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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 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) 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 ML18094B3291990-02-14014 February 1990 Forwards Printouts Containing RW-859 Nuclear Fuel Data for Period Ending 891231 & Diskettes 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 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 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) 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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:LEGAL/LAW FIRM TO NRC
MONTHYEARML19354E4191990-01-25025 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 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 ML19332D8511989-11-30030 November 1989 Forwards Antitrust Comments W/Exhibits & One Copy of Comments Sans Exhibits of Cities of Benton,Conway,North Little Rock,Osceola,Prescott & West Memphis,Ak & Farmers Electric Cooperative Corp ML19325E3711989-10-30030 October 1989 Forwards 891027 Ltr to Counsel for NRC for Filing on Appropriate Dockets & Legal Issues Re Antitrust Aspect of NRC Review of Consolidation of License Amend Application ML19325E3741989-10-27027 October 1989 Lists Three Legal Issues Re Antitrust Aspects of NRC Review of Consolidation of License Amend Application for Facilities.Licensee Supplemental Info Filed W/Nrr ML18094A6521989-08-24024 August 1989 Forwards Endorsements 140 & 141 to Nelia Policy NF-164, Endorsements 117 & 118 to Maelu Policy MF-44,Endorsements 115 & 116 to Nelia Policy NF-208 & Endorsements 102 & 103 to Maelu Policy MF-77 ML20245C9081989-04-11011 April 1989 Forwards Endorsements 63 & 64 to Maelu Policy MF-102, Endorsements 71 & 72 to Nelia Policy NF-247.Endorsements 106 & 107 to Nelia Policy NF-198,Endorsement 11 to Nelia Certificates N-38,N-39 & N-40 & Endorsement 10 to MF-75 ML20244D9001989-04-0606 April 1989 Forwards Endorsements 94 & 18 to Maelu Policies MF-78 & MF-129,respectively & Endorsements 112 & 24 to Nelia Policies NF-215 & NF-302,respectively ML17347B0961989-03-29029 March 1989 Forwards Endorsements 77 & 100 to Nelia Policies NF-227 & NF-185 & Endorsements 64 & 87 to Maelu Policies MF-88 & MF-55,respectively ML20244E0431989-03-28028 March 1989 Forwards Endorsements 92 & 78 to Nelia Policy NF-174 & Maelu Policy MF-51,respectively & Endorsements 78 & 67 to Nelia Policy NF-197 & Maelu Policy MF-68,respectively ML20245D6071989-03-27027 March 1989 Forwards Endorsements 113 & 114 to Nelia Policy NF-220, Endorsements 133 & 134 to Nelia Policy NF-164,Endorsement 143 to Nelia Policy NF-1 & Endorsement 86 to Nelia Policy NF-195 ML20245D3421989-03-20020 March 1989 Forwards Listed Endorsements,Including Endorsements 14,163, 144,94,75,39 & 31 to Nelia Policies NF-295,NF-100,MAELU Policy MF-29,NELIA Policy NF-182,MAELU Policy MF-61,NELIA Policy NF-281 & Maelu Policy MF-112,respectively ML20235T8911989-01-18018 January 1989 Forwards Endorsements 130 & 131 to Nelia Policy NF-164, Endorsements 107 & 108 to Maelu Policy MF-44,Endorsements 94 & 95 to Nelia Policy NF-107,Endorsements 110 & 111 to Nelia Policy NF-220 & Endorsements 97 & 98 to Maelu Policy MF-73 ML17347A9071989-01-12012 January 1989 Forwards Endorsements 5,11,9,63,62,4,11,11,86 & 85 to Maelu Certificates MW-60,M-56,M-89,MF-88,MF-88,MW-29,M-26,M-25, MF-55 & MF-55,respectively & Listed Endorsements to Listed Nelia Policies ML20205Q3381988-11-0404 November 1988 Forwards Requests for Renewal or Extension of Exemption from Requirements of 10CFR50.54(w)(i) Re