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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K9681999-10-19019 October 1999 Ack Receipt of Transmitting Rev 40 to Physical Security Plan for Washington Nuclear Plant 2.Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required ML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) ML17284A8711999-08-30030 August 1999 Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201 ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld ML17292B7531999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 ML17292B7511999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) ML17284A8701999-08-19019 August 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls ML17292B7501999-08-19019 August 1999 Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage ML17284A8681999-08-12012 August 1999 Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML17284A8541999-08-0202 August 1999 Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld ML17284A8531999-07-30030 July 1999 Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001 ML17284A8301999-07-22022 July 1999 Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl ML17292B7451999-07-20020 July 1999 Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties ML17292B7391999-07-16016 July 1999 Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112 ML17292B7381999-07-12012 July 1999 Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls ML17292B7171999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready ML17292B7181999-07-0202 July 1999 Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO ML17292B7161999-06-30030 June 1999 Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves. ML17292B7131999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. ML17292B7091999-06-21021 June 1999 Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790 ML17292B7041999-06-17017 June 1999 Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls ML17292B7031999-06-10010 June 1999 Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl ML17292B6841999-06-0404 June 1999 Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs ML17292B6851999-06-0101 June 1999 Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities ML17292B6831999-05-25025 May 1999 Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date ML17292B6751999-05-25025 May 1999 Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790 ML20206U4501999-05-19019 May 1999 Ack Receipt of Which Transmitted Rev 39 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required,Since Changes Do Not Decrease Effectiveness of Security Plan ML17292B6661999-05-0707 May 1999 Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility ML17292B6531999-05-0303 May 1999 Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790 ML17292B6561999-04-29029 April 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam ML17292B6421999-04-19019 April 1999 Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999 Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790 ML17292B6401999-04-13013 April 1999 Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests ML17292B6371999-04-12012 April 1999 Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS ML17292B6281999-04-0606 April 1999 Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule ML20196K6961999-03-30030 March 1999 Ack Receipt of ,Transmitting Rev 38 to Physical Security Plan for Plant.No NRC Approval Is Required,In Accordance with 10CFR50.54(p) GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999 Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1) ML17292B6131999-03-24024 March 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication ML20204F0261999-03-19019 March 1999 Forwards Insp Rept 50-397/99-01 on 990201-04 & 0303-05.No Violations Noted.Areas of Physical Security Plan Effectively Implemented with Listed Exceptions ML17292B6001999-03-16016 March 1999 Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement ML17292B5941999-03-16016 March 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld ML17284A8711999-08-30030 August 1999 Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201 ML17292B7531999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 ML17292B7511999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) ML17284A8701999-08-19019 August 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls ML17292B7501999-08-19019 August 1999 Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage ML17284A8681999-08-12012 August 1999 Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety ML17284A8541999-08-0202 August 1999 Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld