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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: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
[Table view] Category:PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA TO NRC
MONTHYEARML19325E9801989-11-0101 November 1989 Requests That Author Name Be Placed on Distribution List Re Schedule of Hearing in Alchemie Case.W/Certificate of Svc. Served on 891101 ML20247F8061989-07-0505 July 1989 FOIA Request for Documentation Re Incidents of Drug &/Or Alcohol Abuse During Past Five Yrs Amoung Employees or Contractors ML20247E6951989-06-27027 June 1989 Advises That Newly Formed Environ Conservation Organization Intends to Oppose Any Util Actions That Might Impact Negatively on Future Operability of Facility ML20247H3631989-06-26026 June 1989 Advises of Formation of Resources Conservation Organization. New Group Intends to Oppose Any Util Actions That Might Impact Negatively on Future Facility Operability.Ad Rossin Will Serve as Organization Coordinator ML20245B3981989-05-0808 May 1989 Discusses Technical & Safety Concerns Re Flow & Pressure Drop Calculations for RWCU & Feedwater & Condensate Sample Panels at Plant ML20245B4081989-03-10010 March 1989 Requests Response to 881014 & 890119 & 23 Ltrs Re Technical & Safety Concerns at Plant ML20244B0011989-03-0808 March 1989 Lists Facts to Consider for Action to Fix or Close GE Reactors Once & for All ML20245B4091989-01-23023 January 1989 Refers to Re Corrosion Inhibitors in Closed Water Sys at Plant.Last Sentence on First Page of Ltr Should Be Changed to Read One Example Is Loss of Air Cooling to Shutdown Board Rooms at Sequoyah ML20245B4101989-01-19019 January 1989 Requests That Jg Partlow Pursue Completion of Engineering Assignment of ED Buggs at Plant Concerning Corrosion Inhibitors for Closed Water Sys.Draft Engineering Rept Recommending Corrosion Inhibitors for Closed Water Sys Encl ML20206D8951988-10-15015 October 1988 Expresses Opinion That Plants Should Remain Closed Until Converted to Alternative Fuel Source ML20245B4121988-10-14014 October 1988 Informs of Several Technical Concerns Expressed While at Util & Requests That Jg Partlow Pursue Resolution of Listed Concerns ML20206D9711988-09-0808 September 1988 Forwards Ltrs Exchanged Between NRC & Author in 1984 Re Problems in Commercial Nuclear Power Field & Change in Federal Regulations to Allow Senior Reactor Operator to Deviate from Tech Specs in Emergency ML20206D9451988-08-12012 August 1988 Annotated Ltr Expressing Appreciation for Reply to & Assurance in Response to Concerns Pertaining to Operation of Ref Plants ML20245D6611988-08-0808 August 1988 Submits Listed Comments in Response to Re Safety Practice to Schedule Nuclear Plant Operating & Maint Personnel for 16 H Shifts &/Or Excessive Overtime ML20206E0281988-07-0707 July 1988 Advises That Nuclear Industry Overlooked Most Important Lesson Resulting from TMI Accident,To Wit,That Station Operator/Mgt Official Stationed in Control Room Would Have Prevented Accident ML20150A7961988-06-30030 June 1988 Comments on Util 880616 Request to Suspend Antitrust License Condition.Economic Advantages for Util Owning Nuclear Power Plants Have Failed to Materialize ML20155B6651988-06-16016 June 1988 FOIA Request for plant-specific Documents Re Fire Protection Requirements,Insp repts,hardware-specific Deficiencies & NRC Communications W/Util ML20206E0361988-04-29029 April 1988 Opines That 10CFR50.54(x) & (Y) Superfluous & Dangerous.Nrc Should Instruct Operators Not to Depart from Tech Specs in Emergency.Author Resume Detailing Experience in Commercial Nuclear Power Field Encl ML20155A7431988-02-24024 February 1988 Discusses Safety Problems at Comm Ed Nuclear Power Plants Re Risking Fuel Meltdown by Turning Off Safety Sys as Directed by Util Policy in Emergency If Core