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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20033E2411990-03-0505 March 1990 Notification of 900307 Meeting W/Ge in Rockville,Md to Discuss Potential Power Reactor Upgrades ML20011F7171990-03-0202 March 1990 Notification of 900313 Meeting W/Util in Rockville,Md to Discuss Plans by Util to Request Tech Spec Change to Increase Allowable Unidentified RCS Leakage Rate from 1 Gpm to 3 Gpm ML20012A9351990-02-28028 February 1990 Advises That Ja Hammer Sucessfully Completed All Requirements for Certification as Operator License Examiner & Is Qualified to Perform Operator Licensing Exams at GE BWR Facilities ML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20011E6591990-02-12012 February 1990 Forwards AEOD/E90-02, Crosby Low Pressure Relief Valves Nozzle Ring Problems, & Proposed Info Notice Recommended to Be Sent to All Licenseees to Inform of Benefits of Proper Maint of Valves ML20006D7831990-02-0808 February 1990 Advises That Board Concluded That Holding Prehearing Telcon Re Scheduling Considered Premature Due to Lack of Record,Per .Request for Future Scheduling Suggested to Be Submitted.W/Certificate of Svc.Served on 900209 ML20006C7501990-02-0101 February 1990 Notification of Significant Licensee Meeting 90-13 on 900208 W/Licensee in Region I Ofc to Discuss Nuclear Safety Concerns Program Enhancements ML20006C4491990-02-0101 February 1990 Requests Telephone Conference Be Set Up at Board Convenience Due to Author Not Being Able to Reach Licensee Counsel ML20006C7931990-02-0101 February 1990 Documents Verification of Close Out of Multi-Plant Action G-01, Reactor Coolant Pump Trip, for Plants,Per 891219 Memo ML20006C4621990-01-26026 January 1990 Responds to 900117 Joint Request on How NRC & Applicant Counsel Expect to Move Proceeding on Hearing Calendar in New Yr.Applicant Has Expressed Desire to Have Proceeding Held in Abeyance Indefinitely Although NRC Does Not Agree ML20006A0231990-01-17017 January 1990 Requests Info,Within 10 Days,On How to Move Proceeding on Hearing Calendar in New Yr.Certificate of Svc Encl.Served on 900118 ML20005E6701989-12-29029 December 1989 Forwards Technical Review Rept AEOD/T927, Followup on Steam Binding of Auxiliary Feedwater Pumps (Afw). No Backleakage Events That Occurred After Issuance of Bulletin 85-001 Resulted in Steam Binding of AFW 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 ML19332F7431989-07-21021 July 1989 Provides Summary of Station Blackout Responses & Staff Review Schedule Per Request.Cursory Check of Licensee Responses to Station Blackout Rule Has Been Performed in Order to Provide Overview of Industry Approach 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 ML20042D1901989-06-0808 June 1989 Memorandum Forwarding Partially Deleted Summary of Discussions During NRC 890517-18 Mgt Meeting Re Problem Plants & Addl Topics.Task Assignments & List of Attendees Also Encl 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 ML20246C9811989-05-0303 May 1989 Provides Update of 881122 Low Power License Recommendation for Plant,Reporting Closure of Technical Issue Associated W/ Agastat 7000 Series Relays.Advises of Plant Readiness to Conduct Initial Criticality & Low Power Testing Operations 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 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 ML20117P9051988-12-15015 December 1988 Forwards Info Re IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings, for Region I Plants for Semiannual Status Rept 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 ML20246C9601988-11-22022 November 1988 Provides Update to Original Region I Assessment & Recommendation for Issuance of Low Power OL for Plant. Advises That Region I Continues to Recommend Low Power OL Issuance for Plant W/Special Note of Items Listed ML20195J0141988-11-22022 November 1988 Notification of 881214 Meeting W/Util in Rockville,Md to Discuss Licensing Actions at Plants ML20246C9761988-11-17017 November 1988 Discusses Team Insp at Plant to Review Licensee Assessment of Readiness to Achieve Initial Criticality & to Complete Low Power Testing.Licensee Conclusions Re Facility Overall Readiness to Conduct Power Operation Confirmed 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 1990-03-05
