|
---|
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
[Table view] |
Text
REGULATORY I 'MATION DISTRIBUTION SYST 'RIDS)
AOCBSSION NBR:8206210584 DOC ~ DATE: 82/06/id NOTARIZED: NO DOCKET FACIL:50-397 NPPSS Nuclear Projecti Unit 2~ washington Public Powe 05000397
'"A UT H NAME
~ AUTHOR AFFILIATION, BOUCHEYiG.D, washington Public Power Supply System
)RBCIP NAME
~ RECIPIENT AFFILIATION SCHKENCERiA ~ Licensing Branch 2
SUBJECT:
Forwards response to request for addi info re area vs magnitude relationship. Info prepared by lioodward Clyde c 0 nsulta n ts ~
DIS;fRIBUTION CODE: B001S COPIES RECEIVED:LTR TITLE: PSAR/FSAR AMDTS and Related Correspondence
+ ENCL SIZE:.
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL A/D LICENSNG 1 0 LIC BR 02 BC 1 0 LIC BR P2 LA 1 0 AULUCKg R ~ 0 1 1 1 INTiERh'ALe ELD/HDS2 1 0 IE FILE 1 1 IE/DEP EPDS 35 1 IE/DEP/EPLB 36 3 3 MPA 1 0 NRR/DE/CEB 11 1 1 NRR/DE/EQB 13 3 3 NRR/DE/GB 28 2 2 NRR/DE/HGEB 30 2 2 NRR/DE/MEB 18 1 1 NRR/DE/MTEB 17 1 1 NRR/DE/GAB 21 1 1 NRR/DE/SAB 24 1 1 NRR/DE/SEB 25 1 1 NRR/DHFS/HFEBPO 1 1 NRR/DHFS/LQB 32 1 1 NRR/DHFS/OLB 30 1 1 NRR/DHFS/PTRB20 1 1 NRR/DSI/AEB 26 1 1 NRR/DS I/ASB 27 1 NRR/DSI/CPB 10 1 1 NRR/DSI/CSB 09 1 1 NRR/DS I/ETS8 12 1 1 NRR/DS I/ICS8 16 1 1 NRR/DS I/PSB 19 1 1 NRR/DSI/RAB 22 1 RSB 23 1 1 NRR/DST/LGB 33 1 1 REG FI 04 1 1 RGN5 2 2 EXTERNAL: ACRS 41 16 16 BNL(AMDTS ONLY) 1 1 FEMA-REP 0 IV 39 1 1 LPDR 03 1 1 NRC PDR 02 1 1 NSIC 05 1 1 NTIS 1 1
>TOTAL NUMBER OF COPIES REQUIRED: LTTR 63 ENCL 58
0 a,
h
[
<t t$
8 a.
C,~
(( 't'k-
~.%,&p,l h
)
N' "I
/
k
'206210584 820614
,PDR 'ADOCK 05000397 ",')
'A '
PDR !'-
Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 June 14, 1982 G02-82-539 SS-L-02-CDT-82-076 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 AREA VERSUS MAGNITUDE RELATIONSHIP Enclosed are sixty (60) copies of the information requested by the NRC concerning Area Versus Magnitude Relationship.
Very truly yours, G. D. Bouchey Deputy Director, Safety and Security CDT/jca Enclosure cc: R Auluck - NRC WS Chin - BPA Feil Site R -. NRC
+DO (
'h Id@ f
~r r
C J
, j
Noodward Clyde Consultants "
TASK 7b AREA VERSUS MAGNITUDE RELATIONSHIP Introduction The purpose of this task is to develop an empirical relationship between earthquake magnitude and fault area that can be used to estimate earthquake magnitudes in the range 4 < Ms < 6 for faults having limited dimensions. The existing empirical relationships are based primarily on data for large magnitude earthquakes (M > 6) and associated fault parameters (e.g., rupture length<
displacement, and rupture area). The data sets for these relationships do not include sufficient information to allow meaningful estimates of earthquake magnitude for'aults having relatively limited dimensions. Therefore, the worldwide histor-ical seismicity record was examined to obtain fault parameter data in this lower magnitude range.
