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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 ML15217A1031990-02-28028 February 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20006G0621990-02-22022 February 1990 Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld ML20006E5881990-02-20020 February 1990 Forwards Proprietary Response to NRC 890725 Questions Re Vipre Core Thermal Hydraulic Section of Topical Rept DPC-NE-3000 & Rev 2 to Pages 3-69,3-70,3-78 & 3-79 of Rept. Encls Withheld (Ref 10CFR2.790) ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML20006E9071990-02-16016 February 1990 Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML18094B3291990-02-14014 February 1990 Forwards Printouts Containing RW-859 Nuclear Fuel Data for Period Ending 891231 & Diskettes ML20011E6151990-02-12012 February 1990 Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) ML20011E5571990-02-0808 February 1990 Forwards Us Bankruptcy Court for Eastern District of Tennessee Orders & Memorandum on Debtors Motion to Alter or Amend Order & Opinion Re Status of Sales Agreement Between DOE & Alchemie.Doe Believes Agreement Expired on 890821 ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested ML20011E5981990-02-0505 February 1990 Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20006C5661990-01-31031 January 1990 Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants ML20006D6611990-01-29029 January 1990 Advises That 900117 License Amend Request to Remove Certain cycle-specific Parameter Limits from Tech Specs Inadvertently Utilized Outdated Tech Specs Pages.Requests That Tech Specs Changes Made Via Amends 101/83 Be Deleted ML20011E2521990-01-29029 January 1990 Forwards Proprietary Safety Analysis Physics Parameters & Multidimensional Reactor Transients Methodology. Three Repts Describing EPRI Computer Code Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790) ML20006C6711990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Plants Have Established Preventive Maint Program for Intake Structure & Routine Treatment of Svc Water Sys W/Biocide to Control Biofouling ML20006B7961990-01-29029 January 1990 Forwards Summaries of Latest ECCS Evaluation Model Changes ML18153C0951990-01-29029 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted ML20006D2431990-01-26026 January 1990 Provides Info Re Emergency Response Organization Exercises for Plants.Exercises & Callouts Would Necessitate Activation of Combined Emergency Operations Facility Approx Eight Times Per Yr,W/Some Being Performed off-hours & Unannounced ML18153C0871990-01-26026 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures to Be Revised & Familiarization Sessions Will Be Conducted Prior to Each Refueling Outage ML18094B2861990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Aggressive Program of Monitoring,Insp & Matl Replacement Initiated in Advance of Generic Ltr 89-13 Issuance ML19354E4191990-01-25025 January 1990 Comments Re Issuance of OL Amends & Proposed NSHC Determination Re Transfer of Operational Mgt Control of Plants & Views on anti-trust Issues Re Application for Amend for Plants ML19354E6711990-01-24024 January 1990 Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226 ML17347B5451990-01-24024 January 1990 Informs of Plans to Apply ASME Code Case N-356 at Plants to Allow Certification Period to Be Extended to 5 Yrs.Rev to Inservice Insp Programs Will Include Use of Code Case ML19354E4461990-01-22022 January 1990 Forwards Proprietary Rev 1 to DPC-NE-2001, Fuel Mechanical Reload Analysis Methodology for MARK-BW Fuel, Adding Section Re ECCS Analysis Interface Criteria & Making Associated Administrative Changes.Rev Withheld ML19354E4451990-01-22022 January 1990 Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters ML20005G7161990-01-20020 January 1990 Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl ML20006A8001990-01-19019 January 1990 Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21) ML16152A9091990-01-18018 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. W/900131 Release Memo ML18153C0771990-01-17017 January 1990 Forwards North Anna Power Station Emergency Plan Table 5.1, 'Min Staffing Requirements for Emergencies' & Surry... Table 5.1, 'Min Staffing Requirements...', for Approval,Per 10CFR50.54(q),NUREG-0654 & NUREG-0737,Suppl 1 ML20006A6241990-01-16016 January 1990 Forwards Draft Qualified Master Trust Agreement for Decommissioning of Nuclear Plants,For Review.Licensee Will Make Contributions to Qualified & Nonqualified Trust as Appropriate ML20006A2011990-01-16016 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel in Anchor Darling Swing Check Valves.Eight Subj Valves Identified in Peach Bottom Units 1 & 2 & Will Be Returned to Mfg ML18153C0731990-01-15015 January 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or or Valves.... Util Replaced Studs in twenty-five Valves ML20006A8201990-01-10010 January 1990 Forwards Errata to Rev 3 to BAW-1543,Tables 3-20 & E-1 of Master Integrated Reactor Vessel Surveillance Program Reflecting Changes in Insertion Schedule for A5 Capsule for Davis-Besse & Crystal River ML20006B8821990-01-10010 January 1990 Reissued Ltr Correcting Date of Util Ltr to NRC Which Forwarded Updated FSAR for Byron/Braidwood Plants from 881214 to 891214.W/o Updated FSARs ML20005G6431990-01-10010 January 1990 Responds to Generic Ltr 89-21 Re Implementation of USI Requirements,Consisting of Revised Page to 891128 Response, Moving SER Ref from USI A-10 to A-12 for Braidwood ML20005G7601990-01-0404 