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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20209H6921999-07-15015 July 1999 Forwards Comments on Preliminary Accident Sequence Precursor Analysis Provided in NRC Re Operational Condition Reported in LER 269/1998-04 ML20195H1681999-06-10010 June 1999 Forwards Copy of Preliminary ASP Analysis of Operational Condition Discovered at Ons,Units 1,2 & 3 on 980212 & Reported in LER 269/98-004,for Review & Comment ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co ML20206E4101999-04-26026 April 1999 Forwards Four Copies of Rev 9 Todpc Nuclear Security & Contingency Plan,Per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 ML20205T1301999-04-0909 April 1999 Informs That on 990317,C Efin & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Y2K.Initial Exam Dates Scheduled for Wks of 000710 & 17 for Approx 13 Candidates ML20205B0571999-03-24024 March 1999 Informs That Author Determined That Partial Exemption from 10CFR170 Fee Requirements Appropriate for Footnote 4 of Review of License Renewal Application for Ons,Units 1,2 & 3, That Staff Determines Has Generic Value to Industry ML20207C0501999-02-25025 February 1999 Submits Annual Rept Specifying Quantity of Each of Principal Radionuclides Released to Environment in Liquid & Gaseous Effluents,Per 10CFR72.44(d)(3).Effluent Release from ISFSI for CY98 Was Zero ML20202J1901999-01-28028 January 1999 Discusses License Renewal for Operating Power Reactors.Two Applications Received for Renewing Operating Licenses. Commission Established Adjudicatory Schedule Aimed at Completing License Renewal Process in 30-36 Months ML20202H7621999-01-28028 January 1999 Discusses Guidance Re License Renewal for Operating Power Reactors Developed in Response to FY99 Energy & Water Development Appropriations Act Rept 105-581 ML20198S8721999-01-0707 January 1999 Responds to Message to Marks Re Info Request on Appeal Deadline & Desire to Serve Appeal Either by e-mail or by Alternative Regular Mail ML20198Q8871999-01-0707 January 1999 Responds to to Chairman SA Jackson Re Issues for Consideration for Commission During Oconee License Renewal Process.Commissioners Must Remain Impartial During Pendency of Case.Copy of Order LBP-98-33 Encl.Served on 990107 ML20198Q8971998-12-17017 December 1998 Expresses Concerns Re License Renewal of Duke Energy,Oconee Nuclear Station,Units 1,2 & 3.Commends NRC on Steps Agency Has Undertaken to Conclude Renewal Process.With Certificate of Svc.Served on 990107 05000269/LER-1998-012, Forwards LER 98-012-01,re RB Spray Pumps Being Declared Inoperable Due to Npsh.Rept Has Been Revised to Indicate Results of Testing & Corrective Actions Taken to Date1998-12-0303 December 1998 Forwards LER 98-012-01,re RB Spray Pumps Being Declared Inoperable Due to Npsh.Rept Has Been Revised to Indicate Results of Testing & Corrective Actions Taken to Date 05000269/LER-1998-013, Forwards LER 98-013-00 Re Condition Prohibited by Ts,Per 10CFR50.73(a)(1)(d).Circumstances & Causes for Event Have Not Been Fully Determined & Will Be Provided in Supplemental LER on or Before 9812021998-11-0202 November 1998 Forwards LER 98-013-00 Re Condition Prohibited by Ts,Per 10CFR50.73(a)(1)(d).Circumstances & Causes for Event Have Not Been Fully Determined & Will Be Provided in Supplemental LER on or Before 981202 ML20155D2651998-10-23023 October 1998 Expresses Appreciation for Supporting Commission Initiative in Issuing Recent Statement of Policy on Conduct of Adjudicatory Proceedings.Case-specific Orders Were Issued in Calvert Cliffs & Oconee License Renewal Proceedings ML20155B1481998-10-21021 October 1998 Informs That as Result of Discussion of Issues Re Recent Events in Ice Condenser Industry,Ice Condenser Mini-Group (Icmg),Decided to Focus Efforts on Review & Potential Rev of Ice condenser-related TS in Order to Clarify Issues ML20154B9421998-09-30030 September 1998 Amends Chattooga River Watershed Coalition