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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20137N1591997-03-31031 March 1997 Informs That Licensee Facility Scheduled to Administer NRC GFE on 970409.Sonalsts,Inc Authorized Under Contract to Support NRC Administration of GFE Activities ML20058M0361993-04-12012 April 1993 Partial Response to FOIA Request for Documents.Forwards Records in App L Which Are Being Withheld Partially for Listed Reasons,(Ref FOIA Exemptions 5) ML17347B5881990-03-0101 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 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 ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 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) 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 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 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 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 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 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 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) 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 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 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 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 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 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 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 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 1997-03-31
[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 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 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) 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 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 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 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 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 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 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 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 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 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 ML20210S9971986-10-0202 October 1986 Requests Change in Facility Svc List Address to Ref Address. Related Correspondence ML20215K9561986-09-22022 September 1986 Supports Licensing of Facility Due to Close NRC Scrutiny of Const & Operation 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 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 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 1989-07-05
[Table view] |
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- DO NOT DISCLOSE Contains identi'y t of e, confidential source AFFIDAVIT - .
My nane is E. Earl Kent. I am making this statement of my own' free will to Mr. David Crow, who has identified .
- himself to me as an' investigator for the Government Accountability Project. I am speaking without threat or promise of material benefit. My reason for making this statement is to express my deep concern over the mr
- quality of construction at the Midland nuclear plant,
^9 . where I was terminated in March of 1982 for persistently I9 bringing defects in construction and specifications
- 60 I to the attention of my superiors. .
Or -
I have worked for seventeen years in engineering, N most recently at six nuclear plants. I hold the title of senior Quality Control Eng,ineer for nuclear welding.
I have been a member of the American Society for Quality Control, and have published several books -
on welding and structural steels. Before coming to Bechtel, I worked as an engineer for Litton Industries, as a field welding inspector for Boyle Engineering
' ,\0 /
Corporation, and as a welding supervisor for Fluor f?
Engineers. I have also wo'ked r as a quality assurance
, gnd quality control engineer for Joy Manufacturing.
I have attend'd e more than half a dozen professional 1
education courses on engineering.,and quality control.
Prior to moving to the Midland plant, I had worked l
for Bechtel at two of its other nuclear units, Pallisades I
e
Paga Two
) ,
,'. Contains identity' of confidential 4
- purce. DO NOT DISCLOSE and San Onofre Plants One and Tdo. In both of these earlier . .
! Bechtel positions, I served as Senior Quality Control
- Engineer. I received top recommendations from my .
l . supervisors at both these plan.ts. There is a letter on file with 3echtel's central office, from the Vice President l of Bechtel's Los Angeles Power Division, for my work there.
Based ony my years of experience in nuclear plants-,
it it my prUfessional opinion that the Midland plant ,
1
- is the worst nuclear facility I have ever seen. This.
affidavit will detail instances where Bechtel Corporation has systematically downgraded standards for safety-related equipment, to the point where I do not_ believe that much of the construction _will not withstand the stresses it j should be built to take. Bechtel has hired engineers and QCinspectorswhoarenotadeqIatelyqualifiedor, trained for the complicated work in a modern nuclear plant. I ,
have seen Bechtel personnel, both QC inspectors and engineers with QC responsibilities, routinely accept substandard work. .
I will also give . examples of the unhealthy degree of reliance that certain NRC inspectors have placed in the
. Bechtel personne,1 whom they are supposed to monitor. NRC -
field inspectors showed a surprising willingness to let the Bechtel personnel do all the dirty work involved
- in supposedly independent investigations. Because NRC
. inspectors often didn't themselves try to take the t
h
Ng
-. . Contains identity of' confidential Page Thrch source. DO !!OT DISCLOSE v
- f. . neasurements, or climb into less accessible areas, the inspec-tion reports that were supposed to represent a completely
\
', separate check on Bechtel performance often wound up basing their approval on Bechtel's evaluations of its own work. 8,.
~~~ s My expertise is in welding' inspection. When I first came to Midland, in December 1981, I reviewed Bechtel's specifications and procedures. I was astonished to see that in numerous places, Bechtel had established standards which
/ ffellbelowthoseof.theASMECode. The ASME Code ref.lects the
- ur .
