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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 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 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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Department of Energy Washington, D.C. 20585 May 7,1982 m
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Docket No. 50-537 HQ:S:82:026 9 'D Mr. Paul S. Check, Director 97
- N $ ks '-
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G1 CRBRP Program Office 'O g //
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission Cu y
/
Washington, D.C. 20555
Dear Mr. Check:
RESPONSES TO REQUEST FOR ADDITIONAL INFORtMTION - EQUIPMENT QUALIFICATION
Reference:
Letter, P. S. Check to J. R. Longenecker, "CRBRP Request for Additional Information," dated March 9,1982 This letter formally responds to your request for additional information contained in the referenced letter.
Enclosed are responses to questions CS 270.1, CS 270.2, and CS 270.4 through CS 270.9 in the area of equipment qualification. These responses will also be incorporated into the PSAR in Amendment 69, scheduled for May 21.
Sinc ely A) h John R. Longenecker, Manager Licensing & Environmental Coordination Office of Nuclear Energy Enclosure cc: Service List pooIy Standard Distribution Licensing Distribution
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8205120354 020507 DR ADOCK 05000537 PDR
Page-1(82-0254)[8,22] - #28 Question _OCS 270.1 (3.11)
% e NRC staff position of environmental qualification of electrical equipent is discussed in NUREG-0588. Discuss your compliance with these requirements.
If you intend to use WARD-D-0165, "CRBRP Requirements for Environmental Qualification of Class lE Quipent", identify any differences between IEEE 323,1974 and the NUREG-0588 Category I requirements and discuss how the CRBR design complies with the NUREG-0588, Category I requirements.
Response .
W e CRBRP program for environmental qualification of safety-related electrical equipent, WARD-D-0165, is consistent with the objectives and requirements delineated in NUREG-0588, Rev.1 " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Quiprent", except as noted below.
Differences in CRBRP reactor technology and plant configurations exist and, as a result, some specific IMR requirements delineated in NUREG-0588 are not applied to CRBRP. These differences are: the use of liquid metal sodium for the reactor coolant; a low pressure coolant system with no mechanism for a highly pressurized containment; the absence of steam, containment spray, and the mechanism for water flooding within the containment; environmental separation of the upper containment from the lower containment; and placment of redundant heat transport loops in separate cells resulting in independent loop environmental conditions (environments in one loop do not propagate to the cells of another loop) .
Paragraph 2.4 of the NUREG-0588, Category 1 requirements, discuss "Other Qualification Methods". In this regard, CRBRP requirements permit type testing, analysis, prior operating experience and/or a combination of these techniques for equipnent qualification. An evaluation of the adequacy of the proposed method would be done before using analysis or operating experience in lieu of testing. Also an evaluation would be done to determine the necessary extent of any partial type tests required to be provided in support of these methods.
In addition to the design differences stated above, CRBRP does not apply two NRC staff positions stated in NUREG-0588. %e first exception deals with the radiation source term used for qualifying Class 1E equipnent located within the containment. NURIn-0588 specifies the worst radiation environment as an instantaneous release from the fuel to the atmosphere of 100 percent of the nobic gases, 50 percent of the iodines, and 1 percent of the remaining fission products. CRBRP uses the normally expected radiation environment over the equignent qualified life plus that associated with the most severe design basis accident during or following which the equipnent must renain functional.
ne worst case radiation IBA is the In-Containment Primary Sodium Storage Tank failure during maintenance. The second exception concerns the application of time margin to safety-related equipnent which performs its safety function QCS270.1-1 Amend. 68 May 1982
Rage-2(82-0254) [8,22] - #28 within a short time period into the event (i.e., less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />).- In NURm-0588 a minimum qualification time margin of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is specified. CRBRP requires that equiptent be qualified for the environment in which it must perform its safety function for the time duration specified for the safety response plus time margin per IEEE 323-1974. Failure of any equipnent af ter its qualification time (whether longer or shorter than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) will not result in unsafe plant conditions.
i QCS270.1-2 Amend. 68 May 1982 I rsteso _ _ _
Page-3 (82-0254) [8,22] - #28 Question CS 270.2 (3.11.1)
Confirm that Section 3.2 contains all safety-related systens (including display instrumentation which is required by the plant emergency procedures) requiring environmental qualification.
Response
section 3.2 of the PSAR contains a generic list of all CRBRP safety-related electrical equipnent. This list does not differentiate between the various instrumentation and control devices, e.g. , Tenperature Sensors (RTD's or - -
thermocouples), Tenperature controllers, Tunperature Indicators (display),
etc. A comprehensive list of CRBRP Class IE equignent, including display instrumentation, is provided in Tables 3-1 and 3-2 of WARD-ir0165, "CRBRP Requirements for Environmental Qualification of Class lE RIuignent," (Ref.13, PSAR Section 1.6).
QCS270.2-1 i
hrend. 68
! 82-0254 __
Page-5 (82-0254) [8,22] - #28 Question OCS 270.4 (3.111 Discuss how you intend to account for the uncertainties caused by the production errors and errors associated with defining satisfactory performance when only a small number of units are tested. This margin should be in addition to the margin applied during the derivation of the specified plant parameters and margin applied to account for the instrument error during testing.
