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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20195C5131999-05-28028 May 1999 Forwards Revs to Sections 3.9 & 5.6 of Its,Based on Resolution Telcons Held Between NRC Staff & Util on 990526 & 27 ML20138Q8301985-12-0303 December 1985 Further Response to FOIA Request for Records Re Voluntary or Required Redress of Sites Where Const Was Terminated, Including Crbr & Legal Analysis.Forwards App E Documents.App D & E Documents Available in Pdr.Photographs Also Available ML20132A8831985-09-12012 September 1985 Responds to 830921 Request That CPPR-167,CPPR-168 & CPPR-169 Be Deleted.Stabilization Plan Has No Significant Environ Impact.Dockets Changed to Canceled Status ML20098G6271984-09-27027 September 1984 Forwards Responses to 840617 Request for Addl Info in Order to Complete Review of Facility Site Stabilization Plan.W/Two Oversize Maps.Aperture Cards Available in PDR ML20095E3971984-08-16016 August 1984 Forwards Duke Power Co & North Carolina Municipal Power Agency 1 1983 Annual Repts LG-84-332, Forwards Most Recent Aerial Photographs of Site for Review of Stabilization Plan.W/O Encl1984-04-24024 April 1984 Forwards Most Recent Aerial Photographs of Site for Review of Stabilization Plan.W/O Encl ML20078C2031983-09-21021 September 1983 Requests Cancellation of CPPR-167,CPPR-168 & CPPR-169 Based on Current & Predicated Economic Conditions.Stabilization Plan Encl LG-83-314, Responds to NRC Requiring Detailed Analysis of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Analysis Will Not Be Submitted,Due to Indefinite Delay in Const of Facility1983-04-0707 April 1983 Responds to NRC Requiring Detailed Analysis of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Analysis Will Not Be Submitted,Due to Indefinite Delay in Const of Facility LG-83-163, Forwards Amend 19 to Duke Power Nuclear Guides.Amend 20 Will Be Forwarded in Apr 19831983-02-18018 February 1983 Forwards Amend 19 to Duke Power Nuclear Guides.Amend 20 Will Be Forwarded in Apr 1983 LG-83-049, Forwards Response to 821210 Request for Addl Info on IE Bulletin 81-03, Flow Blockage of Cooling Water to Safety Sys Components by Corbicula Sp (Asiatic Clam) & Mytilus Sp (Mussel). Monitoring Program for Clams to Be Established1983-01-17017 January 1983 Forwards Response to 821210 Request for Addl Info on IE Bulletin 81-03, Flow Blockage of Cooling Water to Safety Sys Components by Corbicula Sp (Asiatic Clam) & Mytilus Sp (Mussel). Monitoring Program for Clams to Be Established ML20063E6521982-08-24024 August 1982 Forwards Util & Nc Municipal Power Agency Annual Financial Repts for 1981 ML20062K3871982-05-20020 May 1982 Forwards First Quarter 1982 Yellow Book Updates Re Const Status ML20052F0901982-05-0404 May 1982 Informs That Addl Action Will Be Required in Order to Fully Comply W/Asme Code Requirements for Radiography of safe-end Welds.Discrepancy Will Be Resolved by re-radiographing Affected Welds ML20038D1361981-11-0303 November 1981 Responds to NRC 811014 Ltr Re Violations Noted in IE Insp Repts 50-491/81-03,50-492/81-03 & 50-493/81-03.Corrective Actions:Gas Cans Have Been Emptied & Placed in Motor Pool Storage Area ML20009D9001981-07-0808 July 1981 Responds to IE Bulletin 81-03 Re Blockage of Cooling Water to Safety Sys Components by Clams & Mussels.Provisions Will Be Made to Minimize Introduction of Clams Into Raw Water Sys.Fifteen Manhours Expended in Preparation of Bulletin NUREG-0694, Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance1981-06-12012 June 1981 Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance ML20004C2561981-05-28028 May 1981 Requests Authorization to Use ASME Code Cases 1481-2,1592-14 & 1644-8 in Fabrication of Primary Sys Components for Facilities ML19347D3491981-03-12012 March 1981 Responds to NRC 810223 Request for Addl Info Re Util Plans for Facilities.Completion of Cherokee 1 & 2 Has Been Indefinitely Delayed.Commercial Operating Dates for Cherokee 3 & Perkins 1,2 & 3 Have Not Been Determined ML19347D0311981-03-0404 March 1981 Forwards 810224 Press Release Re Delay of Facility Completion.Financial Situation Has Pushed Facility Completion Into Indefinite Future ML20008E7621981-02-24024 February 1981 Forwards PWR Const Milestones & Activities for McGuire 1 & 2,Catawba 1 & 2 & Cherokee 1.Key Event Dates Provided ML20003C2891981-02-11011 February 1981 Responds to IE Bulletin 80-23, Failures of Solenoid Valves Mfg by Valcor Engineering Corp. Bulletin Does Not Apply ML19345F3631981-02-0505 February 1981 Forwards Evacuation Time Estimates & Color Overlay Site Map, Per Discussions w/P81 Project Manager.W/O Site Map ML19345G0801981-01-27027 January 1981 Forwards Revision 1 to Response Re IE Bulletin 79-14 Revision 1,Suppl 2, Seismic Analysis for As-Built Safety-Related Piping Sys. Describes Program Which Will Give Assurance That Design Documents Reflect Sys Conditions ML19351F9851981-01-27027 January 1981 Responds to IE Bulletin 80-21, Valve Yokes Supplied by Malcolm Foundry Co,Inc. No safety-related Valves Using Specified Valve Yokes Are Used ML20002B9171980-11-11011 November 1980 Forwards Supplemental Responses to NRC 801016 Ltr Re Violations Noted in IE