Cooling Is Adequate. Vice President Instruction Encl ML20148G9001988-02-0101 February 1988 FOIA Request for Documents Re 10CFR50,App R Insps & Enforcements ML20206E0431988-01-29029 January 1988 Expresses Concern Re Two Hazardous Practices at Ref Plants, Including Risking Meltdown by Authorizing Operators to Turn Off Nuclear Plant Safety Sys During Emergency ML20149G1051987-12-18018 December 1987 Opposes NRC Reduction at TMI-2.Reducing Staff Prior to Completion of Core Removal Inappropriate & Misguided Move. Recent Shutdown of Oyster Creek for Incident Re Destruction of Data Decreases Util Standing W/Local Residents ML17303A6161987-09-30030 September 1987 Forwards Scenario Review for Rancho Seco Emergency Preparedness Exercise,871104. Incomplete Scenario Provided for Review.Plant data,in-plant Chemistry & Radiological Data & Controller Info to Support Fire Drill Missing Elements ML20235T7341987-09-0101 September 1987 Requests That EIS Documents Re Meltdown Prepared by Impartial Sources Be Made Available to Public.Observation of Plant Life Indicates Level of Contamination of General Environ Causing Widespread Severe Damage ML20238B7731987-08-0707 August 1987 FOIA Request for Records Explaining Status of Listed LERs Omitted from List,Previously Received from Nrc,Of LERs Filed by Commercial Nuclear Power Plant Licensees for Operating Year 1986 ML20238E0261987-07-15015 July 1987 Responds to Recipient 870528 Response to Bg Strout Re Maine Yankee & Pilgrim.Author Distressed by NRC Answers & Requests Addl Response to Listed Questions ML20235L7061987-07-0808 July 1987 Opposes Util Application for Amends to Licenses,Allowing New Ownership & Financing Arrangement.Nshc Should Not Be Made W/O Public Hearings on Serious Financial Qualifications Questions ML20235K0421987-07-0202 July 1987 FOIA Request for List of All Licensed Reactor Operators & Senior Reactor Operators for Facilities ML20235F7451987-06-30030 June 1987 FOIA Request for Documents Re Safeteam Programs Being Used at Listed Facilities ML20215L5051987-06-23023 June 1987 Provides Brief Updated Rept on Status of Comm Ed Proposal Before State of Il Commerce Commission to Restructure Ownership & Other Financial Arrangements Re Facilities.Urges NRC Not to Make Finding Prior to Hearing ML20215L4871987-06-23023 June 1987 Urges NRC Not to Approve Comm Ed Request for Amend of Any OL Re Braidwood 1 & 2 & Not to Determine No Significant Hazard Exists W/O First Holding Adjudicatory Hearings on Serious Financial Qualifications Issues ML20215D6371987-06-12012 June 1987 Forwards Reply to Responses from NRC & B&W Owners Group. NRC Response Evidences No Independent Review of B&W Claims. Commission Urged to Take Personal Jurisdiction of Petition to Ensure That Latest Commitment Not Frustrated ML20236H1481987-05-30030 May 1987 Discusses Varga Reply to 870428 Mailgram Re Proof That LOCA Could Not Occur in Reactor Core at Plants.Evidence in Files of Repeated AEC & NRC Repression & Ignorance of Legitimate ACRS Concerns Cited.Congressional Hearings Requested ML20215K8391987-04-22022 April 1987 Opposes Licensing of Facilities for All the Same Old Reasons ML20214E2281987-04-16016 April 1987 FOIA Request for PRAs for Listed Plants Be Placed in PDR ML20214L0951987-03-13013 March 1987 Comments on Proposed Rule 10CFR50 Re Mod of Safety Rules to Enable Facilities to Startup Operation.Opposes Rule Due to Result of NRC Abdicating Responsibility as Protector of Safety of Populations Exposed to Radiation During Accidents ML20236D9381987-03-0404 March 1987 Partially Withheld Ltr Discussing Nuclear Power Industry Problems as Encountered During 6 Yrs of Employment at Limerick.Shoreham, & Hope Creek.Demotions & Terminations for Reporting Safety Concerns Described ML20215K8531987-02-24024 February 1987 Advises That Nassau County Board of Cooperative Educational