ML17284A8531999-07-30030 July 1999 Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001 ML17284A8301999-07-22022 July 1999 Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl ML17292B7451999-07-20020 July 1999 Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties ML17292B7391999-07-16016 July 1999 Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112 ML17292B7381999-07-12012 July 1999 Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls ML17292B7171999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready ML17292B7181999-07-0202 July 1999 Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO ML17292B7161999-06-30030 June 1999 Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves. ML17292B7131999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. ML17292B7091999-06-21021 June 1999 Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790 ML17292B7041999-06-17017 June 1999 Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls ML17292B7031999-06-10010 June 1999 Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl ML17292B6841999-06-0404 June 1999 Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs ML17292B6851999-06-0101 June 1999 Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities ML17292B6751999-05-25025 May 1999 Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790 ML17292B6831999-05-25025 May 1999 Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date ML17292B6661999-05-0707 May 1999 Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility ML17292B6531999-05-0303 May 1999 Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790 ML17292B6561999-04-29029 April 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam ML17292B6421999-04-19019 April 1999 Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999 Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790 ML17292B6401999-04-13013 April 1999 Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests ML17292B6371999-04-12012 April 1999 Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS ML17292B6281999-04-0606 April 1999 Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999 Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1) ML17292B6131999-03-24024 March 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication ML17292B5991999-03-16016 March 1999 Informs That Listed Property & Liability Insurance Coverage for WNP-2 Is in Force,In Compliance with Licensing Responsibilities Delineated in 10CFR50.54(w)(3) ML17292B5911999-03-16016 March 1999 Forwards 1998 Environ Operating Rept, Per Reporting Requirements of Section 5.4.1 of WNP-2 Epp.No Design or Operational Changes or Tests in 1998 Involved Unreviewed Environ Question ML17292B5941999-03-16016 March 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls ML17292B6001999-03-16016 March 1999 Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement ML17292B5901999-03-11011 March 1999 Forwards Hard Copy of Addl Occupational Exposure Data Requested in GL 94-04,per 990303 e-mail.Original Electronic Version Was Corrupted ML17292B5681999-03-0101 March 1999 Forwards Radioactive Effluent Release Rept for 1998, IAW 10CFR50.36a(a)(2) & TS 5.6.3 & Complete Copy of WNP-2 ODCM Per TS 5.5.1 ML17292B5651999-02-22022 February 1999 Forwards Relief Request 2ISI-20,proposing Alternate Exam Expected to Reduce Dose Significantly & Still Provide Adequate Safety & Quality.Attached Relief Request Will Be Used to Support ALARA Dose Reduction Efforts During Maint ML17292B5581999-02-0404 February 1999 Requests Change to Co Which Modified WNP-2 OL to Reflect Schedule for Implementing Thermo-Lag 330-1 Fire Barrier C/As.Change Requested to Reflect That Final Implementation of C/As Will Be Completed During Fall 1999 Not Spring 1999 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML17286A2801990-08-27027 August 1990 Forwards fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71(d) ML17286A2671990-08-23023 August 1990 Provides Info on Steps Taken to Minimize Potential Effects of NRC Maint Insp Interface Record, Form on Candor of Supply Sys Personnel When Talking W/Nrc Inspectors ML17286A2641990-08-20020 August 1990 Advises That Tech Spec Rev Re ATWS Recirculation Pump Trip Will Be Submitted by 900928,per Discussions W/ P Eng & H Lee ML17285B4341990-08-20020 August 1990 Withdraws 900302 Request for Amend to Tech Spec 3.8.1.1, AC Sources Reducing Excessive Testing of Diesel Generators. IR 05000397/19900141990-08-10010 August 1990 Provides Info Re Final Assessment of Causes & Corrective Actions Associated W/Recent 25 Kv iso-phase Bus Electrical Fault Incident,Per Request in Cover Ltr to Insp Rept 50-397/90-14.Plant