Insp Repts 50-369/80-08,50-370/80-05, 50-413/80-09,50-414/80-09,50-491/80-02,50-492/80-06 & 50-493/80-06.Final Rept to Be Submitted by 810131 ML19340B1411980-10-14014 October 1980 Requests Load Info Re Design Pressure,Loca & SSE Loads & Drawings for Five Containment Vessels Referred to in Statement of Work for FY81 ML19344E9781980-08-29029 August 1980 Responds to IE Bulletin 80-19,Revision 1.No mercury-wetted Matrix Relays Are Used or Planned for Use in Reactor Protection Sys ML19344F1871980-08-26026 August 1980 Responds to IE Bulletin 80-16.No Rosemount Models 1151 & 1152 Pressure Transmitters Are Used in safety-related Applications ML19336A6421980-08-15015 August 1980 Responds to NRC 800718 Ltr Re Violations Noted in IE Insp Repts 50-369/80-08,50-370/80-05,50-413/80-09,50-414/80-09, 50-491/80-07,50-492/80-06 & 50-493/80-06.Corrective Actions: Records Storage Facility Constructed ML19344E5061980-08-14014 August 1980 Responds to IE Bulletin 80-20, Failure of Westinghouse Type W-2 Spring Return to Neutral Control Switches. Review Showed No Westinghouse Type W-2 Switches Used in safety- Related Applications ML19331D3631980-08-0606 August 1980 Submits Response to IE Bulletin 79-03A.No SA-312 or A-312, Type 300 Series Fusion Welded Pipe in Use or Planned for Use Is Subj to Design Stresses Greater than 85% of ASME Code Allowable Stresses ML19338C3401980-08-0404 August 1980 Ack Receipt of IE Insp Repts 50-491/80-09,50-492/80-08 & 50-493/80-08 on 800611-13.No Proprietary Info ML19331B6111980-08-0404 August 1980 Submits Const Completion & Fuel Load Target Dates,In Response to NRC 800711 Ltr.For Unit 1,const Completion & Fuel Load Target Dates Are Jul 1980 & Jul 1991 for Unit 2.OL Application to Be Submitted by Sept 1986 ML19327A5411980-07-31031 July 1980 Responds to 800702 Request for Info Re Evacuation Times for Power Plants W/Current or Pending Cps.Cherokee & Perkins Stations Pose No Population Density Situation Which Would Cause Long Evacuation Times ML19331C2621980-07-28028 July 1980 Ack Receipt of IE Insp Repts 50-491/80-08,50-492/80-07 & 50-493/80-07 on 800624-25.No Proprietary Info ML19326E0641980-07-0707 July 1980 Forwards Response to IE Bulletin 80-08, Exam of Containment Liner Penetration Welds. Piping Penetrations Are Designed & Fabricated in Accordance w/1977 Edition of ASME Boiler & Pressure Vessel Code,Including Summer 1977 Addenda ML19327A0081980-06-25025 June 1980 Responds to NRC 790627 Ltr Re Violation Noted in IE Insp Repts 50-491/79-10,50-492/79-10 & 50-493/79-10.Corrective Actions:Corrected Procedure for Determining Bulk Density of Test Sand & Increased Testing of Filter Matl ML19318A8361980-06-0909 June 1980 Forwards Response to IE Bulletin 80-05 Re Vacuum Conditions Resulting in Damage to Holdup Tanks.Lists Vacuum Conditions in Low Pressure & Holdup Tanks by Tank Name,Sys,Quantity/ Unit,Design Pressure & Protective Measures ML19323G8791980-05-0808 May 1980 Ack Receipt of IE Insp Repts 50-491/80-05,50-492/80-05 & 50-493/80-05.No Proprietary Info ML19309G2151980-04-0303 April 1980 Ack Receipt of IE Insp Repts 50-491/80-04,50-492/80-04 & 50-493/80-04 on 800304-07.No Proprietary Info ML19309E8061980-03-28028 March 1980 Ack Receipt of IE Insp Repts 50-491/80-03,50-492/80-03 & 50-493/80-03 on 800303-05.No Proprietary Info ML19305D9951980-03-28028 March 1980 Ack Receipt of IE Insp Repts 50-491/80-02,50-492/80-02 & 50-493/80-02 on 800226-29. No Proprietary Info ML19305E1751980-03-19019 March 1980 Submits Response to IE Bulletin 80-03.Review Revealed That No Charcoal Adsorber Cells Have Been Received from Manufacturers ML19294B8521980-02-11011 February 1980 Ack Receipt of IE Insp Repts 50-491/80-01,50-492/80-01 & 50-493/80-01.No Proprietary Info ML19312D1301980-02-0505 February 1980 Responds to IE Bulletin 79-28.No Namco EA180 Limit Switches from Affected Production Period Are Used or Planned for Use ML19262C2231980-02-0404 February 1980 Informs of Change in Projected Commercial Operation Dates for Facilities.Units 1 & 2 Will Be Placed in Commercial Operation in Jan 1990 & Jan 1992,respectively.FSAR Will Be Filed in Jan 1987.Schedules Are Periodically Reviewed ML19312D5911980-01-22022 January 1980 Responds to NRC 791227 Ltr Re Violations Noted in IE Insp Repts 50-491/79-20,50-492/79-20,& 50-493/79-20.Corrective Actions:Samples Taken,Nonconforming Item Report Written & Computer Tickler Sys Implemented ML19305B9131980-01-15015 January 1980 Responds to NRC 791227 Ltr Re Violations Noted in IE Insp Repts 50-491/79-20,50-492/79-20 & 50-493/79-20.Corrective Actions:Concrete Aggregate Samples Taken,Nonconforming Item Rept Written & Computerized Tickler Sys Implemented ML19257D5661980-01-0707 January 1980 Forwards Revision to Response to IE Bulletin 79-02,Revision 2,re Pipe Support Base Plate Designs.Will Account for Base Plate Flexibility in Calculations of Bolt Loads by Using Conservative Hand Calculation Method ML19257D3801980-01-0404 January 1980 Responds to IE Bulletin 79-25, Failures of Westinghouse Bfd Relays in Safety-Related Sys. No Westinghouse Bfd/Nbfd Relays Are Used in safety-related Sys 1999-05-28
