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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
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Q. Who are the men who will op.
erate the Bodega plant? What kind Q
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' f j!.? f4,, of qualifications will they have?
A. They will be PG&E veterans 6 % 7.i .;; f., M#
' f .9 with years of experience in conven-
>y tional power plants plus specialized I training and experience in reactor
, 4, / operation. They will be examined i and licensed by the AEC. They will i Hearings will be held soon by the Atomic Energy Commission on a have had on-the-job training at Val-j request by PG&E to construct a 330,000-kilowatt atomic plant at Bodega lec tos, Dresden or Humboldt Bay Bay,45 miles north of San Francisco. Because some misinformation has --or perhaps all three.
i been circulated in protest against building this plant the following infor. Q. Concern has been shown by
- mation is presented some people about the " hot water" I' Q. Will the Bodega atomic plant the accident and never has released that will be discharged from the be " experimental"? the results of an investigation it con. plant's cooling system. What will A. No. It will be a permanent, ducted. What are the factsy the temperature of the water be? )
l A. Cooling water will be taken full-sized plant adding 330,000 kilo- A. Briefly, the story is this:
I watts to the PG&E system. There was an accident in the AEC's from Bodega Harbor, which has a mean temperature of about 55 F.,
l Q. Will Sonoma County rest. SL1 reactor at Arco on January 3, dents find their lives and welfare in 1961. Three men were killed in the pumped through the plant a con- )
{ feopardy because of the atomic accident, the only one with fatalities densers and discharged into the !
plant, as some opponents of the in the history of U.S. reactor opera. pen sea,at abou,t 73, F. The ocean j
! project claimr tion. On September 24,1962, the will dissipate this difference withm ;
i A. No. Millions of Araericans AEC issued a final report supple- a very short distance of the outfall. {
l live in the vicinity of nuclear re. menting three interim reports. Q. Will the warm water affect <
actors in other parts of the nation. The report clearly indimtes that marine Ufe?
l Just for one example, Consolidated the accident was caused by human A. No. This is based on extensive Edison's Indian Point Pitnt (275,- failure, not the failure of the reactor - . -n - -
n !
000 kw) is Just 24 miles north of system. Further, the SL-1 reactor 1: 3
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New York City. cannot be compared in any way - J
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Q. Is it true that the PG&E re. with the Bodega reactor. The SL-1 g_d,$d i^
actor will use a safety system "that was designed as a low-power reactor has never been tested on a working to be used by the Armed Forces in reactor" as some crities have remote locations. Thus, it incorpo- [~Ka L p( F"TG I l
claimed? ra,ted few of the safeguards con-A. No. The Bodega safety system tamed in the design of a large cen- Hum,,bohit--Newest
,,, ,, p.,,, g,,;i;,y PG&E consists of instruments to detect po. tral station such as Bodega. The de-tentially hazardous conditions and sign of the Bodega reactor will make operating experience at PG&E's devices to control such conditions. it unpossible for an individual oper- conventional power plants and on It will be similar to the system in. ator to make the mistake which oc- testimony of Dr. Ernest Salo, chair-stalled in the PG&E nuclear unit at curred in the SL-1* man of the Division of Natural Re-Humboldt Bay. The Humboldt Bay Q. One letter to a newspaper said sourms at Humboldt State College.
designs were examined in detail that "over 500 known accidents He said: "It is a generally accepted during the licensing of that plant have occurred,43 of which were ma- fact that the discharge of warm af-and components based on these de- for"in the operation of U.S. atomic fluent waters into the open ocean
- signs have been tested in working reactors. Are these figures correctf does not create a temperature prob. .
reactors in large part. Features A. The figure 43 perhaps comes tem of biological significance, and I [
' which have not yet undergone ac- from t.n AEC report which lists, for believe the proposed discharge at i tual test in a reactor have been ex- the period November 1,1960, to Bodega Head is no exception."
tensively pre-tested. November 30,1961, 43 " reportable Q. Will the plant interfere with Q. Opponents of Ihe Bodega accidents." Aside from the Arco ac- the marine biologicallaboratory the plant frequently mention a reactor cident, nearly all the "43 major acci. U. of California plans to build?
accident at Arco,ldaho,in January, dents" were construction or indus- A. No. As the Commission said 1.061. Some cccounts claim that the trial accidents, such as fire in a in its decision," Spokesmen for both AEC never has learned the cause of instruction building, a head-on the U. ol' California's proposed bi-s - ..
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Here Are Answers to e Most Common Queries ology station and the State Division ments will continue. Should there About Atomic Power
. A. Several important considera-of thatBeaches they are and Parks made not opposing it clear ever be a significant increase above tions led to the selection of the Bo-the nu.
i the amout of natural radioactivity, dega site. First, the region to the
, clear plant and that it will not inter. PG&E will immediately take action north of San Francisco Bay will un-fere with their respective plans for to correct this situation. A similar dergo great growth in the next few operations Head." and land use on Bodega procedure will be followed in the years. Thousands of new homes and
'. Q. A recent " Letter to the Edi-Bodega Bay area.