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20033E2411990-03-0505 March 1990 Notification of 900307 Meeting W/Ge in Rockville,Md to Discuss Potential Power Reactor Upgrades ML20011F7171990-03-0202 March 1990 Notification of 900313 Meeting W/Util in Rockville,Md to Discuss Plans by Util to Request Tech Spec Change to Increase Allowable Unidentified RCS Leakage Rate from 1 Gpm to 3 Gpm ML20012A9351990-02-28028 February 1990 Advises That Ja Hammer Sucessfully Completed All Requirements for Certification as Operator License Examiner & Is Qualified to Perform Operator Licensing Exams at GE BWR Facilities ML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20011E6591990-02-12012 February 1990 Forwards AEOD/E90-02, Crosby Low Pressure Relief Valves Nozzle Ring Problems, & Proposed Info Notice Recommended to Be Sent to All Licenseees to Inform of Benefits of Proper Maint of Valves ML20006D7831990-02-0808 February 1990 Advises That Board Concluded That Holding Prehearing Telcon Re Scheduling Considered Premature Due to Lack of Record,Per .Request for Future Scheduling Suggested to Be Submitted.W/Certificate of Svc.Served on 900209 ML20006C7931990-02-0101 February 1990 Documents Verification of Close Out of Multi-Plant Action G-01, Reactor Coolant Pump Trip, for Plants,Per 891219 Memo ML20006C4491990-02-0101 February 1990 Requests Telephone Conference Be Set Up at Board Convenience Due to Author Not Being Able to Reach Licensee Counsel ML20006C7501990-02-0101 February 1990 Notification of Significant Licensee Meeting 90-13 on 900208 W/Licensee in Region I Ofc to Discuss Nuclear Safety Concerns Program Enhancements ML20006C4621990-01-26026 January 1990 Responds to 900117 Joint Request on How NRC & Applicant Counsel Expect to Move Proceeding on Hearing Calendar in New Yr.Applicant Has Expressed Desire to Have Proceeding Held in Abeyance Indefinitely Although NRC Does Not Agree ML20006A0231990-01-17017 January 1990 Requests Info,Within 10 Days,On How to Move Proceeding on Hearing Calendar in New Yr.Certificate of Svc Encl.Served on 900118 ML20005E6701989-12-29029 December 1989 Forwards Technical Review Rept AEOD/T927, Followup on Steam Binding of Auxiliary Feedwater Pumps (Afw). No Backleakage Events That Occurred After Issuance of Bulletin 85-001 Resulted in Steam Binding of AFW 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 ML19332F7431989-07-21021 July 1989 Provides Summary of Station Blackout Responses & Staff Review Schedule Per Request.Cursory Check of Licensee Responses to Station Blackout Rule Has Been Performed in Order to Provide Overview of Industry Approach 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 ML20042D1901989-06-0808 June 1989 Memorandum Forwarding Partially Deleted Summary of Discussions During NRC 890517-18 Mgt Meeting Re Problem Plants & Addl Topics.Task Assignments & List of Attendees Also Encl 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 ML20246C9811989-05-0303 May 1989 Provides Update of 881122 Low Power License Recommendation for Plant,Reporting Closure of Technical Issue Associated W/ Agastat 7000 Series Relays.Advises of Plant Readiness to Conduct Initial Criticality & Low Power Testing Operations 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 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 ML20117P9051988-12-15015 December 1988 Forwards Info Re IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings, for Region I Plants for Semiannual Status Rept 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 ML20246C9601988-11-22022 November 1988 Provides Update to Original Region I Assessment & Recommendation for Issuance of Low Power OL for Plant. Advises That Region I Continues to Recommend Low Power OL Issuance for Plant W/Special Note of Items Listed ML20195J0141988-11-22022 November 1988 Notification of 881214 Meeting W/Util in Rockville,Md to Discuss Licensing Actions at Plants ML20246C9761988-11-17017 November 1988 Discusses Team Insp at Plant to Review Licensee Assessment of Readiness to Achieve Initial Criticality & to Complete Low Power Testing.Licensee Conclusions Re Facility Overall Readiness to Conduct Power Operation Confirmed 1990-03-05
[Table view] |
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\\l UNITED STATES GOVERNMENT Memorandum To Harold L. Price, Director of Regulation parg:0CT I 6 1967 FRoM Milton Shaw, Director, Division o Reactor Development & Technology SUBJEcr:
TRANSMITTAL OF SITE ADVISORY COMMITTEE REPORT RDT:PM:D258 In accordance with our agreement, I am providing herewith 25 copies of the report of the Advisory Committee to Secretary Udall relating to the Bolsa Island site.
