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Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARML20106J8711985-02-15015 February 1985 Notification Concerning Site redress.Near-term Planning for Site Redress Predicated Upon Commencing Redress by May 1985. Certificate of Svc Encl ML20107M9411984-11-0808 November 1984 Response to Motion to Dismiss Proceeding Re Revocation of Lwa.Authorization of Revocation of LWA & That Proceedings Be Dismissed W/O Prejudice Recommended.Certificate of Svc Encl ML20106J7951984-10-30030 October 1984 Response to Applicant 841019 Motion to Dismiss Proceeding. Motion Acceptable Subj to Conditions Set Forth in Redress Plan & NRC .Certificate of Svc Encl ML20093M2611984-10-19019 October 1984 Motion to Dismiss Proceeding.Applicable Conditions of Existing Federal Water Permit & State Water Quality Requirements Will Remain in Effect.Supporting Documentation & Certificate of Svc Encl ML20098F7391984-09-28028 September 1984 Notice of Change of Address & Telephone Number.Certificate of Svc Encl ML20098F9571984-09-28028 September 1984 Notice of Change of Address & Telephone Number.Certificate of Svc Encl.Related Correspondence ML20097G9671984-09-19019 September 1984 Notice of Change of Address & Telephone Number.Certificate of Svc Encl.Related Correspondence ML20087F4701984-03-15015 March 1984 Answer to Applicant Petition for Review of ASLB 840229 Memorandum & Order Re Crbr LWA Proceedings on Site Redress Plan.Intervenors Main Concern Is That Redress Be Rapid & Effective.W/Certificate of Svc ML20086T0141984-03-0505 March 1984 Petition for Review of Appeal Board 840229 Memorandum & Order Readmitting Intervenors to Proceedings.Intervenor Participation Will Protract Proceeding for Project Which Is Terminated.Certificate of Svc Encl ML20080N0471984-02-21021 February 1984 Answer Opposing NRDC & Sierra Club Appeals to ASLB Decisions.Certificate of Svc Encl ML20080C6021984-02-0606 February 1984 Brief in Support of Appeal of ASLB 840120 Order Re NRDC Motion to Intervene ML20080C6121984-02-0606 February 1984 Notice of Appeal of ASLB 840120 Notice Denying NRDC Motion to Intervene ML20080C6411984-02-0606 February 1984 Brief of Intervenors in Support of Appeal of ASLB 840120 Order.Certificate of Svc Encl ML20083J4351984-01-0909 January 1984 Response to NRDC Reply Per ASLB 831228 Order.Contentions Raised in NRDC Motion to Intervene Moot.Motion Should Be Denied.Certificate of Svc Encl ML20083E4231983-12-27027 December 1983 Notice of Project Termination.Certificate of Svc Encl ML20082S4471983-12-12012 December 1983 Request to Reply to Util 831205 & NRC 831208 Responses to NRDC Motion to Intervene ML20082S4541983-12-12012 December 1983 Reply to Util 831205 & NRC 831208 Responses to NRDC Motion to Intervene.Appropriate ASLB Course of Action Is Termination of Proceedings on Grounds of Mootness. Certificate of Svc Encl ML20082Q6841983-12-0909 December 1983 Amended Notice of Appearance in Proceeding.Certificate of Svc Encl ML20082M5271983-12-0505 December 1983 Response Supporting Intervenor 831123 Motion to Terminate Appeal Proceedings,Vacate Partial Initial Decision & Authorize Revocation of Lwa.Certificate of Svc Encl ML20082M5401983-12-0505 December 1983 Response Opposing NRDC 831123 Motion to Intervene.Proceeding Moot Due to Project Cancellation.Cp Partial Initial Decision Should Be Issued.Certificate of Svc Encl ML20082E1261983-11-23023 November 1983 Petition of NRDC for Leave to Intervene & Request for Hearing Re Effect of Crbr Termination on CP Proceedings. Contentions Listed ML20081D7931983-10-31031 October 1983 Confirmation of Info Re Legislative Status Discussed W/Aslb in 831028 Telcon.Certificate of Svc Encl ML20081A5041983-10-25025 October 1983 Supplemental Citations Supporting Thesis That Following Hydrodynamic Core Disruptive Accident,Reactor Vessel Closure Head Is More Susceptible to Failure than Reactor Vessel Head.Certificate of Svc Encl ML20078B9771983-09-26026 September 1983 Response Opposing NRC 830913 Motion for Leave to File Supplemental Affidavit of Lg Hulman.Affiant Revised Testimony Incorrect,Misleading & Irrelevant.Certificate of Svc Encl ML20024F3471983-09-0707 September 1983 Order Rejecting NRC 830902 Proposed Opinion,Findings of Fact & Conclusions of Law in CP Proceeding & Lg Hulman Supplemental Affidavit.Nrc Failed to Follow Correct Form for Proposed Findings.Motion Necessary to Admit Affidavit ML20024F1921983-09-0606 September 1983 Supplemental Affidavit of Lg Hulman Correcting Pages 8,505- 8,509 to Transcript of 830810 Testimony ML20024F2561983-09-0202 September 1983 Reply to Applicant Proposed Opinion,Findings of Fact & Conclusions of Law Recommending Issuance of Cp.Unexecuted Supplemental Affidavit Clarifying & Revising Portions of Hearing Transcript & Certificate of Svc Encl ML20024F1891983-09-0101 September 1983 Motion to Correct 830808-11 Transcript.Certificate of Svc Encl ML20076C9811983-08-22022 August 1983 Motion to Correct Transcript of Aug 1983 CP Evidentiary Hearings.Certificate of Svc Encl ML20076A7871983-08-17017 August 1983 Motion to Reschedule 830929 Oral Argument to 830928. Certificate of Svc Encl ML20077J5051983-08-15015 August 1983 Proposed Initial Decision,Findings of Fact & Conclusions of Law Re Cp.Certificate of Svc Encl ML20024E5021983-08-0909 August 1983 Transcript of 830809 Hearing in Oak Ridge,Tn.Pp 7,934-8,480. Supporting Documentation Encl ML20024D2231983-08-0202 August 1983 Stipulation Re Authenticity of NRC & Applicant Exhibits. Requests ASLB Approval.Certificate of Svc Encl ML20077B6661983-07-22022 July 1983 Response Opposing Intervenor 830518 Exceptions to ASLB 830228 Partial Initial Decision on Lwa.Aslab Should Affirm ASLB Decision.Site Suitability Arguments Incongruous. Certificate of Svc Encl ML20024C7501983-07-11011 July 1983 Pages 53 & 54 to Testimony of Tl King & ET Rumble Re Adequacy of DBA Spectrum ML20024C0621983-07-0808 July 1983 Testimony of Tl King Re ASLB Question 13 on Fuel Sys Fallback Positions.Lists Possible Impacts on Crbr Programmatic Objectives from Implementing NRC Positions. Prof Qualifications Encl ML20024C3641983-07-0808 July 1983 Limited Appearance Statement of TB Cochran Re Issues Raised in CP Proceeding.Discusses Radiological Consequences of Crbr Core Disruptive Accident & Site Suitability.Certificate of Svc Encl ML20024C0431983-07-0808 July 1983 Testimony of Rj Dube Re ASLB Question 10 on Matl Control & Accountability.R&D Activities on Measurement Capabilities for Matl Control & Accounting Unnecessary for Continued Fuel Safeguards.Prof Qualifications Encl ML20024C0381983-07-0808 July 1983 Testimony of Lg Hulman,Ef Branagan & Dj Perrotti on ASLB Question 9 Re Protective Action Guides.No Rev to Protective Action Guides Necessary for Crbr.If Guides Revised,Nrc Will Consider Applicability at OL Stage.Prof Qualifications Encl ML20024B6671983-07-0808 July 1983 Testimony of Vd Hedges,Jw Anderson & Je Karr Responding to ASLB Areas of Interest 5 & 6.Owners Mgt Organization Described.Westinghouse,Ge,Atomics Intl,S&W & Burns & Roe Are Project Contractors.Certificate of Svc Encl ML20024B6661983-07-0808 July 1983 Testimony of Hw Hibbitts,Ek Sliger & Le Strawbridge Re ASLB Areas of Interest Related to Emergency Planning.Crbr Radioactive Releases Could Contain Sodium Oxides & Hydroxide Aerosols.Prof Qualifications & Certificate of Svc Encl ML20024C0501983-07-0808 July 1983 Testimony of Tl King & RM Stark Re ASLB Question 12 on Items Identified for Resolution at OL Stage.Nrc & Applicants Developing Program & Schedule to Review & Resolve Items,To Minimize Impacts on Final Design & Const ML20024C0241983-07-0808 July 1983 Testimony of Cl Allen,Lw Bell,Hb Holz,Lg Hulman,Jk Long, B Morris,Jj Swift,Cr Bell,Ta Butler,Et Rumble,D Swanson & Tg Theofanous Re Analyses of Core Disruptive Accidents.Prof Qualifications Encl ML20024C0761983-07-0808 July 1983 Testimony of Tl King on ASLB Question 14 Re Operation W/ Leaking Fuel Pins.Sodium Entry Into Fuel Pin May Cause Increased pellet-to-clad Gap Conductance,But Would Not Adversely Affect Fuel