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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20248E9391989-09-29029 September 1989 Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed ML20248C8311989-09-20020 September 1989 Request for Hearing by Alchemie.* Forwards Response & Request for Hearing,In Response to NRC 890818 Order Modifying License & Order to Show Cause Why Licenses Should Not Be Revoked,For Appropriate Action ML20247H9261989-09-0909 September 1989 Advises That SALP Meeting for Facilities Scheduled for 891115.Assessment Input Should Be Submitted by 891016 ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247B7541989-07-19019 July 1989 Confirms That Licensee 880711,890221 & 0630 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Licensing Action for TACs 69886,69887,69893 & 69894 Considered Complete ML20247E6721989-07-17017 July 1989 Proposes Closeout of Plant Correspondence Control Ticket Re Environ Conservation Organization Request for Notification Whenever License Amend Requests Result in Impairment of Plant Operability.Intervenor Will Be Placed on Svc List ML20246K5991989-07-12012 July 1989 Notification of 890725 Meeting W/Util in Birmingham,Al to Discuss Status of Current Licensing Activities & Corporate Initiatives for Plants.Meeting Agenda Encl ML20246L6801989-07-10010 July 1989 Notification of Significant Licensee Meeting 89-101 W/Util on 890718 in King of Prussia,Pa to Discuss Util Engineering Reorganization ML20247A9561989-07-0606 July 1989 Notification of 890717 Meeting W/Lead Plant Utils in Rockville,Md to Discuss Implementation of Revised STS ML20246H3771989-05-12012 May 1989 ALAB-913.* Advises That Time Provided within Which Commission May Act to Review Aslab Decision ALAB-913 Expired.Commission Declined Review.Decision Became Final on 890501.W/Certificate of Svc.Served on 890512 ML20246P9601989-05-10010 May 1989 Discusses 890413 Meeting W/Rosemount & Industry Re Malfunctions of Rosemount Transmitters.List of Attendess, Agenda,Nrc Info Notice 89-042 & Viewgraphs Encl ML20245E9781989-04-17017 April 1989 Forwards Regulatory History AC83-2 Re Licensee Action During Natl Security emergency,10CFR50 (54FR7178) ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl ML20244A5571989-04-10010 April 1989 Notification of 890502 Meeting W/Util in Rockville,Md to Discuss Nonlinear Piping Analysis to Remove Snubbers & Pipe Supports ML20244A5461989-04-10010 April 1989 Notification of 890503 Meeting W/Util in Rockville,Md to Discuss Using Leak Before Break Methodology on Lines Connected to RCS ML20247B7351989-03-24024 March 1989 Notification of 890503 Meeting W/B&W,Inel & Util in Rockville,Md to Discuss Licensing Submittals for Plants ML20236A9721989-03-0707 March 1989 Forwards Feb 1989 Status Rept Re Current Review Milestones for Each Std Plant Project ML20235S6271989-02-28028 February 1989 Notification of 890307 Meeting W/Bwr Owners Group in Rockville,Md to Discuss Items of Current Interest.Agenda Encl ML20246N3171989-02-23023 February 1989 Notification of 890313 Meeting w/C-E in Rockville,Md to Discuss Results of Salem Project & Licensing of Future C-E Projects ML20245E9441989-01-31031 January 1989 Forwards Proposed plant-specific Backfit for Improved Auxiliary Feedwater Sys Reliability Analyses for Required Improvement in Secondary DHR Capability at Plant ML20196C2701988-12-0202 December 1988 Notification of 881207 Meeting W/Util in Rockville,Md to Discuss Dcrdr Submittal of 880825 ML20196B6081988-11-29029 November 1988 Forwards Status Rept for Nov 1988 Re Std Plant Design Technical Reviews ML20206M9231988-11-23023 November 1988 Lists Questions Raised by Board Study of Licensee Environ Repts on Facilities,For Responses & Comments.Served on 881125 ML20195J0141988-11-22022 November 1988 Notification of 881214 Meeting W/Util in Rockville,Md to Discuss Licensing Actions at Plants ML20206J6441988-11-16016 