Property Insurance.Fee Paid ML17345A4751988-10-24024 October 1988 Forwards Endorsements 10 to Nelia Certificates N-59,N-25, N-26,MAELU Certificates M-59,M-25,M-26,respectively & Endorsements 8 to Nelia Certificate N-89 & Maelu Certificate M-89,respectively ML17345A4051988-09-16016 September 1988 Forwards Endorsements 73 & 74 & 95 & 96 to Nelia Policies NF-227 & NF-185,respectively & Endorsements 60 & 61 & 82 & 83 to Maelu Policies MF-88 & MF-55,respectively ML20155F7771988-08-0505 August 1988 FOIA Request for Documents Re Low Level Radwaste Facilities to Be Built at Plants ML20151D8121988-07-15015 July 1988 Forwards Opposition of City of Clyde,Oh to Util Application to Suspend Antitrust Conditions at Facilities,Per 880616 53FR22589 & 53FR22590 ML20155A2501988-06-0303 June 1988 Forwards Endorsements 4 & 4 to Nelia Certificate NW-78 & Maelu Certificate MW-18 & Endorsements 3 & 3 to Nelia Certificate NW-125 & Maelu Certificate MW-46,respectively ML20154P0371988-05-26026 May 1988 Forwards Policy Endorsments,Including Endorsments 51,36,91 & 77 to Nelia Policies NF-252,NF-281,NF-182 & NF-238, Respectively & Endorsements 32,28,72 & 65 to Maelu Policies MF-108,MF-112,MF-61 & MF-93,respectively ML20154K8561988-05-18018 May 1988 Forwards Endorsements 93 & 94 to Maelu Policy MF-73 & Endorsements 106 & 107 to Nelia Policy NF-220 ML18093A8111988-04-28028 April 1988 Forwards Endorsements 102 & 103 to Nelia Policy NF-208, Endorsements 89 & 90 to Maelu Policy MF-77,Endorsements 100 & 101 to Nelia Policy NF-230 & Endorsements 84 & 85 to Maelu Policy MF-90 ML20151A6361988-03-28028 March 1988 Forwards Endorsements 1 & 2 to Nelia Certificates NW-96, NW-103 & NW-34 Respectively,Endorsements 1 & 2 to Maelu Certificates MW-32,MW-62 & MW-8 Respectively & Endorsement 140 to Nelia Policy NW-1 & Endorsement 43 to Policy MF-95 ML20148K1111988-03-22022 March 1988 Forwards Listed Endorsements to Listed Policies,Including Endorsement 102 to Maelu Policy MF-26,Endorsement 123 to Nelia Policy NF-76,Endorsement 71 to Maelu Policy MF-56 & Endorsement 89 to Nelia Policy NF-189 ML17347A6951988-03-17017 March 1988 Forwards Endorsement 71 to Nelia Policy NF-227,Endorsement 58 to Maelu Policy MF-88,Endorsement 88 to Nelia Policy NF-185 & Endorsement 75 to Maelu Policy MF-55 ML20150D4821988-02-23023 February 1988 FOIA Request for All Plans (Subsequent to Util 870807 Commitment to Excellence Action Plan) by Util to Commission Re Restart of Facility ML20147F8231988-02-18018 February 1988 FOIA Request for Documents Re Purchase,Shipment, Distribution,Installation & Removal of Asbestos & asbestos- Containing Products at Various Nuclear Power Stations in State of CT for Jan 1966 - Dec 1975 ML20148H0821988-01-12012 January 1988 Forwards Endorsements 105 & 16 to Nelia Policies NF-215 & NF-302 & Endorsements 87 & 10 to Maelu Policies MF-78 & MF-129 ML17342B0731988-01-0707 January 1988 Forwards Endorsements 69 & 70 to Nelia Policy NF-227, Endorsements 86 & 87 to Nelia Policy NF-185,Endorsements 56 & 57 to Maelu Policy MF-88 & Endorsements 73 & 74 to Maelu Policy MF-55 ML20236U2571987-11-0505 November 1987 FOIA Request for Documents Re Ball Type Main Steam Isolation Valves Used at Facilities ML20236F7221987-10-0202 October 1987 Forwards,On Behalf of Util,Request for Exemption Per 10CFR50.12(a)(2)(v).Fee Paid ML20235J0031987-09-21021 September 1987 Forwards Endorsements 122 & 123 to Nelia Policy NF-164, Endorsements 99 & 100 to Maelu Policy MF-44,Endorsements 100 & 101 to Nelia Policy NF-220 & Endorsements 87 & 88 to Maelu Policy MF-73 ML18093A1291987-05-11011 