Svcs Has Not Entered Into Any Agreement W/Lilco to Have Salisbury Campus Used for Relocation Facility in Event of Radiological Emergency ML20207T2381987-02-18018 February 1987 FOIA Request for Rept on Odds of Large Radioactive Release at Us Commercial Nuclear Reactors,Including Surry,Peach Bottom,Sequoyah,Grand Gulf & Zion ML20236D1281987-02-15015 February 1987 Forwards Preliminary Investigation of Worker Allegations About Safety of Plant Conducted by Gap in 1986.Investigation Revealed Enough Info to Raise Serious Questions Re Const Quality.Petition Per 2.206 Forthcoming ML20211B6601987-01-0505 January 1987 FOIA Request for Documents Re Allegations,Investigations, Fines,Convictions & Other Dispositions of Cases in Which Operators of Listed Facilities Charged W/Violating Federal whistle-blowing Statutes ML20207Q0971986-12-29029 December 1986 FOIA Request for Documents Re Util Proposed Reduction of EPZ at Seabrook,Changes to Containment at GE Plants, Including Pilgrim & Vermont Yankee & Insp of Pilgrim 1 Since Shutdown in Apr ML20215K9121986-11-26026 November 1986 Requests Opinion of Fairness of Shoreham Proceeding ML20212D7651986-11-12012 November 1986 Expresses Safety Concerns Re Containment Pressure Boundary, Based on 850916 Sser ML20215K9561986-09-22022 September 1986 Supports Licensing of Facility Due to Close NRC Scrutiny of Const & Operation ML20211C5631986-09-12012 September 1986 FOIA Request for Three Classes of Documents Re Use of Western Piping & Engineering Clamps at Perry Nuclear Power Plant & All Complaints/Correspondence Involving Deficiency Complaint at River Bend Plant ML20213C7931986-09-12012 September 1986 FOIA Request for Documents Re Western Piping & Engineering Pipe Clamps Furnished to Perry 1 & 2 & Van Meter 820607, 0721,0818 & 840125 Complaints to NRC Re Design Deficiencies at River Bend ML20215N9491986-09-11011 September 1986 FOIA Request for Ltrs,Depositions & Other Communications in Connection W/Nine Mile Point & Shoreham Nuclear Power Stations ML20215L4061986-09-11011 September 1986 FOIA Request for All Ltrs,Depositions & Other Communications Re Facilities ML20215K2791986-09-0404 September 1986 FOIA Request for Six Categories of Documents Re 1982 Civil Penalty & Ofcs of Investigations & Inspector & Auditor Investigations of Listed Facilities 1989-07-05
[Table view] |
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( f6 205 Northern California Association To Preserve Bodega Head and Harbor
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Anse! Adams t David Brower
- John Emmons October 28,1%4 (
Harold Gilliam Joel Gustafson Weldon F. Heald Mr. Harold Price, Director Joel Hedgpeth Division of Licensing and Regulation Francis Herring U.S. Atomic Energy Commission Washington 25, D.C.
D. B. Luton Willsom Penn Mott, Jr.
Dear Mr. Price:
Thomas Parkinson
- ""*'"""" Per our telephone conv ersation today, enclosed is T E"5 8'Ya*'d* the notice of the hearing on November 13th issued by the California Assembly Rules Committee.
David E. Pesonen Ezecutive Secretary Sincerely,
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Purpose; to work for preservation of the scense and historic heodlands of Bodego ure the Boy and to ins ecological integrity of the surrounding marine environenent A Cahfornia Non proht Corporation
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September 11, 1964 i
NOTICE OF HEARING -
The Assembly Committee on Rules will hold a hearing November 13th on HR No. 585 of the 1963 Session, relative to a study of the feasibility of the power plant on Bodega Bay. The Committee will meet in Room 2117 of the Capitol Annex in Sacramento at 10:00 A. M.
Those who wish to appear before the Committee should notify the Assembly Rules Committee in writing by October 30the Notification should
' be sent to Room 3173, State Capitol, Sacramento.