November 1988 Requests Responses to Listed Questions Re Proceeding, Including Explanation of Environ Consequences Caused by Movement of Centrifuges from State of Oh to State of Tn. Served on 881117 ML20206E6361988-11-14014 November 1988 Forwards Fr Notice Re Applications for Amends to Licenses DPR-51,NPF-6 & NPF-38,authorizing Addition of Sys Energy Resources,Inc as Licensee & Requests Comments on Antitrust Issues ML20206J5741988-11-10010 November 1988 Forwards H Thompson as Balance of NRC Response to State of Tn Re Enrichment of Naturally Occurring Radionuclides in Proposed Facilities,Per NRC ML20206J5571988-11-0909 November 1988 Forwards NRC Review & Evaluation of Facilities Security Plans Discussing Equipment & Procedures Used by Applicant to Meet Requirements in 10CFR95.W/o Encl ML20195G2581988-11-0808 November 1988 Partially Deleted Memo Re Commissioner Carr 880113-15 Visit to Plant,Meeting W/State of Mo Officials & Visit to Mallinckrodt,Inc ML20205T6491988-11-0707 November 1988 Ack Receipt of to Chairman Zech Re Alchemie Applications to Operate Facility for Separation of Stable Isotopes at Oak Ridge,Tn & Construct Similar Facility at Oliver Springs,Tn ML20205T5821988-11-0707 November 1988 Notification of 881115 Meeting W/Devonrue & Util in Rockville,Md to Discuss Proposed Std Alternate AC Design to Meet Station Blackout Rule ML20205R6731988-11-0404 November 1988 Forwards NRC Testimony of Jj Swift Addressing ASLB Inquiries of 881018 & Two Attachments.Related Correspondence ML20205N3691988-10-28028 October 1988 Advises That ASLB Tentatively Calling for Telcon on 881109 W/Parties & State of Tn to Discuss Need for Further Prehearing Conference & Other Scheduling Matters,Per 881026 Request.Served on 881031 ML20206B2481988-10-27027 October 1988 Notice of Significant Licensee Meeting 88-174 on 881118 in King of Prussia,Pa to Discuss Configuration Mgt ML20195B6131988-10-26026 October 1988 Forwards Status Rept on Std Plant Design Technical Reviews ML20205K3321988-10-26026 October 1988 Forwards SER Re Const Mod & Licensing of & Application for CP for Facilities.Nrc Review of Safeguards/Security Plans for Two Proposed Facilities Sent to Board & Applicant.Telcon to Discuss Scheduling Matters Requested.W/O Encls ML20155H3621988-10-18018 October 1988 Requests Addl Info Re NRC Environ Assessments Submitted on 880914 for Uncontested Proceedings,To Complete Review of Adequacy of NEPA Assessments.Served on 881018 ML20204G0741988-10-17017 October 1988 Forwards Mh Mobley from State of Tn to NRC Not Received Until 881014.NRC Will Address Matters in Ltr in SER ML20204J5841988-10-12012 October 1988 Forwards AEOD/E807, Pump Damage Due to Low Flow Cavitation, in Response to Item 5 of Actions Directed by EDO to Respond to Diagnostic Evaluation Team Rept.Nrr Issued Bulletin 88-004 Addressing Low Flow Problem ML20205L2281988-10-12012 October 1988 Forwards AEOD/e807, Pump Damage Due to Low Flow Cavitation, in Response to Action Item 5 Assigned by EDO in 880406 Memo Re Diagnostic Evaluation Team Rept for Plant. NRR Issued Bulletin 88-004 Addressing Recirculation Problem ML20155C6941988-10-0505 October 1988 Advises That Review Briefing for Listed Plants Scheduled for 881013.Viewgraphs Encl ML20205Q4941988-10-0303 October 1988 Discusses Concerns Raised by State of Tn Re Abundance of Naturally Occurring Radioactivity in Alchemie Processing. Enrichment of Naturally Occurring Radioisotopes Will Not Pose Significant Health Hazard ML20206E0861988-09-28028 September 1988 Requests Verbal Concurrence W/Publishing Notice of Receipt of Petition for Rulemaking PRM-50-50,per 880926 Telcon W/ C Young.Related Info Encl 1990-02-26