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Plan. Privacy Info Should Be Deleted Prior to Placement in Pdr.W/ D Grimsley 900118 Release Memo ML18153C0491990-01-0303 January 1990 Advises of Implementation of fitness-for-duty Program Which Complies w/10CFR26.Util Support Objective of Providing Assurances That Nuclear Power Plant Personnel Will Perform Tasks in Reliable & Trustworthy Manner ML20005F4641990-01-0303 January 1990 Advises That Licensee Implemented 10CFR26 Rule Re fitness-for-duty Program W/One Exception.Util Has Not Completed Background Check for Some of Program Administrators.Checks Expected to Be Completed by 900105 ML18094B2331990-01-0303 January 1990 Certifies Util Implementation of fitness-for-duty Program, Per 10CFR26.Training Element Required by Rule Completed on 891215.Chemical Testing for Required Substances Performed at Min Prescribed cut-off Levels,Except for Marijuana ML17347B5051990-01-0202 January 1990 Certifies That Util Has fitness-for-duty Program Which Meets Requirements of 10CFR26.Util Adopted cut-off Levels Indicated in Encl ML20042D3731990-01-0202 January 1990 Forwards Revised Crisis Mgt Implementing Procedures, Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9, Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML17347B4961989-12-28028 December 1989 Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Considering Expansion of Plants to Include Addl safety-related & Position Changeable Valves W/ Emphasis on Maint & Testing ML20042D3381989-12-28028 December 1989 Forwards Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. Util Will Comply W/Ltr Recommendations W/Noted Exceptions.Response to Be Completed When Ltr Uncertainties Cleared ML18094B2201989-12-27027 December 1989 Advises of Intent to Provide follow-up Response to Generic Ltr 89-10 by 900831 to Describe Status of Program, Recommendation Exceptions & Any Schedule Adjustments ML18094B2291989-12-27027 December 1989 Requests to Apply ASME Section XI Code Case N-460 to Facilities Re Reduction in Exam Coverage on Class 1 & 2 Welds.Fee Paid 1990-03-01
[Table view] Category:ENGINEERING/CONSTRUCTION/CONSULTING FIRM TO NRC
MONTHYEARML19327A8691989-09-0707 September 1989 Submits Info Re Alchemie & Anderson County Bank Financing Transaction ML19332F2171989-07-10010 July 1989 FOIA Request for Documents Re Communications Between Ofcs of Edo,Deputy Edo,Ofc of Director,Regional Administrators & Commissioners Ofcs Re Plants During period,890301-0615 ML20246F1311989-06-26026 June 1989 FOIA Request for Minutes of Meeting Ref in 820210 Memo from NRR Re Design & Const Assurance for Upcoming OL Cases ML20245D9851989-06-22022 June 1989 Forwards 21 Insp Rept Executive Summaries,Per NRC Contract NRC-03-87-029,Task Order 037.Individual Quality Evaluations of Insp Repts Also Prepared ML20247P9411989-05-17017 May 1989 FOIA Request for Final Open Item Transmittal Ltrs Per NRC Insp Procedure 94300B for Listed Plants ML20245C1421989-04-0303 April 1989 Forwards Endorsements 75,108,108,96 & 110 to Maelu Policies MF-56,MF-26,MF-58,MF-39 & MF-52,respectively & Endorsements 93,129,127,109 & 122 to Nelia Policies NF-186,NF-76,NF-188, NF-151 & NF-173,respectively ML20247N1551989-03-31031 March 1989 Forwards Revised Proprietary Conformance of HPCS Div to NUMARC 87-00 Alternate AC Criteria, for Review as Result of Comments from 890216 Meeting.Rept Withheld ML20246M7331989-03-15015 March 1989 Responds to NRC Info Notice 88-082, Torus Shells W/ Corrosion & Degraded Coatings in BWR Containments. Summary of Relevant Projects for Various Utils Successfully Employing Underwater Alternative to Draining Vessel Encl ML20246N1281989-02-27027 February 1989 FOIA Request for Jl Smith to NRC Re Spent Fuel Shipment from Brunswick Nuclear Power Station to Harris Plant ML17285A2351989-02-0606 February 1989 Forwards Proprietary Draft Conformance of HPCS Div to NUMARC 87-00 App B Aac Criteria, for 890214 Meeting ML17285A2341989-01-0606 January 1989 Discusses Issues Highlighted at BWR/6 Alternate Ac Task Force Meeting on 881115,including Need for Capability of Div III Sys to Maintain Plant in Safe Shutdown Condition (Hot Shutdown) for Min of 4 H ML20206H0511988-11-14014 November 1988 Urges Relicensing of Pilgrim & Expedited Operation of Seabrook.Newspaper Clipping Encl ML20150D5721988-03-0808 March 1988 Provides Summary of Utils Test Results & Calculations on Emergency Diesel Generators,Including Review of Design of Static Exciter & Voltage Regulator for Emergency Diesel Generators ML20196C1591988-02-0303 February 1988 Forwards Monthly Progress Rept P-C6177-5, Independent Analysis & Assessment, for Period Ending 880131 ML20147G0741988-01-18018 January 1988 FOIA Request for All Documents Re NRC Investigation of Wg Dick Allegations About S&W & Lilco Re Performing NRC Instructions to Bring Facility Up to Fuel Load Stds ML20235A1251987-12-16016 December 1987 Forwards Info Re Resource Technical Svcs,Inc,Including Summary of NRC Contract Work,Nrc Form 26 for Three Existing Contracts,Audit Info,Work History & Lists of Expertise Available for Special Insps & of Current Resource Svcs ML20237B8051987-11-25025 November 1987 FOIA Request That Encls to Listed Documents,Including NRC Forwarding Amend 1 to License NPF-73,be Placed in PDR ML20236S4291987-10-20020 October 1987 FOIA Request for Listed Documents,Including Encls from NRC Requesting Addl Info on Gpu Topical Repts TR-033 & TR-040 & Encl to NRC Meeting Summary Re SPDS ML20236U5221987-10-19019 October 1987 FOIA Request for LERs for Listed