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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20212J3731999-06-25025 June 1999 Responds to Re Annual Fee Invoice AM4270-99 & Fee Categories Assigned to License SNM-7.Fee Category 3O on Invoice AM4270-99 Erroneously Issued & Has Been Canceled. Payment Received & Invoice Revised & Considered Paid ML20212J3791999-06-21021 June 1999 Ack & Accepts Majority of Fee Categories Assigned to License SNM-7 in Fy 1999 Annual Matls Fee Invoice AM4270-99,dtd 990601.Forwards Corrected Copy of Annual Fee Invoice.Without Encl ML20207D4741999-05-27027 May 1999 Forwards Insp Rept 70-0008/99-01 on 990414-15.No Violations Noted.Based on Results of Insp,Nrc Did Not Identify Any Radioactive Matls in Excess of NRC Release Guidelines for Unrestricted Use ML20207D0421999-05-26026 May 1999 Discusses Which Provided Info Re Battelle Memorial Inst Special Nuclear Matl Possession Limits,Per 990121 Request.Sum Quantities of Special Nuclear Matl Would Exclude Transfer of SNM-7 License to State of Oh ML20199J9311999-01-21021 January 1999 Submits RAI Re Bcl Decommissioning Project Request to Change Decommissioning Schedule & Other Listed Subj Matters.Respond to Request within 15 Days from Date of This Ltr ML20199D8461999-01-11011 January 1999 Discusses Insp Rept 70-0008/98-03 on 981215-17.No Violations Were Identified.Insp Consisted of Observations & Evaluations of on-going Decommissioning Activities Including Reviews of Environ Monitoring Sys & Controls & Radiation Protection ML20198D5001998-12-14014 December 1998 Forwards Insp Rept 70-0008/98-02 on 981116-18 & 1211.No Violation Noted.Purpose of Insp Was to Determine Adequacy of Confirmantory Survey Conducted by Orise in Building 2 ML20206N4301998-12-14014 December 1998 Forwards Insp Rept 70-0008/98-01 on 981116-18 & 1211.No Violations Noted.Insp Consists of Radiological Surveys,Used by NRC to Evaluate Orise Effectiveness in Conducting Its Confirmatory Survey & Releasing Bldg for Restricted Use ML20195J6221998-11-23023 November 1998 Responds to Indicating That Battelle No Longer Disputes Listed Invoices & That Payment Sent ML20195E2121998-11-17017 November 1998 Responds to Re Receipt of Overdue Notices for Listed Invoices ML20155B5831998-10-0606 October 1998 Forwards Matl Balance Rept (Form DOE/NRC-742 & 742C) for Period Ending 980930.Any Questions Re Rept Should Be Directed to Listed Name & Number ML20237A7281998-08-13013 August 1998 Ack Receipt of Disputing Fee Categories for Invoice AM4515-98.Interest-fee Waiver Period Being Extended Until Issues Raised in Subj Ltr Resolved.Review & Analysis of All Activities Under License SNM-7 Completed ML20236R8581998-07-17017 July 1998 Refers to 980529 & 0717 Ltrs Re Battelle Memorial Institute Characterization & Final Status Surveys for Building KA-7 North ML20247N8071998-05-18018 May 1998 Requests Info Which Demonstrates That Funding for Battelle Decommissioning Project Will Be Maintained,Such That It Will Meet Scheduled Commitment W/Agency ML20217P7131998-05-0404 May 1998 Discusses Insp Rept 70-0008/98-01 on 980408-10.No Violations Noted.Insp Consisted of Observations & Evaluations of on-going Decommissioning Activities.Conduct of Activities Characterized by safety-conscious Decommissioning Operation ML20198N2051997-10-29029 October 1997 Forwards Insp Rept 70-0008/97-02 on 970825-27.No Violations Noted.Purpose of Insp Was to Determine Adequacy of Decommissioning Activities Conducted in Bmi Bldgs 1,6 & 7 as Authorized by Bmi License ML20217J0871997-10-0707 October 1997 Forwards Copy of Matls Balance Rept (Form DOE/NRC-742 & 742C) Covering License Matl Held at Battelle for Period Ending 970930 ML20149H4511997-06-20020 June 1997 Informs That Leaking 8 Mci Ni-63 Source Housed in Electron Capture Detector Was Found to Be Leaking on 970618.Source Was Bagged,Tagged,Sealed & Transferred to Radiation Safety Svcs Control.Contamination Survey Was Performed ML20137Z2381997-04-0404 April 1997 Forwards Matls Balance Rept,Form DOE/NRC-742 & 742C,covering License Matl Held for Period Ending 970331 for License SNM-7 ML20135D1621997-02-20020 February 1997 Summarizes Factors Pertinent to Radiological Status of Retired Battelle Research Reactor Facility for CY96 as Required by Battelle NRC License SNM-7 ML20134G7181997-02-0505 February 1997 Forwards Insp Rept 70-0008/97-01 on 970106-10.No Violations Noted ML20029D1941994-04-26026 April 1994 Forwards Safety Insp Rept 70-0008/94-01 on 940131-0325 & Notice of Violation.Licensee Radiation Protection Program Found to Be Adequate to Protect Radiological Safety of Employees & Public ML20058P9051993-12-16016 December 1993 Discusses Radiation Protection self-assessment Conducted in Jul 1992,resulting in Significant Improvement to R&D Portion of Radiation Protection Program,Bringing Program to Performance Levels of Bcldp Program ML20058N0301993-12-15015 December 1993 Discusses Safety Insp of License SNM-0007 on 931108-10.No Violations Noted.Major Areas Inspected:Activities Conducted Under License Re Radiation Safety & Compliance to Commission Rules & Regulations ML20058G5351993-12-0606 December 1993 Advises of Completion of Review of Decommissioning Plan for Battelle Memorial Inst Columbus Operations. Program Adequate & Acceptable.Clarifying Info Requested Re Section 2.1.3.4.4, Soil Remediation ML20057E6201993-10-0505 October 1993 Forwards Amend 4 to License SNM-7,authorizing Lower Possession Limit & Possession & Use of Small Piece of Spent Fuel ML20057B7751993-09-15015 September 1993 Forwards Rept Bcldp 091593, Site Environ Rept for CY92 on Radiological & Nonradiological Parameters ML20056H5421993-09-0202 September 1993 Informs That Licensee Will Implement Provisions of New 10CFR20 Requirements on 931101 for All NRC Regulated Activities ML20056G6431993-08-30030 August 1993 Forwards Insp Rept 70-0008/93-01 on 930727-29.No Violations Noted ML20046D5911993-08-18018 August 1993 Forwards Decontamination Work Plan for Bldg 7A & Decontamination Rept for Bldg 7A. Issues from Last Months Meeting Which Merit Reiteration Listed ML20045G4371993-06-25025 June 1993 Reiterates Points Discussed at 930622 Meeting,Namely Providing Balance of Financial Assurance Package to D Futoma by Middle of Jul & Submitting Battelle Licensing Renewal Application Shortly Thereafter ML20045D5511993-06-18018 June 1993 Expresses Thanks for Agreeing to 930622 Meeting in Rockville,Md to Discuss Status of Battelle 900725 Request for Exemption,As Supplemented on 930525 & Submittal of Battelle Amend/Renewal for License SNM-7 ML20045A9821993-06-0101 June 1993 Notifies That Battelle Columbus Lab Decommissioning Project Under Battelle Memorial Inst Will Implement Provisions of New 10CFR20,effective 930601 ML20044G4221993-05-25025 May 1993 Forwards Revised Decommissioning Plan for Battelle Memorial Inst Columbus Operations to Nrc ML20035B8251993-03-26026 March 1993 Notifies That Nrc,Ofc of Nuclear Matl Safety & Safeguards, Responsibility for Licensing of Facility Has Been Transferred from Fuel Cycle Safety Branch to Division of Fuel Cycle Safety & Safeguards ML20035A9151993-03-23023 March 1993 Provides