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20248E9391989-09-29029 September 1989 Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed ML20248C8311989-09-20020 September 1989 Request for Hearing by Alchemie.* Forwards Response & Request for Hearing,In Response to NRC 890818 Order Modifying License & Order to Show Cause Why Licenses Should Not Be Revoked,For Appropriate Action ML20247H9261989-09-0909 September 1989 Advises That SALP Meeting for Facilities Scheduled for 891115.Assessment Input Should Be Submitted by 891016 ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247B7541989-07-19019 July 1989 Confirms That Licensee 880711,890221 & 0630 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Licensing Action for TACs 69886,69887,69893 & 69894 Considered Complete ML20247E6721989-07-17017 July 1989 Proposes Closeout of Plant Correspondence Control Ticket Re Environ Conservation Organization Request for Notification Whenever License Amend Requests Result in Impairment of Plant Operability.Intervenor Will Be Placed on Svc List ML20246K5991989-07-12012 July 1989 Notification of 890725 Meeting W/Util in Birmingham,Al to Discuss Status of Current Licensing Activities & Corporate Initiatives for Plants.Meeting Agenda Encl ML20246L6801989-07-10010 July 1989 Notification of Significant Licensee Meeting 89-101 W/Util on 890718 in King of Prussia,Pa to Discuss Util Engineering Reorganization ML20247A9561989-07-0606 July 1989 Notification of 890717 Meeting W/Lead Plant Utils in Rockville,Md to Discuss Implementation of Revised STS ML20246D8841989-06-19019 June 1989 Staff Requirements Memo Re 890601 Briefing on Operating Reactors & Fuel Facilities in Rockville,Md.Commission Expressed Disappointment in Long Term Operating Performance of Turkey Point Nuclear Power Plant ML20246H3771989-05-12012 May 1989 ALAB-913.* Advises That Time Provided within Which Commission May Act to Review Aslab Decision ALAB-913 Expired.Commission Declined Review.Decision Became Final on 890501.W/Certificate of Svc.Served on 890512 ML20246P9601989-05-10010 May 1989 Discusses 890413 Meeting W/Rosemount & Industry Re Malfunctions of Rosemount Transmitters.List of Attendess, Agenda,Nrc Info Notice 89-042 & Viewgraphs Encl NUREG-1353, Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-13531989-05-0202 May 1989 Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-1353 ML20245E9781989-04-17017 April 1989 Forwards Regulatory History AC83-2 Re Licensee Action During Natl Security emergency,10CFR50 (54FR7178) ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl ML20244A5461989-04-10010 April 1989 Notification of 890503 Meeting W/Util in Rockville,Md to Discuss Using Leak Before Break Methodology on Lines Connected to RCS ML20244A5571989-04-10010 April 1989 Notification of 890502 Meeting W/Util in Rockville,Md to Discuss Nonlinear Piping Analysis to Remove Snubbers & Pipe Supports ML20247B7351989-03-24024 March 1989 Notification of 890503 Meeting W/B&W,Inel & Util in Rockville,Md to Discuss Licensing Submittals for Plants ML20236A9721989-03-0707 March 1989 Forwards Feb 1989 Status Rept Re Current Review Milestones for Each Std Plant Project ML20235S6271989-02-28028 February 1989 Notification of 890307 Meeting W/Bwr Owners Group in Rockville,Md to Discuss Items of Current Interest.Agenda Encl ML20246N3171989-02-23023 February 1989 Notification of 890313 Meeting w/C-E in Rockville,Md to Discuss Results of Salem Project & Licensing of Future C-E Projects NUREG/CR-5176, Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants1989-02-14014 February 1989 Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants ML20245E9441989-01-31031 January 1989 Forwards Proposed plant-specific Backfit for Improved Auxiliary Feedwater Sys Reliability Analyses for Required Improvement in Secondary DHR Capability at Plant ML20196C2701988-12-0202 December 1988 Notification of 881207 Meeting W/Util in Rockville,Md to Discuss Dcrdr Submittal of 880825 ML20196B6081988-11-29029 November 1988 Forwards Status Rept for Nov 1988 Re Std Plant Design Technical Reviews ML20206M9231988-11-23023 November 1988 Lists Questions