Procedure 10.25.141 Will Be Revised ML17285B4171990-08-10010 August 1990 Provides Info Re Final Assessment of Causes & Corrective Actions Associated W/Recent 25 Kv iso-phase Bus Electrical Fault Incident,Per Request in Cover Ltr to Insp Rept 50-397/90-14.Plant Procedure 10.25.141 Will Be Revised ML17285B4041990-08-0202 August 1990 Submits Justification for Continued Operation W/Emergency Diesel Generator 2 Shorted Turns ML17285B3981990-07-30030 July 1990 Advises That Installation of Detector Check Valve in Fire Protection Underground Piping Sys Complete,Per 890911 Ltr. Sys Monitors for Underground Sys Leakage Over Entire Fire Protection Sys ML17285B3991990-07-27027 July 1990 Forwards Justification for Continued Operation Re Emergency Diesel Generator 2 Shorted Turns.Justification Concludes That Diesel Generator Capable of Supporting Present Operability Requirements of Tech Specs ML17285B3711990-07-12012 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Confirms That Items 1,2,3,4 & 5 of Requested Actions of Operating Reactors Completed ML17285B3761990-07-12012 July 1990 Discusses Potential for Surface Entry & Mining Near Plant Sites.Concludes That NRC Need Not Consider Issue as One Requiring Continued Monitoring ML17285B3781990-07-11011 July 1990 Requests Waiver of Compliance from Tech Spec 3.8.1.2 Re Ac Sources - Shutdown.Waiver Will Allow Performance of Rotor Pole Ac Voltage Drop Test to Provide Confirmation That for Extended Run Degradation Condition Will Not Occur ML17285B3841990-07-10010 July 1990 Forwards Util 1990 Emergency Exercise Scenario.W/O Encl ML17285B3661990-07-0505 July 1990 Advises of Listed Organizational & Personnel Changes, Effective 900707.J Burn Will Be New Director of Projects, C Powers Promoted to Director of Engineering & J Baker Promoted to Plant Manager ML17285B3641990-06-29029 June 1990 Advises That All Equipment Identified W/Atws Safety Function Acceptable from Environ Qualification Standpoint. ATWS Equipment Has Been Determined to Be Qualified to Normal Design Environ Conditions Followed by ATWS Accident Environ ML17285B3571990-06-28028 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. ML20055D2391990-06-28028 June 1990 Forwards Response to Re Violations Noted in Insp Rept 50-397/90-12.Response Withheld (Ref 10CFR73.21) ML17285B3501990-06-22022 June 1990 Advises That Mods to Recirculation Pump Trip Sys Implemented During 1990 Spring Refueling Outage.Remaining ATWS Items to Be Resolved as Listed ML17285B3511990-06-20020 June 1990 Forwards WPPSS-FTS-129, BWR Transient Analysis Model, for Review & Approval ML17285B3441990-06-20020 June 1990 Advises That Util Intends to Utilize R-value of 0.13% Delta K/K in Cycle 6 Implementing Procedures.Should R-value Change in Final Startup & Operations Rept,Changed Value Shall Be Used Instead ML17285B3451990-06-19019 June 1990 Forwards Rev 10 to EPIP 13.1.1, Classifying Emergency. Rev Includes New Format of Matrix Charts Intended to Improve Identification of Symptomatic & situation-based Emergency Conditions ML17285B3431990-06-18018 June 1990 Advises of Appointment of AL Oxsen to Position of Deputy Managing Director,Effective 900601 ML17285B3461990-06-15015 June 1990 Responds to NRC Evaluation Findings of Licensed Operator Requalification Program.Quality of Written Exam & Job Performance Measure Question Bank Testing Matls Will Be Improved to Meet Std Prior to Next Program Evaluation Cycle ML17285B3301990-06-12012 June 1990 Forwards Warrant for $50,000 in Response to Order Imposing Civil Monetary Penalty Dtd 900521 ML17285B3251990-06-0707 June 1990 Advises That Calculated Max Control Room Temp Re Station Blackout Will Be Provided by 900701 ML17285B2931990-05-29029 May 1990 Responds to NRC 900426 Ltr Re Violations Noted in Insp Rept 50-397/90-09.Validity of Violation Challenged.Opposes Issuance of Severity Level IV Violation Based on Listed Reasons ML17285B2861990-05-22022 May 1990 Advises That Submittal of Improved Tech Spec Scheduled for Mar 1991 & Implementation Tenatively Scheduled for Oct 1991 ML17285B2881990-05-11011 May 1990 Forwards Engineering Std EES-4,Rev 0, Setpoint Methodology, as Committed in Util 900329 Ltr.W/O Encl ML17285B2471990-05-0101 May 1990 Advises That No Changes to Tech Specs Required as Stated in 891130 Ltr in Response to Generic Ltr 89-21 Requesting Plant Status on Implementation of USI Re ATWS ML17285B2741990-04-26026 April 1990 Advises That Util Has No Comments on Licensed Operator Annual Requalification Exam During Wks of 900226 & 0305.All Comments Resolved When Exams Administered ML17285B2321990-04-25025 April 1990 Submits Revised Scheduled Completion