713 Order.Order of 830719 Rescheduled Hearings for 830808-12.Certificate of Svc Encl ML20024D0291983-07-22022 July 1983 Forwards Clinch River Breeder Reactor Plant Sys Design Description - Nuclear Island HVAC Sys, as Example of Procedure Outlines Available for Performance of PRA ML20080A8311983-07-20020 July 1983 Opposes Plant Const Since Little Prior Experience Exists W/Breeder Reactor Design ML20024D5121983-07-19019 July 1983 Requests Specs for Electrical Power Cable Insulation to Be Used at Facility ML20077A5331983-07-19019 July 1983 Advises of Incorrectly Cited Ref on Page 1 of Attachment B & on Page 2 of Attachment C to .Certificate of Svc Encl ML20077H1911983-07-19019 July 1983 Responds to NRC Re Violations Noted in IE Insp Rept 50-537/83-05.Corrective actions:Westinghouse-Oak Ridge Audit Program Revised to Be Computerized Sys.Implementation Throughout Yr Will Be Measured by Planned Surveillances ML20072P1101983-07-15015 July 1983 Forwards Applicant Proposed Exhibit List for CP Hearings,For Review.Stipulation as to Authenticity & Admissibility Requested.Certificate of Svc Encl ML20024C1621983-07-0808 July 1983 Informs That Auxiliary Feedwater Sys Evaluation,Per PSAR App C,Section C.6.4 & App H,Section II.E.1.1,scheduled for Completion by mid-1985 ML20085A7291983-07-0606 July 1983 Forwards Rev 6 to Vol 2 to CRBRP-3, Assessment of Thermal Margin Beyond Design Base (Tmbdb) ML20105B9551983-07-0606 July 1983 Forwards Addl Info Per Request at 830610 Meeting on Programmatic Objectives Re Fuel Burnup.Fftf Operates W/Peak Burnup of Over 61,000 Megawatt Day/Mt.Burnup Occurred Under Temp & Power Conditions Similar to Crbr Conditions ML20079R7401983-06-23023 June 1983 Summarizes 830606 Meeting W/Crbr Project Personnel Re Schedule for Resolution of Confirmatory Items.All Identified Items & Preliminary Schedule Info Discussed.List of Attendees Encl ML20079R2661983-06-21021 June 1983 Lists Typographical & Transcription Errors in 830512 Deposition.Certificate of Svc Encl ML20024A6781983-06-20020 June 1983 Informs of Planned Optional Use of Mechanical Couplers for Reinforcing Bar Splice Sys in Nuclear Island Mat.Qa Program Will Be Established.Exception to ASME Code,Section III & Reg Guide 1.136 Requirements Encl ML20076J0951983-06-17017 June 1983 Summarizes Programmatic Objectives 830610 Meeting Re Fallbacks Identified in Chapter 4 of SER & Impact on Crbr Project.Viewgraphs & Supporting Documentation Encl ML20076J0511983-06-16016 June 1983 Advises That DOE Addressees Include Tj Garrish,L Silverstrom & Wd Luck.Rt Johnson & WE Bergholz Should Be Deleted from Svc List.Certificate of Svc Encl ML20023D9611983-05-27027 May 1983 Submits Agreements Reached at 830524 Meeting W/Crbr Project Re Pra.Description of Addl Tasks Needed to Integrate Plan I & II Efforts Encl ML20072B3431983-05-27027 May 1983 Forwards Crbr Erosion & Sediment Control Plan Rept, Providing Implementation Status of Control Plan Measures Currently Utilized ML20023D4031983-05-20020 May 1983 Forwards Amend 77 to PSAR ML20076D3151983-05-19019 May 1983 Forwards Rev 1 to Crbr Project Heat Transport Sys In-Containment Piping Reserve Seismic Margins & Rept Re Consequences of Leaks from Small Diameter Primary Heat Transport Sys Piping ML20076D2281983-05-17017 May 1983 Forwards Rev 5 to Vol 2 to Thermal Margin Beyond Design Base. Rev Incorporates Isotopic Inventory for Heterogeneous Core,Current Meteorology,Addl Organ Doses & More Realistic Pu Sparging Calculations ML20023C5821983-05-16016 May 1983 Submits Supplemental Info to 830401 Ltr Re Cable Separation by Confirming That Approx 75 Ft of DHR Svc & Steam Generator Auxiliary Heat Removal Sys Cable Will Be Run in Separate Conduits or Encl Raceways ML20079Q2881983-05-10010 May 1983 Forwards Corrected 830509 Response to NRDC & Sierra Club First Set of Interrogatories & Request to Produce Directed to Applicant.Original Document Not Identified as Response ML20024D9551983-05-0909 May 1983 Submits Estimate of LMFBR Safety & Licensing Review Needs Over Next Several Yrs.Preparation of Portions of FSAR Will Begin in 1984 1986-03-13
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20205L1831986-03-13013 March 1986 Comments on Proposed Rule 10CFR9.Rule Opposed Due to Opinion That Broad New Class of Secret Sessions or Meetings W/O Transcripts Will Be Created ML20128B2801985-06-27027 June 1985 Updates DOE .Bids for Redress of Crbr Site Opened on 850604.Contract Awarded to Beaver Excavating Co,Canton, Oh,On 850613.Contractor Scheduled to Complete Site Redress on or Before 851216 ML20133C6881985-05-0808 May 1985 FOIA Request for Documents Re Redress of Sites Where Nuclear Plant Const Begun & NRC Legal Analysis of Need for Site Redress W/ or W/O Current CP & LWA ML20107M8141984-11-0707 November 1984 Clarifies & Reaffirms Util Commitments Re Redress of Site in Accordance W/Util 840305 Final Site Redress Plan & NRC 840606 Approval of Plan ML20107H8031984-11-0606 November 1984 Reaffirms Commitments to Redress Site in Accordance W/ 840305 Final Site Redress Plan & NRC 840606 Approval Ltr. Related Correspondence ML20087B4361984-03-0808 March 1984 Confirms That ASLB Intends to Vacate Notice of 840314 Conference & Reschedule Later Date Due to Delay in Funding for Review of Redress Plan & Possible Lack of Availability of One ASLB Member.Certificate of Svc Encl ML20086T4631984-03-0505 March 1984 Forwards Site Redress Plan. Minor Clarifications & Corrections to Draft Plan Submitted 840227 Made in Response to NRC Comments ML20087A4141984-03-0202 March 1984 Forwards Page 15 Inadvertently Omitted from 840227 Transmittal of Draft Crbr Plant Redress Plan.Related Correspondence ML20080T9331984-03-0101 March 1984 Forwards Page 15 of Crbr Program Redress Plan,Inadvertently Omitted from 840227 Transmittal.Certificate of Svc Encl ML20080S6661984-02-27027 February 1984 Forwards Draft Site Redress Plan,In Response to N Grace 831208 Request.Plan Will Be Finalized for Submission on 840302,following Receipt of Comments ML20079F9411984-01-13013 January 1984 Informs of Receipt & Storage,Through S&W Engineering,Of Spent Fuel Transfer Port Assembly Large Shield Plug.Due to Failure of Congress to Appropriate Addl Funding,Doe No Longer Seeking CP & Is Closing All Licensing Activities ML20083G3551984-01-10010 January 1984 Advises That Svc of DOE & Project Mgt Corp 831227 Notification Re Project Termination Affected Again on All Parties on Attached Svc List ML20083H2331983-11-15015 November 1983 Summarizes Current Status of SER Open Items Re Structural Response During Faulted Conditions & Beyond Dbas.Program Lacks Planned Analytical Support.Models to Support Experimental Efforts Should Be Developed ML20081B9721983-10-24024 October 1983 Summarizes 831004 Meeting W/Nrc,Acrs & Lnr Assoc Re Mgt of Crbr PRA Program.Viewgraphs & List of Meeting Attendees Encl ML20078A7571983-09-0707 September 1983 Forwards Evaluation Repts of Faults 1,2 & 3 Discovered on Site During Foundation Excavation.Faults Not Capable within Meaning of App a to 10CFR100.W/seven Photographs ML20076A7761983-08-17017 August 1983 Advises That Author Will Present Oral Argument on Behalf of Applicants & Forwards Motion Requesting Argument Be Rescheduled for 830928 ML20076A8171983-08-17017 August 1983 Confirms Redirection for Shipping Applicant Voluminous Exhibits.Certificate of Svc Encl ML20081A5601983-08-11011 August 1983 Summarizes 830808 Informal Meeting on Contract Re PRA Review of Crbr (Task 4) & NRC Concerns Associated W/Technology for Energy Corp Deliverables Schedule ML20077J0781983-08-11011 August 1983 Forwards Pages from Transcript of Crbr CP 830810 Hearings Per ASLB Direction.Certificate of Svc Encl ML20076H8811983-08-0909 August 1983 Expresses Appreciation for NRC Presentation on 10CFR21 & 10CFR50.55(e) Requirements.Info Should Be Most Useful to Personnel Involved in Project in Following Requirements ML20024E0391983-08-0505 August 1983 Forwards Errata Sheets for Applicant Prepared Testimony. Certificate of Svc Encl.Related Correspondence ML20077D1321983-07-25025 July 1983 Advises of Omission in Applicant 830722 Response Re CP Evidentiary Hearings.Hearings Did Not Commence on 830718 But Were Postponed Per 830713 Order.Order of 830719 Rescheduled Hearings for 830808-12.Certificate of Svc Encl ML20024D0291983-07-22022 July 1983 Forwards Clinch River Breeder Reactor Plant Sys Design Description - Nuclear Island HVAC Sys, as Example of Procedure Outlines Available for Performance of PRA ML20080A8311983-07-20020 July 1983 Opposes Plant Const Since Little Prior Experience Exists W/Breeder Reactor Design ML20024D5121983-07-19019 July 1983 Requests Specs for Electrical Power Cable Insulation to Be Used at Facility ML20077H1911983-07-19019 July 1983 Responds to NRC Re Violations Noted in IE Insp Rept 50-537/83-05.Corrective actions:Westinghouse-Oak Ridge Audit Program Revised to Be Computerized Sys.Implementation Throughout Yr Will Be Measured by Planned Surveillances ML20077A5331983-07-19019 July 1983 Advises of Incorrectly Cited Ref on Page 1 of Attachment B & on Page 2 of Attachment C to .Certificate of Svc Encl ML20072P1101983-07-15015 July 1983 Forwards Applicant Proposed Exhibit List for CP Hearings,For Review.Stipulation as to Authenticity & Admissibility Requested.Certificate of Svc Encl ML20024C1621983-07-0808 July 1983 Informs That Auxiliary Feedwater Sys Evaluation,Per PSAR App C,Section C.6.4 & App H,Section II.E.1.1,scheduled for Completion by mid-1985 ML20085A7291983-07-0606 July 1983 Forwards Rev 6 to Vol 2 to CRBRP-3, Assessment of Thermal Margin Beyond Design Base (Tmbdb) ML20105B9551983-07-0606 July 1983 Forwards Addl Info Per Request at 830610 Meeting on Programmatic Objectives Re Fuel Burnup.Fftf Operates W/Peak Burnup of Over 61,000 Megawatt Day/Mt.Burnup Occurred Under Temp & Power Conditions Similar to Crbr Conditions ML20079R7401983-06-23023 June 1983 Summarizes 830606 Meeting W/Crbr Project Personnel Re Schedule for Resolution of Confirmatory Items.All Identified Items & Preliminary Schedule Info Discussed.List of Attendees Encl ML20079R2661983-06-21021 June 1983 Lists Typographical & Transcription Errors in 830512 Deposition.Certificate of Svc Encl ML20024A6781983-06-20020 June 1983 Informs of Planned Optional Use of Mechanical Couplers for Reinforcing Bar Splice Sys in Nuclear Island Mat.Qa Program Will Be Established.Exception to ASME Code,Section III & Reg Guide 1.136 Requirements Encl ML20076J0951983-06-17017 June 1983 Summarizes Programmatic Objectives 830610 Meeting Re Fallbacks Identified in Chapter 4 of SER & Impact on Crbr Project.Viewgraphs & Supporting Documentation Encl ML20076J0511983-06-16016 June 1983 Advises That DOE Addressees Include Tj Garrish,L Silverstrom & Wd Luck.Rt Johnson & WE Bergholz Should Be Deleted from Svc List.Certificate of Svc Encl ML20023D9611983-05-27027 May 1983 Submits Agreements Reached at 830524 Meeting W/Crbr Project Re Pra.Description of Addl Tasks Needed to Integrate Plan I & II Efforts Encl ML20072B3431983-05-27027 May 1983 Forwards Crbr Erosion & Sediment Control Plan Rept, Providing Implementation Status of Control Plan Measures Currently Utilized ML20023D4031983-05-20020 May 1983 Forwards Amend 77 to PSAR ML20076D3151983-05-19019 May 1983 Forwards Rev 1 to Crbr Project Heat Transport Sys In-Containment Piping Reserve Seismic Margins & Rept Re Consequences of Leaks from Small Diameter Primary Heat Transport Sys Piping ML20076D2281983-05-17017 May 1983 Forwards Rev 5 to Vol 2 to Thermal Margin Beyond Design Base. Rev Incorporates Isotopic Inventory for Heterogeneous Core,Current Meteorology,Addl Organ Doses & More Realistic Pu Sparging Calculations ML20023C5821983-05-16016 May 1983 Submits Supplemental Info to 830401 Ltr Re Cable Separation by Confirming That Approx 75 Ft of DHR Svc & Steam Generator Auxiliary Heat Removal Sys Cable Will Be Run in Separate Conduits or Encl Raceways ML20079Q2881983-05-10010 May 1983 Forwards Corrected 830509 Response to NRDC & Sierra Club First Set of Interrogatories & Request to Produce Directed to Applicant.Original Document Not Identified as