Raised by Board Study of Licensee Environ Repts on Facilities,For Responses & Comments.Served on 881125 ML20195J0141988-11-22022 November 1988 Notification of 881214 Meeting W/Util in Rockville,Md to Discuss Licensing Actions at Plants ML20206J6441988-11-16016 November 1988 Requests Responses to Listed Questions Re Proceeding, Including Explanation of Environ Consequences Caused by Movement of Centrifuges from State of Oh to State of Tn. Served on 881117 ML20206E6361988-11-14014 November 1988 Forwards Fr Notice Re Applications for Amends to Licenses DPR-51,NPF-6 & NPF-38,authorizing Addition of Sys Energy Resources,Inc as Licensee & Requests Comments on Antitrust Issues ML20206J5741988-11-10010 November 1988 Forwards H Thompson as Balance of NRC Response to State of Tn Re Enrichment of Naturally Occurring Radionuclides in Proposed Facilities,Per NRC ML20206J5571988-11-0909 November 1988 Forwards NRC Review & Evaluation of Facilities Security Plans Discussing Equipment & Procedures Used by Applicant to Meet Requirements in 10CFR95.W/o Encl ML20195G2581988-11-0808 November 1988 Partially Deleted Memo Re Commissioner Carr 880113-15 Visit to Plant,Meeting W/State of Mo Officials & Visit to Mallinckrodt,Inc ML20205T5821988-11-0707 November 1988 Notification of 881115 Meeting W/Devonrue & Util in Rockville,Md to Discuss Proposed Std Alternate AC Design to Meet Station Blackout Rule ML20205T6491988-11-0707 November 1988 Ack Receipt of to Chairman Zech Re Alchemie Applications to Operate Facility for Separation of Stable Isotopes at Oak Ridge,Tn & Construct Similar Facility at Oliver Springs,Tn ML20205R6731988-11-0404 November 1988 Forwards NRC Testimony of Jj Swift Addressing ASLB Inquiries of 881018 & Two Attachments.Related Correspondence ML20205N3691988-10-28028 October 1988 Advises That ASLB Tentatively Calling for Telcon on 881109 W/Parties & State of Tn to Discuss Need for Further Prehearing Conference & Other Scheduling Matters,Per 881026 Request.Served on 881031 ML20206B2481988-10-27027 October 1988 Notice of Significant Licensee Meeting 88-174 on 881118 in King of Prussia,Pa to Discuss Configuration Mgt ML20205K3321988-10-26026 October 1988 Forwards SER Re Const Mod & Licensing of & Application for CP for Facilities.Nrc Review of Safeguards/Security Plans for Two Proposed Facilities Sent to Board & Applicant.Telcon to Discuss Scheduling Matters Requested.W/O Encls ML20195B6131988-10-26026 October 1988 Forwards Status Rept on Std Plant Design Technical Reviews ML20155H3621988-10-18018 October 1988 Requests Addl Info Re NRC Environ Assessments Submitted on 880914 for Uncontested Proceedings,To Complete Review of Adequacy of NEPA Assessments.Served on 881018 ML20204G0741988-10-17017 October 1988 Forwards Mh Mobley from State of Tn to NRC Not Received Until 881014.NRC Will Address Matters in Ltr in SER ML20204J5841988-10-12012 October 1988 Forwards AEOD/E807, Pump Damage Due to Low Flow Cavitation, in Response to Item 5 of Actions Directed by EDO to Respond to Diagnostic Evaluation Team Rept.Nrr Issued Bulletin 88-004 Addressing Low Flow Problem ML20205L2281988-10-12012 October 1988 Forwards AEOD/e807, Pump Damage Due to Low Flow Cavitation, in Response to Action Item 5 Assigned by EDO in 880406 Memo Re Diagnostic Evaluation Team Rept for Plant. NRR Issued Bulletin 88-004 Addressing Recirculation Problem 1990-02-26
[Table view] |
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1 Redney L. Southwick, Assistant to the
,. Manager for Fuhlic Infoinnation, SAN JCLE STATEHENTS ON RAE.1N M
- PI:RLS
) C ~~Mf Pacific Ces and Electric conducted a news conference this morning on their findings as a result of a trip to Alaska, comparing earthquake effects there with those which might be expected at Bodega Head. Attached are statements prepared for the news conference. Clips from local papers will be forwarded as tiny 3, become available.