Industries must be assured adequate I Q. How valid is the concern of
- suppliesof electricity. For the great.
tor" referred to " enormous subsidies someSonoma County residents that est eiliciency, reliability and econ.
' paid for by ordinary taxpayers" in the plant might emit radioactive omy, a new generating plant is helping PG&Elinance Bodega. Will gases inlandt required within the area. Features
! any Government funds be used in l
I building the plantf A. All gases from the plant's which led to the selection of Bodega
! stack will be controlled A. No. As with every PG&E de- uously monitored by automatic at other possible and contin- Head as the site cannot be found
' locations in the re-I velopment, the company itself will equipment. If there ever is radioac- gi n the plant must serve. These finance Bodega in the free market. Livity in the gases in excess of ac- technical and economic considera-l i
AEC charges PG&E for the use of ceptable limits, a valve would close tions include a reliable coolmg water i
the uranium fuel at its cost and al. automatically and stop any further . system, good foundah,on conditions
' lows credit for the value of the plu- discharge from the stack. and harbor facilities for receivmg tonium created in the fission reac. .-. and shippmg heavy loads.
tion, all to the end that such charges '
Q. Will the Bodega reactor be and credits should not contain any U.S. subsidy.
T4e ;t !**y?d pr b k,, built
- @Q o. on the San Andreas Fault? ,
I Q. How much of Bodega Head W, f A. No. It will be built on solid l
will the plant require 1 r
. @y w granite bedrock foundation some a,,,
Q. distance to the west of the western
+f]h A. PG&E owns 225 acres at the tip of the Head. About 25 acres will b. ==m c'
bMs edge of the fault zone. The Bodega jbs. site foundation has been verified l be required for the atomic unit and van.ch_p;oneer PGAE and confirmed by expert consultants switchyard. Additional PG&E land ' oucl. r power plan, will be used during construction. in geology and seismology. Dr.
The Head proper-the elevated George W. Housner, professor of ap-l Q. Can a boiling-water reactor plied mechanics at the California land at the south end of the penin- blow up like a bomb 7 Institute of Technology and a reo.
' sula-amounta to about 300 acres. A. No. A power reactor is de. 0.gnized expert in earthquake de-The remainder of the peninsula is about 1,000 acres. signed quite differently and uses sign, has advised PG&E that the different fuel. The Atomic Energy plant can be built there safely.
Q. Will the public have access to Commission has conducted exten. Q. Why will PG&E build transmis-l Bodega Head after the plant is sive tests in which a reactor was de. sion lines from the plant overhead built?
iiberately allowed to "run away" instead of underground A. Yes-and it will be the first uncontrolled, but an atomic explo' A. Undergrounding here would time the public has ever enjoyed sion did not occur. It couldn't. q free access to Bodega Head, pri. be unreliable and hazardous be-Q. Did the public have adequate cause the conduits would have to vately owned in the past. Under the opportunity to express its views cross the San Andreas Fault. A Public Utilities Commission permit about the location of the Bodega major earth movement at the fault PG&E will provide public access to planff as much of Bodega Head as is con- could rupture the conduits, releap l ,
sistent with public safety. A. The California Public Utilities ing thousands of gallons of inflam-
, Q. Why has PG&B installed in- Commission as required bylaw, held mable insulating oil contained in l open public hearings on PG&E's them. Restoration would take sev.
struments to measure radioactivity application. Hearings.were held in eral weeks. An overhead line is un.
at boldt and Bayinatomic the vicinity plantf of the Hum. San Francisco on March 7-8 9, May likely to be affected and could 4122 and June 6 7-8, 1962, a total restored within hours if it were. In '
A. There is some radioactivity in of eight full days. Time and place creased costs, which would neces-the air everywhere, regardless of were well publicized in newspapers
)~
' proximity to a reactor. The instru. and as many as 200 people attended sarily be reflected in customers' electric bills, are also a factor-un.
ments around the Eureka area are some sessions. Under CPUC ndes, derground installations are esti-to measure the natural radioactivity it was easy for anyone to express his in the air there before the plant be- views or cross-examine witnesses. mated to cost $4.4 million compared gins operating. During the life of with an estimated $240,000 for over.
Q. lan't there some otherplace to head construction of the 2.18 miles the Humboldt plant, daily measure. locate the plantf i of line involved. .l APRIL,1963 7 -
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li/11/63 4/19/43 PFP 4 1 6 ;* sin /*'r'G410 AV6 LTR. memos REPORTS OTHER:
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2 TOs ORIG.s CCs OTHERs
.r . L ACTION NECESSARY Q CONCURRENCE ] DATE ANSWEREDs l .
CLAASIT.s NO ACTION NECESSART O COMMENT - O aTs l POST OTT2CE TILE CODES b REG. NO
, DESCRIPTION: (Must Se UnclosalSed) RLTERRED TO DATE RECEIVED BT DATE I. I. r . r.* t i n
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S.e eld. f.ncucred bv letter dnmed 5/16/63 ENCIOSUmES' signed by Eber U. Price.