Mods to Page 1.4 of Encl A,BCL-1081 Part 1,sent to Licensee by Ltr Re Revised Bco Organizational Info ML20012G4691993-02-23023 February 1993 Forwards Info Re Organizational Changes Associated W/License SNM-7,consisting of Rev 4 to Renewal Application BCL-1081, Revised Organizational Info & BCL-1081,App a, Charter of Radiological Safety Committee (Rsc) ML20126M6401992-12-28028 December 1992 Submits Amend 1 to Irrevocable Standby Ltr of Credit 99245 to Extend Expiration Date to 930801 & to Disregard Cancellation Notice ML20126F7371992-12-23023 December 1992 Advises That Licensee Elects Not to Renew Standby Ltr of Credit 99245 Issued on 900727 ML20125C9661992-12-10010 December 1992 Suppls Info in 920619 Response Re Certification of Financial Assurance for Decommissioning Facilities at Columbus & West Jefferson,Oh & Acceptance of Current NRC Guidance of Acceptable Cleanup Criteria ML20125C8721992-11-23023 November 1992 Forwards Site Environmental Rept for 1991 on Radiological & Nonradiological Parameters ML20128A7461992-11-23023 November 1992 Forwards Bcldp 10192, Site Environ Rept for CY91 on Radiological & Nonradiological Parameters. Environ Monitoring Program Will Continue Until Conclusion of Activities ML20057A7101992-02-25025 February 1992 Forwards Executed Contract NRC-04-92-047 ML20058G9741990-11-0505 November 1990 Informs That Battelle Filed Certification of Financial Assurance for License SNM-7,in Response to ML20062G8911990-11-0202 November 1990 Requests Response as Described in Encl Demand for Info within 30 Days ML20058Q3121990-08-16016 August 1990 Forwards Finding of No Significant Impact & Environ Assessment, Approved by DOE on 900614 ML20055H7411990-07-27027 July 1990 Provides Irrevocable Standby Ltr of Credit Opened in Favor of NRC for Licensee.Fund Will Be Made Available Upon Presentation of Listed Documents ML20055H7421990-07-25025 July 1990 Forwards Request for Exemption from Requirements of 10CFR70.25(f)(4) & 10CFR30.35(f)(4) ML20055H7391990-07-25025 July 1990 Forwards Certification of Financial Assurance for Decommissioning for License SNM-7.Full Decommissioning Funding Plan Will Be Submitted W/Application for Renewal of License ML20055C9401990-05-0707 May 1990 Forwards Response to Questions Re Decommissioning of Pu Facilities 1999-06-25
[Table view] Category:NRC TO RESEARCH INSTITUTION/LABORATORY
MONTHYEARML20006F2361990-02-12012 February 1990 Forwards Safety Insp Rept 70-0008/90-01 on 900116-18.No Violations Noted ML20247L4801989-09-13013 September 1989 Forwards Safety Insp Repts 50-006/89-02 & 70-0008/89-02 on 890627-30.No Violations Noted ML19327B4071989-06-28028 June 1989 Advises That NRC Form 327s Forwarded to NMSS or Region II Ofc to Be Marked as 10CFR2.790(d) or Natl Security Info ML20246P7591989-03-22022 March 1989 Forwards Safety Insp Repts 70-0008/89-01 & 50-006/89-01 on 890214-16.No Violations Noted ML20207K2041988-09-23023 September 1988 Requests Addl Info Re 880805 Application for Amend to License SNM-7,authorizing Controlled Field Studies Using Up to 3 Ci C-14 Labelled Compounds ML20153G6241988-09-0101 September 1988 Ack Receipt of 880314 Application for Renewal of License SNM-7.Existing License Will Not Expire Until NRC Determination Re Renewal Made ML20153F4651988-09-0101 September 1988 Forwards Insp Rept 70-0008/88-02 on 880719-20.No Violations Noted ML20154L9171988-05-12012 May 1988 Discusses Fees Required for Renewal of License SNM-7 & Confirms 880401 Telcon.Should Company Decide to Discontinue Incineration Authorization,Facility Should Send Written Request to NRC ML20151X0041988-04-27027 April 1988 Forwards Safety Insp Repts 50-006/88-01 & 70-0008/88-01 on 880404-07.No Violations Noted ML20236N4571987-11-10010 November 1987 Forwards Safety Insp Repts 50-006/87-03 & 70-0008/87-03 on 871019-23.No Violations Identified ML20235E3321987-09-23023 September 1987 Reconfirms NRC Approval of Decommissioning Plan Referred to in Trust Agreement,In Response to Recipient . Commitment to Provide Funds for Decommissioning Plan Made Condition of License SNM-7 w/830429 Renewal of License ML20236W9061987-09-23023 September 1987 Responds to Re Bmi Need for NRC Current Ltr Approving Decommissioning Plan Referred in Trust Agreement. DOE Accepted Responsibility for Cleanup of Contamination at Bmi & DOE Will Provide Majority of Funds ML20235C4691987-09-16016 September 1987 Notifies That Region II Sponsoring One & one-half Day Nuclear Fuel Cycle Licensee Workshop on 871027-28 in Atlanta,Ga.Workshop Will Bring Together NRC Officials & Fuel Cycle Licensee Representatives to Discuss NRC Programs ML20214X3771987-06-0909 June 1987 Forwards Safety Insp Repts 70-0008/87-02 & 50-006/87-02 on 870518-22.No Violations Noted ML20214T6011987-06-0202 June 1987 Forwards Amend 2 to License SNM-7,revising Condition 23 to Include Reactor in Financial Plan for Decommissioning & Adding Condition 27 to Require Radiological Monitoring. Safety Evaluation & Environ Assessment Encl ML20207R8201987-03-16016 March 1987 Forwards SAI81-307-WA, Environ Impact Assessment,Bmi for Ref Used as Background Source of Info & Basis for Description of Site & Surrounding Environ for Vol Reduction Demonstration Facility ML20212L0891987-03-0505 March 1987 Forwards Corrected Annex a, List of Effective Pages to License SNM-7 ML20212L1341987-03-0303 March 1987 Forwards Amend 1 to License SNM-7,authorizing Operation of Vol Reduction Demonstration Facility.Revised Pages 2.1-2.5 of Part II of Application for Renewal Should Be Submitted When Facility Installation Initiated ML20210S2971987-02-10010 February 1987 Forwards Safety Insp Repts 50-006/87-01 & 70-0006/87-01 on 870112-16 & Notice of Violation ML20210S7771986-10-0101 October 1986 Forwards Safety Insp Rept 70-0008/86-02 on 860908-11.No Violations Noted ML20206N1591986-06-24024 June 1986 Forwards Environ Assessment of Bmi Vol Reduction Demonstration Facility in West Jefferson,Oh,In Response to 830815 Application to Amend License SNM-7.Finding of No Significant Impact Will Be Forwarded ML20199C7251986-06-12012 June 1986 Forwards Safety Insp Rept 70-0008/86-01 on 860512-16 & Notice of Violation.Rept Includes Review of Findings from State of Sc 851211 Insp.No Response Required Since Corrective Actions Already Implemented ML20137Q2731985-09-17017 September 1985 Forwards Safety Insp Rept 70-0008/85-02 on 850819-23.No Noncompliance Identified ML20027D8201982-10-12012 October 1982 Forwards Outline of safety-related Info Re Design & Operation of Low Level Waste Incinerator,In Response to Re Application for Amend to License SNM-7 ML20053B6411982-05-24024 May 1982 Informs of 10CFR170,Category 13 Fee Requirement for 820324 Request for Approval of Route to Be Used for Shipment of Spent Fuel to Pleasanton,Ca ML20054D5921982-03-23023 March 1982 Forwards Rept Re Risk Analysis of Postulated Pu Releases from Bmcl Bldg JN-1B,West Jefferson Oh as Result of Severe Natural Phenomena ML20041B9281982-02-0404 February 1982 Informs That Commission 811211 Approval of Route for Shipment of Irradiated Reactor Fuel Requires Category 13 Fee.Invoice Will Be Submitted ML20040D7991982-01-26026 January 