Attachment As stated
.,' cc: ( Harold Price, Director of Rep lationy HQ, w/ attach.
Ro'litrEMaTe6GTesC~M.redoEof hagulation, HQ, w/ attach.
R. W. Smith, Compt. V., SAM, w/ettach.
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SAN FRANCISCO 6, CALIP.
'! . . . . , T ELEPHON E SU 14211 - 1 BIOGRAPHICAL NOTES .. ;
F. F. MAlffZ p-l l
Mr. F. F. Mautz is the Chief Civil Engineer for P. G. and E. He has l.
l - . responsibility for the structural design of the Bodega. atomic plant. Mr.'Mautz ,
has been an engineer with P. G. and E. for 28 years, ever since his graduation '
l with honors as a civil engineer from the. University of California at- Berkeley :1
.i in 1936. since 1946 his responsibilities in the Company have included all '
phases of P. G. and E.'s thermal power plant design program, and certain civil structural design responsibilities for hydroelectric projects.- At an early 1
date, Mr. Mautz assumed a prominent role in the Company's-nuclear studies and i projects, including since 1957 studies and design of the Bodega atomic plant. .j l
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- T ELE PHON E SU 14 211 REMARKS BY F. F. MAlfIZ !
l Our purpose in going to Alaska was to observe directly the extent of damage to structures caused by the Alaskan earthquake and to determine, to the
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- extent possible, the reason for riamage or lack of damage to structures there.
We were particularly interested in finding the relationship, if any, between the damage done by the Alaskan earthquake and our plans for the Bodega Bay nuclear plant. Our preliminary information about the Alaskan earthquake j had indicated that the damage in Alaska was largely due to unstable soil con-l l
l ditions, such as do not exist at our Bodega site. But, in the interest of com- !
pleteness, and in order to learn all that might possibly bear upon our studies 1
of the safety of the Bodega Head reactor site, we wished to make a first hand inspection of the damage in Alaska.
We found essentially that the damage in the Alaskan quake was due to a combination of two factors: (1) poor foundation conditions, and (2) failure to follow known atructural design and construction standards for earthquake areas. ,
Major damage to structures, and usually the more spectacular type of damage, was due primarily to soils failures -- that is, massive slumping and sliding of the ground made possible by the presence of a bluff. This ground i
was of a type that would be expected to act in such a manner during heavy earthquake shocks. Such type of ground, as I have indicated, is not found at the Bodega reactor site.
Of particular interest was the manner in which important major struc-tures designed to resist earthquakes, such as power generating stations in the i
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i area, withstood the earthquake and subsequent shocks. These structures gave a good account of themselves. For example, none of the power plants in the earth-quake area was forced out of operation during the earthquake. because of mechani-1 cal, electrical or structural failure.
Our observations indicated that in every case where structures of any type vere built on good foundations, particularly on rock, they suffered little
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or no damage, while those erected on unconsolidated materials or poor foimdations sufiered the greatest amount of damage.
Where the likelihood of earthquake forces was taken into account by the application of known principles in design and in. selection of' foundation condi-
, tions, as ve are doing at Bodega, structures withstood the earthquake and the ;
I resulting after-shocks without ceasing to perform their primary function and with safety to persons in and about them. ,
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. . S AN FRANCISCO S. CALIF. .
,,,,,, T E LE PHON E SU 14211 BIOGRAPHICAL NOTES DR. GEORGE W. HOUSNER Dr. George W. Housner is a Professor of Applied Mechanics and Civil Engineering at California Institute of Technology. His special field is earth-1 quake engineering, and he is an international authority in this field. Among Dr. Housner's professional associations are: President of the Earthquake Engineering Research Institute; Director of the International Association of Earthquake Engineering; and a Director of the International Institute of Seismology and Earthquake Eng16ering. As a consultant his experiences in-clude assignments for the Atomic Energy Commission, the National Aeronautics and Space Administration, and the California Water Plan. He has consulted on l l l
1 the seismic design of practically every nuclear reactor proposed for location in seismic areas, such as the five built or proposed in California and others in Nevada, New York, New Jersey, Tennessee, and Japan.