Petition to Intervene in Proceedings Re Application of Duke Energy Corp to Renew OLs for Oconee Nuclear Station,Units 1,2 & 3 ML20154A8971998-09-30030 September 1998 Requests That Submitted Info Be Attached to Amends to Petition to Intervene in Proceedings Re Application of Duke Energy Corp to Renew Operating Licenses for Units 1,2 & 3 ML20153H6881998-09-27027 September 1998 Requests Consideration of Motion to Enlarge Time Required to Submit Amended Petition to Intervene in Proceeding Re Application of Duke Energy Corp to Renew OLs for Facilities ML20153E4721998-09-24024 September 1998 Forwards Notices of Appearances for Attorneys Representing Duke Energy Corp,Applicant in Proceeding for License Renewal of Oconee Units 1,2 & 3.With Certificate of Svc ML20153D1831998-09-17017 September 1998 Ack Receipt of of Duke Energy Co Inviting Reconsideration of Denial by NRC CFO of Duke Exemption Request from Annual Fee Requirements for General License Under 10CFR171.11(d) ML20151S7501998-08-31031 August 1998 Provides Update on Commitment Made by Licensee in Response to NOV & Imposition of Civil Penalty Re Valves in Ldst Instrument Lines That Were Incorrectly Translated Into Station Procedures ML20237B0871998-08-11011 August 1998 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 981007.Sample Registration Ltr Encl ML20236V9581998-07-27027 July 1998 Forwards Corrected Pages 3.5-30b of 961211 & 3.16-2 of 970205 TS Bases.Old Amend Numbers Were Left on Pages.Rev Changes Footer on Both Pages to Reflect Bases Changes ML20236P9451998-07-15015 July 1998 Forwards Emergency Response Data Sys Implementation Documents Including Data Point Library Updates for Oconee (Number 255),Dresden (Number 257) & Susquehanna (Number 258) ML20153D1961998-07-0909 July 1998 Requests NRC Reconsider & Grant Util Request for Exemption from Duplicative License Fee Under 10CFR171.11(d) for Storage of Spent Nuclear Fuel at Oconee Nuclear Station ML20236J9871998-06-24024 June 1998 First Final Response to FOIA Request for Documents.Documents Listed in App a Already Available in Pdr.Documents Listed in App B Being Released in Entirety ML20247G0881998-05-14014 May 1998 Provides Rev 2 to Section 3.3, Instrumentation, in Support of TS-362 Amend Request.Position on Testing of Analog Trip Type Instruments W/Regard to Transition from CTS to ITS, Restated.Summary Description of Its/Bases Changes,Encl 05000269/LER-1998-002, Forwards LER 98-002-01 Re non-isolable Weld Leak on Pressurizer Surge Line Drain Pipe Which Resulted in Unit Shutdown1998-04-30030 April 1998 Forwards LER 98-002-01 Re non-isolable Weld Leak on Pressurizer Surge Line Drain Pipe Which Resulted in Unit Shutdown ML20217G0351998-03-26026 March 1998 Submits Ltr to Update Commitment Made by Oconee in Response to Subject Violation.Update Assures That Details of Particular CA Are Appropriately Contained in Docketed Correspondence ML20203J9301998-02-26026 February 1998 Submits Response to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. Suppl 1 to Bulletin Attached & Contains Listed Commitments ML20199J7441998-02-0202 February 1998 Responds to NRC Bulletin 96-004 for NUHOMS-24P Sf Storage Sys Used at Plant Site.Nrc Reviewed Response & Found Response to Be Acceptable ML20198K9321998-01-13013 January 1998 Ack Receipt of Requesting Exemption from 10CFR171 for ISFSI License SNM-2503 & General License Provisions of 72.214 ML20198M9361998-01-12012 January 1998 Responds to Request That rept,BAW-2303P,rev 3 Be Considered Exempt from Mandatory Public Disclosure.Determined That Info Sought to Be Withheld Contains Proprietary Commercial Info & Will Be Withheld from Public Disclosure ML20203C8481997-12-10010 December 1997 Forwards Emergency Response Data Sys Implementation Documents for Plants.W/O Encl 05000269/LER-1997-003, Forwards LER 97-003-01 Re post-LOCA Boron Dilution Design Basis Not Being Met.Rept Includes Updated Info & Revised Corrective Action1997-11-12012 November 