Performance.Prof Qualifications Encl ML20024C0221983-07-0808 July 1983 Testimony of RA Becker,Hc Garg,S Hou,Tl King,B Morris,Ce Rossi,R Schemel,Jj Swift,Ak Agrawal,Je Hanson & ET Rumble Re Adequacy of DBA Spectrum.Core Disruptive Accidents May Be Excluded from DBA Spectrum for Crbr.W/Prof Qualifications ML20024B6641983-07-0505 July 1983 Testimony of Lw Deitrich,H Fauske,L Strawbridge & Tw Ball Re Hypothetical Core Disruptive Accident (Hcda) Analyses.Crbr Designed So Hcdas Beyond Dba.Prof Qualifications & Certificate of Svc Encl ML20024A9021983-06-29029 June 1983 Transcript of 830629 Conference in Bethesda,Md.Pp 7,298- 7,354 ML20072F2651983-06-22022 June 1983 Response to Intervenor 830621 Motion to Withdraw Contentions 1,3,9(c),9(f) & 9(g) from Consideration at Jul 1983 CP Hearings.Intervenors Should Be Dismissed as Parties. Certificate of Svc Encl ML20079R2491983-06-21021 June 1983 Motion to Withdraw Contentions 1,3,9(c),9(g) from Consideration at Jul 1983 CP Hearings & Request for Leave to Submit Written Statement on Issues Raised.Limited Resources Prohibit Continued Full Participation ML20079R2631983-06-21021 June 1983 Response Opposing Applicant 830519 & 23 Motions for Summary Disposition of Contentions 9(g),9(c) & 9(f).Motions Moot Since Intervenors Moved to Withdraw Contentions from Consideration 1985-02-15
[Table view] Category:TRANSCRIPTS
MONTHYEARML20024E5021983-08-0909 August 1983 Transcript of 830809 Hearing in Oak Ridge,Tn.Pp 7,934-8,480. Supporting Documentation Encl ML20024C7501983-07-11011 July 1983 Pages 53 & 54 to Testimony of Tl King & ET Rumble Re Adequacy of DBA Spectrum ML20024C3641983-07-0808 July 1983 Limited Appearance Statement of TB Cochran Re Issues Raised in CP Proceeding.Discusses Radiological Consequences of Crbr Core Disruptive Accident & Site Suitability.Certificate of Svc Encl ML20024C0761983-07-0808 July 1983 Testimony of Tl King on ASLB Question 14 Re Operation W/ Leaking Fuel Pins.Sodium Entry Into Fuel Pin May Cause Increased pellet-to-clad Gap Conductance,But Would Not Adversely Affect Fuel Performance.Prof Qualifications Encl ML20024C0241983-07-0808 July 1983 Testimony of Cl Allen,Lw Bell,Hb Holz,Lg Hulman,Jk Long, B Morris,Jj Swift,Cr Bell,Ta Butler,Et Rumble,D Swanson & Tg Theofanous Re Analyses of Core Disruptive Accidents.Prof Qualifications Encl ML20024C0501983-07-0808 July 1983 Testimony of Tl King & RM Stark Re ASLB Question 12 on Items Identified for Resolution at OL Stage.Nrc & Applicants Developing Program & Schedule to Review & Resolve Items,To Minimize Impacts on Final Design & Const ML20024C0221983-07-0808 July 1983 Testimony of RA Becker,Hc Garg,S Hou,Tl King,B Morris,Ce Rossi,R Schemel,Jj Swift,Ak Agrawal,Je Hanson & ET Rumble Re Adequacy of DBA Spectrum.Core Disruptive Accidents May Be Excluded from DBA Spectrum for Crbr.W/Prof Qualifications ML20024B6671983-07-0808 July 1983 Testimony of Vd Hedges,Jw Anderson & Je Karr Responding to ASLB Areas of Interest 5 & 6.Owners Mgt Organization Described.Westinghouse,Ge,Atomics Intl,S&W & Burns & Roe Are Project Contractors.Certificate of Svc Encl ML20024C0381983-07-0808 July 1983 Testimony of Lg Hulman,Ef Branagan & Dj Perrotti on ASLB Question 9 Re Protective Action Guides.No Rev to Protective Action Guides Necessary for Crbr.If Guides Revised,Nrc Will Consider Applicability at OL Stage.Prof Qualifications Encl ML20024C0431983-07-0808 July 1983 Testimony of Rj Dube Re ASLB Question 10 on Matl Control & Accountability.R&D Activities on Measurement Capabilities for Matl Control & Accounting Unnecessary for Continued Fuel Safeguards.Prof Qualifications Encl ML20024C0621983-07-0808 July 1983 Testimony of Tl King Re ASLB Question 13 on Fuel Sys Fallback Positions.Lists Possible Impacts on Crbr Programmatic Objectives from Implementing NRC Positions. Prof Qualifications Encl ML20024B6661983-07-0808 July 1983 Testimony of Hw Hibbitts,Ek Sliger & Le Strawbridge Re ASLB Areas of Interest Related to Emergency Planning.Crbr Radioactive Releases Could Contain Sodium Oxides & Hydroxide Aerosols.Prof Qualifications & Certificate of Svc Encl ML20024B6641983-07-0505 July 1983 Testimony of Lw Deitrich,H Fauske,L Strawbridge & Tw Ball Re Hypothetical Core Disruptive Accident (Hcda) Analyses.Crbr Designed So Hcdas Beyond Dba.Prof Qualifications & Certificate of Svc Encl ML20024A9021983-06-29029 June 1983 Transcript of 830629 Conference in Bethesda,Md.Pp 7,298- 7,354 ML20023C3851983-05-13013 May 1983 Transcript of 830513 Conference in Bethesda,Md.Pp 7,106- 7,279 ML20028F8961983-02-0303 February 1983 Transcript of ACRS Subcommittee on Crbr & Thermal Hydraulics Working Group 830203 Joint Meeting in Washington,Dc Re Plant Thermal Hydraulic Design Issues & Emergency Power Sys. Pp 1-343.Supporting Documentation Encl ML20083N8191983-02-0202 February 1983 Applicant Corrections to 821116-19 Transcripts,Inadvertently Omitted from 830124 List of Transcript Corrections. Certificate of Svc Encl ML20070M6581983-01-24024 January 1983 Proposed Transcript Corrections.Certificate of Svc Encl ML20028C1611983-01-0505 January 1983 Transcript of 830105 Hearing in Bethesda,Md.Pp 6,913-7,105 ML20028B5381982-12-0101 December 1982 Transcript of ACRS Working Group on Structures & Matls for Crbr 821201 Meeting in Bethesda,Md.Pp 1-214.Supporting Documentation Encl ML20069L0331982-11-12012 November 1982 Suppl to TB Cochran Part V Testimony on Contentions 1,2 & 3, Based on Final Suppl to Fes ML20069L0371982-11-12012 November 1982 Testimony of TB Cochran,Part Iv,As Supplemented by New Info in Final Suppl to Fes,Re Contentions 1,2 & 3 on Potential for Severe Accidents at Crbr & Adequacy of NRC & Util Analyses of Accidents ML20069L0451982-11-12012 November 1982 Testimony of TB Cochran,Part Iii,As Supplemented by New Info in Fes Final Suppl,Re Contentions 6(b)(1) & (3) on Adequacy of NRC Analysis of Environ Impacts of Crbr Fuel Cycle. Certificate of Svc Encl ML20066E2831982-11-10010 November 1982 Errata to 821101 Testimony.Certificate of Svc Encl ML20027E2301982-11-0404 November 1982 Unofficial Transcript of 821104 Public Affirmation/ Discussion & Vote in Washington,Dc Re SECY-82-410 on Petition for Delineation of LWA Proceedings for Crbr & SECY-82-440 Re Summer Ol.Pp 1-4 ML20028A7351982-11-0101 November 1982 Testimony of TB Cochran,Part V,Re Contentions 4 & 6(b)(4) on Analysis of Acts of Sabotage,Terrorism or Theft.Nrc & Applicants Substantially Understated Risks to Plant & Overstated Effectiveness of Proposed Safeguards ML20071P0981982-11-0101 November 1982 Testimony of Lj Kripps Re NRDC & Sierra Club Contentions 5a & 7c on Applicant Alternative Siting Analyses.Clinch River Site Is Preferred Site for LMFBR Demonstration Plant. Related Correspondence ML20071P1151982-11-0101 November 1982 Testimony of GL Sherwood,Dc Newton,Wm Hartman & Oo Yarbro Re NRDC Contentions 6.b.1 & 6.b.3 on Adequacy of NRC Analyses of Environ Impacts of Crbr Fuel Cycle.Eis Estimates Conservative.Related Correspondence ML20065T9861982-11-0101 November 1982 Testimony of TB Cochran Re Contentions 1,2 & 3 on Adequacy of NRC & Applicant Analyses of Potential for Severe Accidents.Methodology in Fes App J Crude by Current Stds & App Assumptions Not Supported by Analysis ML20065T9831982-11-0101 November 1982 Testimony of TB Cochran Re Contentions 6(b)(1) & (3) on Adequacy of NRC Analysis of Environ Impacts of Crbr Fuel Cycle.Nrc Analysis Inadequate Due to Failure to Address Uncertainties Associated W/Nrc Estimates ML20071P2571982-11-0101 November 1982 Testimony of J Longenecker,Ca Anderson & Nn Kaushal Re NRDC Contentions 7a & 7b on Inadequate Analyses of Crbr Alternatives.No Alternatives Substantially Better than Crbr. Certificate of Svc Encl.Related Correspondence ML20071P2481982-11-0101 November 1982 Testimony of Ef Penico & Ga Hammond Re NRDC Contentions 4 & 6.b.4 on Safeguards.Safeguards Adequately Analyzed & Safeguards Sys Developed.Related Correspondence ML20071P1731982-11-0101 November 1982 Testimony of Gh Clare,Le Strawbridge & Lw Deitrich Re NRDC Contentions 2d,2f,2g,2h,3c,3d & 5b on Environ Effects of Crbr