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20195C5131999-05-28028 May 1999 Forwards Revs to Sections 3.9 & 5.6 of Its,Based on Resolution Telcons Held Between NRC Staff & Util on 990526 & 27 ML20098G6271984-09-27027 September 1984 Forwards Responses to 840617 Request for Addl Info in Order to Complete Review of Facility Site Stabilization Plan.W/Two Oversize Maps.Aperture Cards Available in PDR ML20095E3971984-08-16016 August 1984 Forwards Duke Power Co & North Carolina Municipal Power Agency 1 1983 Annual Repts LG-84-332, Forwards Most Recent Aerial Photographs of Site for Review of Stabilization Plan.W/O Encl1984-04-24024 April 1984 Forwards Most Recent Aerial Photographs of Site for Review of Stabilization Plan.W/O Encl ML20078C2031983-09-21021 September 1983 Requests Cancellation of CPPR-167,CPPR-168 & CPPR-169 Based on Current & Predicated Economic Conditions.Stabilization Plan Encl LG-83-314, Responds to NRC Requiring Detailed Analysis of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Analysis Will Not Be Submitted,Due to Indefinite Delay in Const of Facility1983-04-0707 April 1983 Responds to NRC Requiring Detailed Analysis of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Analysis Will Not Be Submitted,Due to Indefinite Delay in Const of Facility LG-83-163, Forwards Amend 19 to Duke Power Nuclear Guides.Amend 20 Will Be Forwarded in Apr 19831983-02-18018 February 1983 Forwards Amend 19 to Duke Power Nuclear Guides.Amend 20 Will Be Forwarded in Apr 1983 LG-83-049, Forwards Response to 821210 Request for Addl Info on IE Bulletin 81-03, Flow Blockage of Cooling Water to Safety Sys Components by Corbicula Sp (Asiatic Clam) & Mytilus Sp (Mussel). Monitoring Program for Clams to Be Established1983-01-17017 January 1983 Forwards Response to 821210 Request for Addl Info on IE Bulletin 81-03, Flow Blockage of Cooling Water to Safety Sys Components by Corbicula Sp (Asiatic Clam) & Mytilus Sp (Mussel). Monitoring Program for Clams to Be Established ML20063E6521982-08-24024 August 1982 Forwards Util & Nc Municipal Power Agency Annual Financial Repts for 1981 ML20062K3871982-05-20020 May 1982 Forwards First Quarter 1982 Yellow Book Updates Re Const Status ML20052F0901982-05-0404 May 1982 Informs That Addl Action Will Be Required in Order to Fully Comply W/Asme Code Requirements for Radiography of safe-end Welds.Discrepancy Will Be Resolved by re-radiographing Affected Welds ML20038D1361981-11-0303 November 1981 Responds to NRC 811014 Ltr Re Violations Noted in IE Insp Repts 50-491/81-03,50-492/81-03 & 50-493/81-03.Corrective Actions:Gas Cans Have Been Emptied & Placed in Motor Pool Storage Area ML20009D9001981-07-0808 July 1981 Responds to IE Bulletin 81-03 Re Blockage of Cooling Water to Safety Sys Components by Clams & Mussels.Provisions Will Be Made to Minimize Introduction of Clams Into Raw Water Sys.Fifteen Manhours Expended in Preparation of Bulletin ML20004C2561981-05-28028 May 1981 Requests Authorization to Use ASME Code Cases 1481-2,1592-14 & 1644-8 in Fabrication of Primary Sys Components for Facilities ML19347D3491981-03-12012 March 1981 Responds to NRC 810223 Request for Addl Info Re Util Plans for Facilities.Completion of Cherokee 1 & 2 Has Been Indefinitely Delayed.Commercial Operating Dates for Cherokee 3 & Perkins 1,2 & 3 Have Not Been Determined ML19347D0311981-03-0404 March 1981 Forwards 810224 Press Release Re Delay of Facility Completion.Financial Situation Has Pushed Facility Completion Into Indefinite Future ML20008E7621981-02-24024 February 1981 Forwards PWR Const Milestones & Activities for McGuire 1 & 2,Catawba 1 & 2 & Cherokee 1.Key Event Dates Provided ML20003C2891981-02-11011 February 1981 Responds to IE Bulletin 80-23, Failures of Solenoid Valves Mfg by Valcor Engineering Corp. Bulletin Does Not Apply ML19345F3631981-02-0505 February 1981 Forwards Evacuation Time Estimates & Color Overlay Site Map, Per Discussions w/P81 Project Manager.W/O Site Map ML19345G0801981-01-27027 January 1981 Forwards Revision 1 to Response Re IE Bulletin 79-14 Revision 1,Suppl 2, Seismic Analysis for As-Built Safety-Related Piping Sys. Describes Program Which Will Give Assurance That Design Documents Reflect Sys Conditions ML19351F9851981-01-27027 January 1981 Responds to IE Bulletin 80-21, Valve Yokes Supplied by Malcolm Foundry Co,Inc. No safety-related Valves Using Specified Valve Yokes Are Used ML20002B9171980-11-11011 November 1980 Forwards Supplemental Responses to NRC 801016 Ltr Re Violations Noted in IE Insp Repts 50-369/80-08,50-370/80-05, 50-413/80-09,50-414/80-09,50-491/80-02,50-492/80-06 & 50-493/80-06.Final Rept to Be Submitted by 810131 ML19340B1411980-10-14014 October 1980 Requests Load Info Re Design Pressure,Loca & SSE Loads & Drawings for Five Containment Vessels Referred to in Statement of Work for FY81 ML19344E9781980-08-29029 August 1980 Responds to IE Bulletin 80-19,Revision 1.No mercury-wetted Matrix Relays Are Used or Planned for Use in Reactor Protection Sys ML19344F1871980-08-26026 August 1980 Responds to IE Bulletin 80-16.No Rosemount Models 1151 & 1152 Pressure Transmitters Are Used in safety-related Applications ML19336A6421980-08-15015 August 1980 Responds to NRC 800718 Ltr Re Violations Noted in IE Insp Repts 50-369/80-08,50-370/80-05,50-413/80-09,50-414/80-09, 