ResDonse CRBRP conservatively calculates the most severe specified service conditions that include accident environments that result from a review of all design basis events. The events that produce the most severe environmental transient are used. Often this would require multiple design basis accidents occurring to generate the most severe environmental conditions (temperature, pressure, radiation, humidity, etc.) . These conservatisms assure rargins between the service conditions specified and the actual conditions which could realistically be expected in a design basis event. Quantifiable margin is then applied to the conservatively calculated most severe service condition design parameters as per IEEE 323, Section 6.3.1.5.
In defining the type testing, the margin applied to the test profile envelops the specified design condition profile. In addition to applying margin to the environmental parameters, margin is added to the test duration. Further margin is applied in type testing by adding a margin transient (Section 4.2.2, step #7 of WARD-I)-0165 "CRBRP Requirements for Environmental Qualification of Class IE B]uipnent") .
'Ihrough application of these margins, CRBRP accounts for uncertainties associated with reasonable error in defining satisfactory perforrance when a smil number of units is tested, normal variations in the commercial production of equipnent, and accuracies of data resulting from type test measurements.
When conducting a type test for an item being qualified, an acceptance test is performed to assure that production problans do not exist. Also the equipnent specification requirements assure that the delivered plant equipnent design and manufacture is verified by inspection, testing (such as factory tests, burn-in tests, system tests, etc.), design control measures, and quality assurance methods.
QCS270.4-1 Amend. 68 May 1982 82-0254 _
Page-6(82-0254) [8,22] - #28 Question OCS 270.5 (3.lH Since equipment may be exposed to a sodium aerosol environment and this condition is unique to CRBRP, describe in detail how you plan to qualify the equipent for the sodium aerosol environment. Provide the results of the testing performed to date. How do you assure the operability of diesel generators in the sodium aerosol environment?
ResDonse CRBRP requires that Class lE equipnent which is rquired to perform its sa'fety' function during or after exposure to a sodium aerosol environment, must be qualified for the sodium aerosol environment. 'Ivo specific aerosol environments are identified. Sodium aerosol environments within cells where sodium aerosols originate or within cells that directly ingest significant quantities of sodium aerosols are specified " severe sodium aerosol environments". Extremely low sodium aerosol environments in air filled cells, other than those in which the aerosols originate, are classified as a "non-severe sodium aerosol environment". RIuipnent in the low sodium aerosol environment is located in general plant areas outside containment. This equipnent does not experience any significant changes in its service conditions due to a design basis event which has occurred in another plant location.
Class lE equipnent required to function within non-severe or severe sodium aerosol environments is required to be qualified by rsing either analysis, type testing, prior operating experience, or a combination of the previous qualification methods. The qualification procedure must comply with IEEE 323-1974 and IEEE 344-1975 as endorsed by FG 1.89 and RG 1.100 respectively, with application of pertinent NURIE 0588 guidance as discussed in Response CS 270.1.
For equignent required to function within severe sodium aerosol environments; the equignent is aged to its end of life condition, subjected to the seismic / vibration condition, and then exposed to the worst case Design Basis Event transients (temperature, pressure, radiation, humidity, sodium aerosols). The equipneat being type tested is rquired to be either identical to the plant hardware or all differences existing must be identified and justification provided that the differences do not affect the qualification results. Prior to subjecting equipnent to this type test, equipnent specification acceptance testing must be completed. The type tests shall be performed in the numerical order to meet the requirements of IEEE 323-1974, paragraph 6.3.2 as well as the requirements specified in WARD-D-0165, Section 4.2.2.
Where equipnent is required to function within non-severe sodium aerosol environments; the equipnent will be placed in its end of life state where required, subjected to off normal temperature, humidity and sodium aerosol environments, and then exposed to the seismic / vibration environment. 'Ibe CRBRP aging program for equipnent located in non-severe environments permits equipnent and catponents to be excluded from the stimulated aging requirment QCS270.5-1 Amend. 68 May 1982 asuman
Page-7(82-0254) [8,22] - #28 based on documented demonstration of no significant degradation of pertinent properties during its projected installed service life provided scheduled maintenance, surveillance and inspection is properly performed.
% e qualification test sequences depicted above are the most severe test sequences. Equip ent located in severe environments is exposed to the most severe Design Basis Event transients last, since exposing the test its to the most severe environment after exposure to the lesser environmental parameters results in the most severe test. For Equipent located in non-severe environments, the most severe condition that can challenge operation of the equignent is the seismic event; therefore, the seismic parameters are inse'rted' last. It should be pointed out that the abnormal temperature condition and the low sodium aerosol environment represent design requirements for which the equiprnent can be designed to prevent failures. Even though equignent located in non-severe environments will be designed to operate for the off normal temperature and aerosol environments, CRBRP requires that the equignent be qualified for these environments per Section 4.1 of WARD-D-0165.
At present, no qualification testing has been completed for equipoent located in non-severe or severe sodium aerosol environments.