Dates for Commitments Made in Response to Violations Noted in Insp Repts 50-397/89-06 & 50-397/89-17 ML17285B2121990-04-19019 April 1990 Responds to Fire Protection Issues Identified in 900201 Notice of Violation.Corrective Actions:Major Hardware Changes Implemented & Independent Consultant Will Be Employed to Review Fire Protection Program ML17285B2221990-04-16016 April 1990 Forwards Status Rept for Commitments Made in 891130 Ltr Re commercial-grade Dedication Process.Resolution of 10 Samples Identified by NRC & 50 Samples Identified by Cynga Completed ML17285B1881990-04-11011 April 1990 Responds to NRC 900312 Ltr Re Violations Noted in Insp Rept 50-397/90-01.Corrective Actions:Complete Job & Task Analysis Completed for Health Physics Technician Training Program & New Program Will Include Training on Fundamentals ML17285B1821990-04-0505 April 1990 Requests Exemption from Filing Requirements of 10CFR55.45(b)(2)(iii) & (IV) to Allow Delayed Submittal of NRC Form-474, Simulation Facility Certification & to Administer Simulation Test as Upgraded,Respectively ML17285B1741990-04-0505 April 1990 Advises That NRC Approved Use of Final Feedwater Temp Reduction in Amend 77 to License NPF-21 ML20012F6141990-04-0404 April 1990 Forwards Rev 17 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML17285B2041990-03-29029 March 1990 Requests Review of Encl Topical Rept WPPSS-FTS-127,Rev 0, Qualification of Core Physics Methods for BWR Design & Analysis. Upon Rept Approval,Tech Spec Changes (Per Generic Ltr 88-16) Scheduled for Jan 1992 ML17285B1421990-03-29029 March 1990 Forwards Revised Schedule for Plant Equipment Setpoint Methodology Program Plan.Methodology Revised to Incorporate Latest ISA Std Draft.Setpoint Program Design Team for FY90 Onsite,Trained & Began Work on 900312 ML17285B1381990-03-29029 March 1990 Forwards Concluding Rept of Results Requested by Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety- Related Equipment. Air Quality Testing Performed to Date Reveals Steadily Improving Results ML17285B1131990-03-28028 March 1990 Advises of Release of Subchannel Thermal Hydraulic Computer Code & Requests Review of VIPRE-01 Mod-02 & Issuance of SER for PWR & BWR Applications.Bwr Qualification Analyses Completed & Rept on BWR Applications Encl ML17285B1331990-03-23023 March 1990 Responds to NRC 900221 Ltr Re Violations Noted in Insp Rept 50-397/89-40.Corrective Actions:Plant Procedure 10.25.63, Emergency Lighting Insp in Process of Being Expanded to Provide Instructions & Check Sheets to Ensure Uniform Insps ML17285B1311990-03-21021 March 1990 Forwards Proposed Bases Change Re 891129 Request for Amend to Tech Spec Table 4.3.6.1, Srm/Irm Detector Not-Full-In Functional Test. Bases Change Describes Special Circumstances Re Test Exception ML17285B1291990-03-19019 March 1990 Responds to Generic Ltr 89-19 Re Resolution of USI A-47 on Safety Implications of Control Sys in LWRs & Generic Ltr 89-21 Re Status of Implementation of Usis.Tech Specs Adequate to Verify Operability of Overfill Protection Sys ML17285B1171990-03-19019 March 1990 Suppls 900102 Response Re Implementation of fitness-for-duty Program at Facility.All Items Identified as Incomplete as of 900103 Completed at End of Jan 1990 ML17285B1121990-03-15015 March 1990 Provides Level of Property & Liability Insurance Coverage for Facility,Per 10CFR50.54(w)(2) Annual Requirement ML17285B0931990-03-0202 March 1990 Forwards Supplementary Info Re 900214 Application for Amend to License NPF-21,revising Tech Spec 3.3.7.5 to Address Failed Safety/Relief Valve Position Indicators ML17285B0741990-03-0202 March 1990 Responds to NRC 900201 Ltr Re Violations Noted in Insp Rept 50-397/89-30.Corrective Action:Plant Personnel Currently in Process of Making Improvements to Plant Operations Procedure Writers Guide ML17285B0861990-03-0101 March 1990 Forwards Compilation of Responses to Regulatory Impact Survey Questionnaire,Per Generic Ltr 90-01 ML17285B0581990-02-26026 February 1990 Forwards Washington Nuclear Plant-2 Semiannual Radioactive Effluent Release Rept,Jul-Dec 1989 & Amend 7 to Odcm. 1990-08-27
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REGULATO INFORMATION DISTRIBUTION STEM (RIDS)
AOCE!SSION NBR :8205260179 DOC ~ DATE: 82/05/14 NOTARI'ZED: NO DOCKET ¹ FACIL250 397 NPPSS Nuclear Rrojeoti Unit 2i washington 'Public Powe 05000397 "AUTH~ NAME AUTHOR AFFILIATION BOUCHEYgG ~ DE Nashington Public "Power Supply System
>RBC IP ~ NAME, RECIPIENT AFFILIATION 9CH'FENCER i A ~ Licensing Br anch '2
SUBJECT:
Provides Justification for adeguacy of "pr esent,design re tor nado missile .protection for diesel generator exhausts.
