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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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W4 Donohoe, Apt.16 Palo Alto, California February 16, 1964
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Atomic Energy Commission Washington 25, D.C. (' ' ' 'c ,,~ - . . ,/.3 -
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Dear Mr. Chairman:
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The proposed plan by Pacific Gas and Electric to use~ '
Bodega Head, California, for the site of an atomic power plant will soon come up for review by the Atomic Energy i Commission. I would like to voice disapproval of the 4 plan and to encourage rejection of this site. f
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I Bodega Head seems a risky choice for an atomic power
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plant. Recent geological studies have shown that trie 7 proposed site would be dangerously situated on the fault f
! line of an earthquake. Statistics point out the increased l risks of placing a potentially destructive power almost on top of an ignition.
We can control some of our man-made forces; in only a few instances have.we been able to curb or control natural l forces. We would be optimistic to think we could stop an i earthquake from occurring.
Too many lives are at stake to play the odds at Bodega Head. I hope you will take every possible step l
to avoid a highly dangerous situation by finding a more suitable location for the Pacific Gas and Electric power plant.
All your decisions are of great interest and importance to our nation, and I wish you. strength, insight, and support in your work.s.j~5,%
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, f 'j ,(Ng Tours very sincerely,
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Pa2o -alto, California
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For Information For appropriate handling For preparation of reply for Chairman's signature For discussion at Commissioners' Information Meetin'g For distribution to other Consnissioners Daily Log
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Houa rd C. Brown, J r.
For the Chairman u-8 I
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