Plants,Including All Attachments & Encls from Original Documents ML20235V1321987-08-28028 August 1987 Forwards EGG-NTA-7471, Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28.... Based on Licensee Responses,Plants Reviewed Conform W/Exceptions Listed in Section 14 ML17342A7741987-07-13013 July 1987 Forwards Technical Evaluation of Rept, Retran Code: Transient Analysis Model Qualification, Dtd Jul 1985. Criteria for Use of Single & Two Loop Plant Models Listed. NRC Audit of Util QA Procedure Recommended ML20235K8731987-07-0909 July 1987 Informs That Tayloe Assoc Cannot Produce Mag or nine-track Tapes of Hearing Transcripts Until NRC Finalizes Arrangements W/Others to Provide Lexis Format,Including Library & File Numbers & Segmentation Info ML20237J2141987-07-0202 July 1987 FOIA Request for Listed Documents Ref in NUREG-1150 & Related Contractor Repts ML20238E3011987-06-29029 June 1987 FOIA Request for All Documents Described in App,Including Listed LERs & Revs for Plants,W/Original Attachments & Encls ML18052B1911987-06-17017 June 1987 Forwards EGG-NTA-7720, Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28,Reactor Trip Sys Vendor Interface:Calvert Cliffs-1 & -2,Millstone-2 & Palisades, Final Informal Rept. Plants Conform to Generic Ltr Item ML20234B6211987-05-12012 May 1987 Requests That Listed Plants Be Added to Encl 870508 FOIA Request Re 94300 Region Input on Plant Readiness ML20234B6571987-05-0808 May 1987 FOIA Request for Placement,In Pdr,Region Input to NRC Headquarters,Nrr Re Status of Listed Plants in Terms of Plant Readiness for OL IE Manual,Chapter 94300 ML20214R4051987-05-0808 May 1987 FOIA Request for Region Input to NRR Re Status of Listed Plants Readiness for Ol,Per IE Manual Chapter 94300 ML18150A1861987-05-0101 May 1987 Forwards EGG-NTA-7612, Conformance to Generic Ltr 83-28, Item 2.2.2 - Vendor Interface Programs for All Other Safety- Related Components,North Anna Units 1 & 2 & Surry Units 1 & 2, Final Informal Rept ML20214Q8801987-04-17017 April 1987 Forwards EGG-NTA-7591, Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface,Hatch-1 & 2,Millstone-1, Final Rept.Plants Conform to Item ML20214R0621987-04-17017 April 1987 Forwards EGG-NTA-7613, Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28,Reactor Trip Sys Vendor Interface,Arnold, Brunswick-1 & 2, Final Rept.Plants Conform to Item ML18150A1171987-04-14014 April 1987 Forwards Final rept,EGG-NTA-7625, Conformance to Item 2.1 (Part 2) Generic Ltr 83-28,Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. ML20214R8611987-03-27027 March 1987 Forwards EGG-NTA-7614, Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28,Reactor Trip Sys Vendor Interface:Cook-1 & -2,Haddam Neck, Final Informal Rept.Facilities Conform to Generic Ltr ML20214R1361987-03-26026 March 1987 Forwards Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28,Reactor Trip Sys Vendor Interface:Maine Yankee, St Lucie 1 &-2 & Waterford 3, Final Rept.Plants Conform to Generic Ltr ML20214R1861987-03-26026 March 1987 Forwards Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components,Haddam Neck & Millstone 1,2 & 3, Final Rept ML20211D6631987-02-12012 February 1987 Notifies of 830204 Meeting W/Util,Idvp,Nrc & BNL in San Francisco,Ca to Discuss Status of Containment Annulus Steelwork & Status of Auxiliary Bldg ML20211D7031987-02-12012 February 1987 Notifies of 830209 Meeting in San Francisco,Ca to Discuss Shake Table Tests of Electrical Equipment ML20211D7441987-02-12012 February 1987 Notifies of 830517 Meeting in San Francisco,Ca to Discuss Development of Piping Stress Intensification Factor ML20209A8551987-01-16016 January 1987 FOIA Request for Documents to Be Placed in Pdr,Including NRC Re Calibr of Test Equipment allegation,1986 Inservice Insp Repts for McGuire 1 & Surry 1 & NRC 830307 SALP on Nine Mile Point 2 ML20207K0151986-12-19019 December 1986 FOIA Request That Encls to Insp Rept 50-247/86-26,Byron Semiannual Radioactive Effluent Rept & Millstone 1 & 2 SALP Rept Be Placed in PDR ML20211P2051986-11-24024 November 1986 FOIA Request for La Crosse & Big Rock Point Semiannual Effluent Repts & Turkey Point & St Lucie SALP Repts ML20214R8831986-11-0505 November 1986 FOIA Request for Encls to 860821 SALP Repts ML20213F8841986-10-30030 October 1986 FOIA Request for Encls to NRC 860724 & 31 Requests for Addl Info Re Vermont Yankee Spent Fuel Pool Expansion & Browns Ferry Seismic Reevaluation Program,Respectively ML20209D1691986-10-29029 October 1986 Forwards Rev 3 to EGG-EA-7035, Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Braidwood Units 1 & 2,Bryon Station Units 1 & 2,Callaway Plant Unit 1,Indian Point.... Licensees Conform to All Items W/Exception of Trojan ML20214J9761986-10-15015 October 1986 FOIA Request for Containment Event Trees for Listed Facilities,Technical Repts & Memoranda Re Interpretation & Quantification & Identification of FIN Numbers,Contractors & Investigators Involved in Creation/Analysis of Event Trees ML20214K0231986-10-15015 October 1986 FOIA Request for All Documentation Re Accident Sequence Evaluation Program Repts Re Listed Facilities in Preparation for NUREG-1150 ML20245A4451986-09-25025 September 1986 Forwards Revised Draft EGG-NTA-7188, Conformance to Generic Ltr 83-28 Item 2.1 (Part 1) Equipment Classification Hope Creek,Peach Bottom 2 & 3,Perry 1 & 2 & Pilgrim 1 ML20215M9941986-05-21021 May 1986 FOIA Request for Documents Re Eg Case 771201 Memo to Tj Mctiernan Concerning Chronology of Events Associated W/ Facility Fault Assessments ML20210T4441986-03-27027 March 1986 FOIA Request for Initial (Cycle 1) Startup Test Repts & Suppls for Seven Plants & Original Monthly Operating Rept for June 1983 for Virgil C Summer Plant ML20195C5951986-03-14014 March 1986 FOIA Request for Structural Integrity Test Repts for Shoreham,Limerick-1,Nine Mile Point-2 & Susquehanna 1989-09-07