I best judgment of the national society of professionals in this ,
area. It is the result of many y' ears of testing. Despite i
this Bechtel in some cases made th'e decision, based on their own engineers' short-term testing in San Francisco, to modify these standards.
If Bechtel had made these changes only to take account of particular needs at Midland, that would be one thing. But' in the area of welding, where I was qualified to judge, the new specifications were inadequate to the needs of a nuclear facility. There is an inter-office meio, dated 24 April 1981, which I have in my files. It is between the project QC head, E. Smith, and a main office materials and quality services official, D. Hackney. The subject is socket weld engagement length. Hackney states that as long as the pipe is not with ,
i j * ' drawn from\ ;th e fitting it will be approved. This means that a i
gap of nea ly any length will be tolerated between the end of the pipe and the bottom of the sobkst.
Thcsc gar:. vcaken the l joint, and make it susceptible to vibration. The ASME Code e
e
, ---.,--n ,--...-.----n
Fa9o Four Contains identity of confidential sourca. DO NOT DISCLOSE D%
.- ' has, for this reason, established a much more rigorous specification. -
This is only one example of the systematic downgrading of welding standards I saw at Midland. The Hackney meno became
one of many sheet-memos placed in the specifications book.
. Equally as serious as the problem of downgraded specifi-cations were the problems created by the incompetence and ignorance of QC. Even something basic like knowing how to use the fillst gauges correctly to measure the size of welds was -
beyond the ability of some of the Bechtel inspectors.
In early February, I was working with one of these Bechtel QC inspectors, John Kunski. John was about to approve a fillet weld when I saw that it had not been fully welded.
, Fillet welds have to be full across the blade, not just touch-ing one edge of the blade. I drew John a diagram to show him this. When John looked at the' diagram, he saw that I was right.
But the' welder refused to put any more weld on -- he said he'd been doing it that way for two years, and his boss had always approved it. We finally had to call his boss in, and explain it to him, before we would get the, weld to be redone. Paul Schulz, another QC inspector, was also there to hear the explanation, and he admitted af ter I showed him the diagram that he'd been approving bad welds himself.
e Undersized and improperly done welds were serious problems, but at least they, didn't affect phe integrity of the piping .
itself. High-pressure piping, which contains up to 1500 pounds per square inch, is very vulnerable material. It reacts like
Page Fivo C ntains identity of confidential source. D0 !!OT DISCLOSE a balloon to a pinprick. A weakness in any part of the piping
. is a danger to the entire length. Because of this, I was very a
concerned to discover that many welds in the piping had been, improperly ground down, grinding down the pipe wall thickness b
along with it.
This was not only a violation in itself. -It was part of a larger problem having to do with" inspections of the parent metal for the piping systems. In small bore piping, the only way to inspect the inside of the piping' for corrosion is to 2:c.r , . .
take what is called a thickness and materials (TM) reading.
This is a time-consuming process if done correctly. To the
, best of my knowledge, the Bechtel QC inspectors rarely took the time necessary to do this type of verification. They usually relied on visual inspection only. Visual inspection, can detect corrosion only on the outside of the piping.
l When I performed a thorough inspection myself of the l .
piping, using TM readings for the inside of the pipe wall, I l
discovered extensive corrosion. Although the QC reports' appear
~
to assure that the piping is of safety-grade quality, these reports fail to reflect the problems of the piping systems which I discovered. To allow severely corroded piping to.be approved for safety-related systems is in my opinion inexcusable, a'nd certainly very dangerous to the successful operation of ghe plant.
Another piping problem with which I was personally familiar developed because Bechte,1 allowed electrodes used in welding to be taken out of their hermetically-sealed containers
~
g, %
Page Six Eontains identity of confidential snurce. DO NOT DISCLOSE
- J for eight hours before use. The American Welding Society (AWs) standardI allows only four hours in the open air. When the ,
electrodes are left out, the chemicals in their coating attract ambient humidity. When this moisture is absorbed, it will .
become steam under .the heat applied during the . welding process.