Response ML20024D9551983-05-0909 May 1983 Submits Estimate of LMFBR Safety & Licensing Review Needs Over Next Several Yrs.Preparation of Portions of FSAR Will Begin in 1984 ML20073S2761983-05-0505 May 1983 Forwards Revised Responses to SER Item 6 Re Qa,Including Info to Complete Identification of safety-related Structures,Sys & Components Controlled by Crbr QA Program for PSAR.Marked-up Tech Specs Encl ML20073Q3491983-04-28028 April 1983 Forwards Revised Response to SER Item 6, Qa. Response Provides Addl Info Re Identification of safety-related Structures,Sys & Components Controlled by QA Program ML20069L1801983-04-27027 April 1983 Informs That Evaluation of Seismic Adequacy of Primary Heat Transport Sys Branch Line & Consequences of Line Failure Being Conducted,In Response to ACRS 830419 Request.Results Will Be Forwarded by 830517 ML20073R2221983-04-27027 April 1983 Requests to Make Limited Appearance Statement at 830718 CP Hearings Re Regional Socioeconomic Impacts ML20071G2761983-04-18018 April 1983 Recommends That Commission Retain Technical Cadre of Experts to Review Crbr & Overall DOE Breeder Program ML20073K3441983-04-18018 April 1983 Forwards Static Tests of 1/20-Scale Models of Crbr Head in Support on LMFBR Safety Program 1986-03-13
[Table view] Category:OTHER U.S. GOVERNMENT AGENCY/DEPARTMENT TO NRC
MONTHYEARML20128B2801985-06-27027 June 1985 Updates DOE .Bids for Redress of Crbr Site Opened on 850604.Contract Awarded to Beaver Excavating Co,Canton, Oh,On 850613.Contractor Scheduled to Complete Site Redress on or Before 851216 ML20107H8031984-11-0606 November 1984 Reaffirms Commitments to Redress Site in Accordance W/ 840305 Final Site Redress Plan & NRC 840606 Approval Ltr. Related Correspondence ML20086T4631984-03-0505 March 1984 Forwards Site Redress Plan. Minor Clarifications & Corrections to Draft Plan Submitted 840227 Made in Response to NRC Comments ML20087A4141984-03-0202 March 1984 Forwards Page 15 Inadvertently Omitted from 840227 Transmittal of Draft Crbr Plant Redress Plan.Related Correspondence ML20080S6661984-02-27027 February 1984 Forwards Draft Site Redress Plan,In Response to N Grace 831208 Request.Plan Will Be Finalized for Submission on 840302,following Receipt of Comments ML20079F9411984-01-13013 January 1984 Informs of Receipt & Storage,Through S&W Engineering,Of Spent Fuel Transfer Port Assembly Large Shield Plug.Due to Failure of Congress to Appropriate Addl Funding,Doe No Longer Seeking CP & Is Closing All Licensing Activities ML20081B9721983-10-24024 October 1983 Summarizes 831004 Meeting W/Nrc,Acrs & Lnr Assoc Re Mgt of Crbr PRA Program.Viewgraphs & List of Meeting Attendees Encl ML20078A7571983-09-0707 September 1983 Forwards Evaluation Repts of Faults 1,2 & 3 Discovered on Site During Foundation Excavation.Faults Not Capable within Meaning of App a to 10CFR100.W/seven Photographs ML20076H8811983-08-0909 August 1983 Expresses Appreciation for NRC Presentation on 10CFR21 & 10CFR50.55(e) Requirements.Info Should Be Most Useful to Personnel Involved in Project in Following Requirements ML20024D0291983-07-22022 July 1983 Forwards Clinch River Breeder Reactor Plant Sys Design Description - Nuclear Island HVAC Sys, as Example of Procedure Outlines Available for Performance of PRA ML20077H1911983-07-19019 July 1983 Responds to NRC Re Violations Noted in IE Insp Rept 50-537/83-05.Corrective actions:Westinghouse-Oak Ridge Audit Program Revised to Be Computerized Sys.Implementation Throughout Yr Will Be Measured by Planned Surveillances ML20024C1621983-07-0808 July 1983 Informs That Auxiliary Feedwater Sys Evaluation,Per PSAR App C,Section C.6.4 & App H,Section II.E.1.1,scheduled for Completion by mid-1985 ML20105B9551983-07-0606 July 1983 Forwards Addl Info Per Request at 830610 Meeting on Programmatic Objectives Re Fuel Burnup.Fftf Operates W/Peak Burnup of Over 61,000 Megawatt Day/Mt.Burnup Occurred Under Temp & Power Conditions Similar to Crbr Conditions ML20085A7291983-07-0606 July 1983 Forwards Rev 6 to Vol 2 to CRBRP-3, Assessment of Thermal Margin Beyond Design Base (Tmbdb) ML20079R7401983-06-23023 June 1983 Summarizes 830606 Meeting W/Crbr Project Personnel Re Schedule for Resolution of Confirmatory Items.All Identified Items & Preliminary Schedule Info Discussed.List of Attendees Encl ML20024A6781983-06-20020 June 1983 Informs of Planned Optional Use of Mechanical Couplers for Reinforcing Bar Splice Sys in Nuclear Island Mat.Qa Program Will Be Established.Exception to ASME Code,Section III & Reg Guide 1.136 Requirements Encl ML20076J0951983-06-17017 June 1983 Summarizes Programmatic Objectives 830610 Meeting Re Fallbacks Identified in Chapter 4 of SER & Impact on Crbr Project.Viewgraphs & Supporting Documentation Encl ML20076J0511983-06-16016 June 1983 Advises That DOE Addressees Include Tj Garrish,L Silverstrom & Wd Luck.Rt Johnson & WE Bergholz Should Be Deleted from Svc List.Certificate of Svc Encl ML20023D9611983-05-27027 May 1983 Submits Agreements Reached at 830524 Meeting W/Crbr Project Re Pra.Description of Addl Tasks Needed to Integrate Plan I & II Efforts Encl ML20072B3431983-05-27027 May 1983 Forwards Crbr Erosion & Sediment Control Plan Rept, Providing Implementation Status of Control Plan Measures Currently Utilized ML20023D4031983-05-20020 May 1983 Forwards Amend 77 to PSAR ML20076D3151983-05-19019 May 1983 Forwards Rev 1 to Crbr Project Heat Transport Sys In-Containment Piping Reserve Seismic Margins & Rept Re Consequences of Leaks from Small Diameter Primary Heat Transport Sys Piping ML20076D2281983-05-17017 May 1983 Forwards Rev 5 to Vol 2 to Thermal Margin Beyond Design Base. Rev Incorporates Isotopic Inventory for Heterogeneous Core,Current Meteorology,Addl Organ Doses & More Realistic Pu Sparging Calculations ML20023C5821983-05-16016 May 1983 Submits Supplemental Info to 830401 Ltr Re Cable Separation by Confirming That Approx 75 Ft of DHR Svc & Steam Generator Auxiliary Heat Removal Sys Cable Will Be Run in Separate Conduits or Encl Raceways ML20024D9551983-05-0909 May 1983 