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 ML15217A1031990-02-28028 February 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20006G0621990-02-22022 February 1990 Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld ML20006E5881990-02-20020 February 1990 Forwards Proprietary Response to NRC 890725 Questions Re Vipre Core Thermal Hydraulic Section of Topical Rept DPC-NE-3000 & Rev 2 to Pages 3-69,3-70,3-78 & 3-79 of Rept. Encls Withheld (Ref 10CFR2.790) ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML20006E9071990-02-16016 February 1990 Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML20011E6151990-02-12012 February 1990 Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) ML20011E5571990-02-0808 February 1990 Forwards Us Bankruptcy Court for Eastern District of Tennessee Orders & Memorandum on Debtors Motion to Alter or Amend Order & Opinion Re Status of Sales Agreement Between DOE & Alchemie.Doe Believes Agreement Expired on 890821 ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested ML20011E5981990-02-0505 February 1990 Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20006C5661990-01-31031 January 1990 Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants ML20006B7961990-01-29029 January 1990 Forwards Summaries of Latest ECCS Evaluation Model Changes ML20006C6711990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Plants Have Established Preventive Maint Program for Intake Structure & Routine Treatment of Svc Water Sys W/Biocide to Control Biofouling ML20006D6611990-01-29029 January 1990 Advises That 900117 License Amend Request to Remove Certain cycle-specific Parameter Limits from Tech Specs Inadvertently Utilized Outdated Tech Specs Pages.Requests That Tech Specs Changes Made Via Amends 101/83 Be Deleted ML20011E2521990-01-29029 January 1990 Forwards Proprietary Safety Analysis Physics Parameters & Multidimensional Reactor Transients Methodology. Three Repts Describing EPRI Computer Code Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790) ML18153C0951990-01-29029 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted ML18094B2861990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Aggressive Program of Monitoring,Insp & Matl Replacement Initiated in Advance of Generic Ltr 89-13 Issuance ML18153C0871990-01-26026 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures to Be Revised & Familiarization Sessions Will Be Conducted Prior to Each Refueling Outage ML20006D2431990-01-26026 January 1990 Provides Info Re Emergency Response Organization Exercises for Plants.Exercises & Callouts Would Necessitate Activation of Combined Emergency Operations Facility Approx Eight Times Per Yr,W/Some Being Performed off-hours & Unannounced ML19354E4191990-01-25025 January 1990 Comments Re Issuance of OL Amends & Proposed NSHC Determination Re Transfer of Operational Mgt Control of Plants & Views on anti-trust Issues Re Application for Amend for Plants ML19354E6711990-01-24024 January 1990 Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226 ML17347B5451990-01-24024 January 1990 Informs of Plans to Apply ASME Code Case N-356 at Plants to Allow Certification Period to Be Extended to 5 Yrs.Rev to Inservice Insp Programs Will Include Use of Code Case ML19354E4451990-01-22022 January 1990 Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters ML19354E4461990-01-22022 January 1990 Forwards Proprietary Rev 1 to DPC-NE-2001, Fuel Mechanical Reload Analysis Methodology for MARK-BW Fuel, Adding Section Re ECCS Analysis Interface Criteria & Making Associated Administrative Changes.Rev Withheld ML20005G7161990-01-20020 January 1990 Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl ML20006A8001990-01-19019 January 1990 Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21) ML16152A9091990-01-18018 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. W/900131 Release Memo ML18153C0771990-01-17017 January 1990 Forwards North Anna Power Station Emergency Plan Table 5.1, 'Min Staffing Requirements for Emergencies' & Surry... Table 5.1, 'Min Staffing Requirements...', for Approval,Per 10CFR50.54(q),NUREG-0654 & NUREG-0737,Suppl 1 ML20006A2011990-01-16016 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel in Anchor Darling Swing Check Valves.Eight Subj Valves Identified in Peach Bottom Units 1 & 2 & Will Be Returned to Mfg ML20006A6241990-01-16016 January 1990 Forwards Draft Qualified Master Trust Agreement for Decommissioning of Nuclear Plants,For Review.Licensee Will Make Contributions to Qualified & Nonqualified Trust as Appropriate ML18153C0731990-01-15015 January 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or or Valves.... Util Replaced Studs in twenty-five Valves ML20005G6431990-01-10010 January 1990 Responds to Generic Ltr 89-21 Re Implementation of USI Requirements,Consisting of Revised Page to 891128 Response, Moving SER Ref from USI A-10 to A-12 for Braidwood ML20006A8201990-01-10010 January 1990 Forwards Errata to Rev 3 to BAW-1543,Tables 3-20 & E-1 of Master Integrated Reactor Vessel Surveillance Program Reflecting Changes in Insertion Schedule for A5 Capsule for Davis-Besse & Crystal River ML20006B8821990-01-10010 January 1990 Reissued Ltr Correcting Date