New SRP reauirement should not be imposed. Removal of item from SER outstanding issue list requested'ept encl.
o DI'STRIBUTION CODE: B001S COPIES RECEIVED:LTR . ENCL SIZE:,~
TI'TLE: PSAR/FSAR AMDTS and Related Corr espondenoe NOTES:
RECIPIENT 'COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCI. ID CODE/NAME LTTR ENCL A/D LICENSNG 1 0 LIC BR ¹P BC 1 0 LIC BR ¹2 L'A 1 ~
0 AULUCK,RE 01 1 1 INTERNAL: ELD/HDS2 1 0 IE F ILg 1 IE/DEP EPDS 35 1 1 IE/DEP/EPLB 36 3 3 MPA 1 0 NRR/DE/CEB 11 1 1 NRR/DE/EQB 13 3 3 NRR/OE/GB 28 2 2 NRR/DE/HGEB 30 2 2 NRR/OE/MEB 18 1 1 NRR/OE/MTEB 17 1 1 NRR/DE/QAB 21 1 1 NRR/DE/SAB 24 1 1 NRR/DE/SEB 25 1 1 NRR/DHFS/HFEB40 1 NRR/OHFS/LQB 32 1 1 NRR/DHFS/OLB 34 1 1 NRR/DHFS/PTRB20 1 1 NRR/DSI/AEB 26 1 1 NRR/DS I/ASB 27 1 1 NRR/OSI/CP8 10 1 1 NRR/OS I/CSB 09 1 1 NRR/DS I/ETSB 1? 1 1 NRR/DS I/ICSB 16 1 1 NRR/DSI/PS B 19 1 1 NRR/DS I/RAB 22 1 1 NRR/OS I/RSB 23 1 1 NRR/DST/LGB 1 1 04 1 1 RGN5 2 2 EXTiERNAL: ACRS 41 16 16 BNL(AMDTS ONLY) 1 1 FEMA REP DIV 39 1 1 LPDR 03 1 1 NRC PDR 02 1 1 NSIC 05 1 1 NTIS 1 1 TOTAL NUMBER OF COPIES REQUIRED: L'TTR 63 ENCL '58
Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 May 14, 1982 G02-82-446 SS-L-02-PLP-82-031 Docket No. 50-397 Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Schwencer:
Subject:
NUCLEAR PROJECT NO. 2 WNP-2 TORNADO MISSILE PROTECTION FOR DIESEL GENERATOR EXHAUSTS On April 26-27, 1982, members of our staff met with R. Auluck, J. Ridgely, and R. Lobel of the NRC staff to discuss, among other things, tornado missile protection for the WNP-2 diesel generator exhausts. The Supply System position on this issue is presently being evaluated by the NRC staff, but discussions have indicated that NRC management attention may be warranted.
In summary, the NRC staff has advised the Supply System that the WNP-2 design must take into consideration protection against tornado missiles for up to 30 feet above the highest grade elevation within 1/2 mile of the plant site, in accordance wth the new Standard Review Plan (SRP).