1982 Confirmation of Action Re 820125 Telcon Concerning Submittal of Radiological Contingency Plan.Failure to Comply W/Order to Modify License Is Violation of Regulation.Contingency Plan Due by 820129 ML20040B0411982-01-0404 January 1982 Transmits Increment of Analysis of Effects of Natural Phenomena Re Pu Operations at West Jefferson,Oh ML20039C1511981-12-11011 December 1981 Forwards IE Insp Rept 70-0008/81-02 on 811117-20.No Noncompliance Noted ML20010C3731981-08-0303 August 1981 Forwards Vol 1 of Effect of Natural Phenomena on Existing Pu Fabrication Facilities ML20005B3761981-06-30030 June 1981 Immediate Action Ltr Confirming 810629 Telcon Re Measures to Be Taken to Assure That External Package Contamination Levels Do Not Exceed DOT Limits During Transport of Model NAC-1D from Facility to Turkey Point ML20005A8711981-06-25025 June 1981 Immediate Action Ltr Re 810624 Telcon Concerning Problem of Removable Contamination on Surface of NAC-1D Cask.Cask Will Not Be Released from Facility Until Measures Have Been Taken to Ensure That Contamination Levels Do Not Exceed DOT Limit ML20009B6621981-06-19019 June 1981 Issues Amend 17 to License SNM-7 Adding Condition 26 to Incorporate Decontamination/Decommissioning Plans Described in 781122,1215,790425 & 801001 & 1215 Submittals.Amend Also Adds Condition 22 to License 34-06854-05 ML19347F5691981-05-14014 May 1981 Advises Refund Is Forthcoming for Overpayment on Amend MPP-1 to License SNM-7,issued on 801222 Per 800522 Application. Amend Added Section 12 Re Physical Protection Requirements ML19345H3051981-05-14014 May 1981 Informs That Fee Will Be Required to Review Request for Approval of Spent Fuel Shipment Route ML19352A7711981-04-28028 April 1981 Responds to 810406 Request.All Present License Conditions Are Deleted,Effective Immediately.License Conditions 2.1 & 2.2 Are Added to Amend MPP-1,as Reflected in Encl ML19350D1741981-04-0606 April 1981 Confirms 810409 Meeting to Discuss Instances of Employee Overexposure to External Radiation & Health Physics Performance in Hot Cell Lab ML20003C5871981-02-20020 February 1981 Forwards Organizational Charts Depicting NRC Region 3 Reorganization,Effective 810216 ML19350B5541981-02-11011 February 1981 Forwards Order Re Mod of Licenses SNM-7 & 34-06854-05, Requiring Preparation & Submission of Radiological Contingency Plan ML19341B4181981-01-19019 January 1981 Advises of Forthcoming Partial Amend Fee Refund Re 801031 Withdrawal of 780817 Application ML20126H3231980-12-22022 December 1980 Advises That Physical Security Plan Submitted 800522 Is Approved.Plan Should Be Implemented within 30 Days of Receipt of Ltr.Encl to Withheld (Ref 10CFR2.790) ML19350D5361980-12-0808 December 1980 Responds to 801031 Withdrawal of Request for Amend to Licenses SNM-7 & 34-06854-05.Licensee 780817 Request Re Upper Limits of Radioactivity in Hot Cell Storage Pool Is Void.Proposed Nonroutine Pool Conditions Will Be Reviewed ML19341B7301980-12-0808 December 1980 Informs That Due to Withdrawal of 780817 Request for Amend to Licenses SNM-7 & 34-06854-05,temporary Departure from Upper Limits of Radioactivity in Hot Cell Storage Pool Considered Void ML19343A8431980-11-10010 November 1980 Confirms Arrangements for 801112 Meeting to Discuss Item of Noncompliance & Related Issues Involving Shipment of Spent Fuel Cask in Jul 1980 ML20030A3221980-10-0606 October 1980 Approves Proposed Route for Transport of Spent Reactor Fuel, in Response to 800812 Request.Encl Arrangements & Approved Route ML19338D5111980-08-21021 August 1980 Forwards IE Circular 80-20, Changes in Safe-Slab Tank Dimensions. No Written Response Required ML19320D0721980-07-0202 July 1980 Notifies of Fee Required for Review of 791218 Request for Route Approval for Shipment of Monticello Spent Fuel ML19320C7141980-06-24024 June 1980 Forwards IE Circular 80-14, Radioactive Contamination of Plant Demineralized Water Sys & Resultant Internal Contamination of Personnel. No Written Response Required ML19323H3721980-06-0202 June 1980 Advises That Major Safeguards Amend Fee Is Required for Review of Physical Protection Plan Submitted on 800522 1990-02-12
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20212J3731999-06-25025 June 1999 Responds to Re Annual Fee Invoice AM4270-99 & Fee Categories Assigned to License SNM-7.Fee Category 3O on Invoice AM4270-99 Erroneously Issued & Has Been Canceled. Payment Received & Invoice Revised & Considered Paid ML20207D4741999-05-27027 May 1999 Forwards Insp Rept 70-0008/99-01 on 990414-15.No Violations Noted.Based on Results of Insp,Nrc Did Not Identify Any Radioactive Matls in Excess of NRC Release Guidelines for Unrestricted Use ML20207D0421999-05-26026 May 1999 Discusses Which Provided Info Re Battelle Memorial Inst Special Nuclear Matl Possession Limits,Per 990121 Request.Sum Quantities of Special Nuclear Matl Would Exclude Transfer of SNM-7 License to State of Oh ML20199J9311999-01-21021 January 1999 Submits RAI Re Bcl Decommissioning Project Request to Change Decommissioning Schedule & Other Listed Subj Matters.Respond to Request within 15 Days from Date of This Ltr ML20199D8461999-01-11011 January 1999 Discusses Insp Rept 70-0008/98-03 on 981215-17.No Violations Were Identified.Insp Consisted of Observations & Evaluations of on-going Decommissioning Activities Including Reviews of Environ Monitoring Sys & Controls & Radiation Protection ML20198D5001998-12-14014 December 1998 Forwards Insp Rept 70-0008/98-02 on 981116-18 & 1211.No Violation Noted.Purpose of Insp Was to Determine Adequacy of Confirmantory Survey Conducted by Orise in Building 2 ML20206N4301998-12-14014 December 1998 Forwards Insp Rept 70-0008/98-01 on 981116-18 & 1211.No Violations Noted.Insp Consists of Radiological Surveys,Used by NRC to Evaluate Orise Effectiveness in Conducting Its Confirmatory Survey & Releasing Bldg for Restricted Use ML20195J6221998-11-23023 November 1998 Responds to Indicating That Battelle No Longer Disputes Listed Invoices & That Payment Sent ML20195E2121998-11-17017 November 1998 Responds to Re Receipt of Overdue Notices for Listed Invoices ML20237A7281998-08-13013 August 1998 Ack Receipt of Disputing Fee Categories for Invoice AM4515-98.Interest-fee Waiver Period Being Extended Until Issues Raised in Subj Ltr Resolved.Review & Analysis of All Activities Under License SNM-7 Completed ML20236R8581998-07-17017 July 1998 Refers to 980529 & 0717 Ltrs Re Battelle Memorial Institute Characterization & Final Status Surveys for Building KA-7 North ML20247N8071998-05-18018 May 1998 Requests Info Which Demonstrates That Funding for Battelle Decommissioning Project Will Be Maintained,Such That It Will Meet Scheduled Commitment W/Agency ML20217P7131998-05-0404 May 1998 Discusses Insp Rept 70-0008/98-01 on 980408-10.No Violations Noted.Insp Consisted of Observations & Evaluations of on-going Decommissioning Activities.Conduct of Activities Characterized by safety-conscious Decommissioning Operation ML20198N2051997-10-29029 October 1997 Forwards Insp Rept 70-0008/97-02 on 970825-27.No Violations Noted.Purpose of Insp Was to Determine Adequacy of Decommissioning