50-491/80-07,50-492/80-06 & 50-493/80-06.Corrective Actions: Records Storage Facility Constructed ML19344E5061980-08-14014 August 1980 Responds to IE Bulletin 80-20, Failure of Westinghouse Type W-2 Spring Return to Neutral Control Switches. Review Showed No Westinghouse Type W-2 Switches Used in safety- Related Applications ML19331D3631980-08-0606 August 1980 Submits Response to IE Bulletin 79-03A.No SA-312 or A-312, Type 300 Series Fusion Welded Pipe in Use or Planned for Use Is Subj to Design Stresses Greater than 85% of ASME Code Allowable Stresses ML19338C3401980-08-0404 August 1980 Ack Receipt of IE Insp Repts 50-491/80-09,50-492/80-08 & 50-493/80-08 on 800611-13.No Proprietary Info ML19331B6111980-08-0404 August 1980 Submits Const Completion & Fuel Load Target Dates,In Response to NRC 800711 Ltr.For Unit 1,const Completion & Fuel Load Target Dates Are Jul 1980 & Jul 1991 for Unit 2.OL Application to Be Submitted by Sept 1986 ML19327A5411980-07-31031 July 1980 Responds to 800702 Request for Info Re Evacuation Times for Power Plants W/Current or Pending Cps.Cherokee & Perkins Stations Pose No Population Density Situation Which Would Cause Long Evacuation Times ML19331C2621980-07-28028 July 1980 Ack Receipt of IE Insp Repts 50-491/80-08,50-492/80-07 & 50-493/80-07 on 800624-25.No Proprietary Info ML19326E0641980-07-0707 July 1980 Forwards Response to IE Bulletin 80-08, Exam of Containment Liner Penetration Welds. Piping Penetrations Are Designed & Fabricated in Accordance w/1977 Edition of ASME Boiler & Pressure Vessel Code,Including Summer 1977 Addenda ML19327A0081980-06-25025 June 1980 Responds to NRC 790627 Ltr Re Violation Noted in IE Insp Repts 50-491/79-10,50-492/79-10 & 50-493/79-10.Corrective Actions:Corrected Procedure for Determining Bulk Density of Test Sand & Increased Testing of Filter Matl ML19318A8361980-06-0909 June 1980 Forwards Response to IE Bulletin 80-05 Re Vacuum Conditions Resulting in Damage to Holdup Tanks.Lists Vacuum Conditions in Low Pressure & Holdup Tanks by Tank Name,Sys,Quantity/ Unit,Design Pressure & Protective Measures ML19323G8791980-05-0808 May 1980 Ack Receipt of IE Insp Repts 50-491/80-05,50-492/80-05 & 50-493/80-05.No Proprietary Info ML19309G2151980-04-0303 April 1980 Ack Receipt of IE Insp Repts 50-491/80-04,50-492/80-04 & 50-493/80-04 on 800304-07.No Proprietary Info ML19305D9951980-03-28028 March 1980 Ack Receipt of IE Insp Repts 50-491/80-02,50-492/80-02 & 50-493/80-02 on 800226-29. No Proprietary Info ML19309E8061980-03-28028 March 1980 Ack Receipt of IE Insp Repts 50-491/80-03,50-492/80-03 & 50-493/80-03 on 800303-05.No Proprietary Info ML19305E1751980-03-19019 March 1980 Submits Response to IE Bulletin 80-03.Review Revealed That No Charcoal Adsorber Cells Have Been Received from Manufacturers ML19294B8521980-02-11011 February 1980 Ack Receipt of IE Insp Repts 50-491/80-01,50-492/80-01 & 50-493/80-01.No Proprietary Info ML19312D1301980-02-0505 February 1980 Responds to IE Bulletin 79-28.No Namco EA180 Limit Switches from Affected Production Period Are Used or Planned for Use ML19262C2231980-02-0404 February 1980 Informs of Change in Projected Commercial Operation Dates for Facilities.Units 1 & 2 Will Be Placed in Commercial Operation in Jan 1990 & Jan 1992,respectively.FSAR Will Be Filed in Jan 1987.Schedules Are Periodically Reviewed ML19312D5911980-01-22022 January 1980 Responds to NRC 791227 Ltr Re Violations Noted in IE Insp Repts 50-491/79-20,50-492/79-20,& 50-493/79-20.Corrective Actions:Samples Taken,Nonconforming Item Report Written & Computer Tickler Sys Implemented ML19305B9131980-01-15015 January 1980 Responds to NRC 791227 Ltr Re Violations Noted in IE Insp Repts 50-491/79-20,50-492/79-20 & 50-493/79-20.Corrective Actions:Concrete Aggregate Samples Taken,Nonconforming Item Rept Written & Computerized Tickler Sys Implemented ML19257D5661980-01-0707 January 1980 Forwards Revision to Response to IE Bulletin 79-02,Revision 2,re Pipe Support Base Plate Designs.Will Account for Base Plate Flexibility in Calculations of Bolt Loads by Using Conservative Hand Calculation Method ML19257D3801980-01-0404 January 1980 Responds to IE Bulletin 79-25, Failures of Westinghouse Bfd Relays in Safety-Related Sys. No Westinghouse Bfd/Nbfd Relays Are Used in safety-related Sys ML19256G1341979-12-20020 December 1979 Estimates Submittal Date for FSAR for Cherokee 1 as Jan 1984 ML19210E8511979-11-29029 November 1979 Ack Receipt of IE Insp Repts 50-491/79-19,50-492/79-19 & 50-493/79-19 on 791023-26.No Proprietary Info ML19269F4841979-11-16016 November 1979 Responds to NRC 791031 Ltr Re Violations Noted in IE Insp Repts 50-491/79-18,50-492/79-18 & 50-493/79-18.Corrective Actions:Const Procedure CKP-8 Revised Re Electrode Stubs. Personnel Involved Have Been Instructed 1999-05-28
[Table view] Category:UTILITY TO NRC