Oral presentations will be limited and therefore, it is requested that those wishing to present evidence to the Committee do so in writing. Any written presentation should be sent to the Committee by October 23rd.
V _ _ ___-____-_-__ -
e 14A-Press Democret., Scmts Rose, Calif. Sun., Oct. I I,1964 One of these asked the com.: The August quesdons ai s 4,;
j pany to postulate a total sk*-
a S' eaM O
q ing motion of the rock "i
==r itae aa t= =ar air caea '*"*d in the foundation," of as much picked up c statement in the '
earlier amendment that "a de-dr"a=>c *a ir i iti de
- made" for certain vital pieces l AEC Hea as three feet, and asked wheth- of equipnent, and asked PG&Et
)er the structure and the leak.! for a full description of the ac l
- l" tightness of the reactor contains celeration to be used in the' On bay A,,,,PI 'ti AALe he f I tact.
ment building would remain ind analysis.The PG1E pointed out that it s: fy a marfynum acceleration of:
a modified des!gn calls for the re l me times the forc actor containment structure to where PG&E has insisted that' missim a experts probe moreling thesit possibility centered in the containment of such aAs the Atomic e of.
Energ deeply into the controversialllarge inovement and ataround 'accels it.
l, the Intensity of an earthquake aAl to build the Bodegs ' ' force '
uclear la erauons of force of gravity.up to one times thelcgfg,*ip((g . e and strue ur Without conceding t h a t af
! walls of the pit would be filled ground acceleration of more yetr have all but vanished. -
- Flont' DesiIn with water, and the structure it, than a th Ad there has been public spec. , credible,,ird of a gravity is tdation that the AEC may be design PG&E has submitted modification that would a major' selected sand ply knownthe of concludes company charac-self a re-sit on a "
trying to , warn off' Pacific iteristics which will permit hori. precise nature of the strain in-e generally that th Gas & Electric Co. float ' the reactor vessel on a! zontal movements of upy to three v layer of sandand(to accomodate feet without impairing theac-fune ce De utility, which nearly two large i
displacements) in ther years ago asked the AEC for latest amendment sa permission to build the plant, . tem would have "ys theture, sysd uon of although the the struccontainment tur struc 1 mined after final substantial doesn't buy that. Rather, the margins of safety" against fail might be shifted or mtated . . .,el plant.
company subscribes to the stre with the one-gravity figureJ %ere will be "no rigid struc- But it ssys the , company's; theory that the AEC is merely It insists, however, I " proposed design criteria f o r'
!t t h a t wel btecomecum between critical stmetres, equipment doing its homework before go- ground acceleration of mor e any major component," the and systems , , . contains sub-ing to public hearing.
than a third of one gravity is amendment says, and connec- s:antial margins of s a f e t y Last week the AECs Advisory " incredible " ;
tions between the reactor con- against failure" for a one-grav-Committee On Reactor Safe. ne extended AEC PG&E!tainment structure and other guard considered the I a t e s t dialogue ity force.
on the earthquake! parts of the plant wul "have suf-PG&E answer to the A final AEC question posed query for more detail on a tion Nuclear Industryoftorelasayj threelatestin Augastquestion Ive move- happen in the event of a three-asked what would prompted th critical point-the earthquake that the " extreme conditions as ' ment.', feet safety of the plant.
sumed by some of the AEC'.d That of course,is only a par- foot fault motion elsewhere at~
ation-which might be a report 'ary demands on design whichResults of the AC
'and only one segment of the an- ;ure.
to the AEC on its findings, or a,those questions imply h a v e query for more information naturally lead ' to speculation swer. :
PG&E rep!!cd that those pip-rren't expected to be made pubJ that the AEC is warning PG&E But the AEC returned in late l ing connections'in the p1a n!
!!c for a week or so. August with more questions
'that the plant will not be ap-; bearmg on the problem, which area "necessary for a safet ing aclentista and engineers a she."Re ACRS, shutdown of the reactor" wouldt proved for the Bodega Bay licomposed finally produced Nine, filed by the company Sept.
of lead-Arnend m en t be made flex!b're enoust andi year and a half ago gave p,re l given protection to accommod
!!minary, conditional approval!the magazine says, "is that to the plant desjgn.
be.And alternative AEC fleply explanation,16.
date the motion.