Accident Analyses.Related Correspondence ML20071P1431982-11-0101 November 1982 Testimony of AA Weinstein,Rk Disney & Jf Murdock Re NRDC Contention 8 on Costs & Effects of Decommissioning Crbr. Plant Can Be Decommissioned by Prompt Total Dismantlement. Related Correspondence ML20071P1261982-11-0101 November 1982 Testimony of J Preston,Ro Mcclellan,Jw Healy & Rc Thompson Re NRDC Contentions 11b & 11c on Genetic & Cancerous Effects of Plant on Employees.Calculated Somatic Effects for Plant Small.Related Correspondence ML20071P1111982-11-0101 November 1982 Testimony of Hw Hibbitts Re NRDC Contention 5(b) Re Alternative Sites.Risk from Crbr to DOE Facilities in Site Vicinity Low.Related Correspondence ML20065T9881982-10-28028 October 1982 Testimony of Cj Johnson Re NRC Analysis of Environ (Health) Impacts of Crbr & Fuel Cycle.Nrc & Applicant Estimates of Environ Releases & Environ Contamination from Proposed Fuel Cycle Unrealistic.Certificate of Svc Encl ML20027C9821982-10-26026 October 1982 Transcript of ACRS Crbr Thermal Hydraulic Working Group 821026 Meeting in Washington,Dc.Pp 1-278.Supporting Documentation Encl ML20065U0321982-10-13013 October 1982 Transcript of E Branagan 821013 Deposition in Bethesda,Md Re Dose Estimates of Hiroshima & Nagasaki & Health Impacts. Certificate of Svc Encl.Related Correspondence ML20062L0691982-08-16016 August 1982 Testimony of Kz Morgan on Contentions 1 & 2.Requirements of 10CFR100 Not Met.Crbr Site Not Suitable for LMFBR ML20062L0511982-08-16016 August 1982 Testimony of TB Cochran on Contentions 1a,3b & 3d Re Core Disruptive Accidents & DBAs & Contentions 2 & 3c Re Site Suitability Analysis Under 10CFR100 ML20062K3091982-08-16016 August 1982 Testimony of RO Mcclellan,Jw Healy & Rc Thompson on Behalf of Joint Applicants Re NRDC Contention 2e on Calculation of Guideline Value for Radiation Doses from Postulated Release. Prof Qulifications & Certificate of Svc of Encl ML20062K2861982-08-16016 August 1982 Testimony of Nw Brown,Gh Deitrich,Vs Oblock & Le Strawbridge on Behalf of Joint Applicants Re NRDC Contentions 1,2 & 3 on Adequacy of Accident Analyses.Prof Qualifications & Certificate of Svc Encl ML20062L1111982-08-12012 August 1982 Testimony of Jc Cobb on Contention 2 Re Proposed Stds & Guidelines for Pu & Other Alpha Emitting Radionuclides. Toxicity of Pu Underestimated.Certificate of Svc Encl ML20062L0911982-08-11011 August 1982 Testimony of F Von Hippel on Contentions 1 & 2 Re Core Disruptive Accident Probabilities at Crbr ML20062A4891982-08-0202 August 1982 Transcript of 820802 Conference in Bethesda,Md.Pp 685-875 ML20071K9001982-07-29029 July 1982 Oral Comments of Mm Todorovich on 820729 in Washington,Dc Supporting DOE Exemption Request ML20062H2781982-07-29029 July 1982 Transcript of 820729 Oral Presentation on Crbr. Pp.1-213 ML20062B5101982-07-21021 July 1982 Transcript of 820721 Public Meeting in Washington,Dc Re Affirmation of Crbr Order.Pp 1-3 ML20054M7171982-07-0909 July 1982 Transcript of 820709 Public Meeting Re Briefing on Crbr Schedule in Washington,Dc.Pp 1-19 1983-08-09
[Table view] Category:DEPOSITIONS
MONTHYEARML20024E5021983-08-0909 August 1983 Transcript of 830809 Hearing in Oak Ridge,Tn.Pp 7,934-8,480. Supporting Documentation Encl ML20024C7501983-07-11011 July 1983 Pages 53 & 54 to Testimony of Tl King & ET Rumble Re Adequacy of DBA Spectrum ML20024C3641983-07-0808 July 1983 Limited Appearance Statement of TB Cochran Re Issues Raised in CP Proceeding.Discusses Radiological Consequences of Crbr Core Disruptive Accident & Site Suitability.Certificate of Svc Encl ML20024C0761983-07-0808 July 1983 Testimony of Tl King on ASLB Question 14 Re Operation W/ Leaking Fuel Pins.Sodium Entry Into Fuel Pin May Cause Increased pellet-to-clad Gap Conductance,But Would Not Adversely Affect Fuel Performance.Prof Qualifications Encl ML20024C0241983-07-0808 July 1983 Testimony of Cl Allen,Lw Bell,Hb Holz,Lg Hulman,Jk Long, B Morris,Jj Swift,Cr Bell,Ta Butler,Et Rumble,D Swanson & Tg Theofanous Re Analyses of Core Disruptive Accidents.Prof Qualifications Encl ML20024C0501983-07-0808 July 1983 Testimony of Tl King & RM Stark Re ASLB Question 12 on Items Identified for Resolution at OL Stage.Nrc & Applicants Developing Program & Schedule to Review & Resolve Items,To Minimize Impacts on Final Design & Const ML20024C0221983-07-0808 July 1983 Testimony of RA Becker,Hc Garg,S Hou,Tl King,B Morris,Ce Rossi,R Schemel,Jj Swift,Ak Agrawal,Je Hanson & ET Rumble Re Adequacy of DBA Spectrum.Core Disruptive Accidents May Be Excluded from DBA Spectrum for Crbr.W/Prof Qualifications ML20024B6671983-07-0808 July 1983 Testimony of Vd Hedges,Jw Anderson & Je Karr Responding to ASLB Areas of Interest 5 & 6.Owners Mgt Organization Described.Westinghouse,Ge,Atomics Intl,S&W & Burns & Roe Are Project Contractors.Certificate of Svc Encl ML20024C0381983-07-0808 July 1983 Testimony of Lg Hulman,Ef Branagan & Dj Perrotti on ASLB Question 9 Re Protective Action Guides.No Rev to Protective Action Guides Necessary for Crbr.If Guides Revised,Nrc Will Consider Applicability at OL Stage.Prof Qualifications Encl ML20024C0431983-07-0808 July 1983 Testimony of Rj Dube Re ASLB Question 10 on Matl Control & Accountability.R&D Activities on Measurement Capabilities for Matl Control & Accounting Unnecessary for Continued Fuel Safeguards.Prof Qualifications Encl ML20024C0621983-07-0808 July 1983 Testimony of Tl King Re ASLB Question 13 on Fuel Sys Fallback Positions.Lists Possible Impacts on Crbr Programmatic Objectives from Implementing NRC Positions. Prof Qualifications Encl ML20024B6661983-07-0808 July 1983 Testimony of Hw Hibbitts,Ek Sliger & Le Strawbridge Re ASLB Areas of Interest Related to Emergency Planning.Crbr Radioactive Releases Could Contain Sodium Oxides & Hydroxide Aerosols.Prof Qualifications & Certificate of Svc Encl ML20024B6641983-07-0505 July 1983 Testimony of Lw Deitrich,H Fauske,L Strawbridge & Tw Ball Re Hypothetical Core Disruptive Accident (Hcda) Analyses.Crbr Designed So Hcdas Beyond Dba.Prof Qualifications & Certificate of Svc Encl ML20024A9021983-06-29029 June 1983 Transcript of 830629 Conference in Bethesda,Md.Pp 7,298- 7,354 ML20023C3851983-05-13013 May 1983 Transcript of 830513 Conference in Bethesda,Md.Pp 7,106- 7,279 ML20028F8961983-02-0303 February 1983 Transcript of ACRS Subcommittee on Crbr & Thermal Hydraulics Working Group 830203 Joint Meeting in Washington,Dc Re Plant Thermal Hydraulic Design Issues & Emergency Power Sys. Pp 1-343.Supporting Documentation Encl ML20083N8191983-02-0202 February 1983 Applicant Corrections to 821116-19 Transcripts,Inadvertently Omitted from 830124 List of Transcript Corrections. Certificate of Svc Encl ML20070M6581983-01-24024 January 1983 Proposed Transcript Corrections.Certificate of Svc Encl ML20028C1611983-01-0505 January 1983 Transcript of 830105 Hearing in Bethesda,Md.Pp 6,913-7,105 ML20028B5381982-12-0101 December 1982 Transcript of ACRS Working Group on Structures & Matls for Crbr 821201 Meeting in Bethesda,Md.Pp 1-214.Supporting Documentation Encl ML20069L0331982-11-12012 November 1982 Suppl to TB Cochran Part V Testimony on Contentions 1,2 & 3, Based on Final Suppl to Fes ML20069L0371982-11-12012 November 1982 Testimony of TB Cochran,Part Iv,As Supplemented by New Info in Final Suppl to Fes,Re Contentions 1,2 & 3 on Potential for Severe Accidents at Crbr & Adequacy of NRC & Util Analyses of Accidents ML20069L0451982-11-12012 November 1982 Testimony of TB Cochran,Part Iii,As Supplemented by New Info in Fes Final Suppl,Re Contentions 6(b)(1) & (3) on Adequacy of NRC Analysis of Environ Impacts of Crbr Fuel Cycle. Certificate of Svc Encl ML20066E2831982-11-10010 November 1982 Errata to 821101 Testimony.Certificate of Svc Encl ML20027E2301982-11-0404 November 1982 Unofficial Transcript of 821104 Public Affirmation/ Discussion & Vote in Washington,Dc Re SECY-82-410 on Petition for Delineation of LWA Proceedings for Crbr & SECY-82-440 Re Summer Ol.Pp 1-4 ML20028A7351982-11-0101 November 1982 Testimony of TB Cochran,Part V,Re Contentions 4 & 6(b)(4) on