MONTHYEARML20098G6271984-09-27027 September 1984 Forwards Responses to 840617 Request for Addl Info in Order to Complete Review of Facility Site Stabilization Plan.W/Two Oversize Maps.Aperture Cards Available in PDR ML20095E3971984-08-16016 August 1984 Forwards Duke Power Co & North Carolina Municipal Power Agency 1 1983 Annual Repts LG-84-332, Forwards Most Recent Aerial Photographs of Site for Review of Stabilization Plan.W/O Encl1984-04-24024 April 1984 Forwards Most Recent Aerial Photographs of Site for Review of Stabilization Plan.W/O Encl ML20078C2031983-09-21021 September 1983 Requests Cancellation of CPPR-167,CPPR-168 & CPPR-169 Based on Current & Predicated Economic Conditions.Stabilization Plan Encl LG-83-314, Responds to NRC Requiring Detailed Analysis of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Analysis Will Not Be Submitted,Due to Indefinite Delay in Const of Facility1983-04-0707 April 1983 Responds to NRC Requiring Detailed Analysis of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Analysis Will Not Be Submitted,Due to Indefinite Delay in Const of Facility LG-83-163, Forwards Amend 19 to Duke Power Nuclear Guides.Amend 20 Will Be Forwarded in Apr 19831983-02-18018 February 1983 Forwards Amend 19 to Duke Power Nuclear Guides.Amend 20 Will Be Forwarded in Apr 1983 LG-83-049, Forwards Response to 821210 Request for Addl Info on IE Bulletin 81-03, Flow Blockage of Cooling Water to Safety Sys Components by Corbicula Sp (Asiatic Clam) & Mytilus Sp (Mussel). Monitoring Program for Clams to Be Established1983-01-17017 January 1983 Forwards Response to 821210 Request for Addl Info on IE Bulletin 81-03, Flow Blockage of Cooling Water to Safety Sys Components by Corbicula Sp (Asiatic Clam) & Mytilus Sp (Mussel). Monitoring Program for Clams to Be Established ML20063E6521982-08-24024 August 1982 Forwards Util & Nc Municipal Power Agency Annual Financial Repts for 1981 ML20062K3871982-05-20020 May 1982 Forwards First Quarter 1982 Yellow Book Updates Re Const Status ML20038D1361981-11-0303 November 1981 Responds to NRC 811014 Ltr Re Violations Noted in IE Insp Repts 50-491/81-03,50-492/81-03 & 50-493/81-03.Corrective Actions:Gas Cans Have Been Emptied & Placed in Motor Pool Storage Area ML20009D9001981-07-0808 July 1981 Responds to IE Bulletin 81-03 Re Blockage of Cooling Water to Safety Sys Components by Clams & Mussels.Provisions Will Be Made to Minimize Introduction of Clams Into Raw Water Sys.Fifteen Manhours Expended in Preparation of Bulletin ML20004C2561981-05-28028 May 1981 Requests Authorization to Use ASME Code Cases 1481-2,1592-14 & 1644-8 in Fabrication of Primary Sys Components for Facilities ML19347D3491981-03-12012 March 1981 Responds to NRC 810223 Request for Addl Info Re Util Plans for Facilities.Completion of Cherokee 1 & 2 Has Been Indefinitely Delayed.Commercial Operating Dates for Cherokee 3 & Perkins 1,2 & 3 Have Not Been Determined ML19347D0311981-03-0404 March 1981 Forwards 810224 Press Release Re Delay of Facility Completion.Financial Situation Has Pushed Facility Completion Into Indefinite Future ML20008E7621981-02-24024 February 1981 Forwards PWR Const Milestones & Activities for McGuire 1 & 2,Catawba 1 & 2 & Cherokee 1.Key Event Dates Provided ML20003C2891981-02-11011 February 1981 Responds to IE Bulletin 80-23, Failures of Solenoid Valves Mfg by Valcor Engineering Corp. Bulletin Does Not Apply ML19345F3631981-02-0505 February 1981 Forwards Evacuation Time Estimates & Color Overlay Site Map, Per Discussions w/P81 Project Manager.W/O Site Map ML19345G0801981-01-27027 January 1981 Forwards Revision 1 to Response Re IE Bulletin 79-14 Revision 1,Suppl 2, Seismic Analysis for As-Built Safety-Related Piping Sys. Describes Program Which Will Give Assurance That Design Documents Reflect Sys Conditions ML19351F9851981-01-27027 January 1981 Responds to IE Bulletin 80-21, Valve Yokes Supplied by Malcolm Foundry Co,Inc. No safety-related Valves Using Specified Valve Yokes Are Used ML20002B9171980-11-11011 November 1980 Forwards Supplemental Responses to NRC 801016 Ltr Re Violations Noted in IE Insp Repts 50-369/80-08,50-370/80-05, 50-413/80-09,50-414/80-09,50-491/80-02,50-492/80-06 & 50-493/80-06.Final Rept to Be Submitted by 810131 ML19344E9781980-08-29029 August 1980 Responds to IE Bulletin 80-19,Revision 1.No mercury-wetted Matrix Relays Are Used or Planned for Use in Reactor Protection Sys ML19344F1871980-08-26026 August 1980 Responds to IE Bulletin 80-16.No Rosemount Models 1151 & 1152 Pressure Transmitters Are Used in safety-related Applications ML19336A6421980-08-15015 August 1980 Responds to NRC 800718 Ltr Re Violations Noted in IE Insp Repts 50-369/80-08,50-370/80-05,50-413/80-09,50-414/80-09, 50-491/80-07,50-492/80-06 & 50-493/80-06.Corrective Actions: Records Storage Facility Constructed ML19344E5061980-08-14014 August 1980 Responds to IE Bulletin 80-20, Failure of Westinghouse Type W-2 Spring Return to Neutral Control Switches. Review Showed No Westinghouse Type W-2 Switches Used in safety- Related Applications ML19331D3631980-08-0606 August 1980 Submits Response to IE Bulletin 79-03A.No SA-312 or A-312, Type 300 Series Fusion Welded Pipe in Use or Planned for Use Is Subj to Design Stresses Greater than 85% of ASME Code Allowable Stresses ML19338C3401980-08-0404 August 1980 Ack Receipt of IE Insp Repts 50-491/80-09,50-492/80-08 & 50-493/80-08 on 800611-13.No Proprietary Info ML19331B6111980-08-0404 August 1980 Submits Const Completion & Fuel Load Target Dates,In Response to NRC 