|
---|
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 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 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 ML20073R2221983-04-27027 April 1983 Requests to Make Limited Appearance Statement at 830718 CP Hearings Re Regional Socioeconomic Impacts 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 ML20071G2761983-04-18018 April 1983 Recommends That Commission Retain Technical Cadre of Experts to Review Crbr & Overall DOE Breeder 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 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 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 ML20072B3431983-05-27027 May 1983 Forwards Crbr Erosion & Sediment Control Plan Rept, Providing Implementation Status of Control Plan Measures Currently Utilized 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 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 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 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 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 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 ML20071C6891983-03-0404 March 1983 Forwards Description of Cell Liner Design Validation Program & Fallback Plan If Base Criteria Not Validated,Per NRC Request 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 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 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 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 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 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 ML20071B0341983-02-23023 February 1983 Forwards Edited PSAR Pages Re Secondary Control Rod Sys Capability.Info Will Be Included in Future PSAR Amend 1985-06-27
[Table view] |
Text
3
. o O
Department of Energy Washington, D.C. 20545 Docket No. 50-537 HQ:S:83:242 APR 0 81983 Dr. J. Nelson Grace, Director CRBR Program Office Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Dr. Grace:
RESPONSE TO SAFETY EVALUATION REPORT (SER) OPEN ITEM N0. 5 - EMERGENCY PLANNING This letter provides additional clarification of information contained in the Preliminary Safety Analysis Report (PSAR) Section 13.3, " Emergency Planning." A working meeting on this subject was held on March 21, 1983.
The enclosed resolution of the specific questions identified at the meeting shoula enable the staff to complete their review and close out this SER open item. The attached PSAR change pages will be included in the next scheduled PSAR amendment.
Any questions regarding the information provided can be addressed to Mr. Ken Yates (FTS 626-6097) or Mr. Wayne Hibbitts (FTS 626-6455) of the Project Office Oak Ridge staff.
Sincerely,
. b J n R. Longen er Acting Director, Office of Breeder Demonstration Projects Office of Nuclear Energy Enclosure cc: Service List Standard Distribution Licensing Distribution g
8304110760 830408 PDR F ADDCK 05000537 PDR
Enclosure CRBRP/NRC WORKING MEETING EMERGENCY PLANNING MEETING LOCATION /DATE: Landow Building, Room Illi, Bethesda, Maryland, March 21, 1983 ATTENDEES: Richard Stark, NRC
, Don Perrotti, NRC Wayne Hibbitts, CRBRP/P0 Peter Planchon, Westinghouse /0R Eric Sliger, TVA
, Lonnie Kepley, CRBRP/P0 Kenneth Yates, CRBRP/P0 Richard Baker (part time), CRBRP/P0 Pat Docherty, Westinghouse /WLLC0 The following information is provided in respons2 to requests made by NRC staff (Don Perrotti and Richard Stark) concerning questions related '
to the PSAR and the CRBRP SER:
Questions / Areas of Discussion
- 1. The PSAR Section 13.3.3 requires additional information to address agreements to be established among emergency planning agencies.
Response: The attachment provides a revision to the PSAR Section
- 13.3.3 which further describes emergency planning arrangements mquested in the SER Section 13.3.2.1.
- 2. Verify the principal agency in North Carolina responsible for coping with smergencies in North Carolina.
Response: The North Carolina Department of Crime Control and Safety is the principal agency responsible for coping with emergencies in North Carolina.
- 3. Identify in the PSAR the application of real-time meteorology.
Response: The attached proposed update to the PSAR Section 13.3.2, page 13.3-4, par. 6, and page 13.3-5, par. 3, con fims that real-time meteorological infomation will be utilized in dose assessments related to actual releases of radioactivity with readout capability in the Control Room, TSC, CECC, MSECC, and State of Tennessee Emergency Operations Center.
- 4. Provide a more detailed discussion of the EPZ bcundary determination including known impediments to evacuation.
Response: The preliminary evacuation time estimates (PSAR Appen-i- dix 13.3A) assumed a circular 10 mile plume exposure EPZ boundary. The final EPZ boundary will be determined 4
-, ~ , _ , , , . , ., . . _ . . . - . . _ _ _ - , , _ . . , _ _ _ _ _ _ _ . . . , .
=c _-
by the State of Tennessee following coordination of planning efforts with local government agencies. The applicant will provide CRBRP specific information to the State to supplement, as necessary, NUREG-0396 EPZ size guidance.