Activities Conducted in Bmi Bldgs 1,6 & 7 as Authorized by Bmi License ML20134G7181997-02-0505 February 1997 Forwards Insp Rept 70-0008/97-01 on 970106-10.No Violations Noted ML20029D1941994-04-26026 April 1994 Forwards Safety Insp Rept 70-0008/94-01 on 940131-0325 & Notice of Violation.Licensee Radiation Protection Program Found to Be Adequate to Protect Radiological Safety of Employees & Public ML20058N0301993-12-15015 December 1993 Discusses Safety Insp of License SNM-0007 on 931108-10.No Violations Noted.Major Areas Inspected:Activities Conducted Under License Re Radiation Safety & Compliance to Commission Rules & Regulations ML20058G5351993-12-0606 December 1993 Advises of Completion of Review of Decommissioning Plan for Battelle Memorial Inst Columbus Operations. Program Adequate & Acceptable.Clarifying Info Requested Re Section 2.1.3.4.4, Soil Remediation ML20057E6201993-10-0505 October 1993 Forwards Amend 4 to License SNM-7,authorizing Lower Possession Limit & Possession & Use of Small Piece of Spent Fuel ML20056G6431993-08-30030 August 1993 Forwards Insp Rept 70-0008/93-01 on 930727-29.No Violations Noted ML20035B8251993-03-26026 March 1993 Notifies That Nrc,Ofc of Nuclear Matl Safety & Safeguards, Responsibility for Licensing of Facility Has Been Transferred from Fuel Cycle Safety Branch to Division of Fuel Cycle Safety & Safeguards ML20057A7101992-02-25025 February 1992 Forwards Executed Contract NRC-04-92-047 ML20062G8911990-11-0202 November 1990 Requests Response as Described in Encl Demand for Info within 30 Days ML20055C9401990-05-0707 May 1990 Forwards Response to Questions Re Decommissioning of Pu Facilities ML20006F2361990-02-12012 February 1990 Forwards Safety Insp Rept 70-0008/90-01 on 900116-18.No Violations Noted ML20247L4801989-09-13013 September 1989 Forwards Safety Insp Repts 50-006/89-02 & 70-0008/89-02 on 890627-30.No Violations Noted ML19327B4071989-06-28028 June 1989 Advises That NRC Form 327s Forwarded to NMSS or Region II Ofc to Be Marked as 10CFR2.790(d) or Natl Security Info ML20246P7591989-03-22022 March 1989 Forwards Safety Insp Repts 70-0008/89-01 & 50-006/89-01 on 890214-16.No Violations Noted ML20207K2041988-09-23023 September 1988 Requests Addl Info Re 880805 Application for Amend to License SNM-7,authorizing Controlled Field Studies Using Up to 3 Ci C-14 Labelled Compounds ML20153G6241988-09-0101 September 1988 Ack Receipt of 880314 Application for Renewal of License SNM-7.Existing License Will Not Expire Until NRC Determination Re Renewal Made ML20153F4651988-09-0101 September 1988 Forwards Insp Rept 70-0008/88-02 on 880719-20.No Violations Noted ML20154L9171988-05-12012 May 1988 Discusses Fees Required for Renewal of License SNM-7 & Confirms 880401 Telcon.Should Company Decide to Discontinue Incineration Authorization,Facility Should Send Written Request to NRC ML20151X0041988-04-27027 April 1988 Forwards Safety Insp Repts 50-006/88-01 & 70-0008/88-01 on 880404-07.No Violations Noted ML20151V6851988-04-20020 April 1988 Responds to Submitting Ltr of Notification to Cover 21 Shipments of Noncompressible Radwaste.Ltr Should Be Augmented W/Shipment Specific Info Inaccordance w/10CFR71.97 Requirements,Per 880418 Telcon ML20236W8781987-12-0303 December 1987 Responds to Re Fulfillment of DOE & NRC Responsibilities for Decontamination & Decommissioning of Bmi Hot Cell Trust Fund.Nrc Confirmatory Survey Will Depend on Bmi Final Radiological & DOE Confirmatory Survey ML20236N4571987-11-10010 November 1987 Forwards Safety Insp Repts 50-006/87-03 & 70-0008/87-03 on 871019-23.No Violations Identified ML20236W9061987-09-23023 September 1987 Responds to Re Bmi Need for NRC Current Ltr Approving Decommissioning Plan Referred in Trust Agreement. DOE Accepted Responsibility for Cleanup of Contamination at Bmi & DOE Will Provide Majority of Funds ML20235E3321987-09-23023 September 1987 Reconfirms NRC Approval of Decommissioning Plan Referred to in Trust Agreement,In Response to Recipient . Commitment to Provide Funds for Decommissioning Plan Made Condition of License SNM-7 w/830429 Renewal of License ML20235C4691987-09-16016 September 1987 Notifies That Region II Sponsoring One & one-half Day Nuclear Fuel Cycle Licensee Workshop on 871027-28 in Atlanta,Ga.Workshop Will Bring Together NRC Officials & Fuel Cycle Licensee Representatives to Discuss NRC Programs ML20237G2291987-08-11011 August 1987 Forwards Branch Technical Position on Disposal or Onsite Storage of Thorium or U Wastes from Past Operations,Per 870623 Meeting.Nrc Prepared to Respond to Battelle Hot Cell Trust Funds Upon Receipt of Request ML20234F5731987-07-0101 July 1987 Responds to FOIA Request for Documents Re Plutonium Accountability at Listed Facilities.Forwards App a Documents.Documents Also Available in Pdr.App B Documents Partially Withheld (Ref FOIA Exemptions 3 & 4) ML20215J9581987-06-16016 June 1987 Partial Response to FOIA Request for Documents Re Maxey Flats Area of Fleming County,Ky.Forwards App C & D Documents.App C,D & E Documents Available in PDR ML20214X3771987-06-0909 June 1987 Forwards Safety Insp Repts 70-0008/87-02 & 50-006/87-02 on 870518-22.No Violations Noted ML20214T6011987-06-0202 June 1987 Forwards Amend 2 to License SNM-7,revising Condition 23 to Include Reactor in Financial Plan for Decommissioning & Adding Condition 27 to Require Radiological Monitoring. Safety Evaluation & Environ Assessment Encl ML20207R8201987-03-16016 March 1987 Forwards SAI81-307-WA, Environ Impact Assessment,Bmi for Ref Used as Background Source of Info & Basis for Description of Site & Surrounding Environ for Vol Reduction Demonstration Facility ML20212L0891987-03-0505 March 1987 Forwards Corrected Annex a, List of Effective Pages to License SNM-7 ML20212L1341987-03-0303 March 1987 Forwards Amend 1 to License SNM-7,authorizing Operation of Vol Reduction Demonstration Facility.Revised Pages 2.1-2.5 of Part II of Application for Renewal Should Be Submitted When Facility Installation Initiated ML20210S2971987-02-10010 February 1987 Forwards Safety Insp Repts 50-006/87-01 & 70-0006/87-01 on 870112-16 & Notice of Violation ML20210S7771986-10-0101 October 1986 Forwards Safety Insp Rept 70-0008/86-02 on 860908-11.No Violations Noted ML20206N1591986-06-24024 June 1986 Forwards Environ Assessment of Bmi Vol Reduction Demonstration Facility in West Jefferson,Oh,In Response to 830815 Application to Amend License SNM-7.Finding of No Significant Impact Will Be Forwarded 1999-06-25
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9 Gentlenen:
h h, ' ' ?O-N AS The purpose of this letter is to transmit for your infonnatioh the __- N final increment of the analysis of the effects of natural phenomena;j relative to your Duilding JN-1B at West Jefferson, Ohio. The subject increment of analysis is the risk associated with postulated plutoniaa releases from your West Jefferson, Ohio plant as a result of severe natural phenomena. The NRC staff has endorsed this final version of the
(
review for application in succeeding analyses. However, we will consider challenge of our position when supported oy credible technical bases.