800711 Ltr.For Unit 1,const Completion & Fuel Load Target Dates Are Jul 1980 & Jul 1991 for Unit 2.OL Application to Be Submitted by Sept 1986 ML19327A5411980-07-31031 July 1980 Responds to 800702 Request for Info Re Evacuation Times for Power Plants W/Current or Pending Cps.Cherokee & Perkins Stations Pose No Population Density Situation Which Would Cause Long Evacuation Times ML19331C2621980-07-28028 July 1980 Ack Receipt of IE Insp Repts 50-491/80-08,50-492/80-07 & 50-493/80-07 on 800624-25.No Proprietary Info ML19326E0641980-07-0707 July 1980 Forwards Response to IE Bulletin 80-08, Exam of Containment Liner Penetration Welds. Piping Penetrations Are Designed & Fabricated in Accordance w/1977 Edition of ASME Boiler & Pressure Vessel Code,Including Summer 1977 Addenda ML19327A0081980-06-25025 June 1980 Responds to NRC 790627 Ltr Re Violation Noted in IE Insp Repts 50-491/79-10,50-492/79-10 & 50-493/79-10.Corrective Actions:Corrected Procedure for Determining Bulk Density of Test Sand & Increased Testing of Filter Matl ML19323G8791980-05-0808 May 1980 Ack Receipt of IE Insp Repts 50-491/80-05,50-492/80-05 & 50-493/80-05.No Proprietary Info ML19309G2151980-04-0303 April 1980 Ack Receipt of IE Insp Repts 50-491/80-04,50-492/80-04 & 50-493/80-04 on 800304-07.No Proprietary Info ML19305D9951980-03-28028 March 1980 Ack Receipt of IE Insp Repts 50-491/80-02,50-492/80-02 & 50-493/80-02 on 800226-29. No Proprietary Info ML19309E8061980-03-28028 March 1980 Ack Receipt of IE Insp Repts 50-491/80-03,50-492/80-03 & 50-493/80-03 on 800303-05.No Proprietary Info ML19305E1751980-03-19019 March 1980 Submits Response to IE Bulletin 80-03.Review Revealed That No Charcoal Adsorber Cells Have Been Received from Manufacturers ML19294B8521980-02-11011 February 1980 Ack Receipt of IE Insp Repts 50-491/80-01,50-492/80-01 & 50-493/80-01.No Proprietary Info ML19312D1301980-02-0505 February 1980 Responds to IE Bulletin 79-28.No Namco EA180 Limit Switches from Affected Production Period Are Used or Planned for Use ML19262C2231980-02-0404 February 1980 Informs of Change in Projected Commercial Operation Dates for Facilities.Units 1 & 2 Will Be Placed in Commercial Operation in Jan 1990 & Jan 1992,respectively.FSAR Will Be Filed in Jan 1987.Schedules Are Periodically Reviewed ML19312D5911980-01-22022 January 1980 Responds to NRC 791227 Ltr Re Violations Noted in IE Insp Repts 50-491/79-20,50-492/79-20,& 50-493/79-20.Corrective Actions:Samples Taken,Nonconforming Item Report Written & Computer Tickler Sys Implemented ML19305B9131980-01-15015 January 1980 Responds to NRC 791227 Ltr Re Violations Noted in IE Insp Repts 50-491/79-20,50-492/79-20 & 50-493/79-20.Corrective Actions:Concrete Aggregate Samples Taken,Nonconforming Item Rept Written & Computerized Tickler Sys Implemented ML19257D5661980-01-0707 January 1980 Forwards Revision to Response to IE Bulletin 79-02,Revision 2,re Pipe Support Base Plate Designs.Will Account for Base Plate Flexibility in Calculations of Bolt Loads by Using Conservative Hand Calculation Method ML19257D3801980-01-0404 January 1980 Responds to IE Bulletin 79-25, Failures of Westinghouse Bfd Relays in Safety-Related Sys. No Westinghouse Bfd/Nbfd Relays Are Used in safety-related Sys ML19256G1341979-12-20020 December 1979 Estimates Submittal Date for FSAR for Cherokee 1 as Jan 1984 ML19210E8511979-11-29029 November 1979 Ack Receipt of IE Insp Repts 50-491/79-19,50-492/79-19 & 50-493/79-19 on 791023-26.No Proprietary Info ML19269F4841979-11-16016 November 1979 Responds to NRC 791031 Ltr Re Violations Noted in IE Insp Repts 50-491/79-18,50-492/79-18 & 50-493/79-18.Corrective Actions:Const Procedure CKP-8 Revised Re Electrode Stubs. Personnel Involved Have Been Instructed ML19210D7721979-11-0202 November 1979 Responds to IE Bulletin 79-23 Re Failure of Emergency Transformers.No Connections Made Between Low Kva Rated Transformers & High Kva Emergency Diesel Generators W/O Limitations on Flow of Circulatory Currents ML19256F0531979-10-30030 October 1979 Responds to IE Bulletin 79-14, Seismic Analysis for As-Built Safety-Related Piping Sys. Sys Erection Has Not Progressed Far Enough to Compare Actual Configuration W/Design ML19260A3041979-10-25025 October 1979 Ack Receipt of IE Insp Repts 50-491/79-17,50-492/79-17 & 50-493/79-17 on 790925-28.No Proprietary Info ML19256E3561979-10-16016 October 1979 Ack Receipt of IE Insp Repts 50-491/79-16,50-492/79-16 & 50-493/79-16 on 790913-14.No Proprietary Info 1984-09-27
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DUKE POWER COMPANY ELECTitIC CENTElt, IIOX 33180. CII Alt! OTFE. N. C. 28242 oJ " h ".b September 21, 1983 Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555 Re: Cherokee Nuclear Station Docket No. 50-491 Files: P81-1412.06, CK-1472.00 On April 29, 1983 Duke Power Company's Board of Directors announced cancell-ation of Cherokee Unit 1. Cherokee Units 2 and 3 were cancelled on November 2, 1982. Load forecasts based on current and predicted economic conditions indicated thct Unit 1 would not be needed until 1995. To stretch construction out to that date would increase the total cost of the unit appreciably due to accumulating interest charges.