3 Each speck of moisture will expand to 750 times its initial volume, and results in substantial porosity, or simply empty
, , space, within the completed weld. The weld will appear strong, j but be Wdikened fr6m within.
The AWS standard is used for *
)
ordinary bridges and office build,ings, but apparently Bechtel thought that twice as lenient a standard was appropriate for a nuclear plant. .
X-ray inspections of welding performed under these ,
conditions has revealed porosity. The welds have had'to be torn out and redone, not just once but many times, often within the same joint. This is one more example of Bechtel's not doing it right the first time'. Every time they had to tear the welds out and do them again, it adjed to their costs and ,
to their profits.
Bechtel has a cost-plus contract, and had routinely wasted large amounts of money because they have little incen-r t'ive to do the work right the first time. Each time further -
. , expenditure \s are required to redo work, it adds to their fee.~
e !
I I have sees work ripped out because of shoddy installation, redone, and then ripped out and r,ddone again because it still wasn' t right. One QC engineer, who has been at Midland since O
- - - - - - - - ~ , - . . , , , . ._,n-- - - , , -
Contains identity of confidential Pa9e Seven sourcs. DO NOT DISCLOSE N .. ,
the beginning, told me that over 90 percent of the piping in
-t - .
, the entire plant has had to be cut out and replaced at one ' '
, point o'r other. In my mind, this raises serious questions of safety, but it also makes me wonder who is going to wind up paying t1:a bill for, Midland. Bechtel's indifference to quality will cost the ratepayers a bundle, if they are allowed to pass on their costs to the public. -
, The defects I have described are generic to the Midland plant. Ei6ey have happened because Bechtel has hired inexperi-
- enced welders and inspectors. Th,ere were few formal require-ments to become a welder, or even an inspector.
If this was supposed to be corrected through a thorough training program, it didn't happen. The training periods were only a couple of
; weeks, and based on my experience in working with the ' welders and the inspectors, I can state that they were not properly trained. When inspectors don't know how to use a fillet gauge to measure welds, you know that the overall program standards cannot be very high. -
N'RC inspections often failed to correct problems. In the area of the inside wall corrosion in small-bore piping, this was because the inspectors seem'ed too willing to trust the Bechtel inspectors when they made their tours. It was
. , generally the Gechtel people who actually climbed around on '
the piping and called out their measurements, which the NRC inspectors would then write down.j As a result, many of 'the -
inspection reports do not reflect anything more than Bechtel's own assertions.
s O
'N Paga Eight, icontain's identity of confidantial courcs. DO NOT DJSCLOSE Even when the NRC inspectors did show a willingness to carry out a real inspection,.they would be handicapped by
. their practice of not coming in unannounced. To the best of my knowledge, there were no NRC inspections that weren't pre- ,
ceded by two or three days of preparation directed by Bechtel, during which problems would be repaired and som'etimes concealed.
As a result, the inspectors never saw the plant as it really -
operated on an every-day basis.
My alarming experiences with the ' field welding and the u v=" i
- QC inspectors led me to speak to my boss, Mr. William Creel, numerous times in December and January. Bill generally had the same response: he said that all his men had passed the Bechtel tests and were fully qualified, and he was willing to take their word for it if they said construction was safe.
My real problem began when I tried to talk to the head of Project QC, Mr. Eugene Smith. He told me what Bill Creel t was saying, that everybody was qualified and so there couldn't be problems like the ones I was telling him existed. '
On Friday, February 26, Eugene Smith called me into his-office and told me I was to be terminated. Bill Creel was I
also there, and the two of them tol'd me tha't I hadn't been
(
able to adjust to the way things were done at Midland, and so th'ey would have to let me g'o. They asked me if I had any
. written e comment's to make on the termination notice. I wrote down; "I do not agree with any of the i above, and ask for,a
. complete investigation of this and"all other main prebicms, by the San Francisco home office, and especially Mr. S. Bechtel.
t
- -- \ -
i -
4 j
Pagn Nina tontains identity of confidential
- p. -
Murce. DO NOT DISCLOSE Never in my life have I ever seen so many critical welds accepted in nuclear work. If this many errors are allowed to -
, exist,/the results could be catastrophic."