As you are aware, WNP-2 received its construction permit in 1973 (CPPR-93). WNP-2 is designed and constructed in accordance with Regulatory Guide 1.70 and takes into account protection, against -tornado missiles up to 30 feet above plant grade. Thus, the plant area that is subject to the backfit proposed by the staff is that area between 30 feet above grade and the new level prescribed in the SRP (approximately 60 feet above grade). The issue raised by the staff is the probability that a utility pole could damage or block the diesel generator exhaust. A detailed discussion of the matter is provided in the enclosure of this letter.
We are raising this matter with you to assure that you are aware of it and can take any management action you may deem necessary. In this regard, we invite your attention to the following points:
~ WNP-2 was designed and constructed in accordance with Regulatory Guide 1.70;
~ The new SRP should not be considered a binding legal requirement on WNP-2 at this stage of the review process.
is'P 0 5 $ 6 0 L
A. Schwencer Page Two May 14, 1982 G02-82-446 WNP.-2 Tornado Missile Protection for Diesel Generator Exhausts:
~ The staff's attempt to impose the new SRP for WNP-2 design involves a change in design basis and constitutes a backfit;
~ The staff has made no finding in accordance with 10CFR 50.109.
In any event, tornados of sufficient velocity to generate a missile of the type under consideration are unprecedented in the vicinity of the site.
The probability of occurrence of such
~
tornado in the WNP-2 site vicinity has been estimated to be less than 10 per year (NUREG-0722). Of course, the probability that any missile generated by a tornado would strike the exhaust port for the diesel generator is even lower. In these circumstances, we have concluded that no substantial additional protection would be afforded by the backfit, and that the backfit cannot be justified on a cost-benefit basis due to the extremely low probability of the event.
Because the SRP is a guidance document, and because no finding has been made by the staff in accordance with 10CFR 50.109, we submit that the staff has no justification for imposing the backfit. Further, we believe that the enclosure to this letter provides ample technical justification for the ade-quacy of the present design. Accordingly, we request that the NRC remove this item from, the Safety Evaluation Report Outstanding Issues list.
Please contact me if you have further questions.
A Very truly yours, G. D. Bouchey Deputy Director, Safety and Security GCS/jca cc: R Auluck - NRC WS Chin - BPA R .Feil - NRC Site H Denton - NRC W Dircks - NRC V Stel 1 o - NRC DG Eisenhutt - NRC RL Tedesco - NRC
ATTACHMENT 1 Washington Public Power Supply System Position On Tornado Missile Protection for Diesel Generator Exhausts, WNP-2 March 23, 1982 The Power Systems Branch of the Nuclear Regulatory Commission (NRC) has indicated in the Safety Evaluation Report (SER) for WNP-2 that there is a concern that adequate protection against tornado missiles has not been provided for the diesel generator exhausts. The NRC postulates that a.
utility pole may be blown into the diesel exhaust of one of the divi-sions or into the structure around the exhaust, possibly collapsing part of the exhaust system. Because of the partial blockage of the exhaust area, the diesel performance of that division may be degraded, and the generators may not produce enough power to provide for safe shutdown of the plant. Concurrent, with this event is the loss of offsite power (because of the tornado) and the non-starting of the diesels in the other diesel generator division.
The diesel exhaust piping exits the diesel generator rooms between the reactor building and the diesel generator building, rises to the roof level through a narrow, protected corridor between the two buildings, and enters a tornado missile protected penthouse atop the diesel ~ener-ator building. The exhaust discharges from the penthouse at a 45 angle from the horizontal. The, centerline of the exhaust (at the face of the penthouse) is at elevation 481'84" (see Figure 1). The bottom of the exhaust opening is at 479'7". Allowing a band of concrete 16"'elow that to protect against a missile striking and damaging the concrete encasement below that penetration lowers the lowest point of interest to
,478'3", which is 37'9" above plant grade. The finished plant grade around the diesel generator building is 440'6".