I
' fore the AEC walks into a pub.. All of which indicates the{
One of the conditions h a sllle hearing in this case whichi excerpt above, magn!tude the AEC of quesJons wonder-In b eIng a discus rabed in canedon with h point of emphasis - that thelcontroversy, it simplycetroversial
- wantsplanttolof proposal,flexibility t
. . . reactor and buildings notjestablish that every credible or motions corresponding Whethcr to the a fault latest amend-be located on an active faultrincredible situation has been in..lmonon of up to th line "
i vestigated." to satWy & ACRS wH1 be
. Subsequent excavation byq ,f strenrh to resist the forces ac i bwn s%'. Peably '
PG&E of the hole that would PG&E View companying the dynamic re' AEC staff members could still house the reactor turned up A PGLE spokesman sayssponse t what some geologists have said lbthel ration. ,o the earthquake askvi- some more, which would '
latter is the company's view- "It has not been clearly further delay the date for the is throughan active the pit- fault r u n n in gl that the gamu*t of questions thatl shownpublic ,
. . "hearicg' the AEC said "how i f
Eventually - but probably :
PG&E's consultants hne in sisted the fault is inactive, and ;with the controversial plant prom mentssome for these Ome ak me two sources Erst of b ofha i
posal is to be run by the AEC, strain wi]! be achieved." year--the Bodega case wHI get f that a fractlon anyof movement an inch is ex- "Anexceeding (t before The the public company idea of the order of cram.I " pre!nninary design . . assures, AEC.
hearing.
replied that[ to the heartr4 stage by the tremely unlikely," and that ofitnation ta which the proposed! that a practical design can bel It has said -
more than impossible " a foot " practically l plant is now being subjected l deseloped to protect the pipingling
!can be gained from a few points against fallare ,
Curvey. however, concluded that;" amendments" movements of the rock of up to; application to the AEC. ,
an that. of its originalj th three feet in any direction mightl : sponse resultmg from the ac i De hearing promises to be be expected. , ya Inm Amendment a o Eight,'-submit..'" celebrations," and goes on to give largely a technical show, M e- ^ i
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h -kOS l Fa' action.
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, F or signature.
MEMO ROUTE SLIP . Note and return.
Wnn AFC-n3 mev. May H. lWn INITI Al.S RLMARES TQ (Name ano unit) " ' ars_clipst-Joe Feueberd, biose Servise Br. _ A**- 1, line Freaciese Chronicle,10/*9/64 ! " Atom Plant DFI, MQ can c.seF a n a tw ,--.. <
"AFC Groups Split Escold Price, RSS, gg 2. las Angeles Tissas, 10/24/ M:
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iNm^" "'"T.' Ba** Ilesa Press Democrat,10/23/M,14ttee
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Robert 1mwenstein, rag, SQ m
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noums i nou (s... .no unit, Rodney L. Southwick _
Asst. to the Manager _ _ _ _
for Public Informatie3 __
SAN PHONC NG DATE o s coo me, ,,,-,, o .,u m,-o..u J 10/29/u usc om, not ro .oomo .t et 4,,a
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Atom Plant Safety *
/ Of7 im Again in Dlspute i Tile ATO.LC ENEltGY Comnus.uon (AECi is now in receipt of conflicting professional opin-jon concerning the safety of a proposed nuclear
- power plant 'on Bodega Head.
Its Advisory Committee on Reactor Safe-l l guards te!!s it that there is " reasonable assur-ance" that the facility can be constructed on the site "without undue hazard to publi:. health and safety." But its Division of Nuclear Licensing
- advises that " Bodega Head is not a suitable loca-tion" because of its proximity to the San Andreas fault and the possibility of earthquake damage to "a pioneering construction effoM. based on unveri-fied engineering principles" 5 Though these expert opinions are confusing to the lay mind because of their direct contracic-tion, they offer unmistakable tesdmory that the prime question of the site's safety is s.111 open to doubt. Throughout the Bodega Head controversy, this newspaper has urged both the Pacific Gas
& Electric Co. and the AEC to defer ar.y irrevcca-ble decision on this project at this lor"Sn until
, its safety is assured and there .s c' aty that it involves no more risk e.an a .mna. ecojectat some other site.