1997 Forwards LER 97-003-01 Re post-LOCA Boron Dilution Design Basis Not Being Met.Rept Includes Updated Info & Revised Corrective Action ML20198Q5741997-11-0303 November 1997 Provides Suppl to Initial 971020 Application for Amend to TS Re SG Tubing Surveillance Requirements,In Response to NRC 971030 Request for Addl Info.Proprietary Rev 3 to BAW-2303P, OTSG Repair Roll Qualification Rept Encl.Rept Withheld ML20211P1591997-10-17017 October 1997 Ack Receipt of & Check for $330,000 in Payment for Civil Penalty.Corrective Actions Will Be Examined During Future Insp ML20217D7261997-10-0101 October 1997 Informs That Staff Intends to Use Working Draft SRP-LR as Aid in Reviewing License Renewal Submittals Received from Dpc,Other Licensees & Owners Groups.Policy Issues Will Be Referred to Commission for Resolution ML20211F7981997-09-25025 September 1997 Submits Response to Violations Noted in Insp Repts 50-269/97-10,50-270/97-10 & 50-287/97-10 & Proposed Imposition of Civil Penalty in Amount of $330,000.Corrective Actions:Ldst Instrument Mods on All Three Units Completed ML20217D9341997-09-22022 September 1997 Informs That NRC Staff Has Accepted Deferral of Completion of Certain Actions Requested by Bulletin 96-03, Potential of Plugging of ECCS Strainers by Debris in Boiling Water Reactor ML20211C8021997-09-18018 September 1997 Forwards Revised TS Amend Re Reactor Bldg Structural Integrity.Previously Submitted TSs Contained Editorial Error ML20210T7121997-09-0404 September 1997 Informs That Representatives from Oconee Who Compose LERs Would Like to Meet W/Staff & AEOD at Convenient Place & Time to Facilitate Process.Concerns Addressed in Encl ML20216G5821997-09-0404 September 1997 Informs That 970730 Submittal Re Oconee Nuclear Station, Units 1,2 & 3 Will Be Marked Proprietary & Being Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEC Act of 1954 IR 05000269/19970071997-08-27027 August 1997 Discusses Insp Repts 50-269/97-07,50-270/97-07,50-287/97-07, 50-269/97-08,50-270/97-08 & 50-287/97-08 on 970606 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $330,000 ML20210N1531997-08-13013 August 1997 Confirms 970807 Telcon Between J Burchfield & R Carroll Re Management Meeting to Be Conducted at Oconee Nuclear Station on 970922.Purpose of Meeting to Discuss Oconee Emergency Power Project Initiatives ML20210M8381997-08-13013 August 1997 Confirms Conversation Between J Burchfield & R Carroll on 970807 Re Mgt Meeting to Be Conducted in Region II Ofc on 971113.Meeting to Discuss Status of Plant Performance Improvement Initiatives ML20210N1121997-08-12012 August 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 971008. Facililty Must Submit Either Ltr Indicating No Candidates Scheduled to Participate or Listing Names of Candidates ML20149J4841997-07-21021 July 1997 Forwards Addl Pages to Rev 5 to Duke Power Co Nuclear Security & Contingency Plan. Encl Withheld 1999-08-10
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20209H6921999-07-15015 July 1999 Forwards Comments on Preliminary Accident Sequence Precursor Analysis Provided in NRC Re Operational Condition Reported in LER 269/1998-04 ML20206E4101999-04-26026 April 1999 Forwards Four Copies of Rev 9 Todpc Nuclear Security & Contingency Plan,Per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 ML20207C0501999-02-25025 February 1999 Submits Annual Rept Specifying Quantity of Each of Principal Radionuclides Released to Environment in Liquid & Gaseous Effluents,Per 10CFR72.44(d)(3).Effluent Release from ISFSI for CY98 Was Zero ML20198Q8971998-12-17017 December 1998 Expresses Concerns Re License Renewal of Duke Energy,Oconee Nuclear Station,Units 1,2 & 3.Commends NRC on Steps Agency Has Undertaken to Conclude Renewal Process.With Certificate of Svc.Served on 990107 05000269/LER-1998-012, Forwards LER 98-012-01,re RB Spray Pumps Being Declared Inoperable Due to Npsh.Rept Has Been Revised to Indicate Results of Testing & Corrective Actions