of Util Ltr to NRC Which Forwarded Updated FSAR for Byron/Braidwood Plants from 881214 to 891214.W/o Updated FSARs ML20005G7601990-01-0404 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Plan. Privacy Info Should Be Deleted Prior to Placement in Pdr.W/ D Grimsley 900118 Release Memo ML18094B2331990-01-0303 January 1990 Certifies Util Implementation of fitness-for-duty Program, Per 10CFR26.Training Element Required by Rule Completed on 891215.Chemical Testing for Required Substances Performed at Min Prescribed cut-off Levels,Except for Marijuana ML18153C0491990-01-0303 January 1990 Advises of Implementation of fitness-for-duty Program Which Complies w/10CFR26.Util Support Objective of Providing Assurances That Nuclear Power Plant Personnel Will Perform Tasks in Reliable & Trustworthy Manner ML20005F4641990-01-0303 January 1990 Advises That Licensee Implemented 10CFR26 Rule Re fitness-for-duty Program W/One Exception.Util Has Not Completed Background Check for Some of Program Administrators.Checks Expected to Be Completed by 900105 ML20042D3731990-01-0202 January 1990 Forwards Revised Crisis Mgt Implementing Procedures, Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9, Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML17347B5051990-01-0202 January 1990 Certifies That Util Has fitness-for-duty Program Which Meets Requirements of 10CFR26.Util Adopted cut-off Levels Indicated in Encl ML17347B4961989-12-28028 December 1989 Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Considering Expansion of Plants to Include Addl safety-related & Position Changeable Valves W/ Emphasis on Maint & Testing ML20042D3381989-12-28028 December 1989 Forwards Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. Util Will Comply W/Ltr Recommendations W/Noted Exceptions.Response to Be Completed When Ltr Uncertainties Cleared ML18094B2201989-12-27027 December 1989 Advises of Intent to Provide follow-up Response to Generic Ltr 89-10 by 900831 to Describe Status of Program, Recommendation Exceptions & Any Schedule Adjustments ML18094B2291989-12-27027 December 1989 Requests to Apply ASME Section XI Code Case N-460 to Facilities Re Reduction in Exam Coverage on Class 1 & 2 Welds.Fee Paid ML20005E1911989-12-26026 December 1989 Forwards Revised Page 2 Correcting Plant Implementation Date for USI A-24 Requirements in Response to Generic Ltr 89-21 ML18153C0261989-12-26026 December 1989 Responds to Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & surveillance.Motor-operated Valve Program Structured to Allow Similar Approach to motor-operated Dampers.Results Will Be Submitted in 30 Days 1990-03-01
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F' R A N K ' N E U M A N N 4 s4 s raftfy*FIFTM AVENu r N.E.
s EATTLE. wAs H., g e s c s v-July 26, 1963.
Dr. Robert H. Bryan, Division of Licensing and Regulation, U. 8. Atomic Energy Commission, Washington 25, D. C. ,s
' Dear Dr. Bryans ..
Enclosed are two memoranda coussenting'on'(1) Prof.
- Housner's processed memoranda distributed at Argonne Laboratories l on August 2,1963 and (2) statements made in the course' of his talks -
there. I presume you would want to know about any diffe;ionces in _
basic seismological concepts that' exist between us.
Professor Housner is rather unique in American seismology in that' by training he is not a seismologist (so far as I know) yet is.
almost prolitio in his elucidation of' seismological principles to the
. engineering profession. He speaks of his concepts as facts and,- .
since he seldom quotes the views of others, the listener may easily asstne his views represent those.of the entire seismological profes-sion. Caltech's seismologist Dr. C. F. Richter, who in 1957 wrote a-768-page book on " Elementary Seismology", frequently mentions Housner.
as an earthquake engineer but says-little or riothing about his purely seismological concepts. Most seismologists would hesitate to question the late Dr. Gutenberg's conclusions on the interpretation of seismo-l logical data, or question other phenomena that virtually all seismolo-gists have accepted as authentio-for many years. .Housner ovidently places the results of his mathematical studies above everything else; to him they are the facts.- -
Please let me know in case I can do 'anything that will help ~ mat-ters along.
Sincerely your .
Y^auR . wg Frank Neumann.
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d* NOTES ON SI MEMORANDA DISTRIBUTED BY PROF.( jUSNER AT THE ARGONNE LABORATORIES ON JULY 2, 1963 l (By F. Neumann)
]
Memo No.1 Table I. Data from " United States Earthquakes 1933 61".. 1 y-This is a series of annual reports,many of which I authored. Ordinarily distance to fault was'not given, nor the durations; some of the tabular figures must be Housner's.
Housner is evidently trying to tie magnitude in with something but not having much success. I used the same figures and, with distance and I
acceleration as arguments, plotted the actual magnitudes. There was no j consistency anywhere. I(do not see what purpose the ,two Housner charts serve.
Memo No.2 Table II. Soectrum intensities. 1 I have never seen any need for spectral intensities that are based on j (x-y) instead of y, where y is the motion of the ground and x the motion of the oscillator. In his 1952 paper on this subject he tried to relate it to MM intensity but there was poor agreement. He admitted that they j are not the same thing which is quite obvious. Again, I do not see the purpose of the chart.
Memo No.3 Effect of ground on intensity of shaking.