Submits Estimate of LMFBR Safety & Licensing Review Needs Over Next Several Yrs.Preparation of Portions of FSAR Will Begin in 1984 ML20073S2761983-05-0505 May 1983 Forwards Revised Responses to SER Item 6 Re Qa,Including Info to Complete Identification of safety-related Structures,Sys & Components Controlled by Crbr QA Program for PSAR.Marked-up Tech Specs Encl ML20073Q3491983-04-28028 April 1983 Forwards Revised Response to SER Item 6, Qa. Response Provides Addl Info Re Identification of safety-related Structures,Sys & Components Controlled by QA Program ML20069L1801983-04-27027 April 1983 Informs That Evaluation of Seismic Adequacy of Primary Heat Transport Sys Branch Line & Consequences of Line Failure Being Conducted,In Response to ACRS 830419 Request.Results Will Be Forwarded by 830517 ML20073K3441983-04-18018 April 1983 Forwards Static Tests of 1/20-Scale Models of Crbr Head in Support on LMFBR Safety Program ML20073D7311983-04-12012 April 1983 Forwards Addl Info to Resolve SER Open Item 4 Re Solid State Programmable Logic Sys ML20073A1201983-04-0808 April 1983 Forwards Responses to Questions Re Identification of safety- Related Structures,Sys & Components by Crbr QA Program.Info Should Enable NRC to Complete Review of QA List & Close Out SER Open Item 6 ML20073A4591983-04-0808 April 1983 Provides Addl Clarification of Info Contained in PSAR Section 13.3, Emergency Planning (SER Open Item 5). Responses to Questions Identified in Crbr 830321 Meeting in Bethesda,Md & Annotated PSAR Pages Encl ML20073A0941983-04-0808 April 1983 Forwards Response to SER Open Item 3 Re Plant Protection Sys Monitor Mods ML20073A8031983-04-0707 April 1983 Commits to Listed Actions to Close Out SER Open Item 1, Review of Rdt Stds F9-4T & F9-5T. Appropriate Info on Verification of Analysis Methods & Computer Programs Used in High Temp Design Will Be Provided at OL Review Stage ML20069H5331983-04-0404 April 1983 Forwards Analysis of Wall Liner at Square Penetrations for Crbr Cell Liner Design Verification Program,Per Commitment in DOE ML20072P9561983-04-0101 April 1983 Commits to Provide Min Physical Separation of 5 Ft Between DHR Sys & Steam Generator Auxiliary Heat Removal Sys Cabling in Same Div.Commitment Resolves SER Open Item 2 ML20069G0761983-03-23023 March 1983 Forwards New Info Re Cell Liner Design Validation Program. Analysis of Wall Liner at Circular Penetrations Encl ML20071F1931983-03-14014 March 1983 Forwards Adequacy of Crbr Program Reactor Vessel NDE Insps. Rept Supports Conclusion That Exam Performed on Reactor Vessel Adequate.Rept Also Applicable to ex-vessel Storage Tank & Heat Transport Sys Vessels ML20071D2591983-03-0808 March 1983 Comments on Design Change to fission-driven Compaction. Compaction of Core Could Lead to Energetics During Hypothetical Core Disruptive Accident.Design Change Feasible ML20071D2511983-03-0707 March 1983 Forwards Corrected PSAR Table 5.6-12 Covering DHR Operating Cases & Sensitivity Evaluations to Be Included in Future PSAR Amend ML20071C7171983-03-0404 March 1983 Addresses ACRS Questions Re Capability of Facility to Continue Shutdown Heat Removal on Natural Circulation W/Loss of Bulk Ac Power for Greater than 2 H.Info Previously Presented to NRC & Documented in PSAR Section 5.7.5 ML20072B6181983-03-0404 March 1983 Forwards Crbr Program Heat Transport Sys Incontainment Piping Reserve Seismic Margins. Rept Addresses Questions Raised During ACRS 830211 Committee Meeting ML20071C6891983-03-0404 March 1983 Forwards Description of Cell Liner Design Validation Program & Fallback Plan If Base Criteria Not Validated,Per NRC Request ML20071C7021983-03-0404 March 1983 Forwards Response to Questions Re Thermal Margin Beyond Design Base,Design & Analysis.Overly Conservative Assumptions Made by NRC Consultants Re Treatment of Sodium Aerosols Inappropriate ML20072B5191983-03-0202 March 1983 Advises That Reliability Assurance Program Will Be Modified to Comply W/Criteria Presented in NRC 830225 Submittal. Project Will Provide Reliability Assurance Program Plan & Schedule Approx 6 Months After Issuance of CP ML20071C2201983-02-28028 February 1983 Forwards Revised PSAR Pages Re Inservice Insp & Addl Info Re NDE Procedure,Per 830214 Discussions.Pages Clarify Design & Provide Info Relative to Piping Insulation & NDE Requirements for Cell Liners & Fire Suppression Decks ML20071C1331983-02-28028 February 1983 Forwards Updated Page to PSAR Chapter 4.4,design Bases Section.Info Concerns Primary Sodium Gas Entrainment & Assembly Flow Blockage Criteria.Page Will Be Submitted W/ Next PSAR Amend ML20071C1391983-02-25025 February 1983 Forwards Addl Info on Psar,Section 13.3 Re Coordination W/State of Nc & Local Officials for Emergency Planning.Info Will Be Incorporated in Next PSAR Amend ML20071B0621983-02-24024 February 1983 Forwards Revised Responses to Mechanical Engineering Branch Items 26 & 70 Re Low Temp Components.Info to Be Included in Next Amend to PSAR ML20071B0301983-02-23023 February 1983 Forwards Amended PSAR Page 10.4-7 Re Consequences of Flooding Due to Failures in Circulating Water Sys.Pages Respond to NRC Questions & Will Be Included in Next PSAR Amend 1985-06-27
[Table view] |
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hblT Q;
Department of Energy 9 Washington, D.C. 20545 Docket No. 50-537
-(3 HQ:S:82:105 0CT 151982 r
Mr. Paul S. Check, Director CRBR Program Office , . ,,
Office of Nuclear Reactor Regulation -C U.S. Nuclear Regulatory Commission ,
Washington, D.C. 20555 -s
Dear Mr. Check:
v
SUMMARY
OF HCDA ENERGETICS MEETING HELD ON SEPTEMBER 21, 1982 The meeting agenda, attendance list, and viewgraphs distributed at the subject meeting are enclosed as Enclosures 1, 2, and 3, respectively. The formal presentations and general discussion focused on clarification of technical issues associated with the CRBRP/P0 response to formal NRC questions. Presentations were made by both the NRC and CRBRP consultants. As a result of the meeting, the Project will undertake the actions listed in Enclosure 4.
Sincerely.