May 1987 Forwards Endorsement 94 to Nelia Policy NF-230 & Endorsement 78 to Maelu Policy MF-90 ML20214E3101987-05-11011 May 1987 Forwards Endorsements 120 & 97 to Nelia Policies NF-164 & NF-220 & Endorsements 97 & 84 to Maelu Policies MF-44 & MF-73,respectively ML17347A4841987-05-0707 May 1987 Forwards Endorsements 72,104,46,67,83,96 & 59 to Nelia Policies NF-238,NF-215,NF-252,NF-227,NF-185,NF-198 & NF-247 & Endorsements 60,86,27,54,70,82 & 51 to Maelu Policies MF-93,MF-78,MF-108,MF-88,MF-55,MF-66 & MF-102,respectively ML20235G2321987-04-0101 April 1987 FOIA Request for Documents Re Forged NDE Inspectors Certification Supplied by Barclay Intl for Use at Quad Cities Nuclear Station & Stated Investigations at Plants ML20235B2741987-02-19019 February 1987 FOIA Request for Documents Indicated on Encl Docket Sheets. Request Does Not Encompass Matl Already Available in PDR or Lpdr Denoted by Three or Four Asterisks on List ML20211L3011987-02-12012 February 1987 Forwards Settlement Agreement W/State of Il,Consisting of Draft Testimony & Petition ML18092B4271987-02-0303 February 1987 Forwards Endorsements 90 & 75 to Nelia Policy NF-230 & Maelu Policy MF-90,respectively ML20211C5811986-10-16016 October 1986 Requests,On Behalf of Util,Reevaluation of Finding That No Significant Changes Occurred in Licensee Activities or Proposed Activities Since Completion of Previous Antitrust Review Re Cp,Based on Listed Reasons ML20214T7431986-09-24024 September 1986 Forwards Form 8-K Filed W/Securities & Exchange Commission. Util Believes Info Presented Bears No Issues Currently Before Aslb.Related Correspondence ML20206S2701986-09-17017 September 1986 Notifies of Address Change Effective on 860927.Requests Address on Encl List of Dockets Be Changed ML20206M8311986-08-15015 August 1986 Forwards Util Response to ASLB 860716 Order.W/O Encl.Related Correspondence ML20212H4171986-08-11011 August 1986 Forwards 860430 Scheduling Svcs Agreement Between Georgia Power Co & Oglethorpe Power Corp.Partially Deleted Interconnection Agreement Between Alabama Electric Cooperative,Inc & Ogelthorpe Power Corp Also Encl ML20202F9581986-07-11011 July 1986 Forwards Util Motion for Authorization to Withdraw OL Application & for Dismissal of OL & Order of Mod Proceedings & Motion for Termination of Appeal Board Jurisdiction,For Filing.W/O Encl ML20207D7261986-07-11011 July 1986 Forwards Motion for Authorization to Withdraw OL Application & for Dismissal of OL & Order of Mod Proceedings & Motion for Termination of Aslab Jurisdiction.W/O Encl.Related Correspondence ML20195E9321986-05-27027 May 1986 Denies Illinois Municipal Electric Agency (Imea) Allegations of Activities W/Antitrust Implications.Facts Misstated.Refusal to Sell Power to Imea Denied Per Encl .Related Correspondence ML20211C2281986-05-21021 May 1986 Forwards Endorsements 74,46,45,76,77 & 83 to Maelu Policies MF-66,MF-102,MF-102,MF-66,MF-66 & MF-78,respectively & Endorsements 87,53,52,89,90,33 & 100 to Nelia Policies NF-198,247,247,198,198,256 & 215,respectively ML20211C7541986-05-12012 May 1986 Forwards Endorsements,Including Endorsement 75 to Maelu Policy MF-66,Endorsement 88 to Nelia Policy NF-198, Endorsement 44 to Maelu Policy MF-102,Endorsement 51 to Nelia Policy NF-247 & Endorsement 70 to Maelu Policy MF-90 1990-01-25
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I 2tebruary 14, 1980 Marshall E. Miller, Esq. ~
I Chairman MIDLAND Atomic Safety and Licensing OLMSTEAD/ /PATON Board Panel U.S. :.aclear Regulatory Commission FF Washington, D.C. 20555 Ivan W. Smith, Esq.