Analysis of Acts of Sabotage,Terrorism or Theft.Nrc & Applicants Substantially Understated Risks to Plant & Overstated Effectiveness of Proposed Safeguards ML20071P0981982-11-0101 November 1982 Testimony of Lj Kripps Re NRDC & Sierra Club Contentions 5a & 7c on Applicant Alternative Siting Analyses.Clinch River Site Is Preferred Site for LMFBR Demonstration Plant. Related Correspondence ML20071P1151982-11-0101 November 1982 Testimony of GL Sherwood,Dc Newton,Wm Hartman & Oo Yarbro Re NRDC Contentions 6.b.1 & 6.b.3 on Adequacy of NRC Analyses of Environ Impacts of Crbr Fuel Cycle.Eis Estimates Conservative.Related Correspondence ML20065T9861982-11-0101 November 1982 Testimony of TB Cochran Re Contentions 1,2 & 3 on Adequacy of NRC & Applicant Analyses of Potential for Severe Accidents.Methodology in Fes App J Crude by Current Stds & App Assumptions Not Supported by Analysis ML20065T9831982-11-0101 November 1982 Testimony of TB Cochran Re Contentions 6(b)(1) & (3) on Adequacy of NRC Analysis of Environ Impacts of Crbr Fuel Cycle.Nrc Analysis Inadequate Due to Failure to Address Uncertainties Associated W/Nrc Estimates ML20071P2571982-11-0101 November 1982 Testimony of J Longenecker,Ca Anderson & Nn Kaushal Re NRDC Contentions 7a & 7b on Inadequate Analyses of Crbr Alternatives.No Alternatives Substantially Better than Crbr. Certificate of Svc Encl.Related Correspondence ML20071P2481982-11-0101 November 1982 Testimony of Ef Penico & Ga Hammond Re NRDC Contentions 4 & 6.b.4 on Safeguards.Safeguards Adequately Analyzed & Safeguards Sys Developed.Related Correspondence ML20071P1731982-11-0101 November 1982 Testimony of Gh Clare,Le Strawbridge & Lw Deitrich Re NRDC Contentions 2d,2f,2g,2h,3c,3d & 5b on Environ Effects of Crbr Accident Analyses.Related Correspondence ML20071P1431982-11-0101 November 1982 Testimony of AA Weinstein,Rk Disney & Jf Murdock Re NRDC Contention 8 on Costs & Effects of Decommissioning Crbr. Plant Can Be Decommissioned by Prompt Total Dismantlement. Related Correspondence ML20071P1261982-11-0101 November 1982 Testimony of J Preston,Ro Mcclellan,Jw Healy & Rc Thompson Re NRDC Contentions 11b & 11c on Genetic & Cancerous Effects of Plant on Employees.Calculated Somatic Effects for Plant Small.Related Correspondence ML20071P1111982-11-0101 November 1982 Testimony of Hw Hibbitts Re NRDC Contention 5(b) Re Alternative Sites.Risk from Crbr to DOE Facilities in Site Vicinity Low.Related Correspondence ML20065T9881982-10-28028 October 1982 Testimony of Cj Johnson Re NRC Analysis of Environ (Health) Impacts of Crbr & Fuel Cycle.Nrc & Applicant Estimates of Environ Releases & Environ Contamination from Proposed Fuel Cycle Unrealistic.Certificate of Svc Encl ML20027C9821982-10-26026 October 1982 Transcript of ACRS Crbr Thermal Hydraulic Working Group 821026 Meeting in Washington,Dc.Pp 1-278.Supporting Documentation Encl ML20065U0321982-10-13013 October 1982 Transcript of E Branagan 821013 Deposition in Bethesda,Md Re Dose Estimates of Hiroshima & Nagasaki & Health Impacts. Certificate of Svc Encl.Related Correspondence ML20062L0691982-08-16016 August 1982 Testimony of Kz Morgan on Contentions 1 & 2.Requirements of 10CFR100 Not Met.Crbr Site Not Suitable for LMFBR ML20062L0511982-08-16016 August 1982 Testimony of TB Cochran on Contentions 1a,3b & 3d Re Core Disruptive Accidents & DBAs & Contentions 2 & 3c Re Site Suitability Analysis Under 10CFR100 ML20062K3091982-08-16016 August 1982 Testimony of RO Mcclellan,Jw Healy & Rc Thompson on Behalf of Joint Applicants Re NRDC Contention 2e on Calculation of Guideline Value for Radiation Doses from Postulated Release. Prof Qulifications & Certificate of Svc of Encl ML20062K2861982-08-16016 August 1982 Testimony of Nw Brown,Gh Deitrich,Vs Oblock & Le Strawbridge on Behalf of Joint Applicants Re NRDC Contentions 1,2 & 3 on Adequacy of Accident Analyses.Prof Qualifications & Certificate of Svc Encl ML20062L1111982-08-12012 August 1982 Testimony of Jc Cobb on Contention 2 Re Proposed Stds & Guidelines for Pu & Other Alpha Emitting Radionuclides. Toxicity of Pu Underestimated.Certificate of Svc Encl ML20062L0911982-08-11011 August 1982 Testimony of F Von Hippel on Contentions 1 & 2 Re Core Disruptive Accident Probabilities at Crbr ML20062A4891982-08-0202 August 1982 Transcript of 820802 Conference in Bethesda,Md.Pp 685-875 ML20071K9001982-07-29029 July 1982 Oral Comments of Mm Todorovich on 820729 in Washington,Dc Supporting DOE Exemption Request ML20062H2781982-07-29029 July 1982 Transcript of 820729 Oral Presentation on Crbr. Pp.1-213 ML20062B5101982-07-21021 July 1982 Transcript of 820721 Public Meeting in Washington,Dc Re Affirmation of Crbr Order.Pp 1-3 ML20054M7171982-07-0909 July 1982 Transcript of 820709 Public Meeting Re Briefing on Crbr Schedule in Washington,Dc.Pp 1-19 1983-08-09
[Table view] Category:NARRATIVE TESTIMONY
MONTHYEARML20024E5021983-08-0909 August 1983 Transcript of 830809 Hearing in Oak Ridge,Tn.Pp 7,934-8,480. Supporting Documentation Encl ML20024C7501983-07-11011 July 1983 Pages 53 & 54 to Testimony of Tl King & ET Rumble Re Adequacy of DBA Spectrum ML20024C3641983-07-0808 July 1983 Limited Appearance Statement of TB Cochran Re Issues Raised in CP Proceeding.Discusses Radiological Consequences of Crbr Core Disruptive Accident & Site Suitability.Certificate of Svc Encl ML20024C0761983-07-0808 July 1983 Testimony of Tl King on ASLB Question 14 Re Operation W/ Leaking Fuel Pins.Sodium Entry Into Fuel Pin May Cause Increased pellet-to-clad Gap Conductance,But Would Not Adversely Affect Fuel Performance.Prof Qualifications Encl ML20024C0241983-07-0808 July 1983 Testimony of Cl Allen,Lw Bell,Hb Holz,Lg Hulman,Jk Long, B Morris,Jj Swift,Cr Bell,Ta Butler,Et Rumble,D Swanson & Tg Theofanous Re Analyses of Core Disruptive Accidents.Prof Qualifications Encl ML20024C0501983-07-0808 July 1983 Testimony of Tl King & RM Stark Re ASLB Question 12 on Items Identified for Resolution at OL Stage.Nrc & Applicants Developing Program & Schedule to Review & Resolve Items,To Minimize Impacts on Final Design & Const ML20024C0221983-07-0808 July 1983 Testimony of RA Becker,Hc Garg,S Hou,Tl King,B Morris,Ce Rossi,R Schemel,Jj Swift,Ak Agrawal,Je Hanson & ET Rumble Re Adequacy of DBA Spectrum.Core Disruptive Accidents May Be Excluded from DBA Spectrum for Crbr.W/Prof Qualifications ML20024B6671983-07-0808 July 1983 Testimony of Vd Hedges,Jw Anderson & Je Karr Responding to ASLB Areas of Interest 5 & 6.Owners Mgt Organization Described.Westinghouse,Ge,Atomics Intl,S&W & Burns & Roe Are Project Contractors.Certificate of Svc Encl ML20024C0381983-07-0808 July 1983 Testimony of Lg Hulman,Ef Branagan & Dj Perrotti on ASLB Question 9 Re Protective Action Guides.No Rev to Protective Action Guides Necessary for Crbr.If Guides Revised,Nrc Will Consider Applicability at OL Stage.Prof Qualifications Encl ML20024C0431983-07-0808 July 1983 Testimony of Rj Dube Re ASLB Question 10 on Matl Control & Accountability.R&D Activities on Measurement Capabilities for Matl Control & Accounting Unnecessary for Continued Fuel Safeguards.Prof Qualifications Encl ML20024C0621983-07-0808 July 1983 Testimony of Tl King Re ASLB Question 13 on Fuel Sys Fallback Positions.Lists Possible Impacts on Crbr Programmatic Objectives from Implementing NRC Positions. Prof Qualifications Encl ML20024B6661983-07-0808 July 1983 Testimony of Hw Hibbitts,Ek Sliger & Le Strawbridge Re ASLB Areas of Interest Related to Emergency Planning.Crbr Radioactive Releases Could Contain Sodium Oxides & Hydroxide Aerosols.Prof Qualifications & Certificate of Svc Encl ML20024B6641983-07-0505 July 1983 Testimony of Lw Deitrich,H Fauske,L Strawbridge & Tw Ball Re Hypothetical Core Disruptive Accident (Hcda) Analyses.Crbr Designed So Hcdas Beyond Dba.Prof Qualifications & Certificate of Svc Encl ML20024A9021983-06-29029 June 1983 Transcript of 830629 Conference in Bethesda,Md.Pp 7,298- 7,354 ML20023C3851983-05-13013 May 1983 Transcript of 830513 Conference in Bethesda,Md.Pp 7,106- 7,279 ML20028F8961983-02-0303 February 1983 Transcript of