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T ELE PH ON E S U 14 211 4 REMARKS BY DR. GEORGE W. HOUSNER
$ conclusions from our inspection trip to. Alaska may be summarized as follows: 1 J
- 1. The intensity of ground shaking in Anchorage in the frequencies ]
j pertinent to the design of nuclear power plants was not at all severe, as j
. - l evidenced by the fact that very few one story buildings were damaged and only j a very small fraction of un-reinforced masonry chimneys were toppled by the shock.
1
- 2. I saw no evidence of significant damage to any buildings designed.
and constructed in accordance with approved practice. On the contrary, even some relatively poorly designed and relatively weak buildings survived with only moderate damage.
t 3 Most of the serious damage to buildings was the result of large landslides in areas adjacent to bluffs. The landslides were the consequence of 1 failure of a thick layer of clay which is very soft and slippery when saturated.
News reports dramatir,ed those buildings which were damaged by landslides.
These reports have distorted the over-all picture of the earthquake effect. I estimate that at least 80% of the buildings in Anchorage survived undamaged..
- 4. Although there were few structures founded on rock in the region severely shaken by earthquake, those that were apparently came through without trouble.
5 There was ,nothing anomalous about this earthquake. The ground motions were consistent with our expectations of what such an earthquake should produce. Judging from the damage observed at ' Anchorage and that reported at Cordova, Seward and Whittier, a structure designed according to the criteria 3
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2 being used for the Bodega Bay plant.vould have survived with$ut any damage and with relatively low stresses. . In fact, the structure being designed for the
. Bodega Bay plant would withstand earthquake forces approximately five times-
. those developed'at Anchorage.
- 6. There was nothin6 about the Alaskan earthquake that would indicate a necessity for reconsidering the earthquake design criteria for the Bodega Bay plant.
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245 M AR KET STR E ET 7 S AN FR ANCISCO 6. CALIF. .
, , , , , , T EL EPHON E SU 14 211 i
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i BIOGRAPHICAL N(TfES DR. HUGO BENIOFF Dr. Hugo Benioff is Professor of Seismology at the California Institute i
. of Technology. (Seismology is the scientific study of earthquakes.) He is an ' !
international authority on the mechanisms of earthquakes, and on seismic instru-1 ments. He has been associated with the Seismological Laboratory of the l
California Institute of Technology for 40 years. He has contributed chapters
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I in scientific treatises and articles for the Encyclopedia Britannica on the l i
subject of earthquakes. Dr. Benioff is also the author of numerous scientific papers on this subject. He is a member of the National Academy of Sciences as well as a number of geological, seismological, geophysical and astronomical societies, and has served as a consultant for the U. S. State Department and the U. S. Air Force as well as acting as chairman of the Consulting Board for Earthquake Analysis for the State of California's Department of Water Resources.
0 0 0 S/6/64
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.,,y T E L E P H O N E S U 1 4 211 j
RDfARKS Bf DR. HUGO BENIOFF Our trip to Alaska has reaffirmed much that we already know about 1
earthquakes. Nothing shown by the Alaskan earthquake vould indicate that the 1
- Bodega Head site is not safe. In my opinion the Bodega Head site is an excel- )
lent location for a nuclear reactor from the point of v.irw of earthquake hazards.
The reasons very briefly are these. Bodega Head prorides granitic rock into which the reactor can be buried. Althou6h the site is situated near the San 1 Andreas fault, this is not cause for alarm. Indeed, locations near active I
faults often provide better foundations for structures from the standpoint of earthquake hazards than do locations farther away. It is important for the ,
l public to realize that proximity to a fault is not the most important factor )
in determining the safety of a site from earthquake hazards.
9 I should like to speak somewhat reassuringly to the public about the l 6
San Andreas fault. This fault, which is a major and well-defined geologic j 9
feature of California, is an old geologic structure, having existed for some i
60 to 70 million years. The entire fault structure extends over 1000 miles j l
and varies in vidth from about IKK) to 2000 yards. In the Bodega area the 1906 i break was 13 miles east of the plant site. The possibility of the San Andreas fault shifting its course and rupturing elsewhere, such as through the Bodega i
Head reactor site, is so remote that for all practical purposes it may be dis- l regarded. -
h I do not believe an earthquake on the San Andreas fault could be very l much greater than the 1906 earthquake. Yet, the Bodega reactor structure, I am !
informed, will be designed to withstand an earthquake force even twice that of ;
the 1906 shock. !