Interior l
Assistant Secretary Di Luzio has agreed with this early supply of the reports to your staff and the ACRS; however, since the Commission has not yet formally received the report it is approp'riate that the reports be handled as
" Official Use Only until any formal release of the reports by the Department of the Interior.
Attachment:
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H. BOLTON SEED
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DEPARTMENT OF CIVIL ENGINEERING UNIVERSITY OF CALIFORNIA BERKELEY, CALIFORNIA 94720 October 2, 1967 I
a Secretary Stewart L. Udall j
U. S. Department of the Interior Washington, D. C.
1
Dear Secretary Udall:
The Advisory Cont 4ttee on Geological-Seismological Conditions Pertaining to the Siting of Nuclear Power-Desalting Plants which j
you established' in May 1966 has completed its assigned task, the ll review of the geological-seismological factors associated with the construction of a nuclear power and desalting plant on an island proposed to be constructed about one half mile off-shore of Bolsa Chica State Beach, seven miles southeast of Long Beach, California.
j You asked that the Cenmittae. evafuate the severity of any problems j
disclosed by this review, recommend geo-seismic criteria to be met if the site were to be utilized with appropriate regard for public l
safety, determine the adequacy of existing engineering techniques i
to meet the recommended criteria and, offer an opinion concerning the suitability of the site based on the current state of knowledge and tachnology.
i I am transmitting heecwith a report prepared by the Committee j
presenting th results of our ren'ew and evaluation.
j 1
The Bolsa Island site is cae mile from the Newport-Inglewood j
f ault and no branch f aults he e been found to exist beneath the i
site.
The materials beneatli t.ne island are much more compact than i
they were thought to be earlier, so that settlement due to compac-tion from earthquake vibrMions or weight of the man-made island i
should be extremely small.
The ocean floor is smooth with gentle westward slopes.
There are no channels or other steep sided features that would lead to slope failures with vibrations and, l
with the exception of loose sediments near the ocean floor, there j
are no potentially liquefiable materials underlying the site.
1 The Committee considers it credible, though extremely unlikely, i
that a great earthquake may occur, accompanied by lateral or vertical i
displacements, along the Newport-Inglewood fault during the life of the plant.
If displacements do occur however, they can be expected i
to follow the existing surface break and not develop new parallel faults on either side of the existing fault zone.
In our best j
judgmer.t there will be no fault displacement of the ocean floor j
beneath the island site during the life of the plant, but it is also j
(
a.
Stewart L. Udall 3
October 2, 1967 l
Page 2 4
i recognized that the marine environment of the site precludes the l
possibility of exploring the site by conventional methods to j
positively rule out the existence of minor faults in the site area.
j In recognition of the above factors and others discussed in the report, the principal recommendations of the Committee are:
(
Engineered safety features of the nuclear reactor and related critical structures needed to achieve and maintain a safe shutdown condition of the nuclear reactor should be designed to survive a sudden differential dis-placement of 5 to 10 inches in any direction in the sea floor and ground shaking from a magnitude 8 earthquake on l
the Newport-Inglewood fault; in addition, the plant should l
l be designed so that it can safely withstand the ground j
shaking induced by a magnitude 8.5 earthquake on the 1
l San Andreas fault.