Each of three Class IE Diesel Generators and the auxiliary equipnent for each diesel generator are located in a separate diesel generator room which will not be exposed to sodium aerosols. Each room is served by 100% recirculating cooling system and therefore the ingestion of sodium aerosol into the diesel room is excluded.
ne combustion air to the diesel engines will be filtered by high efficiency (HEPA) filters with a filtration efficiency higher than the 99.97%. It is expected that the trace amounts of aerosol passing through the HEPA filters will not affect the operation of the diesel engines, i
QCS270.5-2 Amend. 68 May 1982 r%r6am .
Page-8(82-0254)[8,22] - #28 Question OCS 270.6 (3.111 WARD-D-0165, Section 4.2.2, its 9, discusses failures during testing. In case of the failure during the test, if a redesign or replacment has been pursued as a solution, the complete assembly must be tested again to assure qualification. Discuss your ccanitment to this rquirement.
Response
WARD-D-0165 endorses IEEE 323-1974, Section 6.8, which contains specific instructions regarding modification to equipnent which fails during testing. -
Modifications involving a redesign or a replacment to the quipnent or to the equipnent specification should not be made after the start of the type test.
CRBRP requires a test failure evaluation on a case by case basis to determine whether or not a rqualification in whole or in part is required.
Modifications, with additional confirmation testing, are pursued as a solution to a test failure only if full justification is provided to document that the change has no bearing on the validity of the test.
OCS270.6-1 Amend. 68 May 1982 fir-(03B -
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'l Ouestion_OCS 270.7-(3.111 WARD-D-0165, Section 4.2.2, page 5, third paragraph: revise IEEE 383-1972 to IEEE 382-1972.
Response
%e typographical error has been corrected and forwarded to the NRC as part of t
Rev. 6 to WARD-D-0165.
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i QCS270.7-1 Amend. 68 May 1982 L _ .QB-0350 _
Page-10(82-0254) [8,22] - #28 Question OCS 270.8 (3.111 WARD-D-0165, Page 4.11, Figure 4.3 and the Table on page 4-13 discuss the aging method similar to the 10 C rule. It is the NRC staff position that the 10 C rule is not an acceptable aging method unless justified by providing the verification based on Arrhenius methodology. Discuss how you comply with this requirement.
Response
he CRBRP equipnent qualification program is designed to conform to IEEE -
323-1974 as clarified by the forward issued by Nuclear Power Engineering Committee (NPEC) on July 24, 1975, as IEEE 325A-1975. This statement includes to " utilize known technology in any aging program".
CRBRP recognizes the limitations of aging techniques and the existence and development of various aging theories. CRBRP evaluates the aging methods to be utilized by the equignent vendor. It is not acceptable for the 10 C rule to be applied without documented assurance that this technique fulfills the objectives of aging. Further CRBRP anticipates that due to the empirical nature of the 10 C rule, use of the Arrhenius model may be the most suitable method. This will be evaluated on a case by case basis. The CRBRP aging program establishes in WARD-D-0165, Section 4.2.2.1 guidance to ensure that equipnent suppliers are raluired to address the aging objectives of the qualification program.
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QCS270.8-1 Amend. 68 May 1982
___83-@250 ,
Page-ll(82-0254) [8,22] - #28 Ouestion OCS 270.9 (3.111 WNu>-D-0165, Section 2.2 defines the mild (non-severe) environment. The definition used by the staff for the mild environment is defined as "an environment that would at no time be more severe then the environment that would occur during normal plant operation or during anticipated operational occurrences". Discuss your compliance with the staff's definition for the mild environment.
ResDonse -
We CRBRP non-severe environment does include the same environmental parameters that are included in the NRC definition of a mild environment.
This applies to the parameters that occur on both IER's and CRBRP, such as temperature, humidity and seismic. The values for those parameters that are included in mild (IER) and non-severe (CRBRP) environments are those that result from normal plant operation, anticipated operational occurrences, or safe shutdown and operating base earthquakes. For the CRBRP design, an additional parameter, sodium aerosols, may be present. Due to the design of CRBRP, specifically the environmentally separated cells into which the plant is divided, the aerosols that may be present as a result of an accident are classified as (1) those that are present in the cell in which the accident occurs, or (2) those that may be present in other cells as a result of a slmrt ingestion period prior to isolation being completed. The aerosols present in the cell in which an accident occurs are classified as severe environmental parameters. The aerosols present in cells other than the accident cell are classified as non-severe since Class IE equipnent located in these areas are not expected to experience an environment any more severe than the environment resulting during normal plant operation or during anticipated operational occurrences.
n e aerosols associated with the non-severg environment are specified for CRBRP as a concentration in air of 15 mg/m3 and a deposited surface concentration of 0.1 g/m 2, he environmental parameters associated with a non-severe environment can be accarmodated by the equipnent design. These non-severe environmental parameters are addressed in the equipnent design specifications. CRBRP further requires that the equipaent be qualified to these parameters. A specific discussion of the qualification procedures appears in Section 4.2.1 of WARI)-IF0165, Rev. 6.
OCS270.9-1 Amend. 68 May 1982
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