(more)
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Some observers have suggested that during a major movement of the San Anireas fault the reactor structure might be damaged by possible associated l
movement along a small auxiliary fracture that traverses the bedrock in the 1
reactor site. This fracture, however, has not moved si6 nificantly during the 1
past 40,000 years. During that time there have been perhaps 200 to 100 move-
, ments along the San Andreas fault of the general magnitude of the San Francisco I
earthquake. This is strong evidence that the stresses which gave rise to this I l
fracture dissipated lond ago and that no further movement along it is to be ex-pected. The reactor structure, however, will be designed to accommodate auxil-
, inry fracturing should it occur. 1 i
i I have treated the subject of the Bodega site at some length to make clear that any concern on the part of the public that the Alaskan earthquake shows the Bodega Head site to be unsafe is wholly unfounded. The Alaskan earth-quake merely reaffirmed knowledge we already had concerning the mechanisms by which earthquakes cause damage. It is our understanding of these mechanisms, I and particularly our understanding of the San Andreas fault system, that permits us to state confidently that the Bodega site is safe for a properly designed j plant.
Indeed, from the standpoint of earthquake hazards, I repeat that the Bodega Head site is an excellent location for a nuclear reactor. It would be l unfortunate if public misunderstanding about the nature of earthquake movements l Vere to lead to the impression that the site is unsafe.
l-s/6/64
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,, ,,,, T EL E PH ON E SU 14 211 BIOGRAPHICAL NUfES E. C. MARLIAVE
- Mr. E. C. Mar 11 ave is an engineering geologist. From 1939 to 1956 he j was Chief Engineering Geologist and was in charge of all geologic work for the.
California Department of Water Resources. In that work one of his primary re-sponsibilities was to determine the safety of sites for dams, tunnels, canals and power plants from the point of view of safety from earthquake hazards. The foundation conditions for most of the ma,jor dams proposed or constructed in California during this period vere required to be approved by Mr. Mar 11 ave.
.Since 1956 Mr. Marliave has been engaged in private consulting work. Among l his many professional associations, he has been honored by election to fellow- l ship in the Geological Society of America and by election as counsellor to the Engineering Geology Division of that Society. He has also been appointed as !
that Division's liaison representative to the Hydraulic Division of the American l Society of Civil Engineers. He is presently retained for special consulting work by the California Department of Water Resources, the Delaware River Basin Commission, the City of Los Angeles and other California municipalities, as well as by a number of private organizations, such as P. G. and E., and by engineering firms, several of which have engaged him on assignments in foreign l countries.
5/6/64 1
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,, ,,,, T E LE PHON E SU *.4 211 l
REMARKS BY MR. MARLIAVE o 1
, In view of what has already been said by the other participants on i the Alaskan trip, I can be very brief.
The recent Alaskan earthquake again confirms certain. facts previously i known. One of the most important items in resisting earthquake damage is a j
. i
! good foundation. This is far more important than distance from an epicenter or j the surface break of a fault.
In the Anchorage area 70 miles vest of the epicenter a soft slippery i
clay underlying much of the residential section slid out from bluffs and se-l verely damnged many homes and buildings. In Valdez,120 miles east of Anchorage, and 40 miles east of the epicenter, the saturated soft glacial material under-I lying the town and dock area slumped and slid out into the harbor, destroying i the dock and severely cracking ground in the town.
3 3
In contrast, the City of Cordova, 75 miles southeast of the epicenter, I
which is founded on rock that is severely jointed, fractured and faulted, was h
undamaged. Even dishes and tall lamps on shelves did not fall. No damage to {
i buildings old or new was observed or reported. ]
This and other shocks such as the 1906 shock near San Francisco clearly demonstrate the importance of a firm foundation.
It is fallacious to suggest that damage that occurred at Anchorage and Valdez could occur ,on Bodega Head. Those foundation materials are markedly 4
different and it would be more appropriate to compare foundation rock at Bodega l
Head with the rock at Cordova, where no damage occurred. l
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