In this connection I might note that the l
Committee considered the possibility of differential displace-I ments of the sea floor in the immediate vicinity of the island to be so remote that it would not need to be considered in the design of any structure other than a nuclear reactor.
l Furthermore, in the event that trench excavations in the l
foundation area of the reactor should establish that there i
are no fault displacements in the upper 10 feet or so of the firm deposits, it might be possible to reduce the recommended fault displacement criteria to some extent.
i Seismic shaking, to which the island area will almost' I
certainly be subjected one or more times during the life f
l of the plant is not expected to cause any significant settle-j l
ment of the underlying foundation soils.
However the design of the island and of the reactor should take into account the probability of a general areal subsidence of about j
l 2.5 ft due to regional tectonic causes and withdrawal of i
fluids during the next 40 years.
l i
l l
Cateful consideration should be given to the character I
of the island fill, its density, its supporting capacity and i
its ability to remain stable under the design ground motions.
i The fill should be mechanically compacted to a sufficiently i
high density to assure stability, or the stability of the island and plant must be assured by a combination of mechani-cal compaction of the fill in critica? zones and the provision i
of stable walls or dikes to retain tl.e fill.
Appropriate precautions should be taken to protect the i
installations against the effects of a tsunami generated j
either at a distance or by a magnitude 8 earthquake along j
one of the major submarine faults in the off-shore area.
1 l
Based on the belief that these and other recommendations set forth in the report can be met by means of appropriate design and I
i
,.a.
Stewart L. Udall October 2, 1967 Page 3 i
construction procedures, the Committee concludes that it is entirely feasible to construct and develop-the Bolsa Island site for a nuclear power and desalting plant with due regard for geologic-seismologic factors without jeopardizing public safety.
Extensive information was available to the Committee for its evaluations.
The bulk of this information was that accumulated by the Bechtel Corporation, its contractors and consultants in the course l
of a comprehensive investigation of the site area.
This investigation was conducted concurrently with the Committee's activities; the in-formation developed was made available to the Committee for independent J
appraisal and several studies were undertaken by Bechtel at the Committee's request.
i The Committee considers that this geologic investigation of the site itself, and its place in the regional geologic-tectonic framework, has been thoroughly and competently performed.
No major sources of information have been overlooked or ignored.
Various techniques of-investigation have been considered, and the applicable ones used by competent' people.
All data have been subjected to more than one completely independent analysis and evaluation, in addition to evaluations made by this Committee.
Although further detailed in-formation on the site or its environment might conceivably be developed from additional investigations, 'the Committee believes that while the. information obtained thereby might improve our know-ledge concerning the local details of the site area, it would not change the total picture appreciably or modify the Committee's con-clusions to any significant degree.
In addition to the considerable volume of information obtained from the Bechtel Corporation, the Committee also reviewed the pertinent literature and obtained much helpful advice from colleagues and' specialist advisors.
The conclusions presented in the report thus represent the best judgment of the Committee supported by ' facts and data interpretations provided by a large number of specialists in various aspects of the problems involved.
The Committee would be glad to meet with you or others if you~ desire to. discuss its evalua-tions and recommendations.
I am confident I speak for all the Committee members when I say it has been a pleasure to serve on 'the Committee. 'The Committee undertook this assignment with due regard for the importance of its advice and recommendations, and I personally feel that the evaluation of the geologic-seismologic and soil factors of the Bolsa Island site and the adequacy of existing design techniques to meet the recommended a
criteria were most thoroughly and carefully considered.
Sincerely yours, N
ton Seed HBS/nh
.