Chairman keej c uC Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: Consumers Power Company (Midland Plant, Units 1 and 2)
Docket Nos. 50-320, 50-330 k Gentlemen:
I have received Ms. ibs' letter of February 8, 1980, on behalf of Consumers Power any, confirming that the commercial operation for bot!
and that the cost for the Mi ts will now extend into 1985
'S3 billion. nuclear units will exceed As we all know, in prior hearings (1976-1978) the I matter of the cost benefit analysis of continuing on with the i Consumers units was analyzed and the Board's then decision was i that the cost benefit analysis did not change sufficient to i
! warrant termination of one or both units. The facts at that time indicated that the plants would be on line in the 1981-82 period and that the <ost would be approximately $1.6 billion.
In addition, at that time, Dow Chemical Company indicated that while the economics of buying process steam from the nuclear units at $1.67 billion was close, it was not sufficient to tip the scale for Dow to pull out.
Things have now drastically changed. Consumers has announced that the cost wil: Le at least $3 billion and that the plants won't even be on 'ine by 1984, beyond which Dow has no obligation to continue under the most recent general agree-ment between Consumers and Dow dated June 1978 and forwarded nr -
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, O Marshall E. Miller, Esq.
Ivan W. Smith, Esq.
February 14, 1980 I
Page Two to all concerned under letter dated June 26, 1978. Indeed, since paragraph 9 of the general agreenent concerning termina-tion indicates that Dow may pull out when there is a clear prospective breach (and that is certainly clear here since Consumers has announced the plants will not be ready by the end of 1984), it would seem that there is a failure of Consumers to meet its obligation at this juncture.
We believe that the Nuclear Regulatory Commission should immediately reinvestigate the cost benefit analysis concerning the Consumers plants since it is not even clear that the 1984-85 deadline or the $3+ billion cost e stima t e will be the end of it. This is in part because any resolutions of the Three Mile Island debacle will have to be f actored into the Midland plants and we all know that no one yet knows what the final answers are (either physically or economically) from Three Mile Island. In addition, Dow Che.-ical has announced to the press that it is seriously reevaluating its nuclear venture with Consumers and is presently under the throes of a S22 million proposed fine from EPA for continuing to run its coal fired plants.
t Thus, since it is now clear that nuclear steam (if at all) can only come 1985 and thereafter, the present situation at Midland represents increased environmental costs resulting from outdated coal operations. Indeed, one would reason that Dow has to begin now with new facilities, in any event, in order to meet Clean Air Standards at the earliest possible time.
We will be preparing appropriate papers for re-investigation of whether the Midland plant should continue.
However, we believe that it is, in the first instance, the Regulatory Staff's and the Atomic Safety an/ 'scensing Board's obligation to monitor nuclear power develoMmer*., such as it is, without forcing intervenors always tr ;ar / the day.