The Board of Directors' reassessment of Cherokee Unit 1 led to the following conclusions which necessitate cancellation:
- 1. Unit l's generating capacity can probably be provided more economically by other types of generation.
- 2. Duke's existi' coal and nuclear units will probably cover baseload requirements , the balance of this century.
I We hereby tender to you Construction Permit numbers CPPR-167, CPPR-168, and CPDR-169 for Cherokee Units 1, 2, and 3. We request that you delete these dockets.
We have enclosed six (6) copies of Duke Power Company's stabilization plan for the Cherokee site.
Very truly yours, ,
L. C. Dail, Vice President Design Engineering Department JHM/pam 8309270473 830921 PDR ADOCK 05000491 l A PDR
Harold R. Denton Page 2 September 21, 1983 Enclosure
, cc: Darrell G. Eisenhut Charles Barth, Esq.
j Division of Licensing USNRC a
USNRC Washington, DC 20555 Washington, DC 20555 Atomic Safety & Licensing Dr. John H. Buck Appeal Panel
! Atomic Safety & Licensing USNRC Appeal Panel Washington, DC 20555
- USNRC Washington, DC 20555 Atomic Safety & Licensing Board Panel j Dr. Donald P. DeSylva USNRC School of Marine and Atmospheric Washington, DC 20555 Science
! University of Miami Office of the Secretary Miami, FL 33149 USNRC Washington, DC 20555 Dr. Walter H. Jordan
- 881 West Outer Drive Ronald L. Ballard j
Oak Ridge, TN 37830 Environmental Engineering Branch USNRC Annette L. Vietti Washington, DC 20555 USNRC Washington, DC 20555 4
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T DUKE POWER COMPANY Cancellation of The Cherokee Nuclear Station August 1983
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TABLE OF CONTENTS PAGE NO.
1.0 INTRODUCTION
1.1 Project Background 1 1.2 Scope of Plan 1 1.3 Limitations of Plan 1 2.0 SITE STABILIZATION PLAN 2.1 State of Completion at Cancellation 2 2.2 Existing Site Conditions 3 2.2.1 Excavations 3 2.2.2 Storage Facilities 4 2.2.3 Dams / Ponds 4 2.2.4 Plant Physical Facilities 4 2.2.5 Transmission Corridors 5 2.2.6 Transportation Facilities 5 2.3 Site Stabilization Activities 2.3.1 Excavations 5 2.3.2 Storage Facilities 6 2.3.3 Dams / Ponds 6 2.3.4 Plant Physical Facilities 6 2.3.5 Transmission Corridors 7 2.3.6 Transportation Facilities 7
1 Cancellation o'7 The Cherokee Nuclear Station
1.0 INTRODUCTION
1.1 PROJECT BACKGROUND The Cherokee Nuclear Station site is located near Gaffney in north central South Carolina, approximately 40 miles southwest of Charlotte, N.C., and 21 miles east of Spartanburg, S.C. Duke Power Company announced plans for the three unit Cherokee Nuclear Station on February 26, 1974. After receiv-ing limited work authorization from the Nuclear Regulatory Commission, on May 28, 1976, Duke broke ground on July 1, 1976. The Construction Pe mits were granted December 30, 1977, and the first concrete pour was made on February 16, 1978.
After several delays in the construction schedule, the Cherokee Nuclear Sta-tion was formally cancelled by decision of the Board of Directors on April 29, 1983. Units 2 & 3 were previously cancelled in 1982.
1.2 SCOPE OF PLAN This plan outlines the existing condition of the Cherokee site and the activities necessary to stabilize the site with respect to erosive forces and unauthorized access. It should not be construed as a plan to restore the site to preconstruc-tion conditions. The plan provides for stabilization of the site for the short-term and control of unauthorized access and prevention of unauthorized use.
The plan will remain in effect until the most appropriate long-term use of the site is determined, at which time it will be incorporated into that use.
1.3 LIMITATIONS OF PLAN l At present many activities associated with original construction and licensing
. 2 of the Cherokee Nuclear Station are being conducted under several permits issued by State and Federal regulatory agencies. In conjunction with plant cancellation, Duke is now in the process of reviewing the need for these perm-its and whether action to modify, renew, or cancel will be necessary.
Although detailed descriptions of these activities are not addressed herein, examples of the permits within this category include the following:
NPOES Permit issued by S.C. Department of Health and Environmental Control (SC-DHEC).
Section 404 Permit issued by Corps of Engineers.
Section 10 Permit issued by S. C. Water Resources Commission.
Air Quality Permit issued by SCDHEC.
FAR-Part 77 Permit issued by Federal Aviation Administration.