This final EPZ boundary will consider also such conditions as demography, topography, land characteristics , access routes, and jurisdictional boundaries. No known impedi-ments have been identified which would significantly affect effective evacuation of the assumed EPZ.
- 5. Does the Edgewood School present an impedinent to evacuation, if so describe.
Response: No, the Edgewood School does not present an impediment to evacuation. The PSAR Section 13.3A, par. C(4)d, is modified to identify the means of evacuating the general population, schools and other institutions.
Miscellaneous Items
- 1. The PSAR Section 13.3A is als ' revised to correct an error to the evacuation time estimates for the 5 mile and 10 mile EPZ.
- 2. The reference attached provides a copy of a letter from Eugene P. Tanner, Director, Tennessee Emergency Managenent Agency, to Mr. H. J. Green, TVA, re: Responsibility for Emergency Response Plans. This letter i is a new reference to PSAR Section 13.3.3.
l
Attachment 4
The director of each center is responsible for directing his staff in carrying out their respective responsibilities. He is delegated the authority during i energencies to locate, direct, and dispatch the personnel and equipment
% necessary to carry out his staff's responsibilities. -
The purpose of the CECC and associated CECC staff is to provide the facilities and. manpower for evaluating, coordinating, and directing the overall activities involved in coping with a radiological emergency.
During an emergency, the CECC Director and his staff will review the response to the emergency by TVA and the appropriate State agencies to ensure that an effective and cooperative effort is being made. The CECC Director, after consultation with the Office of Health and Safety CECC representative, is responsible for providing TVA's recommended protective actions to 'the appropriate State officials.
f The CECC staff will coordinate with all other TVA emergency centers to ensure an effective TVA effort in resMnse to an accident situation. The CECC staff will also provide an accurate description of the emergency situation for TVA management and public information. In addition, the CECC will coordinate with i
offsite Federal sgencies, such as the Nuclear Regulatory Commission JRC) and Department of Energy (DOE), to ensure availability of additional outside resources to TVA.
l l The DNPEC staff provides support services during a radiological emergency to l the affected plant. Support services may be provided by utilizing any necessary manpowec and equipment under the direct control of the Division of g Nuclear Power. If the division is unable to provide adequate services or
,_. support, requests will be made for additional support to other TVA divisions, local agencies, or government installations as may be required.
The Muscle Shoals Emergency Control Center (HSECC) supports the CECC by performing environmental radiological monitoring and dose assessments and by recommending protective actions for the public to the CECC. In performing I these functions, the MSECC assists the Tennessee Department of Public Health
~in evaluating the population exposures resulting from radiological emerMriciliiil The HSECC staff directs offsite environmental monitoring for the l Tennessee Department of Public Health and continues monitoring activities until a State Field Coordination Center is established to coordinate the offsite environmental monitoring effort. The MSECC will continue to evaluate l ' the need for monitoring assistance to the Tennessee Department of Public Health. The State may request assistance from the appropriate DOE Operations Office in accordance with Interagency Radiological Assistance Plan (IRAP) for additional support. The MSECC will monitor the radiation protection problems in the plant during emergencies to provide guidance, manpower, and equipment to the Plant Health Physicist as required to control and mitigate these problems.
f The Knoxville Emergency Control Center (KECC) serves as the focal point for all essential support activities involving TVA Knoxville offices. The TVA i Office of Engineering Design and Construction (OEDC), Division of Engineering l Design (EN DES), has been delegated overall responsibility for the KECC and
( for providing technical support during and following a radiological emergency.
~. Q _ L m ize, $J dCG.- N GL .~-u ed L .A-u - com A
, , w Jo$o e ~ q -m 13 3-4 Amend. 70 l
August 1982
,._.-..,.--. . . . _ . . , ... ---- - - - ~ - - - - - - -
QQ G w feocoL h J M E f/ (u- ~NI'A N A [M S*cm~~ ,
n D.) 5.,y, .n.;f 6~:ZL y C E CC , M S E=c < , e-.J WL'- d M'~
E CH3 05- ~
'- This section addresses the EN DES responsibilities for technical support during emergency conditions.
The KECC also serves as the .comunication center for other essential '1VA offices such as the '1VA Board of Directors, the General Manager, the Nuclear Safety Review Staff, and the Information Office.
4 4
Se radiological emergency cormonications network will consist of a cont >ination of comercial telephone circuits, radio, and microwave circuits.