At this time, we renew tha: uarnian and add the reminder that the public will now i:nd it in-creasingly difficult to agree-in the absence of umfied professional assurance-cons:ruction of the plant at Bodega IIead is in its b(st mter2st.
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ney Questions PG6E EDITOR: I. PG&E hadn't l been 30 ins er.t whei the, I n first cantacted me about buy.
small baad tryingto save Do.
y% ing my land. : hat the) didn't want .he publ.c to know that dega Heads for the pubiic h they wanted it as a tite for when it should be the whole
% a power plant. I would never public roaring to save it for Q have thought of calling it to themselves not leave it to just the attention of the public via the few. The Northern Cali-the ne wspapers. I learred ear. fornia Association to Preserve ly in bfe that when the local Bodega Heads anci Harbor is kids came around and whis- trying to save Bodega Heads pered. "Ixt's do so and so, f r the public. PG&E wants but don't tell your ma," it a f r their stockholders.
was sure to be found out, and If nuclear powered plants I't: get a good rpankirg. are so safe, why are safety Under much the same cir. zones so necessary? W h e n cumstances. v- h e n PG&E PG&E takes visitors to Vale.
whispered. "Doni tell the pub. citos. wnges it uke three lic" I was su c there was graduat.r engineers to escort something wrong witn t h e 'The visi ora around-~the' plant
~
deal, and the public should Githliger causters?'When know about it. And there is the Geyer counters start to sull too much wrong about cTcQQoF~aw'aFI'ar the whole rnatter tnd that e.nourn to snence that chck-inWn?
PG&E is franticar.y trying to hide. ~If u:ere is no danger from Only for the Save Bodega radiation, why did Rrssia.
Heads campq.n, anj its de- Engia.ic. and the United laying actions, the po ver plant States ign a t.ut ban treaty, on &>dega Heads would be to kee*. Inc ai' from b a;n- .
neming cortpletion, d not in ing co .taminated by cv. ppcl.
. actual operEtion. If Plan No. lauon? Why U.e worbide I was so safe, why has PG&E dismay over ChLna's re s '. car had to char.ge th<ir plans tes
some nine times since their !Y ' .a the p_t.uc , ,: Le oripnal plans for de plant, in*ere::ed in anaers to .ne.,e 1: Eey wer so saf(? And if ruest. n i
No. 4 is w .1uch a r thr.n .Wis. ROE 5. GAF7NEY Pla . L.1. can wt be sure Po>ega BO that P an Ac. 20 wu be any ._ _
safer than their orig.nal plan?
Can any plan, built astride an earthquake fault, be safe?
It would be of great inter-est to the public if it could kncw precsely what it is costing PGLE to oppose the opposition . . . what it is cost-ing the puthe throt;gh PG&E services that the pablic pays for to get this plant rammed down our throats, so to speak.
And the angels of heavens must be w"epmc le see our
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7155 5. FIRST ST., SAN JOSE, CALIFORNIA 3202-64-47 CYPRESS 7 3000 1
ll "OR IMMEDIATE RELEASE i
THF GENERAL ELECTRIC Company stated today that it sees absolutely no l
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- the Pacific Gas and Electric Company's decision to withdraw its 1 I
- :1. :: ion for the Bodega Bay Atomic Power Plant should slow the inter-1 f
1 national impetus of nuclear power. I l
t j
i George White, General Manager of General Electric 's Atomic Power j i
Equipment Department, underlined that the same good reasons for applying n-. clear power prevail. "The decision on Bodega Bay hinged on the cuestion of the proximity c: the plant to one of the world's best known zones of I l
reistic activity, the San Andreas Fault." White continued, " General 1
Electric, PGLE and their consultants, the Advisory Committee on Reactor i Safeguarcs, and the Atomic Energy Commission all found the plant and its features would have provided for operation without undue hazard to the 1
health and safety of the public."