Any questions you may have on the enclosed analysis should be eddressed to Ja:nes E. Ayer of this Branch.
Sincerely, Oricinal signed by Leland C. Rouse /
l Leland C. Rouse, Chief Advanced Fuel and Spent Fuel Licensing Branch Division of Fuel Cycle and Material Safety i
Enclosure:
l Risk Analysis of Postulated Plutonium j
Releases from the Battelle Memorial Institute Coluabus Laboratories, Building JN-1B, West Jefferson, Ohio as a Result of Tornado Winds abd Earthquakes 8204250/78
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concurrence copy to be returned to FBrown SS 396 Docket File 70-8 PDR MAR 2 31982 w.o encl NMSS R/F FCAF R/F Docket flo. 70-08 LA File Project M-3 RECunningham TFCarter LCRouse MEMORANDUM FOR:
Leland C. Rouse, Chief JEAyer Advanced Fuel and Spent Fuel LiG80dMd#tanch FR0tt:
J. E. Ayer/W. Burkhardt Advanced Fuel and Spent Fuel Licensing Branch
SUBJECT:
RISTs ANALYSIS OF POSTULATED PLUT0NIUM RELEASES FROM BATTELLE MEMORIAL INSTITUTE BUILDING JN-1B FACILITIES AT WEST JEFFERSON, OHIO, AS A RESULT OF TORNADO WINDS AHD EARTHQUAKES The subject report prepared by Probabilistic Analysis Staff, Office of Nuclear Regulatory Research, is attached. The purpose of this memorandum is to recommand acceptance of the attached review as a final increment of the analysis of the effects of natural phenomena upon the Battelle Memorial Institute Columbus Laboratories, Building Jil-1B, West Jefferson, Ohio.
We recommend that this review including its summary and conclusions be adopted as a staff position subject to your approval. Subsequent to your approval we will make copies available to the public and to Battelle in accordance with review and documentation procedures agreed upon and described in our February 10, 1977 memorandua to R. M. Bernero.
t.1 h; J:
m-
,a J. E. Ayer Advanced Fuel and Spent Fuel Licensing Branch en i.n ;y s!. m.o.c.rd t.
W. Burkhardt Advanced Fuel and Spent Fuel Licensing Branch Oricini signaciby Leland C. Rouse Leland C. Rouse, Chief Advanced Fuel and Spent Fuel Licensing Branch Division of Fuel Cycle and Material Safety
Enclosure:
As stated s
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RISK ANA1.YSIS OF POSTULATED PLUT0NIUM RELEASES FRON THE BATTELLE MEMORIAL INSTITUTE FACILITIES AS A RESULT OF HIGH WINDS AND EARTHQUAKES INTRODUCTION The Nuclear Regulatory Commission has sponsored a program to estimate the potential hazard to the general population as a result of the impact of high winds and earthquakes on the Battelle Memorial Institute Facilities at West Jefferson, Ohio.
This paper outlines the procedures used in combining the results of various increments of analysis obtained in this study to produce a measure of risk. The risk measure presented in this paper is the probability per year that a high wind or earthquake will result in doses above specific levels (complementary cumulative distributions).
The two organs, lungs and bone, were chosen for the dose exceedance probability calculations since these organs are significant and generally dominate the 50-year committed dose equivalents from inhalation. The doses were calculated for the population within a 80 km (50-mile) radius of the plant and for the nearest residence located downwind of the plant. Four tornado wind speeds, 33.5 m/s, 42.5 m/s, 51.4 m/s,134 m/s, and one earthquake event, greater than.25g, were elevated for the analysis.
TORNADO WIND SPEEDS The estimated probabilities for the postulated tornado wind speeds were obtained from T. T. Fujita (Ref.1).
The frequency, F-scale, and associated wind speeds of historical tornadoes are also provided in Ref.1.
1 A
-- _.. _ - -.. ~ - -
-2 To obtain confidence bounds on the probabilities of postulated wind speeds, an error factor of 3 was assumed for the 33.5 m/s windspeed and an error factor of 10 was used for the remaining windspeeds. Assuming that the postulated tornado wind speeds occur in accordance with a Poisson process, the error factor of 10 will, to an order of magnitude accuracy, provide conservative 90% confidence bounds for wind speed occurrence probabilities 4
within the wind speed range of the observed data with one or more points.*
Estimates of complementary cumulative tornado wind speed probabilities and associated confidence bounds are provided in Table 1.
EARTHOUAXES One earthquake event was considered in this analysis.
The earthquake event consisted of a peak ground acceleration level in excess of.25g.
Probabilities vs. peak acceleration with estimated standard deviations (c) were obtained from Ref. 2 and are provided in figure 1.
Table 2 presents peak ground acceleration vs. cc probabilities and associated uncertainty bounds for the earthquake event. For the accompanying risk analysis, the
]
bounds on the probabilities were modified to a factor of 10 for the earthquake event. These modified factor of 10 bounds, in general, include more than 2a variations from the best estimate probability and are conservative ( >90%). The exact confidence represented by the bounds is not critical to the subsequent risk analysis.
- These 90% confidence bounds will in 90% of the cases cover the true wind speed probability if the assumed model and distributions are correct.
. TABLE 1 A.
COMPLEMENTARY CUMULATIVE (cc) PROBABILITIES OF TORNADO WIND SPEEDS AND ASSOCIATED CONFIDENCE LIMITS Tornado Wind cc Probability Conservative 90% Confidence Speed per year Bounds on the Probability 33.5 m/s 1.5E-1 (5.0E-2,4.5E-1) 42.5 m/s 4.0E-3 (4.0E-4,4.0E-2) 51.4 m/s 3.0E-4 (3.0E-5,3.0E-3) 134.0 m/s TABLE 2 B.
EARTHQUAKE PROBABILITY AND ASSOCIATED UNCERTAINTY Peak Ground Probability Approximate 90% Bounds Acceleration per year on the Probability
.259 5.0E-4 (5.0E-5,5.0E-3)
~
.j-10,000
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8 10 12 14 PEAK HORIZONTAL ACCELERATION (% g)
FIGURE I RETURN PERIODS FOR SEISMIC ACCELERATION AT THE BMI WEST JEFFERSON FACILITY TERACORPORATION O
CC CURVES FOR CONSEQUENCES FROM ACCIDENTAL RELEASES The 50-year committed dose equivalent from inhalation following a natural phenomena event of tornadoes or earthquakes were calculated by Jamison and Watson (Ref. 3) and presented in Table 3.