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1 fr U. S. Covernment Prinung CIEce: 1982 437308 u.s.arourcrnzaar comassion MAIL CONTROL FORM rCRM AEC.aus 1 " " * * '
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VD/63 C M,V D F. M NS 3
. V16/63 3061 LTR. MEMO: REPORTS OTHERs I
To, ORIG.s CC: OTHER:
ATOMIC ENERGY COMM. I l
ACTION NECESSARY g CONCURREN::E Q DATE ANSWEREDs NO ACTION NECESSARY C COMMENT O sT ._
CLASSIT.s POST Ol'TICC TILE CODES U REC.NO:
DESCRIPTION: (Must Se Unclass15ed) REFERRED TO DATE RECE!YED 3Y DATE RE TO ATOMIC POWER PIANT AT BODEGA BAT y7" i -
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. j NOTHERN CALITOLNIA ASSOCIATION ;
l TO PRESERVE 'l BCDEGA HEAD AND HARBOt 2731 Durant Avenue Berkeley 4,. California l Telephone: THornwall 1-6399 l (Area Code 415) rot IMMEDIATE RELEAFE 1 l
Monday, May 6 1963- q
~
PG&E CHARGED WIT'1 GIVING TALCE '
TESTIMCNY CN BG)EGA EARTHQUAKE HAZARDS J
San Trancisco, May 6---Detailed charges that PG&E has given the State Public Utilities Commission falso testimony and the Atomic Energy Commission false and 1 altered documents in applying for permission to build the Bodega Bay atomic power-plant were levelled today by the conservation gn>up which has been fighting the 1 project for nearly a year. . .
)
1 A lengthy " memorandum of action" filed today with the CPUC by the Northern California Association to Preserve Bodega Head and Harbor was based on two public q
documents: (1) a late-filed exhibit on earthquake hazards filed by PG&E after the . I close of hearings before the Public Utilities Commis sion test Spring; and (2) the
Preliminary Hazards Summary," subraitted by 'PG&E to the Atomic Energy Comamission. 1 It seeks to prove four main points: .
j
- 1. PG&E testified that the San Andreas fault is more than one-quarter mile from , '
the atomic reactor while knowing that it was less than that (Tederal. regulations state that a reactor must be more than one-fourth mile from a known active earthquake i
fault.)
- 2. The borings into the, foundations show that there is no soli,d rock at the reactor ;
1 site. The reactor will be founded on badly decomposed " quartz-diorite" which is - i mostly clay and that the associated structures will be founded on more than 50 feet
' oter -aturated sand, silt, clay, and decomposed wood. -
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- 3. The reports of PG&E's earthquake harlsrd r!onsultant showed the site to be 7>
so unsuitable that the company has tried to suppress the reports, has altered some 3 of their conclusions and 5ss failed to submit the most recent and damaging information-
' to the /tomic Energy Commission.
- 4. Outside experts brought in by the Assocbtion have found evidence of an l
active earthquake fault right through the proposed reactor site. i U
At the close of the CPUC hearings last Spring, PG&E was required by the Comm-t is sion to file a late exhibit containing all the reports of the company's experts who had consulted on the earthquake hazards of the plant. The memorendum fPed by the i
Association shows that the Commission failed to give the late filed exhibit a close' reading.
"The Commission appears to have relied on a summary of the exhibit prepared by PG6E's engineers--without looking at the actual reports," said David Pesonen, Executive Secretary of the Association.
"In addition," he said, "the conclusions of Dr. Tocher from the University of
, (
California have been altered in PG&E's report to the AEC to make th~c site look more 4,
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suitable than Tocher said it was. " :
Pesonen said that he and others were et first misled into behe.ving that the 1
" bedrock" on Bodega ficad was simiPr to "the stuff you see in the Sierra. " ' But, he added. "we now know tha,t'it's much older, badly fractured and crushed, and 1
. deeply weathered' " .
4 The memorandum asks the CPUC to " retrace its steps" in grenting' a permit' to
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PG&E last November on the grounds that it was obtained through knowingly false testimony.
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The Association memorandum traces chronologically how three reports on the q
. Bodega foundations by the firm of Dames and Moore of San Trancisco, came up w:th progressively less favorable results. "The last Dames and Moore report,"
Pe: sori:n said, " indicated that a quirk of geology had crea ted 'the case of the l
missing layer (of rock)'."
"Thesrs are Dames and Moores words," he said, "and this last report was only made available to the PG6E while the CPUC hearings'were going on." By this tame e " fierce momentum" had built up behind the project. The memorandum notes j
t1at "PG&E was then faced with two unsavory alternatives." (1) They could pull il aut and admit a gross error in planning, or (2) they could go ahead-"and hope they ,
f3 didn't get caught," Pesonen said: "obviously they took the second alternative."
Tae action in filing the memorandum is unrelated to the lawsuit brought by the '
Association to overturn the permit granted three years ago by Sonoma County.
The Association won the first round in that suit on Friday when Superior Judge Littari Gibson struck down the three objections raised last Wednesday by the I
-l Senoma County Board of Supervisors.
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