J n R. Longe ker Acting Directo , Of fice of the Clinch River Breeder Reactor Plant Project Office of Nuclear Energy Enclosures cc: Service List Standard Distribution Licensing Distribution 8210210273 821015 pol PDR ADOCK 05000537 A PDR
LNLLUbOHL 1 Pogn 2 of 2 Ar.CHDA citBi1P/IIRC llCDA Energetics liceting .
Sr pte.niber 21, 1982 Argnnne. Ib tional I.cbora tory Building 207 Con ference Poom DA-126 1..
Introductory rcuarks, (unc/CRBRP, is mi.n). .
- 2. TO.P cncrgetics potential (pin internal fuel motion, sweapout, inccher-nn c e ) , (CRDEP, 15 min - NRC, 15 min).
- 3. 1.0F-d-TOP potential (sodima void worth and other uncertainties), (CRBRP, 30 min - Rnc, 30 min).
- 4. Plenum fi s: ion Das compact. ton (energetics potential, clad relocation,
. :4 initiating powcr phase histories), (CABRP, 30 min - /mC, 26 min). ~
I.UUCil
- 5. Fuel remuval and cuerget ler. rotont.f al in connect.lon wit.h mci tout /ai nular.
pool phctu s (CRDRY, GO v1f *! - UliCa GO mist). -
G. Pole of struct.ui-es in energetic teminction, (CN?iRP, 25 min - luiC, .10 r:d n) .
- 7. Conc 1uding rnnneht., (CRUn!', 30 miss - VRC, 30 min 1 I
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ENCLOSURE 2 Y
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EELOSURE 3 CEBRP HCDA EllERGETICS MEETillG INITI ATING PHASE ASSESSMENTS 1
PRESENTED BY DAVID P. WEBER SEPTEMBER 21, 1982 ARGONNE NATIONAL 1.ABORATORY ARG0llNE, ILLINDIS 60439' 4
e e 6
1 CRBRP HCDA ENERGETICS MEETIllG INITIATING PHASE ASSESSMENT
= LOF'n' TOP POTENTI AL a PLENUM FISSION GAS COMPACTION 6
e
ASSESSMENT OF WHOLE CORE IMPLICATIONS OF MIDPLANE PIN FAILURES IN SLOW RNiP TOP IN HETEROGENEOUS CORE CRBRP WITH SAS/PLUT02 o EOC-410&/SEC SCENARIO
- FAILURE MELT FRACTION, CAVITY PRESSURE, AND PARTICLE i
SIZE CHOSEN TO SIMULATE W2 EXPERIMENT
- ALL FUEL PINS ASSUMED TO Fall C0HERENTLY
- LEAD CHAN!!EL FAILURE (6) LEADS TO LOW PEAK POWER (4 5 Po) AND LIMITED POSITIVE REACTIVITY (10&)
- LIMITED PLUTO-2 PREDICTED SWEEPOUT LEADS TO MORE RAPID POWER REC 0VERY THAN E0C-4 TOP CASE 2 (GEFR 523)
- SUBSEQUENT DRIVER ASSEMBLY FAILURES AT LOW REACTIVITY STATE IMPLY SUB-PROMPT CRITICAL EXCURSION AND SUBCRITICALITY (PEAK POWER = 5 7 Po )
- EOC-310C/SEC SCENARIO a E0C-3 CHANNEL. POWER FACTORS USED WITH EXISTING E0C-4 DATA
? SEC0llDARY ASSEMBLY FAILURES (Cal 11 AND 7) DELAYED Ill TIME (66 AND 82 MSEC) PREVENT SUPERPOSITION OF POSITIVE FUEL FEEDBACKS
= SIGNIFICAllT NEGATIVE FUEL REACTIVITY FROM LEAD CHANNELS WITilIN 300 Msec (~ 45) .
.A t t PLUT02 APPLICATIONS TO IN-PILE TESTS e PRE-TEST AND POST-TEST ANALYSES OF TREAT TESTS E8, H6, AllD L8 WITH PLUTO AllD PLUT02 o TREAT TEST E8
- $3/SEc TOP FFTF SIMULATION
- LOW PUMP PRESSURE AND INITIAL SODIUM VELOCITY
= FAILURE LOCATION ABOVE MID-PLAllE
= CONSIDERABLE EARLY SWEEP 00T WITH EXPERIMENTAL RESULTS FASTER AND LARGER THAN PLUTO CALCULATIONS o TREAT TEST H6
- 50&/SEc TOP FFTF SIMULATION i a PROTOTYPIC PRESSURE DROP AND IlllTIAL S0DIUM VELOCITY a SEVERAL EVENTS SEPARATED BY MORE THAN 100 MSEC
\
o CALCULAT10ll AllD H0DOSCOPE SHOW SIGNIFICANT EARLY SWEEP 00T (10s WITHIN 30 MSEC AllD 28s WITH 90 MSEC) e TREAT TEST L8
= LOF'n' TOP SIMULATION FOR CRBRP A0M0GEllE00S CORE o DEGRADED POTEllTI AL FOR FUEL SWEEP 00T t
a FUEL MOT 10tl REACTIVITY NEGATIVE 20 MSEC AFTER R0D l
FAILURE.
a CALCULATED SWEEP 00T LAGGED MEASUREMEllTS l
- e m w tw g
'M n. a e .:. . .
e CRBRP HCDA ENERGETICS MEETING INITIATING PHASE ASSESSMENT
= TOP ENERGETICS POTENTIAL
o PLENUM FISS10!! GAS C0KPACTION 4
e 9
VOID WORTH Ul1 CERTAINTY IMPLICATI0!ls ON LOF'o' TOP POTENTI AL o SAS3D MODELING ASSUMPTIONS BEST ESTIMATE SODIUM VOID REACTIVITY WORTHS PROVIDED BY AHL/AP SODIUM VOID "0RTH UNCERTAlllTIES BASED 011 AllL/AP ZPPR EXPERIMEllTAL RESULTS AND ANALYTICAL METHODS AllD DATA BASE USED Ill CRITICAL EXPERIMEllTS FUEL MOTION ASSUMPTI0llS IN SLUMPY BASED 011 RECENT AllL/ RAS L6/L7 AllALYSIS e KEY MODELillG P0iHTS i
i =
MAXIMUM POSITIVE COOLANT VOIDillG REACTIVITY PLUS TWICE UllCERTAlllTY RESULTS IN $219 VOIDING REACTIVITY l
=
EXPERil1ENTALLY C0llSISTENT FUEL NOTION MODELING PLAYS l ,
IMPORTANT ROLE IN ANY LOF'n' TOP ' ASSESSMENT l
l l.
l _ _ _ - - - _ _ _
V0ID WORTH UNCERTAlllTY IMPLICAT1011S ON LOF'n' TOP POTENTI AL o SAS3D WHOLE CORE RESULTS COOLANT BOILING IN ALL DRIVER ASSEMBLIES BEFORE LEAD CHANilEL (CH. 6) FUEL MOTION COMPLETE CORE VOIDING IN DRIVER ASSEMBLY CHANilELS 2,4,6,7,9,10 AllD 11 AT TIME OF CHAllllEL 6 FUEL MOT 10ll a PARTIAL VOIDING IN CHAllllELS 12, 13, 14 AND 15
- POWER LEVEL IS LOW (~ 10 P o ) A!!D FAILURE C0!!DITI0lls ARE FAR FROM BEING MET IN LOW POWER CHAllllELS.