- After I wrote this down, Mr. Smith must have called Ann Arbor Headquarters, because he told me to go see Mr. Don
- Daniels on Monday. Mr. Daniels met me at the Holiday Inn in Midland, and I tried to explain to him the problems I had seen '
I in the field and with QC. I drew him the same diagrams I had l dran f'$f John Kunski, about the welding standards. All he *
- saio to this was that all the welders and inspectors were qualified'. The feeling I got was th,at even if I proved what i I was saying, Daniels wouldn't do anything about it. He couldn't believe what I was telling him -- he believed in the 4
i j papers that told him the Midland personnel were qualified.
j . Before Daniels finally told me that I would have to be
, fired, he made another phone call. I believe it was to Eugene Smith and Bill Creel. Creel was the one who most wanted me i
\
\
to go.
,/ -
I was also told that in addition to my bad adjustment to Midland, I was being terminated because I had failed to l pass the Bechtel tests for Level I CiC engineer. Now as I l
stated earlier, I have seventeen years of experience in QC F ~
and welding. At other'Bechtel installations, Palisades and -
i e San ononfre, I held both Level I and Level II certificates.
y -
Midland was not that different from these other Bechtel opera- -
tion's. I cannot believe that I hadn'( passed the Level I test at Midland. I was never,given a copy of the written part of n . - - - - ,.--,r ,.,m_ -r- g,.. , , , . , , _ , . . , , _ - _ _ ,,,, ,- - --- ,..n
N Contains Idsntity-of confidsntial
; Page Tsn
, , sourca. DO NOT. DISCLOSE ,
% %.., g the test. I can only believe that I was fired for insisting that there were serious problems at Midland. which my superiors .
refuses to acknowledge. '
l Because of the way I had been terminated by Bechtel, *
, and because I felt that my observations had not, received any
. attention from the internal hierarchy, I decided that I should speak to the NRC. On March 2, 1982, I arranged for a telephone interview with Roger Warnick, William Paton and Don Danielson of NRC.WEIn that interview I told them what I have detailed .
here in this affidavit. I told them I felt that Bechtel was not adequately investigating the serious " problems I had tried to bring to their attention, and that I felt I had been fired for trying to do this.
After I spoke to the NRC, they sent out an inspectors to look into my allegations. His report indicates that he spent three days on-site. I' don't think that a full investi-gation could be conducted in such a short period of time, by
, only one inspector. However, I do fee ,that the report con-firmed my charges, based on what happened when the inspector
- , met with the top men from Consumers, Mr. }hrguglio and Mr. Bird.
l -
The inspector found them to be extremely hostile to any sug-l gestion that there were serious deficiencies with welding and
. with QC procedures and qualifications. The inspection report found that further investigation was warranted in this area.
) Although the report noted the need for further oversight, ,
5 it seemed to feel that voluntary monitoring, of Bechtel by Consumers would clear up the problem. The problems are too
., - .-c _--.,y,_- , _ - - . _ _ - - - _ - _ _ _ - , . - - - - - , _ , _ - - . , - ,,.s -,- -- _ ----- ___ - _
g .
\ s '
page E16 van source.hentains identity' of con
..' DO NOT DISCLOSE serious and widespread to be left to be corrected by the .
people who created them. 'I believe that only an independent and comprehensive investigation, by the NRC or by outside -
, experts, can provide the assurance that Midland is properly built. '
I am sure that consumers and Bechtel will respond to my charges the say way they responded to th NRC in-3 spectio,n 3 They will deny the problems and promise voluntary ,
efforts to cure them. They will try to ruin my credibility, by saying that I was incompetent,'that I couldn't pass the basic tests. Nevertheless, I stand by my statement. After nearly twenty years of work as an engineer, I know a defi-cient weld when I see one, and I know how many of these welds and other problems went undetected or ignored by the men responsible for inspectin'g them. Bechtel has shown by its attitude that it cannot be trusted to perform work of the high quality necessary in a nuclear plant. I feel that a full investigation into its management and construction practices will show that much work will have to be redone
, before Midland can ,go into oyjeration. The cost will be enormous, if it can be done at all. Despite the cost, I canno.t st'a nd by and watch the plant go on-line in its -
present state of s,afety. To do so would be to betray my responsibilities as a professi pal, as an engineer, and
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- .I
, as a citizen.