Because the magnitude threshold at which surface rupture occurs is about M 5 to 6, fault parameters that are developed from observations of surface rupture, such as rupture length and max-imum displacement per event, are often not reliable indicators of energy release for earthquakes of M < 6. Observations of earth-quakes of M < 6 do not show a consistent relationship between magnitude and the occurrence, length, or amount of surface dis-placement associated with these earthquakes. This suggests that the surface faulting associated with these earthquakes may be more a function of local conditions (e.g., fault type, material properties, depth of focus) than of the magnitude of the event.
For these reasons, magnitude-related fault parameters that depend on geologic evidence of sur'face rupture were not used in developing an empirical relationship in this study.
Recent studies (Wyss, l979) have shown that for earthquakes of Ms > 5.7 earthquake magnitude is related to the rupture area on the fault surface. Rupture areas have been assessed for
fH, Woodward Clyde Consultants historical earthquakes from the dimensions of aftershock sequences, seismic wave analysis, and geodetic modelling. Based on a worldwide data set of about 90 historical earthquakes of all fault types, Wyss (1979) presents a well-defined relationship of the form:
Ns = Log A + 4.15 where A is the rupture area in square kilometers. Wyss (1979) notes that both the length of the rupture area and the rupture area itself are more reliable indicators of the size of an earth-quake than is surface rupture length.
Rupture area is closely related to seismic moment (Purcaro and Berckhemer, 1982) .and, therefore, to the amount of energy released during an earthquake. Rupture area versus seismic moment relationships have been established for seismic moments from 10 dyne-cm to as small as 10 13 dyne-cm (Pearson, 1982).
On this basis, it is apparent that the rupture area versus magni-tude relationship can be extended below M 6. In addition, rupture area may be assessed for historical earthquakes without relying on evidence of surface rupture. For these reasons, the rupture area versus magnitude relationship was judged to be an appropriate empirical approach magnitude for faults having limited dimensions.
The estimation of future rupture areas on a particular fault can be made based on assessments of rupture length and downdip fault width. Fault rupture length is usually estimated from geologic evidence for segmentation of the fault zone or from assumptions regarding the fraction of the total fault length that may rupture during a single event. Downdip fault width is assessed from:
- 1) the maximum depths of historical seismicity; 2) geophysical data that constrain the local crustal model; 3) geodetic data regarding the maximum depths of fault slippage; or 4) the
Woodward Clyde Consultants regional tectonic model. In addition, if the fault rupture length can be estimated, compilations of data relating rupture length 'o downdip fault width for worldwide historical earth-quakes (e.g., Purcaro and Berckhemer, 1982) may be used to assess downdip fault width.
C
, Anal sis and Results In order to compile a sufficiently large number of data points, the seismologic literature was reviewed for all earthquakes having magnitudes of 4 to 6 for which fault rupture areas had been, or could be, assessed. From thes'e, earthquakes were selected that had well-constrained magnitudes and aftershock locations. Aftershock sequences are defined by the seismicity occurring during the first few days after the main shock. In most cases, the rupture area was estimated from the distribution of aftershocks. In some cases, the rupture area, was constrained by seismic wave analysis and/or geodetic data. In the present analysis, the rupture area associated with the main shock is assumed to be defined by a rectangular region on the fault sur-face that encloses the aftershock sequence, unless more rigorous estimates have been made for a specific earthquake in the litera-ture to define an irregularly shaped rupture area. It is assumed that the distribution of slip is uniform over the rupture surface defined by the aftershocks, although it is recognized that the rupture may actually be complex (Aki, 1979).