South Central Bell Telephone Company lines will be used as the primary means of comunications during radiological emergency situations between plant, ;
CECC, DNPEC, MSECC, KEOC, and appropriate Federal and State agencies. His system will be augmented by the '1VA Private Automatic Exchange (PAX). Hard copy data transmission will be accomplished by Panafax frm the CRBRP to the DNPEC, the CEoc, and the MSEC. % e hard copy transmission is then follo?.'ed up and verified by redundant telephone comunications. '1VA will provide the necessary interfaces to the CRBRP Safety Paraneter Display System (SPDS) for transmission of SEDS data to '1VA emergency centers, as appropriate.
The primary means of notification of plant and offsite personnel is the comercial telephone circuits. Additionally, pocket pagers are provided to certain key individuals in the emergency organization.
Figure 13.3-1 illustrates the relationship between the '1VA emergency centers and depicts the interface among '1VA, Federal, State, and local agencies.
_ 13.3.3 coor41natim-With-Offalta-Grouns
'1VA will have agreements with other Federal agencies to assist in the evaluation and control of any radiological emergency. %ese agreements will include such agencies as the Department of Energy (DOE), Oak Ridge Operations Office, and the National Aeronautics and Space Adninistration (NASA), Marshall Space Flight Center. S e CECC staff may request assistance from these outside agencies as required. Se Site Emergency Director will be responsible for notification of NRC's regional office of Inspection and Enforcement.
[ Agreements will be made with the State of Tennessee, Tennessee Dnergency Management Agency, to provide planning for emergencies at 'IVA nuclear facilities. This planning includes evacuation arrangements, traffic control, p A and support fran other state agencies as required. % e Clinch River Breeder p J Reactor Plant Radiological Dnergency Plan will utilize the liaisons already I g established in developing the Browns Ferry, Sequoyah, Watts Bar, and Bellefonte Radiological Plans with the States of Alabama and Tennessee. Se f Tennessee Bnergency Management Agency will notify the State of North Carolina and surrounding states and coordinate assistance from the various state agencies.
'1VA will maintain liaison with the Tennessee Dnergency Management Agency, particularly with respect to the availability of emergency services. We Tennessee Dnergency Management Agency will inform these agencies of ac' c ions to be taken under their respective statutory authority and assist them in Amend. 76 13.3-5, March 1983
W '
[2-76]
-2.::1.c::: ::T -
j( PSAR Section 13.3.3, paragraph 2 (lNS6KT Agreement has been made with the State of Tennessee, Tennessee Emergency Management Agency (TEMA), to provide for planning and conduct of emergency operations for emergencies at CRBRP (Reference 1). TEMA is responsible for coordination of the efforts of all state agencies and local governments in the developmentofresponseplan[sthathaveanimpactbeyondthe /
capability of a single agency or local government to control.
The actual agreements and arrangements involved with such state agency and local government will be specifically defined in the' ~
State of Tennessee CRBRP Radiological Emergency Response Plan ,
which will be provided in the CRBRP FSAR. The TVA CRBRP Radiological Emergency Plan will utili g he liaisons already established in developing the Sequoyahf Wa(tsBar med Radiological Emergency Plans with the State of Tennessee, r.f 1.1_': _ _. TEMA will notify the 8 tate of North Carolina, Department of Crime Control and Safety j and coordinete assistance from the various b %
-sta-te agencies.
$$m do a &
O_
\
- l g h ctyn, ,1 G < a , H .) . , n 'A , j] d ; b,/9 P 1-l l
g _- _ .. . -- - . - - - ~ .
\
C. Est w ted Reaction and Response Tiana f
L
- 1. The time required for the initial accident assessment of the most serious design basis accident may require 15 minutes. This time is an estimate based on the operation of the reactor instrumentation used to follow the course of accidents. Based on TVA's experience, the time required to perform an initial dose projection. and notify offsite authorities can be accomplished in 15 minutes.
For the most serious dasign basis accident, the projected two-hour doses at the exclusion area boundary do not reach the protective action guide level for evacuation.
- 2. The time required to warn all resident and transient persons in any evacuation sector will conform to the requirements of 10 CFR
- SG, Appendix E-1982.
- 3. The estimated elapsed time, af ter the initial warning, to evacuate the 2-mile emergency planning zone (EPZ) is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The g(A%
estimated evacuation time for the 5-mile EPZ is (5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, 2_Q7 minutos.
g/
[
I The estimated h_ou Mr ainutes. evacuation Each estimate time contains of the a 1-hour 50-minute10-a11e EPZ is @
W , , preparation time factor.