ACRS Subcommittee on Crbr & Thermal Hydraulics Working Group 830203 Joint Meeting in Washington,Dc Re Plant Thermal Hydraulic Design Issues & Emergency Power Sys. Pp 1-343.Supporting Documentation Encl ML20083N8191983-02-0202 February 1983 Applicant Corrections to 821116-19 Transcripts,Inadvertently Omitted from 830124 List of Transcript Corrections. Certificate of Svc Encl ML20070M6581983-01-24024 January 1983 Proposed Transcript Corrections.Certificate of Svc Encl ML20028C1611983-01-0505 January 1983 Transcript of 830105 Hearing in Bethesda,Md.Pp 6,913-7,105 ML20028B5381982-12-0101 December 1982 Transcript of ACRS Working Group on Structures & Matls for Crbr 821201 Meeting in Bethesda,Md.Pp 1-214.Supporting Documentation Encl ML20069L0331982-11-12012 November 1982 Suppl to TB Cochran Part V Testimony on Contentions 1,2 & 3, Based on Final Suppl to Fes ML20069L0371982-11-12012 November 1982 Testimony of TB Cochran,Part Iv,As Supplemented by New Info in Final Suppl to Fes,Re Contentions 1,2 & 3 on Potential for Severe Accidents at Crbr & Adequacy of NRC & Util Analyses of Accidents ML20069L0451982-11-12012 November 1982 Testimony of TB Cochran,Part Iii,As Supplemented by New Info in Fes Final Suppl,Re Contentions 6(b)(1) & (3) on Adequacy of NRC Analysis of Environ Impacts of Crbr Fuel Cycle. Certificate of Svc Encl ML20066E2831982-11-10010 November 1982 Errata to 821101 Testimony.Certificate of Svc Encl ML20027E2301982-11-0404 November 1982 Unofficial Transcript of 821104 Public Affirmation/ Discussion & Vote in Washington,Dc Re SECY-82-410 on Petition for Delineation of LWA Proceedings for Crbr & SECY-82-440 Re Summer Ol.Pp 1-4 ML20028A7351982-11-0101 November 1982 Testimony of TB Cochran,Part V,Re Contentions 4 & 6(b)(4) on Analysis of Acts of Sabotage,Terrorism or Theft.Nrc & Applicants Substantially Understated Risks to Plant & Overstated Effectiveness of Proposed Safeguards ML20071P0981982-11-0101 November 1982 Testimony of Lj Kripps Re NRDC & Sierra Club Contentions 5a & 7c on Applicant Alternative Siting Analyses.Clinch River Site Is Preferred Site for LMFBR Demonstration Plant. Related Correspondence ML20071P1151982-11-0101 November 1982 Testimony of GL Sherwood,Dc Newton,Wm Hartman & Oo Yarbro Re NRDC Contentions 6.b.1 & 6.b.3 on Adequacy of NRC Analyses of Environ Impacts of Crbr Fuel Cycle.Eis Estimates Conservative.Related Correspondence ML20065T9861982-11-0101 November 1982 Testimony of TB Cochran Re Contentions 1,2 & 3 on Adequacy of NRC & Applicant Analyses of Potential for Severe Accidents.Methodology in Fes App J Crude by Current Stds & App Assumptions Not Supported by Analysis ML20065T9831982-11-0101 November 1982 Testimony of TB Cochran Re Contentions 6(b)(1) & (3) on Adequacy of NRC Analysis of Environ Impacts of Crbr Fuel Cycle.Nrc Analysis Inadequate Due to Failure to Address Uncertainties Associated W/Nrc Estimates ML20071P2571982-11-0101 November 1982 Testimony of J Longenecker,Ca Anderson & Nn Kaushal Re NRDC Contentions 7a & 7b on Inadequate Analyses of Crbr Alternatives.No Alternatives Substantially Better than Crbr. Certificate of Svc Encl.Related Correspondence ML20071P2481982-11-0101 November 1982 Testimony of Ef Penico & Ga Hammond Re NRDC Contentions 4 & 6.b.4 on Safeguards.Safeguards Adequately Analyzed & Safeguards Sys Developed.Related Correspondence ML20071P1731982-11-0101 November 1982 Testimony of Gh Clare,Le Strawbridge & Lw Deitrich Re NRDC Contentions 2d,2f,2g,2h,3c,3d & 5b on Environ Effects of Crbr Accident Analyses.Related Correspondence ML20071P1431982-11-0101 November 1982 Testimony of AA Weinstein,Rk Disney & Jf Murdock Re NRDC Contention 8 on Costs & Effects of Decommissioning Crbr. Plant Can Be Decommissioned by Prompt Total Dismantlement. Related Correspondence ML20071P1261982-11-0101 November 1982 Testimony of J Preston,Ro Mcclellan,Jw Healy & Rc Thompson Re NRDC Contentions 11b & 11c on Genetic & Cancerous Effects of Plant on Employees.Calculated Somatic Effects for Plant Small.Related Correspondence ML20071P1111982-11-0101 November 1982 Testimony of Hw Hibbitts Re NRDC Contention 5(b) Re Alternative Sites.Risk from Crbr to DOE Facilities in Site Vicinity Low.Related Correspondence ML20065T9881982-10-28028 October 1982 Testimony of Cj Johnson Re NRC Analysis of Environ (Health) Impacts of Crbr & Fuel Cycle.Nrc & Applicant Estimates of Environ Releases & Environ Contamination from Proposed Fuel Cycle Unrealistic.Certificate of Svc Encl ML20027C9821982-10-26026 October 1982 Transcript of ACRS Crbr Thermal Hydraulic Working Group 821026 Meeting in Washington,Dc.Pp 1-278.Supporting Documentation Encl ML20065U0321982-10-13013 October 1982 Transcript of E Branagan 821013 Deposition in Bethesda,Md Re Dose Estimates of Hiroshima & Nagasaki & Health Impacts. Certificate of Svc Encl.Related Correspondence ML20062L0691982-08-16016 August 1982 Testimony of Kz Morgan on Contentions 1 & 2.Requirements of 10CFR100 Not Met.Crbr Site Not Suitable for LMFBR ML20062L0511982-08-16016 August 1982 Testimony of TB Cochran on Contentions 1a,3b & 3d Re Core Disruptive Accidents & DBAs & Contentions 2 & 3c Re Site Suitability Analysis Under 10CFR100 ML20062K3091982-08-16016 August 1982 Testimony of RO Mcclellan,Jw Healy & Rc Thompson on Behalf of Joint Applicants Re NRDC Contention 2e on Calculation of Guideline Value for Radiation Doses from Postulated Release. Prof Qulifications & Certificate of Svc of Encl ML20062K2861982-08-16016 August 1982 Testimony of Nw Brown,Gh Deitrich,Vs Oblock & Le Strawbridge on Behalf of Joint Applicants Re NRDC Contentions 1,2 & 3 on Adequacy of Accident Analyses.Prof Qualifications & Certificate of Svc Encl ML20062L1111982-08-12012 August 1982 Testimony of Jc Cobb on Contention 2 Re Proposed Stds & Guidelines for Pu & Other Alpha Emitting Radionuclides. Toxicity of Pu Underestimated.Certificate of Svc Encl ML20062L0911982-08-11011 August 1982 Testimony of F Von Hippel on Contentions 1 & 2 Re Core Disruptive Accident Probabilities at Crbr ML20062A4891982-08-0202 August 1982 Transcript of 820802 Conference in Bethesda,Md.Pp 685-875 ML20071K9001982-07-29029 July 1982 Oral Comments of Mm Todorovich on 820729 in Washington,Dc Supporting DOE Exemption Request ML20062H2781982-07-29029 July 1982 Transcript of 820729 Oral Presentation on Crbr. Pp.1-213 ML20062B5101982-07-21021 July 1982 Transcript of 820721 Public Meeting in Washington,Dc Re Affirmation of Crbr Order.Pp 1-3 ML20054M7171982-07-0909 July 1982 Transcript of 820709 Public Meeting Re Briefing on Crbr Schedule in Washington,Dc.Pp 1-19 1983-08-09
[Table view] |
Text
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1 UNITED STATES OF AMERICA N
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2 NUCLEAR BEGULATORY COMMISSION
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---x 4 In The Matter of 5 UNITED STATES DEP ARTMENT OF ENERGY a
PROJECT MANAGEMENT CORPORATION
- Docket No. 50-537 6 TENNESSEE VALLEY AUTHORITY a
(Clinch River Breeder Reactor Plant) 7 a
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Bethesda, Maryland 9
Wednesday, October 13, 1982 10 Deposition of EDWARD BRANAGAN, called for 11 e xamina tion by counsel for Intervenors in the 12 above-entitled sction, pursuant. to notice, at the
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13 Nuclear Regulatory Commission Air Rights Building, 4550 14 Hon tgom e ry Avenue, Bethesda, Maryla'nd, commencing at 15 3:20 p.m.,
the witnesses being sworn by Bay Heer, a 16 notary public in ind for the State of Maryland, and the 17 p ro ceedings being taken down by Stenomask by Ray Heer 18 and transcribed under his direction, when were present 19 on behalf of the respective parties:
20 21 22
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8211030357 821029 PDR ADOCK 05000537 G
PDR ALDERSON REPCRTING COMPANY, INC,
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1 APPEABANCES:
2 On behalf of Intervenors, Natural Resources
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Defense Council and the Sierra Club 3
BABBARA A. FINA50HE, Esq.