In the Preliminary Safety Analysis Report (PSAR), the Supply System committed to providing tornado missile protection against several missiles. The 35 feet long utility pole with a 14 inch butt was among these missiles. In the Final Safety Analysis Report (FSAR) for WNP-2, the Suoply System committed to providing tornado missile protection against this utility pole up to thirty (30) feet above lant rade.
(The design missile in the FSAR weighs 1600 pounds and has a velocity of 241 feet per second.)
Also in the PSAR and the FSAR the Supply System committed to providing protection against tornado winds of 360 mph (300 mph rotational and 60 mph translational).
Based upon the commitments in the PSAR, the design criteria were pre-pared and the drawings for the diesel generator building were released for construction in 1973. The Supply System has provided protection for the diesel generator building (and other buildings) appropriate to the commitments in the PSAR and the FSAR.
3/23/81 Subsequent to the release of the drawings for construction noted above, the f p NRC, ti gi th filiypi "pt.30'~b114 in 1975, issued Standard Review Plan (SRP) 3.5.1.4 which called levels within 1 2 mile of the facilit structures:" (Underlining added.)
Thus, the current concern results from the imposition of a criterion =
that did not exist when the building was designed and construction was started.
The Supply System commitments listed above were made based upon the best information that was available at the time of the commitment. Since then, however, research efforts have continued and better information is now availalbe. A report by the NRC (NUREG-0722) (Ref. 1) has been published that gives a better estimate of the probability of tornado and other winds occurring at the plant site. This report was prepared for the EXXON Nuclear Company plant (eight miles south of WNP-2). Because there are no intervening terrain features, WNP-2. Figure 2 it is equally applicable to taken from that report, shows that the Supply System commitment to tornado winds of 360, mph is extremely conservative, since the greatest wind velocity shown is about 220 mph and has a probability of occurrence in any one year of Ps=lxlO . It should also be noted from Figure 2 that tornado wind speeds of 170 mph are classified as "remote" by the report. Another source (Ref. 2) supports the data in NUREG-0722 (see Table 1). The data in Figure 2 and Table 1 show that the probable maximum velocity of tornado winds falls off quite sharply while the probability of occurrence still remains very small. This clearly indicates that the occurrence of a tornado sufficient to generate large missiles is extremely remote.
There are no utility poles in the plant area at elevations within 30 feet of elevation 478'. There are some knolls above elevation one half-mile of the plant, but they are covered by grasses 448'ithin and sagebrush and do not have any utility poles on them. (The nearest ground at elevation 448'r higher is at least 1000 feet from the diesel generator building.)
Calculations based upon a report prepared for the U; S. Atomic Energy Commission (Ref. 3) show that a missile the size of the design utility pole cannot be made air borne with winds of 220 mph (323 fps), let alone have a velocity of 241 feet per second (FSAR commitment) and be 38 feet above plant grade.
Even assuming that a missile could be generated, the probability of the events described in the scenario is so small that additional protection is not deemed necessary for the diesel exhausts. To show this, the probability of this sequence of events will be analyzed.
3/23/82 Assuming that a missile were generated, the probability of it hitting any one of the four exhaust areas (a point target) is:
PH
=" H = 4 18.98 = 1.3x10 ~
AT 30 200 where AH = area of one diesel exhaust port that could result in postulated damage
= elliptical area of pipe and area of concrete that might be damaged ( Figure 1) 52 66.9 (2x 2)m = 18.98 ft~
144 AT = cross-sectional area of tornado
= height x diameter = 30'x200'100's assumed for the radius of the tornado. This is conservative for this situation. A larger radius would result in a smaller PH.)
The probability that either diesel generator will not start when required is PD
= 1x10 ~ (including restart).
Combining these probabilities, the probability of the postulated event is 1.3xlO ~"".
PT
= PS x PH x PD
= (lx10 a)(1.3xlO "")(lxlO ~) ~ 1.3x10">~.
This combined probability is so small as to not warrant consideration in the plant design basis. Even if one hundred poles were to be airborne in a tornado, the probability of the postulated incident occurring in any one year is 1.3x10 >o, which is still too small to form the basis for the plant design.