Table 3 provides the dose to the nearest resident and to the population within a 80 km (50-mile) radius of the plant from tornadoes and earthquakes. The table provides calculations of doses using most likely, and conservative estimates for l
I the source releases and dispersion (meterological). The most likely estimates were computed using the median (50%) values for source releases and dispersions and were assigned a probability of 0.95.
(Themedian l
value was used as the approximate midpoint of the probability interval l
f rom 0 to 0.95). The conservative estimates were calculated using 95%
4 values and were assigned a probability of 0.05.
The probabilities of possible sources and the probability of possible dispersions were thus-discretized into two intervals, O to 0.95 represented by the median value and 0.95 to 1.0 represented by the 95th percentile. This breakdown of probabilities is gross, and care should be taken in interpreting any subsequent risk results to no more than an order of magnitude type of-precision.
u i
Figures 2 and 3 give the step function cc curves of doses to lungs and bones for the population within an 80 km (50-mile) radius of the plant due to damage from tornadoes. These complementary cumulative distributions give the probability per year that tornado-induced damage will result in doses greater than various s.alues shown in the figures.
Figures 4 and 5 provide the corresponding cc distributions of nearest resident doses for high winds.
Figures 6 through 9 contain the corresponding step function cc distributions for earthquakes. These cc step functions and associated appro;imate confidence bounds have a similar interpretation as those presented for tornadoes.
e
TflBLE 3 FIFTY-YEAR BEST-ESTIMATE COMMITTED DOSE EQUIVALENT FROM INHALATION FOLLOWING SEVERE-WIND AND EARTHQUAKE EVENTS (CLASS Y MATERIAL) a Population Dose (person-rem)
Case b Case Case Case Event Organ I (0.90)
II (.048)
III (.048)
IV (.0025) c 33.5 m/s Lungs 4.6-6
?,1-5 4.6-5 2.1-4 Wind Bone 7.9-6
?.7-5 8.0-5 3.7-4 4.25 m/s Lungs 5.1-6 2.6-5 2.2-3 1.3-2 Wind Bone 8.9-6 4.5-5 3.9-3 2.3-2 h
51.4 m/s Lungs 3.0-4 1.3-3 7.6-3 5.7-2 Wind Bone 4.8-4 2.1-3 1/2-2 9.1-2 134 m/s Lungs 9.3-2 9.3-1 3.7+0 3.7+1 Tornado Bone 1.6-1 1.6+0 6.5+0 6.5+1 i
Earthquake Lungs 1.2-2 3.4-2 4.6-1 1.3+0
>0.25g Bone 2.1-2 6.0-2 8.0-1 2.3+0 a
Population within a 80-km radius of the plant bCase (parenthetical values are approximate probabilities):
I - Most likely release (0.95) and most likely dispersion (0.95).
II - Most likely release (0.95) and conservative dispersion (0.05).
III - Conservative release (0.05) and most likely dispersion (0.95).
IV - Conservative release (0.05) and conservative dispersion (0.05).
cScientific notation: 4.6-6 = 4.6x10-6
.. ~ _ _.
TABLE 3(CONTINUED)
Dose at Nearest Residence
( rem)
Case b Case Case Case Event Organ I (0.90)
II (.048)
III (.048)
IV (.0025) c 33.5 m/s Lungs 1.1-9 4.7-9 9.7-9 4.7-8 Wind Bone 1.8-9 8.2-9 1.7-8 8.2-8 4.2-5 m/s Lungs 1.3-9 6.7-9 6.3-7 4.2-6 Wind Bone 2.2-9 1.2-8 1.1-6 7.2-6 51.4 m/s Lungs 6.7-8 2.7-7 2.3-6 1.8-5 i
Wind Bone 1.1-7 4.4-7 3.7-6 2.9-5 i
134 m/s Lungs 1.2-6 1.2-5 4.9-5 4.9-4 Tornado Bone 2.1-6 2.1-5 8.5-5 8.5-4 Earthquake Lungs 4.6-6 2.8-5 1.8-4 1.1-3
> 0.259 Bone 7.9-6 4.8-5 3.1-4 1.9-3 bCase (parenthetical values are approximate probabilities):
I - Most likely release (0.95) and most likely dispersion (0.95).
l II - Most likely release (0.95) and conservative dispersion (0.05).
~
III - Conservative release (0.05) and most likely dispersion (0.95).
IV - Conservative release (0.05) and conservative dispersion (0.05).
Scientific notation: 1.1-9 = 1.1 x10-9 c
_g.
TORNR00 RISK RNALYSIS FOR BMI. POP. LUNG UNSM00THE0 CC0F 100 i
7
^
5 3
c' 10-1 i 2,
^
^
3 i
ID g
10-2 1 w
q, m
m
- u e,
3 E
Ei 10-3 t e
3
^
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OS 10-4 t A
7; "r,
tu v)
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10-6 i O
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p
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10-7
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r 10-9,i 5
m 3
10-10 t 7
s 3
10-11 i l 3 '
g 0-s ' #1'0-5
' 1'0-4
' 1'0-3 1'0-2 t'0-1 1'00
'l
' ' t'0 1
1'02 50 YR DOSE COMMITMENT (PERSON-REM)
FIGURE 2 L
. TORNADO RISK.BNALYSIS FOR BMI. POP. BONE UNSM00THED CCDF 100 i
l L
3 0
10-1 i
?
m n
3
^
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10-2 i N
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10-10 t 7
s 3
- l 10-11 i
' t'0-1 1'00 1'01 1'02
~
3 5 10-6 50 YR DOSE COMMITMENT (PERSON-REM)
FIGURE 3
. TORNA00 RISK RNRLYSIS FOR BMI. N.R. LUNG UNSM00THE0 CC0F 100 i,
7 5 e 3
S 10-1 1 i
7 s e A
3 1
O e
10-2 1 seu f
=
m g!
t 3
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l m
3
^
^
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e c
10-4
,i A
c O!
Ltj 3
= d g
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U 10-5 O
O
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1 G G O
m 10-6,
p g
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~
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Gs e,
n 00 3
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n i
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s m,
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s' i
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'10-8 10-7
'T
' 1'O s
' ' '0 -5
' l'0-4 10-3 l'0-2 1
l 50 YR DOSE COMMITMENT (PERSON-REM)
FIGURE 4
_ _ _ _ _ _ T TORNADO RISK ANALYSIS FOR BMI. N.R. BONE UNSM00THED CCDF 100 3
0 10-1 t E
5 A
3 Aa O
O 10-2 i ww f
m m
3 35 a
a 10-3 i O
7 s
e
=
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X s
10-4 1 A
s 3
11.1 3
g a
3 v
v O
10-5 a
,t I
s 11-3 a s O
10-5 E
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10-7,i o-.
au g
g s
D 3
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e J
^
10-8 1
?
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e 10-10 i 7
J 3
=
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10-8 10-8 1'0-7 1'0-8 l'0-5 l'0-4
' 1'0-3
' ' 1'0 -2 50 YR DOSE COMMITMENT (PERSON-REM)
FIGURE. 5
. EARTHQUAKE RISK RNALYSIS FOR BMI. POP. LUNG UNSM00THE0 CCDF 10-2 1 7
s A
3 10-3 1 7
s e
A X
A 10-4 i y
N 7
O s
=
9 L1-3 O
O
}--
10-5 i
._I b--e 7
m S
T
~
CD O
3 D
CE' Q
O 10-8 1 7
2 3
m 10-7 i 1 10-2 t'0-1 l'00 l'01 50 YR DOSE COMMITMENT (PERSON-REM)
Figure 6 u.
e 9 ERRTHQURKE RISK ANALYSIS FOR BMI. POP. BONE UNSM00THED CCDF 10-2 i
?