4 THOMAS B. COCHRAN FLOYD SMITH 5
Natural Resources Defense Council, Inc.
1725 I Street, N.W.,
Suite 600 6
Eashington, D.C.
20006 7
On behalf of the Department of Energy:
8 STAN ECHOLS, Esq.
Office of the General Couansel 9
Department of Energy Washington, D.C.
20585 10 On behalf of the Nuclear Regulatory Commission:
11 DANIEL SWANSON, Esq.
12 GEORGE HIZUNO,.Esq.
Office of the Executive Legal Director
(
13 U. S.
Nuclear Regulatory Co mmissio n Washington, D.C.
14 On behalf of Project Management Corporation 15 TH05AS A.
SCHEUTZ, Esq.
16 Morgan, Lewis E Bockius 1800 M Street, N.W.
17 Washington, D.C.
20036 18 19 20 21 22 ALDERSON REPORTING COMPANY,INC,
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3
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1 C0N TENTS 2'
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EIAMINATION BY
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3 COUNSEL FOR INTERVENORS, DEPOSITION OFs NBDC AND SIERRA CLUB 4
EDWARD BRANAGAN 4
5 6
7 8
9 10 11 12
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13 14 15 16 17 18 19 20 21 22
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ALDERSON REPORTING COMPANY, INC, 400 VIAGINIA AVE., S.W., WASHINGTON, D.C. 20024 (2C2) 554 2345
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i z E 2.s I I n I E E E 2 Whereupon, 3
EDWARD BRANAGAN, 4 called as s witness by counsel for the Intervenors and S having been first duly sworn by the Notary Public, was 6 examined and testified as follows 7
EIAMINATION BY COUNSEL FOR INTERVENORS, 8
NATURAL RESOURCES DEFENSE FUND 9
AND THE SIERRA CLUB 10 BY HR. COCHRAN.
11 0
Dr. Branagan, refresh my memory of where the 12 genetic risks are documented in this.
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13 A
It is in section 5.7, and the discussion on 14 potential health impacts, pa rt of it, is on page 5-13, 15 5-14, 5-15, and then we pick it up agsin over on page.
16 5-19 through 21.
17 Q
And I recall reading section 5725, you relied 18 on the risk coefficients in the BEIR 1 report for l
19 occupational exposures, is that righ t?
20 A
That is correct.
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21 0
And your conclusion is that the BEIR 3 report' t
22 gives comparable values.
Is that the basis?
Why didn't t
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A Well, if you usa the values in the BEIR 3 3 report which the majority of the BEIR 3 committee would 4 recommend you use, you would get numbers a little less 5 than what you actually get in the BEIR 1 report.
6 O
When you say the majority, you are talking 7 about the overall committee or the somatic risk 8 committee?
9 A
No, the National Academy of Sciences BEIR 3 10 committee.
They had presented several models in there 11 for estimating poten tial health impacts, an d the 12 majority of their members picked a certain model that
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13 would give you lower impacts than the values in the BEIR 14 1 report.
15 Q
And how about the somatic risk panel?
How did 16 their values compare to the BEIR 1 values -- the somatic 17 risk panel of BEIR 37 18 A
That is what I was speaking to -- the somatic 19 risk.
20 Q
Just to refresh your memory, the somatic risk 21 panel was Radford's panel that wrote the minority report 22 to the full committee report.
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1 A
Well, the majority of the members of the BEIR 2 3 committee recommended the lidium quadratic models,
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3 which resulted in lower estimates for the somatic risk 4 than the BEIR 1 report.
5 0
And the majority of the members of the somatic 6 risk committee, of which Radford chaired, recommended
- 7. higher risk coefficients; isn't that correct?
8 A
I can 't substantiate that.
My reading of the 9 BEIB 3 report is that the majority of the members 10 recommended the use of the linear quadratic model for 11 low LET radiation and not the linear dose response 12 model.
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13 Q
A nd, in your opinion, is that the basis for 14 their argument being called into question by the recent 15 reevaluations of the Nagasaki ABCC data?
16 A
The basis for which argument?
17 Q
Chosing the linear quadratic, the quadratic 18 model in BEIH 3, the majority opinion.
19 A
I wouldn't characterize it the way you 20 characterized it.
21 Q
How would you characterize it?
22 A
I would characterize it that they are ALDERSON AEPoRTING COMPANY,INC,
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1 reevaluating the dose estimates of Hiroshima and 2 Nagasaki and the committee is still out in regard to
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3 just how the doses or the health impacts would change.
4 Just the preliminary, though --
5 Q
the preliminary data suggests that they 6 underestimated the doses previously?
7 A
The doses from what?
8 Q
To the victims at Nagasaki.
9 A
I'm not aware of that.
10 Q
Are you familiar with the literature on the 11 reevalua tion of the Nagasaki doses?
12 A
I'm familiar with some of the literature and
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13 you have to be clear when you specify which doses you 14 are talking about.
l 15 Q
Well, what literature are you familiar with?
18 A
In regard to?
17 Q
The reevaluation of the Nagasaki dose data.
18 A
I have read some articles in Science magazine 19 regarding the reevaluation of the Nagasaki data, and I 20 attended a conference held at the Department of Energy, 21 I think it was last November, regarding the evaluations' 22 of the Hiroshima-Nagasaki data.
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1 Q
And is it your view that the reevaluation --
2 what is your view with regard to the likelihood of i
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3 having to reject the majority BEIR 3 opinion on the 4 bas'is of the reevaluation?
5 A
I would hesitate to give an opinion on that 6 until the reevaluation is complete.
It is preliminary 7 to that.
8 0
Then in the absence of that data you would say 9 that the BEIR 3 majority opinion carries with it some 10 signifirant uncertainty with regard to its validity?
11 A
Ho.
12 Q
Do you think it would be valid in any case, no
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13 matter what the Nagasaki reevaluations came out?
14 A
I think the estimates we presented here --
15 Q
I'm not asking about the estimates you 16 presented in there.
I'm asking about the BEIR 3 17 majority opinion on the effect of the reevaluation of 18 Nagasaki data.
19 A
The eff ect on what?
20 Q
I want to ask your opinion as to whether this 21 reevaluation of the Nagasaki data is likely to call into 22 question the vaiidity of the BEIB 3 majority opinion
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2 A
I would suggest that that question would be f
to the BEIE 3 committee and not myself.
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Q I'm sure it would.
I am asking your opinion, 5 though.
6 A
As I said. earlier, as near as I can tell, they 7 are just preliminary estimates on how the doses would be 8 revised and the final dose estimates have not been 9 presented yet, and it is too early to have an opinion 10 without the basic information.
11 Q
Am I correct in assuming, then, in your mind 12 it could go either way?
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13 A
What could go either way?
14 Q
When you get the new evaluations, you might 15 then decide that the model assumed by the majority of 16 the BEIB 3 committee is no longer the most appropriate i
17 model, but the model assumed by the -- recommended in 18 the Radford dissent is the more appropriate.
19 A
It is a possibility.
20 Q
So there is at least that level of uncertainty 21 in terms of the BEIR 3 data; is that correct?
l 22 A
Ihere is uncertainty with regard to the BEIR 3 i
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However, we bracketed that uncertainty in the 2 text of the draft supplement.
We gave ranges of the 3 uncertaint! estimates.
We did not use the linear 4 quadratic model in BEIR 3.
We used the linear model in e
5 the BEIR 1 committee, which is the more conservative 6 model.
7 Q
And that is the 135 cancer deaths per million 8 personrem?
9 A
Potentini cancer deaths, that is correct.
10 Q
On page 5-13, now, in your view, is there any 11 expert opinion that lies outside of that range of 12 estimates for the cancer risk coefficient, say high'er
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13 than 135 deaths per million personrem?
14 A
Yes.
15 0
And in your opinion, Dr. Morgan, one of the 16 experts -- is Dr. Morgan one of the experts that have a 17 larger -- that believes the risk coefficient should be 18 larger?
19 A
My undarstanding is he believes the risk 20 coefficient should be larger, the risk estimate should 21 be larger.
22 Q
And do you believe his analysis to be in s._
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2 A
I am not quite sure how I would characterize
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4 Q
Did Dr. Radford also believe that the risk 5 coefficient should be higher than you have assumed 6 here -- the cancer risk coefficient?
7 A
I'm not sure I would agree with that.
8 Q
Is Dr. Radford an expert in the field?
9 A
Dr. Radford is an expert in the field.
I'm 10 not sure if he would disagree with the ansvers that we 11 used because we did not use values that the majority of 12 the BEIR 3 committee recommended.
We used higher
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13 values.-
14 Q
Does Dr. Goffman believe that the risk 15 coefficient should be larger than the value you have 16 used?