C00LAllT BOILING IN INTERilAL BLANKETS TAKES PLACE AFTER FUEL DISRUPTION AND GROSS DISPERSAL IN CHAllllELS 6, 2, 4 AND 7 o C0llCLUS10N l EVEN USING C0!1SERVATIVE ESTIMATE'S OF THE UllCERTAINTIES 111 C00LAllT V01DillG REACTIVITY,110 THRESHOLD FOR LOF'n' TOP EVEllTS WAS FOUllD WHEll EXPERIMEllTALLY VERIFIED FUEL MOT 10ll BEHAVIOUR WAS BKPLOYED i
i
- e
~~
- c e .m e... g.
CRBRP HCDA EllERGETICS MEETIllG INITIATil1G PHASE ASSESSMENT o TOP ENERGETICS POTENTIAL
- LOF'o' TOP POTENTI AL o PLE110M FISSION GAS COMPACTION 6
e O
POTEllTIAL FOR AUT0 CATALYSIS DUE TO PLEl10M FISS1011 GAS INDUCED FUEL COMPACTION
=
INITIAL ASSESSMENT (BASED ON GEFR-523 EOC-4 LOF BASE CASE 1A) SHOWED COMPLETE BLOWDOWil IN EARLY ASSEMBLIES BUT POTEllTIAL FOR CGiPACTION IN LATER ASSEMBLIES a
AUTOCATALYTit BEHAVIOR WAS AFFECTED BY C0llSERVATIVE MODELING OF EARLY FUEL MOT 10H e
TREAT LOF TESTS, ESPECIALLY L6 AND L7, WERE IDENTIFIED AS THE MOST RELEVAllT DATABASE AllD EXTENSIVE SAS3D/SLUMPY ANALYSES WERE PERF0miED o
FISSION GAS AVAILABILITY AND DISTRIBUT10ll WERE DETERMl!JED WITH FRAS3 CODE e
WHOLE CORE AllALYSES WERE PERFORMED WITH EXPERIMENTALLY CONSISTEllT FUEL DISPERSAL MODELING, LEADING TO ELIMINATI0ll 0F CollCERll FOR PLElluM GAS COMPACT 10!l e
FISS10!! GAS MODEllilG WITH FRAS3
- TECHillCAL APPROACH VAllDATION OF FRAS3..MODELING BY COMPARISON OF PREDICTED AllD MEASURED GAS RELEASES Ill FGR TESTS WHICH MOST CLOSELY REPRESEllT CRBR C0!!DIT10lls PREDICT 10lls 0F THE FRACT10110F THE INITIAL FISSION GAS COUCEllTRATIONS RETAlllED AT TIME OF FUEL MOT 10!l IN L6 AllD L7 TESTS FOR USE IN SAS3D/SLUMPY PREDICT 10lls 0F GAS C0llCEllTRAT10llS FOR EOC-4 LEAD
' CHAllllEL 6 WITH LOF GEFR-523 BEST ESTIMATE THERMAL HISTORY a C0llCLUS10llS 011 GAS RETEllTION t
PERCEllT RETAltlED PERCEllT RETAlHED IN GRAlllS ON GRAIN BOUNDARIES L6 24 -
95
. L7 64 47 CH 6 54 47 l
SAS3D/SLUMPY ANALYSIS OF L6 AND L7 TREAT TESTS e TECHNICAL APPROACH PROCEDURE FOLLOWED FOR HEAT BALANCE AND TEST SIMULATIONS
=
STEADY-STATE SIMULATION OF 1RRADIAT10N HISTORY a
20-SECOND TRANSIENT TO SET INITIAL THEmiAL-HYDRAULIC CONDITION
FISSION GAS PARAMETERS BASED ON FRAS3 ANALYSIS FRACTION OF GRAVITY SET TO 0 2 o VERY LITTLE COUPLING BETWEEN COOLANT VAPOR STREN4, AND FUEL MOTION (0 SODOM = 0 02)
! o EFFECTIVE FUEL VISCOSITY ENHANCED TO ACC0llNT FOR PRESENCE OF PARTIALLY SOLID FUEL (VISFU = 10000)
I o FUEL MOTION INITIATED ON 50% FUEL MELT FRACTION i
i o TEST RESULTS a
SATISFACTORY SIMULATION OF BOTH L6 AND L7 TESTS l
WHOLE CORE AllALYSIS AllD PLEllUM GAS COMPACT 10!! ASSESSMENT WHOLE CORE POWER AND REACTIVITY RESULTS LEAD CHAullEL REACTIVITY STAYS POSITIVE FOR 146 MSEC, WITH PEAK POWER OF 4 7 Po a
REACTOR DRIVEN SUBCRITICAL ON LEAD CHANilEL FUEL MOTIO BY 406 MSEC a
ASSESSMENTS PERFORMED ON SUBSEQUEllT FAILURES AND TIM
=
POTEllTI AL FOR COMPACTION OF FUEL o
PIPFLO MODEllllG IN SAS3D AND 1400 C CLADDING TEMPERATURE FAILURE CONDITION USED l
o TIME C0llSTANT FOR BLOWDOWil CALCULA ED TO BE LESS THAN 250 MSEC a
ALL DRIVER CHANilELS HAVE SEVERAL TIME C0llSTAllTS TO BLOWD0l!!1 PRIOR TO FUEL MOTION INITIATION
4 AUTOCATALYSI,S BY PLElluM GAS COMPACTI0ll 0F pills IS HIGilLY UllLIKELY i
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S0DIUM VOID WORTH ALTERNATIVE METHODOLOGIES 0 USE STATE-OF-THE-ART METHODS AND. CROSS SECTION DATA FOR CALCULA-TIONS. DETERMINE UNCERTAINTIES FROM " KNOWLEDGE" 0F UNCERTAINTIES IN METHODS / DATA.
0 USE INTEGRAL DATA BASE TO DERIVE AN " EXPERIMENTAL"'VALUE. UNCER-TAINTIES FALL OUT OF ANALYSIS O
b o
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I BIAS FACTOR METHOD e SINGLE BIAS FACTOR P=aC e Two FACTORS (LEAKAGE AND NON-LEAKAGE) .
9 P = $N + il I
-E MIN [ (P 'I I)2 '
I 4
COMPUTATIONAL MODEL o ENDF/B-IV DATA 2
o MC -2/SDX PROCESSING TO 20 ENERGY GROUPS
~~
e THREE-DIf4ENSIONAL DIFFUSION THEORY 5 : ,.