Taken to Date1998-12-0303 December 1998 Forwards LER 98-012-01,re RB Spray Pumps Being Declared Inoperable Due to Npsh.Rept Has Been Revised to Indicate Results of Testing & Corrective Actions Taken to Date 05000269/LER-1998-013, Forwards LER 98-013-00 Re Condition Prohibited by Ts,Per 10CFR50.73(a)(1)(d).Circumstances & Causes for Event Have Not Been Fully Determined & Will Be Provided in Supplemental LER on or Before 9812021998-11-0202 November 1998 Forwards LER 98-013-00 Re Condition Prohibited by Ts,Per 10CFR50.73(a)(1)(d).Circumstances & Causes for Event Have Not Been Fully Determined & Will Be Provided in Supplemental LER on or Before 981202 ML20155B1481998-10-21021 October 1998 Informs That as Result of Discussion of Issues Re Recent Events in Ice Condenser Industry,Ice Condenser Mini-Group (Icmg),Decided to Focus Efforts on Review & Potential Rev of Ice condenser-related TS in Order to Clarify Issues ML20154A8971998-09-30030 September 1998 Requests That Submitted Info Be Attached to Amends to Petition to Intervene in Proceedings Re Application of Duke Energy Corp to Renew Operating Licenses for Units 1,2 & 3 ML20154B9421998-09-30030 September 1998 Amends Chattooga River Watershed Coalition Petition to Intervene in Proceedings Re Application of Duke Energy Corp to Renew OLs for Oconee Nuclear Station,Units 1,2 & 3 ML20153H6881998-09-27027 September 1998 Requests Consideration of Motion to Enlarge Time Required to Submit Amended Petition to Intervene in Proceeding Re Application of Duke Energy Corp to Renew OLs for Facilities ML20153E4721998-09-24024 September 1998 Forwards Notices of Appearances for Attorneys Representing Duke Energy Corp,Applicant in Proceeding for License Renewal of Oconee Units 1,2 & 3.With Certificate of Svc ML20151S7501998-08-31031 August 1998 Provides Update on Commitment Made by Licensee in Response to NOV & Imposition of Civil Penalty Re Valves in Ldst Instrument Lines That Were Incorrectly Translated Into Station Procedures ML20236V9581998-07-27027 July 1998 Forwards Corrected Pages 3.5-30b of 961211 & 3.16-2 of 970205 TS Bases.Old Amend Numbers Were Left on Pages.Rev Changes Footer on Both Pages to Reflect Bases Changes ML20153D1961998-07-0909 July 1998 Requests NRC Reconsider & Grant Util Request for Exemption from Duplicative License Fee Under 10CFR171.11(d) for Storage of Spent Nuclear Fuel at Oconee Nuclear Station ML20247G0881998-05-14014 May 1998 Provides Rev 2 to Section 3.3, Instrumentation, in Support of TS-362 Amend Request.Position on Testing of Analog Trip Type Instruments W/Regard to Transition from CTS to ITS, Restated.Summary Description of Its/Bases Changes,Encl 05000269/LER-1998-002, Forwards LER 98-002-01 Re non-isolable Weld Leak on Pressurizer Surge Line Drain Pipe Which Resulted in Unit Shutdown1998-04-30030 April 1998 Forwards LER 98-002-01 Re non-isolable Weld Leak on Pressurizer Surge Line Drain Pipe Which Resulted in Unit Shutdown ML20217G0351998-03-26026 March 1998 Submits Ltr to Update Commitment Made by Oconee in Response to Subject Violation.Update Assures That Details of Particular CA Are Appropriately Contained in Docketed Correspondence ML20203J9301998-02-26026 February 1998 Submits Response to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. Suppl 1 to Bulletin Attached & Contains Listed Commitments 05000269/LER-1997-003, Forwards LER 97-003-01 Re post-LOCA Boron Dilution Design Basis Not Being Met.Rept Includes Updated Info & Revised Corrective Action1997-11-12012 November 1997 Forwards LER 97-003-01 Re post-LOCA Boron Dilution Design Basis Not Being Met.Rept Includes Updated Info & Revised Corrective Action ML20198Q5741997-11-0303 November 1997 Provides Suppl to Initial 971020 Application for Amend to TS Re SG Tubing Surveillance Requirements,In Response to NRC 971030 Request for Addl Info.Proprietary Rev 3 to BAW-2303P, OTSG Repair Roll Qualification Rept Encl.Rept Withheld ML20211F7981997-09-25025 September 