White pointed out that the only doubt expressed by the AEC concerned the ability of the structure to withstand a hypothetical th ree- foo t shear movement brought on by earthquake, and the inability to provide any experi-mental or experier.c> proof-test of the novel design to V.eep the structure
.' tact. PG&E found t!' L s ::tinor t ty view to be sufficient cause to withdraw their application.
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l E White noted PG&E's comments on the.need for nuclear power in Calif-
-ornia as a basic reason why nuclear power would be applied at sites other than Bodega Head.
"The Bodega site was the specific problem in.this case," he said.
"With California one of the nation's two highest fuel-cost areas, with the State running out of hydro-electric power sites, with the growing scarcity of fossil fuals in California, and the fact that nuclear power plants emit no combustion products, there is no question but that nuclear power will l
be applied to California's need for_more and more electric energy."
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l Mr. Thomas Nolan, Director -
United States Geological Survey [ g - h6 V(-
Department of the Interior Washington 25, D. C.
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Dear Mr. Nolan,
b On November 13, 1964, in Room 2117 of the State Capitol in Sacramento, the California Assembly Rules Committee will hold a hearing " relative to a study of the feasibility of the power plant on Bodega Bay." This hearing stems from a reso-f lution which I introduced during the last general session of the Legislature and concerns specifically the proposed nuclear power plant at Bodega Head in l
Sonoma County, California.
An application for a construction permit for this installation is now pending before the Atomic Energy Commission and it is my understanding that the AEC has retained the U. S. Geological Survey to consult on the geologic and seismologic adequacy of the site. Two reports -- TEI-837 (September 1963) and l EEI-344 (December 1963) -- have so f ar been released.
The authors er and of these Mr. Manuel G.studies Bonillawere fromMr. yourJulius office Schlock-in {
j Menlo Park, and Dr. Jerry P. Eaton and Mr. Alfred l Clebsch, Jr. l
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In the interests of a complete record at Ithe forth-would coming Assembly Rules Committee hearing, like to request that the above named U. S. G. S.
personnel appear at the hearings to present their findings on this matter, including any findings they 1
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He have been informally advised by Mr. Harold Price, Director of the Division of Licensing and Regulation, that the' Atomic Energy Commission han no objection to such an appearance or to the release of findings made in the persuit of U. S.
'G . S. Work for the Commission on this project.
I An early reply would be appreciated.
i Sincerely,
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"- ;i ALFRED E. ALOUIST w.
AEA:ew cc: Mr. Paul C. Bateman, Geologist in' Charge U. S. Geological Survey I
345 Middlefield Road Menlo Park, California i
Mr. Harold Price, Director
- Division of Licensing and Regulation U. S. Atomic Energy Commission Washington 25, D. c.
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I Mr. James Lane, Executive Director Assembly Rules Committec )
Room 3173, State Capit.ol {
Sacramento 14, California i
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Continued irem First Fege whose repert. releaseu nt th*
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a J ,j features wouM be adegate.;
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m'vrd by t/e A ,ufu enic!T-befera rendem: a otes.m l(-(
, m r.: hold a }'. ,*e l.cartn: i MU,1 i fr. t'onttT C.1.1/1' nt' A w w - s<m er .* *' after ciecisionwhich a pM.m',
wi;; be meCe n y.gf.'. g.Pl.A ,, gdT $1TI, W.U P MTON safety and beena.ns kwr % g 9.,,
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- en The hearing date, yet set,is egected te be es" 4-wie IP'.! g ,,, yy,gj~
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% bui;* in the The Q.$ ed!be plant 1. 3 nyt *bnuS pke . prnras A"ea pt generate 3A000 ki:rwatts e.f least one maNr -eth sS 3
psor. HM, Caht T'e une e;eetricity has been a high Y during es Met 9 c.
b,a o inDNennrth " 49 fraq r eaw controvers;alissue b North Th, Ayc , heu;ng Ov4 y epp,y rn en. .'.y % 'e 9a f em California smee it w ,g y , ,q., ,M 6p g icy pga repmed two yeart ago . ;We ph ca-O
. e A y c's rieaeiat acic Gas & Electr:e Co.