5 A
3 10-3 1 7
5 O
x A
I 10-4 i y
CD 7
Oo s
O L1_
3 O
O A
l-
"_.J 10-5 t H
7 O
r m
s CD O
3 U
M O_.
e 10-6 i 7
5 3
O
(
)
10-7 6 1 3
50 YR DOSE COMMITMENT (PERSON-REM)
FIGURE 7
7
~
. ERRTHQURKE RISK RNALYSIS FOR BMI.N.R. LUNG tlNSM00THED CC0F 10-2 1 7
s e
3 5---
10-3 i 7
s c
3 a
X A
10-4 i w
O 7
O a
s L1-3 o
e H
10-5 i
-.J M
7 D
n 5
g 00 0
3 U
QC 0.-
e 10-6 1 7
s 3
m 10-7 1 5
-t'0-1 10-6
' t'0-8 l'0-4 l'C-3 l'0-2 1
50 YR DOSE COMMITMENT (PERSON-REM)
FIGURE 8
. EARTHQUAKE RISM ANALYSIS FOR BMI.N.R. BONE UNSN00THED CCDF 10-2 7
5 A
3 10-3 i 7
d' 5
O
,k X
A 10-4 i y
V)
Oa s
=
c' Ls-3 iD O
F-10-8 i
_I k-e 7
e nt m
O 3
ID g
CL e
10-s t 7
5 3
m 10-7 i 30-6
' g'0-8 l'0-4
' l'0-3
' l'0-2 l'0-1 i
50 YR DOSE COMMITMENT (PERSON-REM)
FIGURE 9
For all figu: es, the confidence baunds on the smallest dose paint included in the cc summation were used as the confidence lounds for the cc distribution.
' This appr:7.imation assumes the ce probability is dominated by the probability of the snallest dase point.
If the assumption is rot true (e.g., at smallest dare values of the cc curve) then the confidence baunds may be somewhat conservative.
The confidence haunds used are those given earlier and summarized in Table 2.
Because of the approximations used in obtaining them, the confidence bour.!s should be interpreted as only indicating the order of magnitude precision associated with the cc
~
curves.
Figures 10 through 17 present the step function cc curves obtained by applying isotonic regressions to the probability mass functions (probability versus dose) used to construct the basic cc curves in Figures 2 through 9.
The isotonic curves in Figures 10 through 17 are thus smoothed versions of the basic step function cc curves in Figures 2 through 9.
Isotonic regression is a nonparametric raethod of smoothing the basic step function cc curves which does not require assuming specific distribu-tion fonns for the cc curve. -(Other approaches are called parametric approaches and involve, for" example, assuming that a Weibull distribution g
i-fits the points and then finding the parameter:, of the best Wei!' !l.)
Since the isotonic regression does not require as many assumptions as j
the parametric approaches, it is raa.re suited to situations where there are relatively few points calculated for;the cc curve--as was the case in this analysis.
The isotonic regression approach, however, dces have the disadvantage that it still produces step functions and nat smooth.
L
continuous curves.
The isotonic regression methad is explained in Sreater detail in the appendix to this report.
RISK TABLES Table 5 tabulates the risk, defined as pro $ ability times consequence for the various events analyzed in Table a.
The risk tables indicate the contribution to the total risk from the various events considered.
The total risk is the sum of the.various contributions.
The error factors on the risk contributions are roughly the error factors on the probability for the event, assuming.the uncertainties on the probability estimates dominate (or at most, are comparable to the consequence uncertainties.*
e h
y l
'l
.' i l-p 3
"The error factors are the upper confidence level divided by the best 9>
estimate divided by the lower confidence bound.
1 n
TORT 4RDO RISK Rt4RLYSIS FOR BMI. POP. LUNG i
SM00TliED CCDF 100 i
_ j_
.I i
3 O
10-1 i 7
T s
_t;_-_
-e r
g i
10-2 3 i
7
_-4).
r Tg).
. _.. A q_
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10-3 1 m
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s t
wl I
3
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a
[]
)
10-4 1 7
y Z
1 3
3 10-5 1 n
7 t
3 g3 e
3 10-s 1
-f3 n 2 c
_ i_
=
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a__
m m
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- O o
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o 7
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s 3
n 10-8 i O
f
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TZZ 3
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3
- 3 ___
t I
1 0-11.i s.i 3
s,,
3 s,,
3 s,i 3 s,i 3
..2 10-1 100 s,,1 3 s.,2 10-8 10-5 10-4 10-3 10-10 10 50 YR DOSE COMMITMENT (PERSON-REM)
FIGURE 10 t
l.
(
(
\\
6
_ _ _. TORNADO RISK ANALYSIS FOR BMI. POP. BONE SMOOTHED CCDF 100 t
7 r,
3 D
10-1 1
?,
._,.."~
+5 3
0 L_n S
10-2 1,
i t
m'-t)
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()
<]
+3 m
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)
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()
(n H)
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s Lt_
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)
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3
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a 3
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r,
3 m,
10-11 i 10-6 l'0-6 10-4 1'0-3 1'0-2 10-1
' t 0'0 1'01 1'02 3 '
50 YR DOSE COMMITMENT (PERSON-REM)
FIGURE 11
TORNADO RISK RNM TSIS FOR BMI. N.R. LUNG St10DTHED CCDF 100
~
r 71'--.
_ _1 1" _ -
s e l
3 E) 10-1 4 j s a 3
-dL b_
10-2 i y -Ep
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+
10-5 1 Q
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3 $ #
g0-9 t0-8 t'0-7 l'0-8 10-5 l'0-4 l'0-3
' l'0 -2 50 YR DOSE COMMITMENT (PERSON-REii)
FIGURE 12
- lu
, TORNADO RISK ANRLYSIS FOR BMI. N.R. BONE SMOOTHED CCDF 100 1
I 7
s n
J
---O 10-1 i T
7 5 d3' O
'4 3 _Q Ws k
10-2 1
^
n 2
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.--n 10-3 t l
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i
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A s'
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LU W
a r
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{m
---:]
o a
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5 a
t
}
T-O g
L
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F-5 m
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~
r, CD 7
5 CE CD 3
O Cr-10-8 i CL 7
s q
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10-8 i 7
C 10-10 i 7
5 3
r, w
10-11 1 '0 -8 3
t l'0-8
' t'0-7 l'0-6
' ' t'0-5 l'0-4 l'0-3
' ' l'0-2 50 YR DOSE. COMMITMENT (PERSON-REM)
FIGURE 13
EARTHOURKE RISK BNRLYSIS FOR BMI. POP. LUNG SH00THED CCDF 10-2 i
7 5 4 3
10-3 i 7
s -C, 3
g X
A 10-4 i y
(n Og 5 _{3_____._.. ')
Lt.
3
, )- ---
O
>~
I-
"_J 10-5 i s
1
(
.()
C 03 O
3 j.
r Of 0-()
l 10-6 i 7
b l
t l
[]
f 10-7 1 10,1 i 3
s i
3 s
10-2 10-1 100 4
50 YR DOSE COMMITMENT (PERSON-REM)
FIGURE 14 1
. EARTHQUAKE RISK ANALYSIS FOR BMI. POP. BONE SMOOTHED CCDF 10-2 1 3
5 3
10-3 i 7
s O
3
=
X A
10-4 w
W 7
O O
s 0
b_
3 O
O g
_m_
10-8 J
~
7 O
l.
e r,
g 00 0
3 J,
g a.