17 A
I think he does.
I couldn 't give you a 18 specific reference Dn that.
19 0
Is he an expert in this area?
20 A
I'm not sure how expert he is.
21 Q
In your opinion, is Dr. Goffman more of an 22 expert in the area of radiological health effects than g
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I don 't know what his background his
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4 Q
Are you f amiliar with his work ?
5 A
Some of his work.
6 Q
IInve you read his latest book?
7 A
Parts of it.
8 Q
That's all one can expect, it's so thick.
9 (Laughter.)
10 Q
Does Dr. Tamplin believe that the risk 11 estimates -- the cancer risk coefficient is larger than 12 rou have assumed here?
13 A
I think he does.
l 14 Q
Is he an expert in the field?
l l
l 15 A
I'm not sure.
l 16 0
Does Alice Stewart believe that the risk 17 coefficient should be larger than the one you've assumed 18 here?.
19 A
I believe she does.
20 0
And is she an expert in the field?
l 21 A
Yes, I would say she is an expert in the field.
I 22 Q
And how about Dr. Mancuso?
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A I don 't know Dr. Mancuso 's background very 2 auch.
I wouldn't be one to qualify whether or not they 3 are expert or how expert he is in the field.
He is 4 quite controversial.
5 Q
How about George Neal?
6 A
George Neal?
7 Q
Are you familiar with the publications by 8 Hancuso, Stewart and Neal?
9 A
Yes, I sm.
10 Q
Does George Keal believe that the cancer risk 11 coefficient is higher than the one you have assumed 12 here?
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13 A
The papers that I'm f amiliar with, they do 14 give estimates higher than what we've used.
15 Q
In sumasry, is it fair to say that there are a 16 number of experts in the field tha t believe the cancer 17 risk coefficient should be higher than the one you have 18 assumed in this document?
19 A
I would say yes, if you interpret " number" to 20 nean more than one.
21 Q
Vell,. suppose I interpret it to mean more than-22 five?
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ALDERSoN F4 PORTING COMPANY. INC.
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~1 A
You could probably find five people who would 2 think the risk estimators would be higher than the ones
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3 ve have estima ted.
How expert they are I am not quite 4 sure.
5 Q
Well, is it fair to say, then, that you don't 6.know the literature well enough to know whether this 135 7 cancer deaths per million personrem is a conservative 8 value?
9 A
No, that is not a correct statement.
It is a 10 conservative value.
11 Q
Iou believe it to be conservative despite the 12 fact that there are a number of experts in the field
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13 that believe it ought to be larger?
14 A
Tes.
As I stated in the draft supplement, the l
15 risk estimaters that we have there are consistent with 16 the recommendations of the major radiation protection 17 organizations which consist of many individuals who have 18 had input into the deliberations for formulating risk 19 estimaters.
20 0
Could you tall me, other than the members of 21 the BEIR 3 committee, who has endorsed these risk
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I didn't say anyone specifically endorsed our 2 risk estimaters.
What I said is our risk estimaters are
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3 consistent with the recommendations of the UNSCEAR 4 committee, the International Commission on Radiological 5 Protection, the Nitional Council on Radiation Protection 6,and Measurements, and both the BEIR 1 and the BEIE 3 7 committees.
8 Q
And because of that they are conservative and 9 all of these other folks are in error?
10 A
Is that a statement?
11 Q
I am asking you.
Do you agree with that
, 12 sta tem en t?
I mean, is that your conclusion ?
I" 13 A
My conclusion is that the values we used here 14 were conservative.
15 0
And if you conclude that the values used here 16 are conservative, doesn't it imply that these other 17 people's risk coefficients are in error?
18 A
It probably does.
19 Q
And yet you don't know the basis for their 20 conclusions?
21 A
I know the basis for some of their 22 conclusions.
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Do you know the basis for Dr. Morgan's 2 conclusions?
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Yes.
I testified at the summer hearing last 4 summer and Dr. Morgan also testified in the area of 5 health effects, and Leonard Hamilton from Brookhaven 6 also testified.
7 Q
Why is Dr. Morgan wrong?
8 A
Okay.
Right nov ve are talking very 9 generally.
l 10 0
Well, tell me why Dr. Morgan's estimate of the l
11 cancer coefficient is in error.
12 A
Wh at risk estimater are you talking about?
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13 Q
The one you just agreed that was larger than 14 the 135 cancers per nillion personcem.
15
.A I would need a specific publication and a 16 specific ref erence in order to go into detail as to why l
l 17 I disagree with his estimates.
18 Q
Do you know of any risk estimates that Dr.
19 Morgan has made of cancer deaths?
20 A
I know of one that he had at the summer 21 hearing, which was more than a year ago.
l 22 Q
And what numbers did he use?
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I think it was on the order of about ten times 2 what we used here.
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And why is he in error?
4 A
I'a not prepared to go into that today.
5 Q
And could you tell me why Dr. Radford is in 6 e rror?
7 A
I don't believe I said Dr. Radford was in 8 error.
I think I indicated tha t his values "right quite 9 similar to the values we have included in the draft 10 supplement.
11 Q
I believe you indicated you didn' t know what 12 his values were.
Isn' t that more correct?
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13 A
I know that he endorses the linear model 14 rather than the linear quadratic model, and if you do 15 use the linear model in either the BEIR 1 or the BEIR 3 16 reports, you get values very similar to what we have 17 here.
18 Q
And why is Dr. Goffman in error?
19 A
I have not ande a detailed study of Dr.
20 Goffman 's work.
21 Q
And why is Dr. Tamplin in error?
22 A
I have not made a datailed study of Dr.
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2 Q
And why is Alice Stewart in error?
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3 A
Once again, I have not made a detailed study 4 of her specific papers.
5 Q
And why is --
6 A
But I do know that they are much higher than 7 the values that you get from the major radiation 8 protections in the world.
9 Q
On that basis, could you have predicted the 10 theory of relativity in 19077 11 ER. SWANSON:
Objection, and that's a 12 frivol us question.
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13 BI ER. COCHRAN:
(Resuming) 14 0
Answer the question.
He has objected for the 15 record.
16 MR. SWANSONs Tell him it's a frivolous 17 question.
18 THE WITNESSs I don't have any opinion on your 19 question.
20 BY MR. COCHRANs (Resuming) 21 Q
Do you have any basis for choosing 135 cancers 22 deaths per million personrem as opposed to a higher ks ALDERSoN REPORTING COMPANY,INC, l
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Yes.
4 Q
And what is that?
5 A
It is slso -- it is consistant with the 6 UNSCEAR data.
It is consistent with the basic 7 epidemiological data, which is summarized in the United 8 Nations Scientific Committee on Radiation Report.
9 Q
How old is that report?
10 A
There are several UNSCEAR reports.
There was 11 one in 1972.
There was one in 1977, and th ere is a 12 draf t one now circulating.
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13 0
Which report are you referring to?
14 A
The 1977 report.
15 0
And what risk coefficient did the y assign in 16 tha t?
-4 17 A
It is on the order of 10 potential cancer 18 fatalities per rem.
19 Q
And how was that number derived?
20 A
It was derived from many epidemiological 21 studies concerning the victims of Hiroshima and Nagasaki 22 and the railuz dial painters -- many studies.
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A It was derived -- I don 't know what you mean 5 by " independently."
6 Q
Eell, did they derive it f rom these -- this 7 body of epidemiological information you referred to, o r 8 did they just adopt a number that the BEIR 1 or BEIR 3 9 committee had estimated?
10 A
No.
In that res pect they vere definitely 11 independent because they reviewed the basic 12 epidemiological d.ita themsel.ves.
k 13 Q
And whac else besides UNSCEAR?
14 A
The International Commission on Radiological 15 Protection.
16 Q
And what were their risk coefficients?
17 A
Their risk estimaters are contained in th e i
18 ICRP publication number 26.
19 Q
And what else besides the ICRP and DNSCEAR?
20 A
The National Council on Radiation Protections 21 and Measurements.
They also discuss the risk from 22 radiation in various reports.
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'And where are their risk estimates published?
2 A
I think I gave a couple of references in
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There are many NCRP publications.
4 Q
Well, where do they give their cancer death 5 coefficient?
6 A
I couldn't give you a specific' reference for 7 risk estimater.
However, I could give you a number of 8 publications like NCHP report number 39, I believe it 9 is, NCRP report number 42, " Health Effects of 10 Alpha-Emitting Particles."
They discuss health impacts 11 from radiation.
12 Q
This 135 deaths, do you believe that is the
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13 appropriata risk -- cancer risk coefficient to use in 14 estimating the potential cancers from routine, 15 accidental operations at the CRBR7 16 A
Well, as stated in the text there,I said that 17 was a conservative estimate to estimate the potential 18 impacts from radiation exposure.
19 Q
Is that the appropriate one to use -- this 20 conserva tive value or some lesser value or some larger 21 value?
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I think this was the appropriate one to use.
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2 Q
The 135 from BEIR 1,
did it come from the risk
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I think I mentioned 5 something about that in my co m m en t s.
6 A
The 135 potential cancer deaths per million 7 persons is based upon the BEIR 1 report, which reviewed 8 epidemiological studies for many different groups that 9 vere exposed to radiation.
Some of those groups were 10 occupationally exposed.
Others were exposed members of 11 the general public -- for example in Hiroshima and 12 Nagasaki.
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13 Q
In Appendix J did you use that risk estimater 14 in calculating the health effects associated with the 15 accidents?
16 A
I did not work on Appendix'J.
17 Q
Do you know whether that risk estimater was 18 used?