Housner evidently does not believe in the results published in my booklet '
" Earthquake Intensity and Related Ground Motion". The first sentence i is contrary to the findings of many seismologists especially those at the Pasadena (Caltech) Seismological lab. They found differences of 10 to 1 between alluvium and : ock motions; I have suggested a 22:1 ratioti, the U.S. Bureau of Mines, in blasting vibrations, finds ratios of approximately 30:1 between alluvium and rock. Housner admits it enuld be more than 2:1 if there was " appreciable model excitation" but apparently he has not observed it on " firm" alluvium. In my AEC report now in preparation, a ratio of 2:1 is suggested between " sedimentary basement k
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- rock" and " granitic basement rock". What is "well known" about the 2:1 ratio as Housner states in his first sentence?
In showing an example, Housner's "best comparison" is rather unfortunate v- ,
in that we have no reliable record of the acceleration at long Beach and this is stated in the Coast Survey report. The horizontal components are so badly overlapped they are impossible to separate (I spent a long i time trying to do this right af ter the record was tained). The reported l
.23 g is open to doubt. The distance to the " maximum intensity" epicenter ;
near Signal Hill is 4 miles, not 17. This single example is entirely l i
inadequate to prove Housner's 2:1 ratio idea. The Coast Survey currently )
- i adjusts its accelerometers to accomodate expectable accelerations l of .25 g on rock, .40 g on residual clay and shale, and .70 g on I
alluvium. This is a 3:1 ration intended to take care of good building
)
1 sites.
As far as the Taft record is concerned, just what acceleration should l one expect for a shock of given magnitude at a given distance? I know 1
of no formula that would enable one to reach Housner's conclusion.
Mrmo No.4 El Centro. May 18. 1940 earthauake ground motion. -
~
The U.S.C. & G.S. did not rate the inte sity at El Centro as IX but VII to VIII. Ulrib's report,to which reference is made, was a prelim- '
inary report; VII to VIII appears in the Survey's final reports. After special study of descriptive material, I judged it to be MM-8 3 See ray current report for further discussion.
Where were the two farm houses 1000 ft. from the fault that were not
. damaged? Intensity or damage is primarily a function of distance to b
epicenter, not distance to fault. (Housner evidently does not accept I- this thesis, he believes in a " planar
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-3 j M:do No.5 Hebren Lake. Montana Earthouake.
l There is nothing special about the point raised that "a sizable' area in !
the epicentral region was subjected to almost the same level of acceler-v- 1 ations...as in West Yellostone or places 5 to 10 miles from the fault". j i
Generally, however, the acceleration would be somewhat greater and the duration less as one gets closer to the epicenter, the intensity remaining the same. Writers frequently confuse acceleration a'n d intensity.
Dixie Valley--Fairview Peak Earthquakes. -
l
- i Without mention of the epicentral distance of the structurea (near the 1
f cult) that suffered only minor damage, this memorandum.has little or no sig ificance. .
l l Mamo No.6 Acceleration adiacent to a fault produced by the slip displacement.
l l l From the discussion of the El Centro record one would expect to learn j 1
just what this acceleration was at El Centro but it is not to be found. I i
If one assumes that this first motion had the basic characteristics of a sinusoidal motion, which seems reasonable (the computed velocity and displacement curves have such characteristics), and assumes a resultant l
velocity of about 35 cm/sec combined with a period of 3 5 or 4.0 second, the corresponding acceleration would be about .06 g. (This is shown in
~
all of my period-amplitude graphs for the El Centro motion, i.e. Fig.6 {
of my report mailed on July 20,1963.) In fact, a wave of this order i
of period and maximum acceleration can be drawn on the acceleration curves in Memo No. 6 if one tries to draw a curvilinear axis of such nature that the areas (of the high frequency waves) above this axis will equal the areas below it.
I do not see eye-to-eye with all of Housner's reasoning in this memorandum, largely because we have different concepts on how earthquakes are ganerated (fault locks vs. uniform planar friction?). I think the high frequency
' waves were generated the instant the rocks were ruptured at the fault S
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'. '. ' lock, simultaneously with the start of the fault movement. The waves generated by these two events are independent wave forms that have dif.
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forent dispersion characteristics.
y Neither Housner's statementa of " fact" nor mine should be accepted at face value as facts which seismologists generally accept; it is all conjecture which may or may not have useful engineering application.
I cannot see the purpose of this memo in the current' project.
If the El Centro fault had been " greased" no energy could have been stored up and there would have been no earthquake.
M:mo No.7 Damare to structures adjacent to the San Andreas Fault. San Francisco j
earthquake. 1906.
This heading is misleading. The official name is "The California
=
Earthquake.. .. ,"; it was Bodego Head's earthqake as much as San Francisco's, l
both being about 40 miles from the epicenter.
This is an extr2 ordinary document in that Housner, in the opening paragraph, int,roduces an entirely new concept of earthquake intensity, different from anything the Coast and Geodetic Survey, the Caltech Seismological Lab or the Berkeley Seismological Station, use in there - -
^
l published evaluations of intensity. He states that "those structures dich have receihedd little or no damage are good indications of the :
upper bound for intensity of ground motion. For example, if an unreinforced brick chimney was bot broken off, it is clear that the ground motion was not sufficiently intense to destroy the stronger chimneys". He wants to measure intensity by damage that was not done while everyone else measures it by damage that was done. All intensity scales and the people who use them are geared to using positive fact rather than negative assumptions in evaluating intesity from descrip.
tive information so that, invariably, a published intensity means the
. maximum that can be derived from the descriptive data regardless of y
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the fact that other information could indicate intensities (in the -5 same town) that could be one, two, three or even four grades of intensity lower.
v-Nevertheless, Housner uses this kind of logic to justify taking only that information from the Lawson report which yields the lowest, not the highest intensity. In item 3, for instance, he states that "only three or four houses were passed, and these were uni $jured except for broken chimneys a . He does not report that just beyond -this a hotel was badly wrecked and a barn near Bodega Head was completely wrecked.