The 24 earthquakes that were selected for the analysis are sum-marized in Table 1 and are plotted in Figure 1. The empirical relationship between rupture area and earthquake magnitude is of the form:
M = 0.656 Log A + 4.257
Woodward Clyde Consultants The correlation coefficient is 0.834. Local magnitudes, ML,- have not been converted to surface wave magnitudes, Msi because there is little difference between the two scales in this magnitude range. The rupture area versus magnitude relationship is well-defined by the data, particularly in the magnitude range of 5 to
- 6. The slope of the regression of magnitude on the logarithm of rupture area is about 0.7, whereas it is about 1.0 for M > 6 (Wyss, 1979). This difference may reflect differences in the stress drops of earthquakes in the magnitude ranges M > 6 and M < 6 ~
The relationship presented in Figure 1 can be used to estimate 2
earthquake magnitude for rupture areas as small as about 5 km .
For example, the Central fault on Gable Mountain is estimated to have a maximum inferred area of 9 km 2 (Response to 360.20) ~
Assuming that this entire area ruptures during an earthquake, the estimated magnitude from Figure 1 is about Ms 4.9.
r TABLE 1 Event Da te Location Area (km2) Reference 12/21/56 Mizakejimay JP 6.0 550 Utsu (1969) 3/22/57 San Francisco, CA 5. 3 (ML) 45 Tocher (1959) 5/7/61 Hyogo Prefecture, JP 5 ' 570 Utsu (1969) 9/14/63 Watsonville, CA 5. 4 (ML) 210 McEvilly (1966) 11/16/64 Corralitos, CA 5.0 18 McEvilly (1966) 9/10/65 Antioch, CA 4. 9 (ML 18 McEv illy and Casaday ( 1967 )
6/27/66 Parkfield-Cholame, CA 5 5 (ML) 520 Eaton et al (1970) 9/12/66 Truckee, CA 5.9 100 Kanamori and Anderson (1975) ll/12/66 South of Hokkaido, JP 5.9 210 Utsu (1969) 10 7/1/68 Saitama, JP 5.6 60 Abe (1975); Kanamori and Anderson (1975) 5/28/69 Coyote Mountain, CA 5. 9 (ML) 30 Thatcher and Hamilton (1973) 12 10/16/70 SE Akita, JP 6.0 165 Mikumo (1974); Hasegawa et al (1975) 13 9/4/72 Stone Canyons CA 4~7 (ML) 12 Wesson and Ellsworth (1972) 14 2/21/73 Pt ~ Mugu, CA 5.2 15 Ellsworth et al (1973);
Boore & Stierman (1976);
Stierman a Ellsworth (1976);
Castle et al (1977) 15 3/25/73 Gulf of California 5.5 40 Reichle et al (1976)
Table 1 continued Event Date Location Area (km2) Re ference 16 3/28/75 Pocatello Valley, ID 6. 0 (ML) 144 Arabasz et al (1981) 17 7/12/75 Maniwaki, Quebec 4 2 (ML) Horner et al (1978) 18 8/1/75 Orovilleg CA 5.6 150 Lahr et al (1976); Clark et al (1976); Langston a Butler (1976); Hart et al (1977) 19 8/17/76 Kawazu, JP 5.4 31. 5 Abe (1978) 20 1/8/77 Briones Hill, CA 4. 3 (ML) 8(9) Johnston et al (1978);
Prescott (1978)
Savage &
21 8/13/78 Santa Barbara, CA 5.6 50 Lee et al (1978); Wallace et al (1981) 22 8/6/79 Coyote Lake, CA 5~7 200 Lee et al (1979) 23 1/24/80 Livermore, CA 5.9 (ML) 264 Scheimer et al (1982) 24 2/29/80 Arudy, France 5.0 35 Souriau et al (1982)
0 I
Woodward Clyde Consultants REFERENCES Abe, K-< 1975, Static and dynamic fault parameters of the Saitama earthquake of July 1 1968: Tectonophysics, v. 27<
pp. 223-238.
Abe, K., 1978, Dislocations, source dimensions, and stresses associated with earthquakes in the Izu peninsula, Japan, Journal Physics Earth, v. 26, pp. 253-274.
Aki, K., 1979, Characterization of barriers on an earthquake fault: Journal of Geophysical Research, v. 84, no. Bll, pp.
6140-6148.