1 e CORRECT FOR STREAlilNG USING BENOIST DIRECTIONAL DIFFUSION i$
COEFFICIENTS ,
, o EXACT PERTURBATION THEORY e
9 t
t
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9W Ratios of Calculated to tieasured Reactivities for Sodium Voiding C/E Before . Standard Devia-
., Cases Biasing tion After Biasinga CRBR-EMCb BOC-1, positive part of core 0.98 10
. 'CRBR-EMC EOC-4, positive part of core 1.23 6 101 mixed zones -
1.08 12 Axial blankets without control rods 0.91 1 Axial blankets with control rods 1.23 2 Core zones with negative reactivity signals- 1.02 9 a
Separate' bias factors applied to positive and negative components of reactivity. For any subset, the average C/E is 1.0 after biasing.
b Engineering mockup critical experiments foc sodium-void reactivity in CRBR; reactor geometry and composition closely matched.
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Ratios of talculated to Nessured Reactivities for Sodium Voiding C/E Before % Standard Devia-Cases Biasing tion After Biasinga CRBR-EMCb BOC-1, positive part of core 0.98 10 CRBR-EMC EOC-4, positive part of core 1.23 6
, 101 mixed Jones -
1.08 12 Axial blankets without control rods 0.91 1
Axial blankets with control rods 1.23 2 Core zones with negative reactivity signals 1.02 9 aSeparate bias factors applied to positive and negative components of reactivity. For any subset, the average C/E is 1.0 after biasing.
b Engineering mockt? critical experiments foc sodium-void reactivity.in CRDR; reactor gc00 try and composition closely matched.
t O
e l
Bias Factors and Uncertainties for Sodium-void Reactivity in CRBR Calculational Bias Factora Uncertainty,b%
Zone BOC-1 EOC-4 BOC-1 EOC-4 Central core 1.0 0.82 10 6 /
External core 1.0 1.0 10 10 Axial blankets 1.0 1.0 20 20
. Internal blankets 1.0 1.0 20 20 "to be multiplied times the calculated value.
b to be added in quadrature with uncertainties from other sources.
l l
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Bias Factors and Uncertainties for Sodium-void React.vity in CRBR Calculational Bias Factora Uncertainty,bg Zone BOC-1 EOC-4 BOC-1 EOC-4 Central core 1.0 0.82 10 6 External core 1.0 1.0 10 10 Axial blankets 1.0 1.0 20 20 Internal blankets 1.0 1.0 20 20 a
to be multiplied times the calculated value.
b to be added in quadrature with uncertainties from other sources.
4 e
i Additional Uncertainties in CRBR Sodium-void Reactivity
. Uncertaintya ,
Source % of Total Reactivity BOC-1 EOC-4 Fuel pins instead of plates 0 0 4 Sequence of voiding 3.5 3.5 Temperature distribution 2.5 2.5 Fission products 0 3.0 a
To be added in quadrature with the values of
" experimental" uncertainty.
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a Best Estimate Sodium Void Reactivity Worths ($)b ,
BOC-1 EOC-4 Driver Assemblies Core -
0.256 1.528 Lower Axial Blanket -0.225 -0.160 Upper Axial Blanket -0.177 -0.177
- Total -0.146 1.191 Internal Blanket Assemblies Core 1.381 1.593 Lower Axial Extension 0.008 -0.020 Upper Axial Extension -0.007 -0.006 Total 1.382 1.567 a
Void Flowing Sodium (81.8% driver, 72.6% Blanket) b
= .0032 4
e 9
I i
! FUEL REMOVAL AND ENERGETICS POTENTIAL IN CONNECTION WITH MELT-0VT/ ANNULAR POOL PHASE e
PRESENTED BY:
MICHAEL EPSTEIN FAUSKE t. ASSOCIATESs INC.
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QUESTIONS CS760.178B5, -C.6, -C7
-B5, What is the basis for maintaining continuous subtriticali-ty in the high heat loss environment of early melt-out phase?
What are the fuel-losses (quantified), taking into account uncertainties in removal path geometries, driving pressures and freezing mechanisms?
-C6.
What degree of subtriticality is required to prevent pool recriticality from tilermal and fluid dynamics upset conditions? What is your position on the potential for small recriticalities to amplify? What is the Justifica-tion for your position?
i
-C7.
In assessing benign termination from the boiled-up pool, t
Justify the fuel removal mechanisms and rates, in par-ticular, assess the potential for, upper pool sodium entry via rapid condensation of steel vdpor pressure.
e , e *
.. l GENERIC ISSUES COVEREll 1.
DEFINITION OF MELT-0UT PHASE.
2.
DURATION OF MELT-0UT PHASE AND SENSITIVITY CONDITIONS (POWER LEVEL).
3.
RECRITICALITY AND RELATED PHENOMENA.
4.
FUEL FREEZING MECHANISMS AND REMOVAL PATHS.
5.
FUEL REMOVAL REQUIREMENTS FOR PERMANENT S ~
6.
SODIUM RE-ENTRY VIA STEEL VAPOR CONDENSATION.
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POOL DEFINITIONS ,
1.
Melt-Out/ Annular Pool Phase -
Merging of molten driver '
fuel assemblies while the inner blanket fuel assemblies remain intact.
- 2. Large Scale Pool -
Configuration after the melting Of the inner blanket assemblies.
ess 4
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O Fuel Assemblies O Alternate Fuel-Blanket-Assemblies g Blanket Assemblies g Centrol Assemblies A:
Ilff SCALE OF THE_tlELT-00T/Al#10LAR POOL PHASE: Ball 1
- 1. POWER LEVEL BOUNDED BY 50% OF NOMINAL TO PRECLUDE RECRITICALITY ON AN ASSEMBLY SCALE.
- 2. ADIABATIC HEATUP OF INTER BLANKET FUEL ASSEMBLIES:
E0C-4 BOC-1 TIME = 46 SEC 150 SEC
- 3. MOLTEN DRIVER FUEL ENTERS INNER BLANKET FUEL ASSEMBLIES':
E0C-4 BOC-1 TIME = 35 SEC 46 SEC
- 4. CHOICE OF THE POWER LEVEL IS NOT IMPORTANT SO LONG AS LARGE l RAMP RATE RECRITICALITIES CAN BE PR"ECLUDED, i -
I
NEUTRONIC EVENTS DURING THE MELT-00T/ ANNULAR POOL PHASE
- 1. }F RECRITICALITIES SHOULD OCCUR THEY ARE MILD AND DO NOT
, AMPLIFY.
- 2. ASSEMBLY WALL / FUEL MIXING IS MINIMAL DUE TO FUEL CRUSTING AND MELT LAYER STABILITY.
- 3. MECHANISM (S) FOR SODIUM RE-ENTRY HAS EQI BEEN IDENTIFIED.
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16L ANALYTICAL CONSIDERATIONS; ID vs. 3D
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IERMINATION OEJELI:OllI/mg!LAR POOL PHASE 1,
FUEL REMOVAL PATHS ARE AVAILABLE, 2,
FUEL REMOVAL IS SUFFICIENT TO ASOU CRITI'CALITY EVEN WHEN ASSESSED ELS. WITH C B
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Schematic of Prbna2'y Control Assembly.