This is typical of virtually all of the 14 items Housner'inentions to show how low the intensities were. I could summarize many pages of notes that could be included or appended to this letter but they would all boild
, down to this same basic attitude. ,
P'erhaps the most amazing statement of all is the last paragraph in which he states "From the foregoing description of damage it can be concluded l
that the intensity of gr und shaking in the vicinity of the fault was not remarkably intense. Except for cases of special ground conditions,
'~
the damage appears to be consistent with a modified-Mercalli intensity ~
rating of about VII to VIII. It also appears to be consistent with
~
ground motions whose maximum acceleration was approximately 15 to 20%g."
For one thing, he does not describe the damage except that which applies to minimum intensity. This would be consistent in part with my conclusions if one agrees that intensities of VII to I were observed within say 30 l
miles of the epicenter. Housner,would agree to the VII or VIII.
I have spent muc) time and made many notes on the descriptive information in the State Commission's Report to find evidence that intensity along the faul-t might be less than a few miles back. No evidence has been found. it would take weeks to make a thorough study of the entire report but enough has been done in the general epicentral area to feel that this is a true statement. It is felt that if all the intensities were carefully g fr
_ - _ _ _ _L
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.~ . re-evaluated on the MM scale the intensity distribution over the entire l
shaken area would be very similar to that shown elsewhere for the Puget Sound sjpek of 1949 Maximum inten'sities would be registered on poor
.l ground out., to 100 miles or more. Epicentral distance and local geology ]
would be the controlling factors.
Santa Rosa was one of the worst shaken towns in California.. 30 miles I
/ )
from epicenter. " Practically everyone on foot at the. time was throurr J 1
i to the ground...". Other evidence shows that some had difficulty standing, t
others.did not fall. In the epicentral area at some places all men and !
,- l cattle were thrown to the ground, sometimes twice. In iha absence of strue-tures in the epteentral area these facts indicate that the intensity was _
quite as great in the epicentral area as in' Santa Rosa, probably the l 1
- most damaged town in California. (This follows the pattern of the :
Puget Sound shock in 1949.)
In the last paragraph, p.4, how does Housner know that the maximum acceleration was approximately 15 to 20%f At Mr. Doda's ranch, 150 feet west of fault a daughter was lifted off the floor more than once; 1
a ranch hand saw water tank tower lifted vertically upward 5 feet and then j collapse in ruins. Was this 20%gf A bed was also lifted from the floor at Seaview near Fort Ross. .
This entire memorandum is quite obviously an effort to downgrade
- intensities in epicentral areas and is contrary to all the conclusions reached by the writer in his booklet " Earthquake Intensity and Related Ground Motion". l 4
i s;
[- -
J CGGIENTS ON VARIOU8 STATEMENTS MADE BT PROF. G.-W. HOUSNER .
AT ARGONNE LABORATORIES OF A. E. C. ON JULY 2,1963.
v-
', (ByF.Neumann) .
]
l
- 1. statement The longer the fault the sreater the energF release. -
)
Comment: This should be accepted with cautions some strong shocks' _
a show no surface faulting. Magnitude is the best measure of energy
-1 releases the area over which a shook is perceptible is perhaps the i i
i next best measure. I.have never seen any statist.ioal data to' tie in length of faulting with overgy releases it is primarily a theoretical conclusion that could be countered by the " fault lock" theory of Ben . -
ioff which in the writer's opinion fits observed intensity distribution
. < =
in shaken areas better than Housner's " Planar" energy source theory. -
- 2. Statement: Frces O to 10 miles from a fault there is uniform response-(intensity because of focal depth. .
Comment: Is is found fra basement rock (ministan) intensity graphs that one can go to within 3 miles of an epicente'r before uniform maximtan' in- .
tensity is reached. Elsewhere Dr. Housner tries to show that me.ximian -
intensity occurs several miles from a fault. __ ; 4
~
j
- 5. Statements Farm houses along the El Centro Fault were not damaged.
Comment. In his distributed notes he gives distances to faults but not ! ;
to opicenters. Epioentral distance, not fault distance determines the
- intensity.' In printed notes on the 1906 shook he oited a similar case t
i.
that was 150 miles from the epicenter. Why. should there be damaget
- 4. Statement: The velocity spectrtan is a good measure of intensity. ]
Comment. In his 1952 report on " Intensity of Ground Motion During '
Strong Earthquakes" he concludes: "There is only an approximate agree- ,
, ment between the spectrian intensity of an earthquake and the Modified
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, , 2 Merot111 intensity. These two lo not measure prooisely the same thing.
and it isv, concluded that the spectrten intensity is more meaningful for engineering design". Actually, spoetral intensity is a measure of the differential motion between building (or oscillator) and ground, not a measure of the ground motion. I do not know of anyone but Housner who uses it.
~'
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- 5. Statement: He gave impression that El Centro earthquak'e ' motion was about {
1 l the strongest that may be expected anywhere. l Comment: In the reference just quoted he concludes:" It l's estimated that i t1{
the maaimum ground acceleration to which a California city may be subject- _lf Ii ed is 0.66g or approximately twice that experienced at El Centro - ". The
,, writer has cited 0.7g as a minimum and 1.0g as a possible maximum for the mi il 1906 earthquake. 1
- 6. Statement: There is no peaking (of intensity) in.the vicinity of a fault.