Arabasz, W.J., Richins, W.D.< and Langer, C.J., 1981< The Pocatello Valley (Idaho-Utah border) earthquake sequence of March to April, 1975, Bulletin of the Seismological Society of America, v. 71, no. 3, pp. 803 826.
Boore, D.M., and Stierman, D.J. 1976, Calculation of ground motion in a three-dimensional model of the 1966 Parkfield earthquake, Bulletin of the Seismological Society of America,
- v. 66, no. 2, pp. 385-404.
Castle, R.O., Church, J.P., Elliott, M.R., and Savage, J.C.,
1977, Preseismic and coseismic elevation changes in the epicentral region of the Point Mugu earthquake of February 21, 1973: Bulletin of the Seismological Society of America, v. 67, no. 1, pp. 219-231.
Clark, M.M., Sharp, R.V., Castle, R.O., and Harsh, P.W.>
faulting near Lake Oroville, California in August 1976'urface 1975: Bulletin of Seismological Society of America, v. 66<
no. 4, pp. 1101-1110.
R-1
4 4 Woodward Clyde Consultants Eaton, J.P., O'eill, M., and Murdock, J.N., 1971, Aftershocks of the 1966 Parkfield-Cholame, California, earthquake: Bulletin of the Seismological Society of America, v. 60, pp. 1151-1197.
Ellsworth, W.L., Campbell, R.H., Hill, D.p., Page, R.A., Alewineg P W., III, Hanks, T.C ~ , Heaton, J A., Hileman, J A.<
~ ~
Kanamori, H., Minster, B., and Whitcomb, J.H., 1973, Point Mugu, California earthquake of 21 February 1973 and its aftershocks, Science, v. 182, pp. 1127-1129.
Hart, R.S., Butler, R., and Kanamori, H., 1977, Surface-wave constraints on the August 1, 1975, Oroville earthquake:
Bulletin of the Seismological Society of America, v. 67<
no 1 pp 1-7 ~
Hasegawa, A., and Kasakara, K., 1975, On the focal mechanism of the southeastern Akita earthquake of 1970: Journal of the Seismological Society of Japan, v. 28, pp. 141-151.
Horner, R.B.; Stevens, A.E., Hasegawa, H.S., and LeBlanc, G.,
1978, Focal parameters on the July 12, 1975, Maniwaki, Quebec, earthquake; an example of intraplate seismicity in eastern Canada: Bulletin of the Seismological Society of America, v. 68, no. 3, pp. 619-640.
Johnston, M.J.S., Jones, A.C., Daul, W., and Mortensen, C.E.,
1978, Tilt near an earthquake (ML .= 4.3) Briones Hills, California: Bulletin of the Seismological Society of America, v. 68, no. 1, pp. 169-173.
Kanamori, H., and Anderson, D.L., 1975, Theoretical basis of some empirical relations in seismology: Bulletin of the Seismological Society of America , v. 65, pp. 1073-1095.
R-2
A l
~
I
%Voodward Clyde Consultants Lahr> K.M., Lahr, J.C., Lindh, A.G., Bufe, C.G., and Lester, F.W., 1976< The August 1975 Oroville earthquakes: Bulletin of the Seismological Society of America, v. 66 no. 4<
pp. 1085-1099.
Langston, C.A., and Butler, R., 1976, Focal mechanism of the August 1, 1975, Oroville earthquake: Bulletin of the Seismological Society of America, v. 66, no. 4, pp. 111-1120.
Lee, W.H.K., Johnson, C.E., Henyey, T.L., and Yerkes, R.L., 1978/
A preliminary study of the Santa Barbara, California, earthquake of August 13, 1978, and its major aftershocks, U.S.G.S. Circular 797, 14 p.
Lee, W.H.K., Herd, D.G., Cagnetti, V., Bakun, W.H., and Rapport, A., 1979, A preliminary study of the Coyote Lake earthquake of August 6, 1979 and its major aftershocks: U.S.G.S. Open-File Report 79-1621, 43 p.