1997 Submits Response to Violations Noted in Insp Repts 50-269/97-10,50-270/97-10 & 50-287/97-10 & Proposed Imposition of Civil Penalty in Amount of $330,000.Corrective Actions:Ldst Instrument Mods on All Three Units Completed ML20211C8021997-09-18018 September 1997 Forwards Revised TS Amend Re Reactor Bldg Structural Integrity.Previously Submitted TSs Contained Editorial Error ML20210T7121997-09-0404 September 1997 Informs That Representatives from Oconee Who Compose LERs Would Like to Meet W/Staff & AEOD at Convenient Place & Time to Facilitate Process.Concerns Addressed in Encl ML20149J4841997-07-21021 July 1997 Forwards Addl Pages to Rev 5 to Duke Power Co Nuclear Security & Contingency Plan. Encl Withheld ML20141F1381997-06-25025 June 1997 Forwards Rev 4 to Nuclear Security Training & Qualification Plan, Per 10CFR50.4 ML20140C9531997-06-0303 June 1997 Requests NRC Approval of Amend to Oconee ISFSI to Obtain Commission Approval of Proposed Rev 6 to Encl Physical Security Plan.W/O Encls ML20148C8621997-05-22022 May 1997 Informs That TR BAW-2241P Will Be Ref in Future Submittals of P/T Limit Curve Revs for B&W Plants as Result of 970519 Telcon Between L Lois & J Taylor ML20141K1981997-05-19019 May 1997 Forwards Rev 6 to Duke Power Co Nuclear Security & Contingency Plan.Encl Withheld,Per 10CFR73.21 ML20138G8981997-04-30030 April 1997 Forwards Rev 5 to DPC Security & Contingency Plan.Encl Withheld ML20138B3421997-04-22022 April 1997 Submits Response to Request for Addl Info Re Proposed Amend to Reactor Bldg Structural Integrity Tech Specs.Info Provided in Attachments 2 & 3 Supersedes Revised Pages & Markup Pages in Attachment 1 & 2,respectively ML20137N0231997-03-26026 March 1997 Forwards Revised TS 3.1.6 Bases Pages Deleting Detection Time of Reactor Bldg Air Particulate Monitor for RCS Leak of 1 Gpm ML20137B4731997-03-12012 March 1997 Forwards Rev 3 to Security Training & Qualification Plan.Rev Withheld,Per 10CFR73.21 ML20134P3831997-02-18018 February 1997 Submits Clarification of Design Basis Requirements at ONS for Permanently Installed Insulation in Response to NRC Bulletin 93-002, Debris Plugging of Emergency Core Cooling Suction Strainers ML20138L2101997-02-14014 February 1997 Forwards Monthly Operating Repts for Jan 1997 for Oconee Nuclear Station,Units 1,2 & 3 & Revised Monthly Operating Status Repts for Dec 1996 ML20134G5511997-02-0404 February 1997 Requests Exemption to Requirements of 10CFR70.24 Re Criticality Accident Monitoring,Per 10CFR70.14(a) & 70.24(d) ML20133M5971997-01-13013 January 1997 Forwards Revs to Oconee Selected Licensee Commitments Manual ML20138G8411996-12-26026 December 1996 Submits Supplementatl Info Re Emergency Power Engineered Safeguards Functional Test Amend Request ML20132F0911996-12-17017 December 1996 Forwards Response to 961212 & 13 Telcons Re Amend to Licenses for Proposed Changes to Updated Final Safety Analysis Rept Re one-time Emergency Power Engineered Safeguards Functional Test 05000269/LER-1996-008, Forwards Suppl to LER 96-008 Concerning Missed Valve Surveillance Which Resulted in Borated Water Storage Tank Technical Inoperability1996-10-31031 October 1996 Forwards Suppl to LER 96-008 Concerning Missed Valve Surveillance Which Resulted in Borated Water Storage Tank Technical Inoperability ML20134H2231996-10-30030 October 1996 Forwards Revised TS 3.7 Bases,Indicating Info Deleted ML20129B2571996-10-16016 October 1996 Submits Addl Info Re 960220 Application for Amends to Licenses DPR-38,DPR-47 & DPR-55 Concerning Proposed Rev to Chemistry TS Sections 3.1.5,3.1.10 & 4.1,in Response to NRC Telcon Request.Revised TS Pages Encl ML20128H2731996-09-19019 September 1996 Forwards Public Version of Rev 96-06 to Plant Emergency plan.W/961003 Release Memo ML20117D5691996-08-23023 August 1996 Requests Exemption for Ons,Units 1 & 2 & Cns,Units 1 & 2 Iaw/Provisions of 10CFR73.5, Requirements for Physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage ML20116F0051996-08-0101 August 1996 Forwards Corrected Page for Proposed Amend to TS Re Removal of Es Signal from Valves LPSW-4 & LPSW-5 ML20117E6031996-06-26026 June 1996 Forwards Public Version of Change 2 to RP/0/B/1000/01, Emergency Classification & Change 4 to RP/0/B/1000/22, Procedures for Site Fire Damage Assessment & Repair ML20112A0581996-05-14014 May 1996 Responds to NRC Bulletin 96-002, Movement of Heavy Loads Over Spent Fuel,Over Fuel in Reactor Core or Over Safety-Related Equipment ML20115C4371996-05-13013 May 1996 Responds to NRC Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel,Over Fuel in Reactor Core,Or Over Safety-Related Equipment, ML20117D4931996-04-24024 April 1996 Submits Clarification of Reporting Requirements Under 10CFR50.72(b)(2)(vi) ML20107K4991996-04-19019 April 1996 Forwards Rev 2 to Security Training & Qualification Plan. Changes Identified in Rev 2 Do Not Decrease Effectiveness of Plan & Thereby Submitted,Per 10CFR50.54(p),(2).Rev Withheld, Per 10CFR73.21 ML20108C7031996-04-18018 April 1996 Forwards Public Version of Rev 96-03 to Vol B of Epips, Including Cover Sheet,Table of Contents Page 1,change 7 to CP/1&2/A/2002/05 & Change 6 to CP/3/A/2002/05 1999-07-15
[Table view] Category:UTILITY TO NRC
MONTHYEARML16259A2391990-08-22022 August 1990 Forwards Public Version of Rev 27 to Company Crisis Mgt Implementing Procedure CMIP-2, News Group Plan. W/ Dh Grimsley 900906 Release Memo ML20059C1201990-08-20020 August 1990 Forwards Rept Summarizing Util Findings Re Three False Negative Blind Performance Urine Drug Screens Which Occurred During Jan & Feb 1990.Recommends That NRC Consider Generic Communication to Clearly State Reporting Requirement ML20063Q2671990-08-14014 August 1990 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 36 to CMIP-1,Rev 32 to CMIP-4,Rev 36 to CMIP-5,Rev 41 to CMIP-6,Rev 40 to CMIP-7,Rev 27 to CMIP-8 & Rev 35 to CMIP-9.W/DH Grimsley 900821 Release Memo ML20055C9851990-06-25025 June 1990 Forwards Rev 9 to Training & Qualification Plan.Rev Withheld ML16152A9841990-06-19019 June 1990 Forwards Revised Public Version of Rev 90-03 to Vol B of Epips,Including CP/2/A/2002/04C, Operating Procedure for Post-Accident Liquid Sampling, & Maint Directive 8.1 ML20044A4491990-06-14014 June 1990 Forwards Public Version of Rev 90-05 to Vol C to EPIP Manual. W/Dh Grimsley 900627 Release Memo ML16152A9821990-06-14014 June 1990 Forwards Public Version of Rev 90-02 to Vol B to Oconee Nuclear Station Epips. W/Dh Grimsley 900627 Release Memo ML20043E2571990-05-31031 May 1990 Forwards Request for Relief 90-01 from Requirements of Section XI of ASME Boiler & Pressure Vessel Code Re Inservice Insp During Second 10-yr Interval ML20043F4761990-05-30030 May 1990 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Consisting of Rev 20 to CMIP-13 & Deletion of CMIP-15 & CMIP-17.W/900612 Release Memo ML20043A5441990-05-16016 May 1990 Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project ML16152A9621990-05-0909 May 1990 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 35 to CMIP-1,Rev 26 to CMIP-2,Rev 31 to CMIP-4,Rev 35 to CMIP-5,Rev 40 to CMIP-6,Rev 39 to CMIP-7 & Rev 26 to CMIP-8.W/DH Grimsley 900517 Release Memo ML16152A9531990-05-0202 May 1990 Forwards Proprietary DPC-NE-2000P-A & Nonproprietary DPC-NE-2000-A, DCHF-1 Correlation for Predicting Heat Flux in Mixing Vane Grid Fuel Assemblies. Proprietary Rept Withheld ML20042H0321990-04-30030 April 1990 Forwards Public Version of Rev 90-04 to Vol C to EPIP Manual ML15217A1051990-03-26026 March 1990 Forwards Revised 1989 Annual Radiological Environ Operating Rept,Consisting of Revised Pages Summarizing Annual Liquid Dose Calculations ML20012D6941990-03-21021 March 1990 Advises of No Human Engineering Discrepancy Mods of Safety Significance for Overall Operation of Plant,Per 880420 Commitment ML16152A9411990-03-14014 March 1990 Forwards Public Version of Rev 90-01 (Vol a) to Emergency Plan Manual & Revs 90-01 (Vol B) & 90-03 (Vol C) to EPIP Manual.W/Dh Grimsley 900329 Release Memo ML20012B3741990-03-0101 March 1990 Requests Extension to Respond to Generic Ltr 90-01 Re Participation in Regulatory Impact Survey Until 900402.Util in Process of Completing Questionnaires for All Units 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 ML20012B4541990-02-21021 February 1990 Forwards Public Version of Vol C to Rev 90-02 to EPIP Manuals ML20012B3661990-02-21021 February 1990 Forwards Rev 1 to Cycle 12 Reload Rept,Changing Assumed RCS Flow & Correcting Typo ML20012B1691990-02-19019 February 1990 Forwards Public Version of Crisis Mgt Implementing Procedures,Including Rev 34 to CMIP-1,Rev 25 to CMIP-2, Rev 30 to CMIP-4,Rev 34 to CMIP-5,Rev 39 to CMIP-5 & Rev 38 to CMIP-7 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 ML20006C7181990-01-22022 January 1990 Forwards Rev 30 to Security Plan.W/O Encl ML16152A9061990-01-19019 January 1990 Forwards Public Version of Rev 90-01 to Vol C to Oconee Nuclear Station Implementing Procedures Emergency Plan & Rev 89-03 to Vol a to Oconee Nuclear Station Emergency Plan. W/900131 Release Memo 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 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 ML20005G1181990-01-0404 January 1990 Forwards Response to NRC Recommendations in 890828 Audit Evaluation Rept Re Safety & Performance Improvement Program. Util Fully Committed to Enacting Recommendations from Program Via B&W Owners Group Improvement Program 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 ML19351A5721989-12-0707 December 1989 Withdraws Commitment to Install Cavitating Venturies or Any Other Mod to Relieve Operator Burden in Ensuring That Emergency Feedwater Pumps Protected from Runout in Postulated Accidents W/Low Steam Generator Pressurization ML20011D2411989-11-30030 November 1989 Forwards Revised Crises Mgt Implementing Procedures, Including Rev 23 to CMIP-2 & Rev 3 to CMIP-15 ML16152A8751989-11-21021 November 1989 Forwards Proprietary DPC-NE-2003P-A & Nonproprietary DPC-NE-2003-A, Core Thermal-Hydraulic Methodology Using VIPRE-01. Proprietary Rept Withheld ML19332C6571989-11-20020 November 1989 Advises That Listed Addl Protective Measures Will Be Provided for Auxiliary Svc Water Piping,Per 890530 Ltr ML16152A8731989-11-0101 November 1989 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 31 to CMIP-1,Rev 28 to CMIP-4,Rev 32 to CMIP-5,Rev 37 to CMIP-6,Rev 36 to CMIP-7,Rev 25 to CMIP-8 & Rev 31 to CMIP-9.W/891020 Release Memo ML16152A8701989-10-30030 October 1989 Forwards Public Version of Rev 32 to Crisis Mgt Plan for Nuclear Stations. W/891113 Release Memo ML16152A8641989-10-18018 October 1989 Forwards Public Version of Revs 89-05 & 89-07 to Vol B & C, Respectively,Of Implementing Procedures Emergency Plan. W/891030 Release Memo ML19351A2771989-10-13013 October 1989 Advises That Tech Spec Amend Request,Including Revised 15 EFPY Pressure/Temp Limits & Revised Low Temp Overpressure Protection Sys Operability Requirements Will Be Submitted by 891115,per Commitment in 890131 Ltr Re Generic Ltr 88-11 ML19325C9181989-10-0909 October 1989 Forwards Rev 8 to Training & Qualification Plan.Rev Withheld ML20248F1971989-09-29029 September 1989 Clarifies Tech Spec Rev,Consisting of Changes to App J Test Requirements for Valves CA-27,HP-155 & CF-47.All Lines Leading from Auxiliary Bldg to Valves HP-155 & CA-27 Maintained Normally Isolated Through Closed Manual Valves ML20246G9561989-08-23023 August 1989 Submits Details of Method for Reporting Findings Resulting from Design Basis Documentation Program,Per 890728 Meeting. Util Agrees to Submit LER for Each Finding Identified in Design Basis Documentation Program ML20245H4841989-08-0909 August 1989 Forwards Addl Info on DPC-NE-3000, Thermal-Hydraulic Transient Analysis Methodology, Per 890718 & 19 Telcons Re Steam Generator Heat Transfer Modeling W/Retran Code ML20245L6441989-08-0404 August 