I have/read the above twelve- (12) page affidavit. To the best of my knowledge, it is true, accurate and complete.
~
E. EARL KENT SUBSCRIBED AND SWORN TO before me this day of , 1982.
/
Notary Public O
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' ' ,"C,','g' 3" - ALLEGATION DATA FORM e s r,ucae n m.auer., cc.c 1ssics s, jnstfuCt'One on f3verSP Sade
'.'. RECEIVING OFFICE
- 1. Facilitylles) Involved: themet
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(tt more then 3. or it l LAalk fly i r 4/ 0 g o o a 3 a 1 eeneric. write GENERIC) tis h LMk u mr #.u - 0 5 o o o 3 3 0
- 2. Functional Area (s) Involved:
(Check enpropriate bon (es) ) ,
_. operations _ onsite health and safety construction _ offsite health and safety
.,_. safeguards , emergency preparedness
_ other aspecityl 3.
Description:
10.1O IY\lt. le IR k ls l l Nl e llrld 14 Icl 11 In l/r l ld IC l l l l l I , I al.s l el ele ir lo i als I, I /l el.e Is lo in In lelt i II III Irl RIAL /141,Islal, lulelLI A l, lalal. Iflil Plel l II I Iclo I AIRiolsl ilolhl I Alvill leIdlh li l#le le IRliInld-l
- 4. Source of Allegation:
(Check appropriate boml _ Contractor employee _ security guard
_ licensee employee . news media
_ NRC employee 7 private citizen organization Especity) M 4 #"
_ other tspecityl d/If ##E140I MM DD YY
- 5. Date Allegation Received:
- 81. Name of Individual trirst two initi is and inst namel TbUMM Receiving Allegation:
- 7. Office:
7 l
ACTION OFFICE
- 8. Action Office
Contact:
trirst two initi is and seit nemen I1 NISOA
- 9. FTS Telephone Number: g g 3 3 .
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- 10. Status:
(Check one) Open, if followup actions are pending or in progress j
l Closed, if followup actions are completed l MM DD YY
- 11. Date Closed:
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- 12. Remarks: lg lg lyly lNlj; l7l g l0 l l cl, lf,j plf. lg l7.lyl, I/VI lBle I TIE I (Limit to 50 chorecters)
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, March 8, 1983 ML l I'"~: 4 JL l~i.2TE-Murj MEMORANDUM FOR: James G. Keppler -
Yind. &k Regional Ariministrator, Region III FROM: Guy Cunningham, III Executive Legal Director
SUBJECT:
AFFIDAVITSSUPPLIEDTOREGIdN'IIIBYGAP As you know the Government Accountability Project furnished six affidavits to Region III in June 1982. I understand that initially it was believed that the allegations contained in those affidavits were to be investigated by the Office of Investigation. However, it has been brought to my attention that during a recent meeting in Region III it was determined that five of the affidavits would be referred to Region III. The sixth affidavit is being investigated by OIA.
. Consumers Power Company's attorneys involved in the Midland proceeding have indicated that they wish to engage in discovery with respect to those affidavits but have voluntarily refrained from conducting any l discovery at our request. Although they were initially told that 01
,. would investigate these allegations they were recently advised that l five affidavits will be referred to Region III for investigation. We are not certain now whether they will continue to voluntarily refrain from engaging in discovery.
l All issues arising out of the December 6,1979 Order modifying construc-i tion permits, except those involving quality assurance have been fully submitted to the Board. As you know, a hearing on the quality assurance issues is scheduled to begin on Tuesday, April 26, 1983.
Because these matters are of importance to the Board I wanted to bring them to your attention so that you can take whatever action you deem appropriate.