McEvilly, T.V.< 1966, The earthquake sequence of'ovember 1969 near Corralitos, California: Bulletin of the Seismological Society of America, v. 56, pp. 755-773.
McEvilly, T.V., and Casadayg K B 1967 The earthquake sequence g
of September, 1965, near Antioch, California: Bulletin of the Seismological Society of America, v. 57, no. 1, pp. 113-124.
Mikumo, T., 1974, Some considerations on the faulting mechanism of the southern Akita earthquake of October 16, 1974, Journal Physics Earth, Tokyo, v. 22, pp.87-108.
Pearson, C.< 1982, Parameters and a magnitude moment relationship from small earthquakes observed during hydraulic fracturing experiments in crystalline rocks: Geophysical Research Letters, v. 9, no. 4, pp. 404-407.
R-3
Woodward Clyde Consultants Purcaru, G., and Berckhemer, H., 1982, Quantitative relations of seismic source parameters and a classification of earthquakes: Tectonophysics, v. 84, pp.57-128.
Reichle, M.S., Sharman, G.F., and Brune, J.N., 1976, Sonobuoy and teleseismic study of Gulf of California transform fault earthquake sequence: Bulletin of the Seismological Society
~ of America, v. 66, no. 5, pp. 1623-1641.
Savage, J.C., and Prescott, W.H., 1978'eodolite measurements near the Briones Hills, California, earthquake swarm of January 8, 1977, Bulletin of the Seismological Society of America, v. 68, no. 1, pp. 175-180.
Scheimer, J.F., Taylor, S.R., and Sharp, M., 1982, Seismicity of the Livermore Valley region: Proceedings of the Conference on Earthquake Hazards in teh Eastern San Francisco Bay Area, California Division of Mines and Geology Special Report (in press).
Souriau, M., Souriau, A., and Gagnepain, J., 1982, Modelling and detecting interactions between earth tides and earthquakes with application to an aftershock sequence in the Pyrenees, BSSR, v. 72, no. 1, pp. 165-180.
Stierman, D.J., and Ellsworth, W.L., 1976, Aftershocks of the February 21, 1973, Point Mugu, California earthquake:
Bulletin of the Seismological Society of America, v. 66, no. 6, pp. 1931-1952.
Thatcher, W., and Hamilton, R.M., 1973, Aftershocks and source characteristics of the 1969 Coyote Mountain earthquake, San Jacinto fault zone, California: Bulletin of the Seismological Society of America , v. 63, pp. 647-661.
R-4
~ .
1 Irs
Woodward Clyde Consultants Tocher, D., 1959, San Francisco Earthquakes of March 1957:
California Division of Mines Special Report 57, pp. 61-71.
Utsu, T., 1969, Aftershocks and earthquake statistics (1):
Hokkaido University Journal of the Faculty of Sciencef
- v. VII'g pp. 129-195.
Wallace, T. C., Helmberger, D.V., and Ebel, J.E., 1981, A broad band study of the 13 August 1978 Santa Barbara earthquake:
Bulletin of the Seismological Society of America, v. 71, no. 6, pp. 1701-1718.
Wesson, R.L., and Elis@orth, W.L., 1972, Preliminary hypocentral data for the Stone Canyon earthquake of September 4, 1972:
Earthquake Notes, Eastern Section Seismological Society of America, v. XLIII, no. 3, pp. 13-15.
Wyss, M., 1979, Estimating maximum expectable magnitude of earthquakes from fault dimensions: Geology, v. 7, pp. 336-340.
R-5
~
7 3 1
~
~
2' 22' 12 18' 16
.8 F 10
~
16 24 I/ ~
9 '11 P
O. 6y ~
'14 13'1 10
'20 0 Ms=0.656 Log r = 0.834 A+ 4.257
~'0 O B Log A = 1.061 Mq 3.973 4.5 5.0 5.5 6.0 Magnitude (Ms)
WASHINGTON PUBLIC POWER SUPPI.Y SYSTEM PLOT OF RUPTURE AREA Figure VERSUS MAGNITUDE 1 Nuclear Project No. 2
a L
nW