Comment: All intensity distribution maps show that there is a peaking of basement rock (minimum) intensities in the immediate epicentral sons which
-I is either on or above a fault. This does not support Housner's planar
~
energy source theory on which the above statement is , based.
i 4
- 7. Statements Faults move in jerks as shown by peaks on mooelerograms. , !
Coment Why then did the El Centro record show not only 5 peaks while the fault was slipping but a continuous series of peaks for 30 seconds after? The writer does not believe the various wave types are generated
j in the manner suggested by Housner who also distibuted a note on the sub- i i
ject.
l
- 8. Statement: Long Beach epicenter was 17 miles from seismograph station. jj l.
Comment The intenrity distribution map shows maximum intensity at Sig- j- {
nal Hill only a few miles away where aftershocks also centered. The l i i ep'icenter 17 miles away was a foreshock that triggered the Signal Hill shookm a rather common occurrence.
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- 9. Statement: He disbelieves Gutenberg's otatenent that in the Imperial J
. I Valley 19,49 earthquake the motion on alluvita was 8 times greater than- -
" i on rock. )
1 Comment: I believe with outesb' erg that this actually did happent it is !
ecumonplaosforfourgradesofintensitytobereportedatthesameepik 3
,f 1 central ' distance but in different areas. This is equivalent to an 8-fold l
range in ground motion. f lo.-8tatements There were stronger motions 5 miles from the San Andreas Fault than right on it. ,
Ccament. This is challenged in comments on his -printed memorandum cover- _
ing this subject. -
1 l
- 13. Statement: Theenergysourceidplanarincharacter. =
Comments.The writer believes that all intensity distribution maps support the fault look concept -- that a fault plane becomes distorted thus pre-
^
l venting smooth motion along the fault surface. When accumulating stresses are sufficient to overcome the look this area' boocsies the focus of an earthquake and the source of maxistan anergy release. Basement rock at-tenuation graphs indicate a circular radiation of energy, not elliptical as called for by the planar energy concept. l l
- 12. statement. 0.5g is a reasonable estimate of the " upper bound" associated !
with any fault displaosment. He does not accept the observation that in , i I
the great Assam earthquake of 1897 the vertical' accelerations exceeded g. I Comnent. In the writer's latest revision of his A.E.C. seismological're- '
h port the reasons are given for believing that g has been exceeded in vert-ioal motion of the ground. In the 1906 shook one person and a bed were. .
thrown upward off the floor and or the ground a water tank was reported 3 to have raised up off the ground and then collapsed.
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- 13. Statement: One mile from the San Andreas Fault 0.2g was an upper limit in 1906. '
v- . .
Ceemente Santa Rosa, in an alluvial' valley 30 miles from the epicenter and 18 miles from the fault, was perhaps the most severely damaged town in California. Compared with damage in other shocks the writer telieves .
./
the acceleration must'have been' alose to 0.2g here.with a duration very .
auch longer than near the epicenter. . This'would not seem incompatible with an acceleration of 0.7 or 1.og at the epicenter.
- 14. Statement In citing factual data from the 1906 earthquake report Hous-
. i 1
nor cited the slight damage to Chittenden Bridge over the Pajarro River ,.
which is practically on the fault.
Comment: There is no lack of evidenos to show that even a large fault .
displacement 18 not necessarily sooespanied by violent vibrations. The important thing is How far was it fres'the opioenter. In this case it .
was 100 miles. -
w j
- 15. Statement Could have a 1906 earthquake every day without damaging the 1
proposed power plant. -}
~
Comments Does Housner not know that all of the Coast Survey's strong i i
4 notion data show that intensity, which is equivalent to damaging po-
' m' tential, is a function of durationt This is indeed a rash statement )
i considering that 700 people were killed in 1906 and the damage in to- t
- i day's dollars would be between one and two billion dollars. 1
- 16. Statement: In California building designa provide for only about one- 1; 2!
fourth the theoretical earthquak's forces. .
I Comment: The usual explanation for this is that structures absorb energy- }
g4 and there are also other reasons that have more of an engineerids than j i
seismological basis. I seldom if ever hear about what part resonance
' plays in building responses to earthquake' forces. All spectra represent.
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e President John F. Kennedy'- OM 5 IAg ylle C6
. ?!hite Housa >'
Yiashington, D.C.
Re: Nuclear Power Plant at Bodega
Dear President Kennedy,
Bay, Califonnia Please use my le tter as one of many in protesting the
. I building the Nublear Power Plant at Bodega Bay, California.
e' j It seems to me that the indication of this proposal
} ' em)odies an attempt at furthering security for the' - i l ^ ', -people' of the world. However' it .also threa tens the ,
security and health of the people in the immediate area. I am sure there are areas of the United States i j less pophisted and less prone to endanger the lifes 7 '!
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l 1 of so many people that would better suit the building
-g r ! of the plant, if the building of 'such a plant is J l necessary. . ,
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- ,a I Thank you for your attention. ,
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;g.gc; Respectfully, j 15 5 m, l
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..=. - . . t Josephine Henson
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7 ^~' 969 Dolores Street l
@; San Francisco 10, . Calif. !
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NO ACTION NECESSARY COMMENT O eri CLAS $1F.s POST OFFICE FILE codes REG. Not DESCRIPT60N (Must Se Unclassified) REFERRED TO DATE RCCEIVED By DATE 14r. req. answers b sees om,etions in re to the propose:1 plant at k4egn head,. Stranis t 4-7 14/ suppl fiJe er - FJL & CTT'N e .a_.-
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