L d
/ _
Guy H. Cunning' nam, III Executive Legal Director I
, y,p MAR 10 53
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GLEN ELLYN, ILUNof 5 60137
***** SEP 17 G82 MEMORANDUM FOR: James G. Keppler, Regional Administrator THRU: R. F. Warnick, Acting Director, Office of Special Cases FROM: W. D. Shafer, Chief Midland Section SUEJECT: GAP COMMUNICATIONS (MS. BILLIE GARDE)
On September 17, 1982, I was requested to contact Ms. Billie Garde to answer some general questions about the Midland project. To the best of my recall, the following was discussed:
((1) She asked about the status of the six GAP affidavits.
I explained that the 01 investigation was progressing and that some of the people had been contacted. I stated that when the investigations were completed that OI would turn the information over to our staff for technical review and inspection.
(2) She asked about the status of the Zack investigation.
I informed her that the investigation was progressing and that Midland had priority after LaSalle. I also told her that CPCo had a copy of the Zack affidavit. She said they did not get it from GAP.
She stated that she was very concerned that we have not pursued the issue as to whether CPCo should have reported the Zack problem under 10 CFR 50.55(e). I explained that this issue would be addressed in our investigation and inspection effort.
(3) We discussed several current issues at the site as follows:
(a) Investigations
- 1. I stated that the investigation into the March 10, 1982 meeting where Messrs. Cook and Landsman alleged they had been lied to was nearing completion and
- that a final report would be forthcoming.
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- 2. I informed her that a request for an investigation into the potential violation of the board order had been forwarded to OI in HQ. I told her 1-did not know if an investigation had. commenced. ,
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f (b) Discussed the development of the Work Authorization Procedure I stated that RIII had determined that a formal communications 1 mechanism was needed to ensure that all work authorizations j would be in writing. 3 (c) Pipe Support and Restraint Problems
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I discussed Isa Yin's inspection report and CPCo's subsequent inspection find,ings in this area. I stated that we have informed CPCo that we want a 100% reinspection of all supports and restraints installed prior to 1981.
(d) Misrouted Electrical Cables I stated that we had informed CPCo that a reinspection of all >
SR cable was mandatory.
(e) Midland Section I identified the Midland Section personnel and stated that the remedial soils work interface was the highest priority we had.
'J I also stated that we were waiting for CPCo's conmitments for improving their program and that you would not allow any major soils work to proceed until the Midladd Section was satisfied that the program was acceptable.
(4) After discussing item 3(e) above, Ms. Garde stated she was l disappointed that GAP input was not solicited during the formation I
of the Midland Section. I stated that this was a management decision
'and could not, connent furthat'. However, I stated that she was welcome to contact me at ai.;::ime in order to ensure good communi-cations. Ms. Garde a W ed te would like to meet with the Midland i Section and would (St. t,th . ) me regarding!when. I encouraged her to do so. She gMeu wt open conmiunications were very byor- i j
tant in that when she made a press release she would be able to discuss what the NRC was doing.
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James G. Keppler gpp j 7 ggy (5) Hs. Garde discussed the SSER and wanted to know if R. Landsman'sI concern about the board violation would be addressed in it.
said I doubted if it would. The SSER document would extensively identify the design elements for the remedial soil underpinning activities. We expected the SSER to be issued on October 4, 1982.
(6) Ms. Garde stated that she was preparing to meet with D. S'aunders and was trying to obtain his affidavit. I wished her good luck and stated that we would be reviewing the relevant allegations we have obtained from Mr. Saunders.
(7) I informed Ms. Garde that our section was developing a monthly status report which would indicate the status of RIII's effort at Midland. I told her the report would be docketed and if she wanted access to it she would have to request it through formal channels. She said she would do that.
I believe that this summary was the extent of our conversation. It was not necessarily in the order I have described above, but I do believe I have I intend to send Ms. Garde a copy of this covered the most salient issues.
summary.
Should you have any questions regarding this communication, I will be happy to discuss them with you.
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/J,D.Shafer, W. hief l
' Midland Section ec: A. B. Davis l .}}