4 Indicates niel Melt Path.
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Re.moval (not to scale).
REQUIREMENTS FOR PERMANENT SUBCRITICALITY AD b
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e REACTIVITY LEVELS FOR VARIOUS DISRUPTE6 CORE CONFIGURATIONS AT BOC-1 Case Description of Core Configuration Reactivity ($)
1 43% of total fuel inventory removed from -1.4 the core. The remaining fuel in the annu-lar regions is hoinogenized in the core and fully compacted with IB and CR assemblies intact.
2 Sace as Case 1 except that only 33% of +10.2 total fuel inventory is removed.
3 Same as 2 except fuel boils up with a linear / 3]
uniform void fraction.
4 41% of total inventory removed from core. The -10.5 remaining fuel, the IB and CR (except B C) 4 assemblies are homogenized and fully compact.
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% Driver Fuel Inventory -
l-Upper Axial 1 l Power Level end Time Interval Blanket and Between Melt-Out/ Annular. Pool g
Location Radial Interassembly Control Rod Phase and Homogeneous Fool
, Blanket Gaps Assemblies Phase **
! ; i .
. 1 1 Carly* < 10% > 40% = 10%
- i BL Fuel l Removal Based on Rate of Removal = 150 sec 0j Limited Opening is Fuel Melt
- in Clad Bkg. Limited ,
C ' - - - - - - - - - -
! Later* = 20% 15% > 40% Time Interval Reduced by 1/4 i l Fuel No fuel Pene- Based on BFM Due to Driver Fuel Penetra-tration into and BOC Gaps tion into Bkt. Assembly I 1 *l Removal UAB - RB only [ ,
= 35 see Early* > 25% > 40%
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, ' Fuel -
~
i Removal . Based on Exp.. Rate of Removal 0% = 46 see 10 l Data Limited is Fuel Melt i l 1 Cla'd 'Bkg. Limited C ---------------------------l---------------- - - - - - - - l - - - - - - - -
l ,
Later* > 40% i > 10% > 30% Time Interval Reduced by 1/2
. Fuel Based on BFM Based on BFM Due to Driver Fuel Penetra-
,4 Removal in UAB (25%) and EOC Caps tion into Bkt. Assembly '
- I Plus (20%) in * = 23 see -
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to RB !
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- ' Relative to the annular pool phase time interval.
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l Defined by loss of inner blanket fuel assemblics structural integrity. .
POTENTIAL FOR LOSS OF FUEL INVENTORY PRIOR TO .
HELT-OUT OF INNER llLANKET ASSEHilLIES L
EFFECT OF SODIUM IMPEDANCE ON FUEL EENETRATION INTO GAPS _
~
~1.
CONDUCTION MODEL:
PENETRATION LENGTH IS REDUCED B MOST 40%.
THIS REDUCTION DOES NOT ALTER THE FUEL REMOVAL INVENTORY.
2.
Butx FREEZING MODEL_:
NO EFFECT ON PENETRATION LENGT O
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RADIAL SHIELO RAD!ilBLANKET 1 A Ok P ACLP)
S CtiOn to Na g Ai Flow at ACLP)
CORE REGION
$ $' . L55tr.'8LY Pi1CH: 12.1 CM ED W Las Y .hh /,Y hkc?Yhhh, '
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- I N N N N N N lutEI noault N Sketch Showing the Inicrstitial Gaps Outside and Below the Core Rcgion.
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_ - _ . - - _ . - -.-. _ -. = - . - - - r. - .- - - - -- - .
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CONSIDERATION OF P0OL S0DIUM ENTRY VIA RAPID CONDENSATION OF STEEL VAPOR PRESSURE l
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SUMMARY
RESPONSE TO QUESTIONS 1,
Once molten fuel mild becomes available on on assembly b recriticality events asis, may be possible but they are limited in amplitude and do not amplify, 2.
Multiple paths for fusl time scale, assemblies.
relative to the melt-outremoval of internal blanket are Correspondingly, fuel removal is not overly sensitive to fuel penetration model escape impedances. assumptions and fuel 3.
There is always time for sufficient fuel removal , 1,.e. about 40% of the driver fuel, to achieve permanent cality subtriti prior to loss Of the annular inner blanketer,barri 4.
The accident sequence will terminate benignly without the development of a homogeneous large scale _
phase confined poo as defined in (Ref, QCS760,178BS-1),
Sodium out re-entry on the basis via steel vapor condensation ruled can be of excessive sodium vaporization when llould sodium comes into contact with steel vapor ,
ROLEOFSTRUCTURESDURINGENERGETIC. TERMINATION e INTERNAL STRUCTURES ACT TO ABSORB, PARTITION AND REDUCE THE LEVEL OF CORE EXPANSION FORCES ON THE PHTS BOUNDARY.
e THE UIS PLAYS AN IMPORTANT MITIGATING ROLE VIA BOTH HYDRODYNAMIC AND HEAT TRANSFER OROCESSES e FINITE ELEMENT ANALYSIS INDICATES THAT A FORCE OF 6.5 MILLION LBF IS REQUIRED TO BUCKLE THE UlS SUPPORT COLUMNS, AND THEREBY REDUCE ITS MITIGATING ROLE.
e THE MAJOR UNCERTAINTY IN THE ABOVE ANALYSIS OF UlS
, COLUV.N BUCKLING IS IN THE YlELD STRESS:
-20 TO +100%.
e INTRAASSEMBLY BLOCKAGES IN UCS ARE STRONG RELATIVE TO EXPECTED CORE PRESSURES, WITH THE BLOCKAGE TEMPERATURE THE CONTROLLING FACTOR.
e OVERALL EFFECT OF STRUCTURES IS TO REDUCE THE PHTS
~
LOADS BELOW THOSE CALCULATED VIA AN ISENTROPIC CORE EXPANSION PROCESS.
ENCLOSURE 4 ACTION ITEMS FOLLOWING THE SEPTEMBER 21, 1982 CRBRP/NRC HCDA ENERGETICS MEETING HELD AT ARGONNE NATION AL L ABORATORY The following action items will be completed and submitted to NRC w i th i n two month s.
- 1. Provide concise statement on TOP Initiating ramp rates.
- 2. Provide EOC-3 neutronics data (data type transmitted to ANL will suffice).
- 3. Provide results of SAS sensitivity eval uation of best parameters for L6 and 17 in-pile tests.
- 4. Provide SAS 3D input deck with SLUMPY parameters used in response to QCS.760.
- 5. Recalculate plenum fission gas effects f or EOC-4 w i th new sodium void worth.
- 6. Provide SAS 3D corrections made to complete item 5.
- 7. Provide TREAT test R-8 fuel pin data.
- 8. Provide analysis supporting fuel freezing upon entry to inner blanket assemblies.
- 9. Provide resul ts of the GAP tests being perf ormed at ANL when av ai l abl e.
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