While the total probability of such an event occurring is extremely small, it should be considered a conservative number since no effect of pole alignment or direction of motion is, considered. A factor of PAL=0.5 could reasonably be assumed to represent the probability that the pole, while airborne, would be aligned in such a way that the postu-lated damage would occur. Also, a factor of PAg=0.5 could be assumed to represent the probability that the pole would be moving axially, as opposed to sideways. The combined probability then that the pole would be properly oriented and moving in a damaging direction is PC 0.25.
which would further reduce the probability shown above.
3/23/82 It should also be noted that the exhaust ports are approximately 65 feet back from the vertical face of the diesel generator building. Thus, any tumbling pole or pole with a vertical or partially vertical orientation would strike the front of the diesel generator building unless all parts of the pole are at least 38'bove the plant grade. This provides addi-tional protection for the exhaust ports against being hit be the postu-lated missile.
In conclusion, it is the Supply System's position that adequate protec-tion is provided for the diesel generator exhausts for the following reasons:
- 1. The probability of any tornado occurring is very small. If one does occur, the strongest winds to be expected are well below the design winds committed to in the PSAR and FSAR.
- 2. The design utility pole is not a credible missile at the elevation of the diesel exhausts.
- a. The maximum tornado wind that might be expected will not missile the size of the design utility pole.
.support a
- 3. Assuming a missile could be generated, the probability of the scenario postulated is so small (1.3xl0->2) that it does not warrant consideration in the plant design basis.
3/23/82 Refer ences:
- 1. NUREG-0722, "The Effects of Natural Phenomena on the EXXON Nuclear Company Mixed Oxide Fabrication Plant at Richland, Washington",
U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, September 1980.
- 2. McDonald, James R., "Assessment of Tornado and Straight Mind Risks at the Hanford Engineering Work Site", Prepared for Lawrence Liver-more Laboratory, University of California by McDonald, Mehta and Minor,= Consulting Engineers, Lubbock, Texas, October 1979.
- 3. HEDL-TME-71-35, "Review of Tornado Considerations for FFTF",
prepared by D. E. Simpson of the Hanford Engineering Development Laboratory for the United States Atomic Energy Commission, Richland, Washington 99352, January 1971.
3/23/82 ScL9 l.EV, Ml'-S'fg,"
QLCV.
4'79'- I" ELGV.
)
CTS'-0" r2
- ,qadi."
A,REA OF POSSLQ LK r';y" b~AGE-FAC.E, OP KXHAU5V'~THOum 0
4)0 F(6URE TH'E AREA THAT COLl~ BE'OLlSl!>BRED 'SUSCEPTIBLE VD C4 &ASK IS ROUCbl4LY KLLI~CALII SWAPS WlTH h. MAQOR, 'DNELlSLOh OF CoCo.9" (%P~+ Mal') Q A RIGOR. DIHFVSIOQ OF &2. (Ro"+ Z.x').
3/23/82 50 >00 I STRAIGHT-UNK W INOS Mindspeeds of Oesign-(I950- T5) lO Basis Storms as a Function of Probability of Occurrence at the Site. (Probability per year of l0 is regarded as high~ IO~ as low, and 10" as remote. Id' Straight-line winds dominate the high- and low-probability cases; tornadoes dominate the remote-probability case. FO~FI F2 5.9 X IO ALL TORNAOOES The use of curves B and 0 combined is recom- I FO~ I FZ t.5 X IO INSSFC TYPO) mended.) (i00 mph
~ 45 m/s.) C p
+// ~i FIGURE 2
3/23/82 SUGARY OF TORNAOO RISKS Qindspeed Nean Recurrence Expected
~mh Interval, Yr ~Pb bill 40 38,500 2.60 x 10 73 110,000 9.07 x 10 113 350,000 286 X106 158 3,570,000 2.80 x 10
'207 55,900,000 1.79 x 10 251 1,471,000,000 6.80 x 10
~Probability of exceeding threshold windspeed in one year.
I TABLE 1