For that reason, we submit this matter r , O Atomic Safety and Licensing Board (and by copy of this letter to the Nuclear Regulatory Staff) to see if one or both of those entities will take the initiative to investigate whether the Midland units, now characterized as economic folly at its worst, should continue. Indeed, not addressing this question at the earliest possible time could force Dow to continue to rely upon the nuclear option and thus in 1985 when the operation dates and costs have escalated, again Dow will have been forclosed from options, and the environ-( ment, always the environment, will be severely oppressed.
- :n . e t
.O . " . Marshall E. Miller, Esq.
- Ivan W. Smith, Esq.
February 14, 1980
[ Page Three Accordingly, we await prompt action by officials of the Commission in the absence of which we will initiate action ourselves.
One further point I was somewhat shocked by Ms.
Gibbs' February 8th letter since it did not forward Bechtel's report to Consumers. I was further shocked that I have not yet received a copy of the request from the Commission to Consumers to " fork over" that Bechtel report now, whether or not in the future Consumers chooses to take issue with it.
Indeed, one would reason that the Atomic Safety and Licensing Board panel would have already on its own motion requested that that report be filed and distributed to the parties.
We are in difficult energy times as we all know.
As a member of the American Bar Association Special Committee On Energy (presently doing a report for the Department of Energy), I know ir. some detail the chaotic picture of energy around the United States. Policy comes in fragnented forms frcm Washington and the state gcVernments, ill-equipped to deal with the emerging chaos, further create vacuumb into which no leadership seems to move. If the Nuclear Regulatory
( Commission and its component parts refuse to take prompt action when warranted, then no one will look to it for leadership. And certainly subsequent to the Kemeny and Rogovin Reports it is encumbant upon the Nuclear Regulatory Commission (and its component parts) to prove to the American public that the Commission, Atomic Safety and Licensing Boards, and the Regulatory Staff are interested in sound protecti of the American public and the surrounding environment and not just " business as usual".
I would hope the Board will take action on its own motion to order Consumers to distribute the Bechtel Report and then promptly reopen hearings as to whether the Midland nuclear units should continue.
I look forward to hearing from someone soon.
Very truly yours, I
A TTh L-Myrcn M. Cherry MMC /dn
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1 8005 200 8df FEB 151980 MEl10RANDUi1 FOR: . Harold R. Denton, Director Office of Nuclear Reactor Regulation
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FROM: R. J. Mattson, Director. -
'~ . r.. _ _ _ _ __.__ . s Division of Systems Safe.ty
SUBJECT:
HEB EQUIPMENT QUALIFICATION EFFORT AND' PDTENTIAL. -
FOR LICENSING DELAYS . :W y.. _
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The attached memorandum from Bob Bosnak notes that"in spite of' oui '
appeals to the Navy and the OMB, we have not been able to obtain the assistance from NRL that we had counted on for our SQRT reviews of 13 pending OL. applications. The only remaining alternative appears to be a contract with a private firm. We are proceeding to issue a request for proposal as soon as possible. 1 I agree with Bosnak's conclusion that schedules for the SQRT reviews will be irrecoverably delayed by at least eight or nine months, and l that we cannot recommend issuance of an operations license for any- q plant until the dynamic equipraent evaluation is complete. i l
Original signed by Roger J. Mattson Roger J. Mattson Director. ,
. Division of Systems Safety i cc: E. Case D. Ross J. Knight R. Bosnak DISTRIBUTION: l entral File !
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- FEB .11 1980 p-MEMORA UM FOR: R. Mattson, Director, DSS THRU: J. .P. Knight, Assistant Director for Engineering, DSS FROM: R. J. Bosank, Chief, Mechanical Engineering Branch, DSS
SUBJECT:
' ' . MEB EQUIPMENT QUALIFICATION EFFORT AND POTENTIAL,FOR LICENSING DELAYS
Background
The Seismic Qualification Review Team (SQRT) was' established by the MEB in 1974 to perform a hands-on audit of OL applicant's program used to qualify electrical and mechanical equipment for dynamic seismic input. ICSB/PSB personnel parti-cipate in the program to assure the proper electrical function of equipment when subject to seismic input. With the advent of dynamic inputs originating from safety relief discharge or LOCA blowdown into pressure suppression con-tainments and from other sources, the scope of the SQRT effort was expanded to include the qualification of electrical and mechanical equipment for the total dynamic environment expected during service.