O 10-6 i 7
5 3
O 10-7
- '0-2 t'0-1 100 l'01 3
5 l
50 YR DOSE COMMITMENT (PERSON-REM)
FIGURE 15
0 9
EARTHOURKE RISK ANALYSIS FOR BMI.N.R. LUNG SN00 tiled CCDF 10-2 7
r, 3
10-3 1 r,
(l
_ _ _.. _ +-
3 10-4 1
-)
3 r,
l+
.... O c
3 g
0 v.
10-s i h
O O
3 i
r O
10-s i 7
=-
3
[3 t o-'
L a,
s ;,
3 50 YR DOSE COMMITMENT (PERSON-REM)
FIGURE 16 EURTHQUAKE RISK ANALYSIS FOR BMI.N.R. BONE SMOOTHED CC0F 10-2 1 7
5 J.
3 10-3 1 7
's C
3 X
A 10-4 i w
W 7
O s
O m
1 3
O
- )
_m-g 10-5 i
~
.-I e-.g 7
O r
i r,
g
.r.
{-
Q3 o
3
_v, 3
E i
O O
10-s i 7
r, 3
)
10-7 g'0-6
' g'0-5 l'0-4 l'0-3 l'0-2 l'0-1 50 YR DOSE COMMITMENT (PERSON-REM)
FIGURE 17
TABLE 4
^
RISK TO NEAREST RESIDENT AND NEARBY POPULATION FROM POSTULATED DAMAGE DUE TO NATURAL PHEN 0MENA a
Population Dose (person-rem / year)
Case b Case Case Case Event Organ I (0.90)
II (.048)
III (.048)
IV (.0025) c 33.5 m/s Lungs 6.21-7 1.50-6 3.28-6 7.88-8 Wind Bone 1.07-6 2.64-6 5.70-6 1.39-7 (1.5x10-I/yr) 4.25 m/s Lungs 1.84-8 4.99-9 4.22-7 1.3-7 Wind Bone 3.20-8 8.64-9 7.49-7 2.3-7 (4.0x10-3/yr) r'o 51.4 m/s Lungs 8.1-8 1.87-8 1.09-7 4.28-8 Y
Wind Bone 1.30-7 3.02-8 1.73-7 6.83-8 (3.0x10-4/yr) 1.44-5 7.5-7 134 m/s Lungs 8.37-9 4.46-9 1.78-8 9.25-9 Tornado Bone 1.44-8 7.68-9 3.12-8 1.63-8 (1.0x10-7/yr)
Earthquake Lungs 5.4-6 8.16-7 1.10-5 1.63-6
> 0.25g Bone 9.45-6 1.44-6 1.92-5 2.88-6
( <5.0x10-4/yr) aPopulation within an 80-km radius of the plant bCase (parenthetical values are approximate probabilities):
I - Most likely release (0.95) and most likely dispersion (0.95).
II - Most likely release (0.95) and conservative dispersion (0.05).
III - Conservative release (0.05) and most likely dispersion (0.95).
IV - Conservative release (0.05) and conservative dispersion (0.05).
cScientific notation: 6.21-7 = 6.21x10-7
TABLE 4(CONTINUED)
Dose at Nearest Residence (rem / year)
Case b Case Case Case Event Organ I (0.90)
II (.048)
III (.048)
IV (.00?5)_
c 33.5 m/s Lungs 1.49-10 3.35-10 6.92-10 1.76-11 Wind Bond 2.43-10 5.85-10 1.21-9 3.08-11 (1.5x10'I/yr) 4.25 m/s Lungs 4.68-12 1.29-12 1.21-10 4.2-11 Wind Bone 7.92-12 2.30-12 2.11-10 7.2-11 (4.0x10-3/yr) t 51.4 m/s Lungs 1.81-11 3.89-12 3.31-11 1.35-11 Wind Bond 2.97-11 6.34-12 5.33-11 2.18-11 5
(3.0x10'4/yr)
L 134 m/s Lungs 1.08-13 5.76-14 2.35-13 1.23-13 Tornado Bone 1.89-13 1.01-13 4.08-13 2.13-13 (1.0x10'7/yr)
Earthquake Lungs 2.07-9 6.72-10 4.32-9 1.38-9
> 0.25g '4 Bone 3.56-9 1.15-9 7.44-9 2.38-9
(< 5.0x10 /yr) b Case (parenthetical values are approximate probabilities):
l I - Most likely release (0.95) and most_likely dispersion (0.95).
II - Most likely release (0.95) and conservative dispersion (0.05).
III - Conservative release (0.05). and most likely dispersion (0.95).
IV - Conservative release (0.05) and conservative dispersion (0.05).
Scientific notation: 1.49-10 = 1.49x10-10 c
References e
1.
" Review of Severe Weather Meterology at Battelle Memorial Institute, Columbus, Ohio," The University of Chicago, report submitted to Argonne National Laboratory under Contract No. 31-109-3731, 30 September 1977.
2.
" Seismic Risk Analysis for Battelle Memorial Institute Nuclear Research Facility, West Jefferson, Ohio," TERA Corporation, Berkeley, CA., remrt submitted to Lawrence Livemore Laboratory, 29 December 1978.
3.
Jamison, J. D. and Watson, E.
C., " Environmental Consequences of Postulated Radionuclide Releases from Battelle Memorial Institute Columbus Laboratories, Jn-1B Building at the West Jefferson Site, as a result of Severe Natural Phenomena." Battelle-Pacific Northwest Laboratory, PNL-4099, November 1981.
4.
Barlow, R. E.,
et. al., Statistical Inference Under Order Restrictions, The Theory and Application of Isotonic Regression, John Wiley and Sons, London,1972.
l
A-1 APPENDIX.
ISOTONIC REGRESSION (Ref. 5)
Isotonic regression was used to develop the risk curves in Figures 10 througlil7. The only basic assumption in an isotonic regress' ion is that the probability of dose to the populatioh or to the nearest residence is non-increasing as the dose increases. The assumption'is that the probability decreases (or is constant) as the consequence increases; which is not.an unreasonable assumption for risk analyses. We should a-note that we make the monotonic assumption on the probability.versus dose and not on the cc curve (which decreases by its definition). A general statement of our isotonic regression problem is as follows:
We are given a sequence of doses (D,...D,) where Dg 5, Dgj.
j A
i = 1.
...n-1 and we give estimates of the probability P(Dj) that the population or nearest residence receives dose Dj..We are interested in minimizing the expression:
S 2
a(Dj) - P(Dj)
D.
P g
I arong all. isotonic functions P on the sequence (Dj,...D,).
We call the function that minimizes this sum of sequences (P*) the a
isotonic regression of P.
The isotonic regression is thus similar to a least squares type of analys,is (a us0a1 regression analysis) where we impose the restri.: tion that P(D ) is non-increasing as Dg g
increases,.
1 4
A-2 The Pool-Adjacent-Violators Algorith:r was used to compute P*.
Plots of the isotonic regressions.of P* versus dose are presented in Figurds 10 through 17. The probability mass functions were used to obtain the isctonic curves.
A The isotonic regression P* of P has the following desirable properties.
A 1.
The isotonic regression P* of P mini.mizes the weighted squared error 16ss, i.e.:
~
~
^
2 n
2 P(D ).- P*(D )
Dj 5, {1 -P(Dj)
P(Dg)
D
{
g g
g i=
i=1 for any isotonic function P.
A 2.
The isotonic regression P* of P minimizes the error in the risk, i.e.:
I max n
n.
[ D P(Dj) - [1 DjP*(Dj) i j
1=1 i=
l max n
n 3
l D P (0 )
{ D P(D ) = [1 1
g 9
l g
9 1=1 i=
1 l
1 l
I
-