Site monitoring under Duke's Control Program to Limit Adverse Environmental Ef-fects During Construction is also under review. Commitments agreed upon with the Nuclear Regulatory Commission and the Environmental Protection Agency under this program will be modified as necessary to provide a complete stabilization of all site facilities.
2.0 SITE STABILIZATION PLAN 2.1 STATE OF COMPLETION AT CANCELLATION Construction activities for Unit 1, including facilities considered common
- to all three units, were 17.8 percent complete just prior to the cancellation of Units 2 and 3. Except for the partially completed powerhouse excavt
- ions, I
progress on Units 2 and 3 was essentially zero. The following listing indicates the approximate percentage of structural concrete work completed for the majcr structures for Unit 1 and for common facilities. ,;
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. - . - - - - . - _ , . , - -. ,.-.n.. -, ,- .... - . - - - .- . . - . - - . . - - - - - . - , - - . - ---.., - -..- .. .. -- - -
3 Structure Unit 1 Common Reactor Building 53%
Auxiliary Building 24%
Turbine Building 73%
Condenser Cooling Water Pump Structure 95%
Service Building 51%
Nuclear Service Water Pump Structures 100%
Makeup Intake Structure 100%
Nuclear Service Water Cooling Towers 64%
Nuclear Service Water Spillway 100%
Nuclear Service Water Cable Tunnels 86%
Yard Valve Structures 2%
- Facilities considered common to all three units before cancellation of Units 2 & 3.
Some equipment has been installed in the plant buildings. This equipment will be removed at Duke's option. Also, buried piping and electrical conduits and trenches, either permanent or temporary, will have ends sealed and be left in place, unless they can be economically salvaged.
2.2 EXISTING SITE CONDITIONS 2.2.1 EXCAVATIONS Approximately one-half of the land surface of the total 2200 acre plant site is comprised of graded yards or building site excavations, borrow areas, spoil areas, and earth embankments where the original terrain was physically nodified in vary-ing degrees during plant construction operations in the period 1976 to 1980.
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- 2.2.2 STORAGE FACILITIES
! Approximately 200 acres of the'siteiis currently being used as open stor-age areas for construction materials. These storage areas generally have been surfaced with gravel. Additionally, two - 200' x 400' and two - 200' x 200' warehouses are used for material and equipment storage. All are equipped with operational fire protection systems. The two larger warehouses are fully heat-ed, and one is also partially cooled.
2.2.3 DAftS/ PONDS Ponds impounded by dams cover approximately 300 acres of the site. Additionally, runoff and groundwater has created ponds in several major excavations. All of the pernianent water-retaining earth structures are essentially complete.
2.2.4 PLANT PHYSICAL FACILITIES i The Cherokee site facilities include several partially completed permanent ware-I houses, and many other temporary construction buildings and facilities already I
in place and useable. All construction buildings are serviced with utilities.
I Six wells of drinking water quality, two temporary electrical substations, approximately 700 acres of graded and graveled parking and storage areas, a permanent fire protection main, and a package sewage treatment system are a-mong the functional on-site facilities.
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5 The CCW Cooling Tower yards are graded and graveled and most of the large diameter underground cooling water pipe located between the tower yards and the turbine buildings is installed.
A permanent aerated lagoon sewage treatment system is partially completed.
Some permanent underground storm drainage piping, primarily in the Unit 1 yard area, is in place.
2.2.5 TRANSMISSION CORRIDORS Transmission corridors associated with the planned high-voltage transmission lines from plant switch yards are sufficiently cleared to accommodate con-struction of tower structures from the system to the site.
2.2.6 TRANSPORTATION FACILITIES A newly constructed railroad spur provides rail access to the site. A recently improved paved state highway provides good vehicle access from the major interstate highway, I-85, at Gaffney. Numerous ungraveled, graveled and paved roads provide additional access to areas within the site.
2.3 SITE STABILIZATION ACTIVITIES 2.3.1 EXCAVATIONS j Backfill will be placed in any unstable excavated areas as required and addition-l al grading will be performed to provide drainage for ponded areas if their exist-ence is considered an environmental problem. Grass cover will be established in all areas except gravel surfaced areas, concrete slabs, and buildings. Areas ,
excavated to rock are considered stable and will not require further treatment.
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. 6 2.3.2 STORAGE FACILITIES Materials presently located in the open storage areas will be removed from the site as storage is no longer required. These areas are presently graveled and will remain so since no further stabilization is necessary. Warehouses will be treated as detailed in section 2.3.4.
2.3.3 DAMS / PONDS The slopes of all permanent water retaining earth structures have been provided
- with erosion protection and will require no further stabilization.
i Holding ponds will be retained and used to collect and treat runoff for the duration of site stabilization. NPDES permit limitations for the various dis-charge points will remain in effect during this period and will govern all discharges from the site. As required, pumping may continue to be used to maintain desirable levels in the ponds. A decision as to the future status i~
of all ponds and associated dams will be made at the conclusion of site stabilization activities consistent with future use of the site.
, 2.3.4 PLANT PHYSICAL FACILITIES Current plans are to remove all temporary construction buildings from the site f
within approximately five years unless a continued need for on-site materials storage is identified or alternate on-site uses for the structures are estab-lished. Concrete slabs that remain after removal of the buildings will be left in place.
4 Partially completed permanent plant structures will be left in place in essen-tially their present conditions. At this time, Duke's only plans with 4
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2.3.5 TRANSMISSION CORRIDORS Transmission corridors presently have grass cover and other natural growth and will require no further stabilization.
2.3.6 TRANSPORTATION FACILITIES The access railroad will be maintained in a serviceable condition with fills and cut slopes stabilized. Parking areas and roadways that are presently gravelled will require no additional stabilization. Ungravelled roadways which are deemed necessary for site access will be maintained in a stable condition. All other roads will be graded for proper drainage and seeded with grass and closed to prevent unauthorized use.