The SQRT review at plant sites conducted by the staff team since its inception '
(all PWR plants and Hatch-2) has emphasized a r.eview of the equipment quali-fication performed by the applicant, most often single frequency / single axis methods, to determine by a review of the qualification and inspection of the installation whether the criteria in.IEEE 344-1975, R/G 1.100,1.92, and SRP 3.9.2 and 3.10 have been satisfied. Typically preparation for a site visit by SQRT has required approximately 4 man weeks, a site visit is 3-5 days for the 4 man team, post visit evaluation approximately 4 man weeks, for a total of approximately 12 man weeks per plant. Because of difficulties with plants such as Diablo Canyon, the lead Mark II plants (Zimmer, LaSalle and Shoreham) and the time expended to attempt to establish a generic qualification of GE NSSS equip-ment, plant visits had slipped by several months by late 1978. With the establishment of the interim organization the SQRT was especially hard hit and all staff effort was halted due to a lack of resources by mid May 1979. ,
The letter from the Office of Management and Budget (OMB) in mid June 1979 that D0D assist NRC resulted directed to the Department of Defense in our contacting the Naval Research Laboratoryrequesting (NRL) in July, reaching tenta-tive agreement with them on work scope, resource requirements and schedules in August and establishing an interagency agreement in September. MEB memo of November 28,1979 (attached) discusses the significant work accomplished by NRL, including meetings with applicants, architect engineers and NSSS vendors, g G O NO b
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prior to the receipt of the NRL letter of November 19 unilaterally terminating our interagency agreement. The November 19 letter came as a complete surprise to both the NRC and NRL staffs participating in the program. The MEB memo of November- 28, 1979 led to the request by Chairman Ahearne to the Office of Management and Budget on the basis of national priority to request reconsidera-tion by the Navy of its November 19 decision. Mr. Denton's letter of January 3,1980 (attached) also requested such reconsideration. On February 7, MEB was advised by Mr. Dan Gessaman of OMB that efforts to effect a reversal of the Navy's decision had been unsuccessful. Mr. Jesse Funches of Chairman Ahearne's staff was so advised on February 8,1980. y
~. -
Current Status and Plans MEB started reviewing alternative sources of assistance in January 1980, both within the government and within ririvate industry. Because of the procedures .
and long lead times in awarding contracts to private firms, we intend to issue an RFP as soon as possible, but plan to continue checking agencies within government to determine the availability of competent resources to assist us.
The alternative of using existing staff personnel is not viable unless experi-enced persons now assigned to D0R and USI are completely released from all other responsibilities.
Impact on Licensing The NRL contract encompassed 13 plants (Zimmer, Shoreham, San Onofre, Summer, LaSalle, Watts Bar, Midland, Susquehanna, Fermi-2, Waterford 3, Farley 2 and Commanche Peak).
As previously discussed, work had commenced on several plants (Zimmer, LaSalle, Shoreham, Summer). Unfortunately such work will need to be repeated when a new cdntractor is selected.
It is our best estimate that as a result or' the NRL cancellation schedules for SQRT will have to be slipped by at least eight or nine months. ihistimeappears to be irrecoverable. An operating license cannot be recommended for any plant until the dynamic equipment evaluation is complete. Applicant milestones such as in situ tests will also be severely impacted, k
8 u
. Bosnak, Chief i R.
Mechanical Engineering Branch Division of S," stems Safety
Enclosure:
MEB Memo - November 28, 1979 Denton Letter - January 3,1980 cc: D. Vassallo 0. Parr R. Satterfield S. Varga H. Brammer F. Rosa L. Rubenstein F. Cherny V. Moore
~
J. Stolz S. Hou D. Ross ..
R. Baer J. Funches
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