19 A
I never reviewed Appendix J.
I don't know.
20 Q
Should I imply that the document used a 21 different risk estimater throughout the document than 22 the one presented in Chapter 5?
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I would have to review Appendix J to see just 2 specifically what they have used here.
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7 Q
Did you use this risk estimater in terms of --
8 vell, am I correct in assuming that there are no cancer 9 death estir:ates in the section on routine releases, or 10 are there?
I just don't recall.
Appendir D, did you 11 apply this risk estimater?
12 A
To Appendix D?
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13 0
To the dosages to estimate the cancers in i
14 Appendix D.
15 A
Yes.
16 Q
But you don't know which risk estimater was 1
17 used 1n Appendix J?
l 18 A
I didn't use any risk estimaters in Appendix l
l 19 J.
20 Q
You don't know what the Staff used?
l 21 A
Not right now.
I haven't reviewed the l
22 specific appendix.
I have an idea of what they used, i
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Are you sure they didn't use the values from 4 WASH-14007 5
A They might have.
6 Q
Why do you say that is consistent?
7 A
Why do I say it is consistent?
8 0
Yes.
9 A
Because the values that we used were derived 10 from the BEIR 1 report.
l 11 Q
They are not the values in WASH-1400.
12 A
Th ey are derived.
Values in WASH-1400 were
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13 derived from the BEIR 1 report, so it is a common 14 basis.
There are minor changes.
15 0
What do you call a " minor change"?
16 A
I think there was some differences in terms of l
17 the risk estimater for thyroid cancers.
18 Q
To your knowledge, though, they wouldn't be 19 off by a factor of five?
20 A
What wouldn't be off by a factor of five?
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The cancer risk coefficient.
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For what?
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That was applied in Appendix J as opposed'to
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Objection.
He's already said he 4 doesu't know what was used in Appendix J.
5 ER. COCHRANs He said there were minor 6 differences.
I want to find out if " minor difference" 7 seans a fartor of five.
8 HR. SWANSON:
He gave you a guess on what was 9 done elsewhere and he told you he doesn 't know what is 10 in this Appendix.
l 11 MR. COCHRAN:
I want to find out what he means 12 when he says a " minor difference."
I don't know whether 13 minor difference to him means a factor of 100 or tec or l
14 five or none.
15 HR. SWANSON:
You can go on, but it is going 16 to be worthless.
He said he doesn't know.
17 BY MR. COCHRANs (Resuming) 18 Q
Io your knowledge, could the valu es 'used in 19 Appendix J be a factor of ten lower risk coefficient in 20 Appendix J than the one you have assumed here?
21 A
Well, you have to be careful with your
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You are talking about risk coefficients.
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1 I did not use risk coefficients.
I used risk 2 estimaters.
Risk coefficients are used to derive risk
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A Q
Well, I will use whatever language you want to 5 use.
You define 135 potential deaths from cancer per l
6 million personrems as a risk estimater?
7 A
That is correct.
8 Q
Now could the risk estimater used in Appendix 9 J be lower than this number by a factor of ten?
10 A
I have not specifically reviewed the risk 11 estf s in this Appendix J.
'12 Q
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15 Q
Well, overall, in terms of --
A Okay.
For example, in the accident assessment 16
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18 They take into account dose rate factors, which is in l
19 addition to the risk estima ter.
So if you zero in on 20 one-parameter, you have got to look at many things.
21 Q
What do you mean they "take into account dose s 22 rate factors" in W ASH-1400?
How. do they take into i
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1 account dose r.ca fac.7rs in WASH-1400 for the cancer 2 risk estimater?
3 A
They use a dose reduction f actor in estinating 4 the doses, and it's either the estimating'the doses or 5 in estimating the risk from the radiation in WASH-1400.
6 Q
And what is that factor?
7 A
It varies d6pending upon the dose rate.
8 Q
Is that the appropriate factor to apply in
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9 calcula ting the accident risk?
10 A
Is what an appropriate factor?
11 Q
Ihe dose reduction factor that you referred to 12 that is used in WASH-1400 to account for dose rate 13 considerations.
14 A
Well, the concept of dose reduction factors 15 has been discussed in NCEP report nur.ber 64, and they 16 recommend the use of dose reduction factors, so the 17 concept is certainly appropriate.
That is why earlier I 18 said that the risk estimaters that we used in Chapter 19 5.7 of the d raf t supplements are conservative.
We do 20 not take into account dose reduction f actors.
21 Q
Are the dose estimaters used in Appendix J 22 conservative?
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1 A
As I just said a number of times, Appendix 2 J -- I have not specifically read this Appendix J.
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3 0
Who is responsible for supplying the dose 4 risk -- the risk estimaters, cancer risk estimaters that 5 were used in Appendix J7 6
A Well, I guess it would be the person who wrote 7 A,ppendix J did that analysis.
8 0
Are you responsible for the dose calculations 9 for other than Appendix J7 10 A
The calculated doses from fuel fabrication 11 facility, which was in Appendix D, from the fuel 12. rep ro cessin g plant, which is in Appendix D, and f rom the 13 reactor, which is in Appendix -- excuse me, Chapter 5.7.
s 14 Q
How about from decommissioning?
15 A
Decommissioning -- I did not calculate the 16 doses from decommissioning.
17 Q
Who did?
18 A
Frankly, I think we are getting into an area 19 here where the project manager would be better able to 20 answer.
Just perchance I happen to know.
Well, I'm not 21 aven quite sure who did that.
That would be more a 22 question for the project manager to answer.
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If you were assigned the task of calculating 2 the risks associated with decommissioning of a reactor 3 for which there are vario'us alternatives, what ' cancer 4 risk coefficient would you use?
5 A
The cancer risk coefficients that were used in 8 evaluating the doses from decommissioning vere the same 7 values that I used in Chapter 5.7.
I supplied those.
8 Q
And you would apply those.
Is it fair to say
~
9 that you believe -- well, first of all, are you familiar i
to with tha various ways one can decommission a nuclear 11 reactor -- entombzent and dismantling and so forth?
12 A
I'm generally f amiliar with it, but I am not 13 En expert in this tres.
e 14 Q
Are you familiar with the fact that some of 15 these involve allowing the plant to sort of be managed 18 for 150 years or so prior to dismantlement?
17 A
I'm generally familiar with that, but I would 18 refer to the -- I would give deference to the specific 19 Staff member who did those analyses.
1 l
20 Q
And if you were requested to calculate or work 1
l 21 on the team that calculated the dosages associated with' l
22 d ec ommissioning a plant which is entombed for 130 years t
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1 or 150 years, what risk coefficient would you use?
2 A
I did not -- I was not involved in calculating
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3 the doses.
4 0
I understand.
Ihis is a hypothetical 5 question.
If you were ass'igned the task of estimating 6 the health effects associated with decommissioning a 7 reactor by.this particular methodology whereby the 8 reacto. is entombed for 130 to 150 years and then 9 dissat.tled, what risk coefficient would you use?
10 A
I would use the ones that we have used in the 11 environmental impact statement.
12 Q
So you would use the 135 cadeer deaths per 13 million manren, calculate the dose to the people tha t 14 are decommissioning the reactor and then estimate the 15 number of deaths, is that correct?
16 A
I would use the estimater that we usen in the 17 draft supplement to estimate the potential cancer 18 f atalities f rom a decommissioning.
19 Q
And if you multiply that by the estimated 20 dosages in 150 years from now when you dismantle th e
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21 reactor, is that correct?
22 A
I think that would give you an assessment of f(.
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Is that, do you think, a better way to
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3 estimate the health effects in 150 years?
4-A Pardon?
5 Q
Can you think of a more appropriate way to 6 estimate the health. effects associated with 7 decommissioning in 150 years?
8 A
There are other ways to do it.
I would do it 9 the way I just explained it.
10 (Counsel for NBDC conferring.)
11 ER. CDCHRANa That's all.
12 (Whereupon, at 3:55 o' clock p.m.,
the taking 13 of the instant deposition ceased.)
14 15 EDWARD BRANAGAN 16 Subscribed and sworn to before me this day 1982.
17 of 18 NOTARY PUBLIC 19 20 Hy commission expires 21 22 ALDERSoN REPORTING COMPANY,'NC, p sagamo.ove _ c w wamur.tnu _ n e onnea tenes au.sm
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1 CERTIFICATE OF NOTARY PUBLIC 2
I, RAYMOND R. HERR III the officer before 3
whom the foregoing deposition was taken, do hereby certify that 4
the witness whose testimony appears in the foregoing deposition g
5 was duly sworn by me; that the testimony of said witness was E
6 taken by me by stenotype to the best of my ability and thereafter R
E 7
reduced to typewriting under my direction; that said depositiori X[
8 is a true record of the testimony given by said witness; that d
9 I am neither counsel for, related to, nor employed by any of i
Cg 10
-the parties to the action in which this deposition was taken; E
g 11 and further that I am not a relative or employee of any attorney is y
12 or coursel employed by the parties thereto, nor fimncially or
=l 13 otharwise interested in the outcome of the action.
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Notary'Public in and for 5
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18 My Commission expires [viu
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l#%4TFa 00mCCURDIPNCP UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION 00LKETED
'MNRC 12 GH 29 P2':46
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trrirr y SELRElARY In the Matter of
)
nocAlinG & SERVICE
)
BRANCH UNITED STATES DEPARTMENT OF ENERGY
)
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PROJECT MANAGEMENT CORPORATION
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Docket No. 50-537
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TENNESSEE VALLEY AUTHORITY
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(Clinch River Breeder Reactor Plant)
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