The site is abert 1000 fe w amn rj a: re.
y r---; mv+ - ' mm.
3 synst co* ct'ct on wert of the edge of he a:twe GeCU "D.r exce; cuF.tion Mc- is the 'tr.
, e not y duputcl % . San Andrus ear? cn'. -
, fault tone, Novereent a:e y certgry ei s hether ue x
-urg. *no saus I exper;. F *c d ca pp gquake ng,;enwnich n, a,. ".al m extmet ce W' the fault produced the grc ge 7 et1906n was
's *redici rg t e u1 mag' j spontble im the f i r e thatj, g.n ;aun td avociat.
a y terw wgr arc llte , devastated Ean Frarcisco. ted wl.h a major quake, it nr t t . p'a it nor, co',equent; t ty, whe'.hr prepoa >/. sa.W ,,
y,,,g,,,g,,, said.
% $nund Basis
- plures wnuld he ade@a'e ' Somi e rrta e th Bodega plant as a tett ca.ici 'It is almost (erta:n that Drs! 9te De*ial for stanic facitxs nea;rt'e site Mllte subjected te s
i ' %c % eel methd* p*M earthquake regionr. ,one or more severe se3'nie, Dr. John raton o' the P ;d:sturNnces du-mg the !.fe.
= we a tn e.. e cuerd 'he rear-wr My wwk. the 49E terior Department, after d.me saide'*** the p'aE* the raontt
.rce,irt sa'<: W 't M nN study that warned s')out t>dsoun.d exte:"mwa! or ex-Mere is crefen'.'y to
..w. 3 ynyt n *M h uld P61' 9 'br med eat u <l F A #:0 seismic dangers s' Bode:' Head, said n win be " ]e :
nwiear p%er rc'" F - ing!y d!!ficult to raject aryithe crent be meted of damage oy thethat l r wesente
, Ts.4 f%v proposed future rra on tle m;ghtcari - reafters~ue- cordacrentJ ty - f w rye the divMon 'p j grounds of extremauake a lD.3 crert-ncy r<4 n,u.
> . temr ncrAed emmt pgapw ' WM< t te ran' cas cred t. aqu tu"e risk" ;f sJe J Pp l
,. prosed by t'ce AK i
. ,m t ve .cre a ygrro;nh 83 88ff'7NC' O'"T'## .
gw p i+ hp mi td @w*
Subsequendy, tt At excb o * "7 I tieu at the v.te focad a fa / ss"d '+ *aWuart-J ' P l
}rrm W r e m?f m tre runrccJ; (i. rect'y under l' a p' l
} ett15 enp.Newe t friht '* I e ,, etly W h Gy e W t> r p; ant area. T Nt' 11 e or nn'.* n ber i 'r-
,4,w.d. 6. ' a e a~
W ~
d#' f " E
' it is n . N'T D
"' /
i
. .o un v ssmtu t o
- s'- r, Depam ee* *3 QC' g, hu "av $ = f .-
c:ared that anothir 19Nfg E ytan.e T4ra to Ps. Tt. Cot f! that wi;t wrick,
- e. - - - - - saed quake wouhi.a p,k tNgg, g,g .M*r t ' uj m*th
. :,,,, . .:, , ,, ,e es. r * *m. awe l Fisiety 7 clors A hied , j ,. e a l
The AEf'A artvw r y & heel a tJ ernercc n ce w tuled. it condeu i mittee, in t*s favru aW.e re rnent pert. said it vas cMnnast ni"w e h not b.pese er writ'- that a the fau:?. v uns th pow er '!arge m clear p&cr* af 7 compwy. 6e d that $.ae com shouki he the e cawrtrro' e' pany has "eder m ed 'r teen e 9 plant to .rfr'. rnore @ fan 6 d n't t ive-t'-". a . "*:t.
e t a-s to p r1 ar - etw : rnm s ~ s% ; f t. e *rty apy ny te b'p 7 A. i , ' y $3; *
'i p: ant dd' > Qr t 'r* ..
f a
/
h
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