- 4. These evacuation time estimates were prepared by the Traffic Management Division of the Tennessee Department of Transportation.
h a. Figures 13 3A-5 and 13 3A-6 are maps showing all roads within 10 miles of the Clinch River Project. Also indicated are the l
2 , 5 , and 10-mile EPZ.
- b. Table 13 3A-1 shows the transient and resioent populations in the 16 directional sectors within 10 miles of the Clinch River
! Project. This table uses 1980 census data.
- c. Table 13 3A-2 shows the estimated transient and resident populations in the 16 directional sectors within 10 miles of the Clinch River Project. This table uses the p'rojected population figures for year 2020. The projected population figures come from a report prepared by the Fire of Dames and Moore dated June 16, 1981. gjg sc s [p
- d. Private automobiles will he primary means for evacuating the population. Buses pay) be used to evacuate it: "f; r::1 Sehool. 3hecypuMeagill be specifically addressed in the CRBRP-REP. g ;s p m., A ,. e
! 5. Table 13 3-1 gives the agencies involved in the CRBRP emergency plan.
13 3A-3 Amend. 70 August 1982
s m pT.i: W , '
"..y..
,a. 2 a<
s..
,. m.
- ..~.q,.... 1..
. . n:a ~. .. .
... v v. .,~.,.t.;..~.....,..
q .e-
- v P :Pr gFS Reference f "..
Y. ~
cr s u Own,. ,a.r.B 2.*E". uta r e
..,. -. . .. wac M!UTARY DEPAFITMENT OF TENNESSEE '
TENNESSES EMERGENCY 24ANAGEMENT AGENCY t. ( r.1. Oc-n .
EMERGENCY CFERATYWS CENTER .
i 3o4i s#oco DefvE ',
"_ l'f"* f pf Maswviu.a sizes ..._Lt.
PMOME Ntal 7414101
'*: [ .._8. _4 _ . '
. i. t 6 July 1982 ts' " T "i - - '
NC VC i . i jY .li Nn., @ h.
Mr. H. J. Green i L00 8o.04 0 g ;<,'
Tennessee Va!!ey Authority , , , ,j .,, , y , ~'~
Division of .% clear Power \y IMO Chestnut Street, Tower 11
.f Chattarmy,a, Ternessee 37401 . f ,)i e, r '.
Dear Mr. Greens o
The Tennessee Emergency .'.tanagement Agency (TEMA) is charged by the Tennes:ee Code Annotated with numerous dut!es including the preparation, coordinatien and updating of emergency respense plans. TEMA is also responsible for the conduct of emergency operaticas by all participating agencies to sustain M life and prevent, minimize or remedy Injury to persons and damage to preparty from disasters caused by nature of man developed technology.
TEM A is responsible fx the coordination of the ef forts of all State -
agencies and local government in the development of resoonse plans that hsve an O 1:r. pact beyond the capabilities ut a smgle agency or local government to r octrol, i.e. p;ans sucn as tne Tennes ee Mutt - oriwnct nal Response Plan for TV A's .
Sequoyah % clear Facility. ,
The preparation of a respunw phn for the Clinch River DreWr Reacter would detmitely be in the c.ategory of those things that TEMA is charged to do. ._.
T.".'.!A s the !?ad Mate agen..y .11 coordinate the State agency planning. %r. e an c.:.cI&nt at this ~ -Wr f acility would invol.c rncre than o** laral government and be beyond their capability to respond tu and centre!. TEM A would also cccrdinate tne local planning and response. -
Sincerely, .
/
.l, ,
ffff0 ' ,
[ tate Director
. EPT/EU/m l
s W. = --' e ? '.-
l '.
? Y,; R N. & . T,v. .37.vy, msyn-rre :~e. . -.. r~ ~. ~ --- ~ ~ .-
@f..l.*'f.
s .(' '*h .3* Ne ..h , . G"W :.
.. - m.v. . ~ : . .. .
a . .- ,-
h6. .' ?
' >- -[ d1' J.M ',k " .
4' ' 9 9 J/.:.f [ ; M q;@ %,, '
'?'.N .w. 5,;::':+ m y. .) {(.[.C..h
$G. ,Q. i[
.gm:.C'[h:q(a's 'kT }
.t.[t, ..
7.,;
%= pe 3.g- .e. .
3..,.;3 .
m.2::n% c ; m. ;e J.hy.g&.MC7
% ,. d .! * . - %f., w m . w . A m ;y'W*D y 1 V .y *,' =a.
fpgleg".,m. 1 ~... m.. .u .
..