1989 Documents 890726 Conference Call Re Implementation Schedule for ATWS Mods.Proposed Schedule for Mods to Install ATWS Mitigation Sys Actuation Circuitry Based on Decision to Utilize Programmable Logic Controller ML20248C0091989-07-31031 July 1989 Advises That Response to Generic Ltr 89-06, SPDS, Will Be Delayed Due to Late Date of Receipt of Ltr.Submittal Anticipted by 890808 ML20247H4211989-07-25025 July 1989 Forwards Rev 29 to Security Plan.Rev Withheld ML20247K0211989-07-21021 July 1989 Responds to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment, Clarifying Info in .Use of Unqualified Components in Vent Paths for Valves Acceptable Based on Secondary Side Cooling ML20246G1711989-07-20020 July 1989 Submits Route Info for Shipment of Eight Irradiated Fuel Rods from Oconee to B&W Lynchburg Research Ctr in Sept 1989, Consisting of Single Shipment w/NLI-1/2 Spent Fuel Shipping Cask.Approval Requested by 890901 ML20247A8991989-07-13013 July 1989 Forwards Rev 4 to Process Control Program ML20246P5721989-07-13013 July 1989 Forwards Request for Relief 89-06 from Requirement of Section of XI of ASME Boiler & Pressure Code Re Second 10-yr Interval Inservice Insp.W/Three Oversize Drawings ML20246K2101989-06-28028 June 1989 Forwards Public Version of Revised Crisis Mgt Implementing procedures.W/890711 Release Memo ML20247N9591989-05-30030 May 1989 Forwards Request for Relief 89-04 from Inservice Insp Requirements of Section XI of ASME Boiler & Pressure Vessel Code,Based on Impracticality of Performing Full Volumetric Exam of Turbine Stop Valve Upper Head to Valve Body Studs ML20247E5401989-05-15015 May 1989 Confirms 890504 Discussion Re Acceptance of Util Proposed Schedule for Implementation of ATWS Mods.Util Cannot Commit to Submitting Final Design Description Earlier than 890901 1990-08-22
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April 29, 1967 Director' Division of Reactor Licensing U S Atomic Energy Commission Washington, D C 20545 Re: Docket Nos 50-270 and 50-287 p M gulatory Suppl File Cy?
Dear Sir:
Duke Power Company is f_iling herewith Amen No 3 to its Application for Licenses for its proposed 0:enee Nuclear Station. This filing includes three signed original copies and 100 copies of material applicable to the Preliminary Safety Analysis Report.
By this amendment, a third nuclear generating unit, to be a duplicate of each of the first two, is embraced in the application. Also, financial information is submitted as requested by the Director's letter of March 17, 1967. Further, this amendment includes replacement pages and errata sheets applicable to the Preliminary Safety Analysis Report to make minor changes and to submit additional information on control rod drives.
This amendment is in a format designed to keep current the Preliminary Safety Analysis Report.
Yours very truly, W
W S Lee WSL/s
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) DOCKET NOS. 8-2693 DUKE POWER COMPANY ) Su-27v 50- M
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AMENDMENT NO. 3 ,
TO APPLICATION FOR LICENSES Duke Power Company, Applicant in the above-captioned proceeding , here-by amends it pplication for Licenses, as heretofore amended and supplemented, as follows: 44-t af -
A. Oconee Nuclear Station, Unit 3.
Supplement 3 to the Preliminary Safety Analysis Report, attached heretc
' and made a part hereof, is herewith filed for the purpose of including in the facilities for which licenses are requested a third pressurized water reactor to be known as "Oconee Nuclear Station, Unit 3" . Except as expressly pro-vided herein below to the contrary and subject to the supplementary and amend-atory material contained in said Supplement 3, all of the provisions of the Ap-plication as heretofore filed and amended, including the general information required by 10 CFR %50.33 and the technical information and safety analysis report required by 10 CFR 50.34, shall apply to the Oconee Nuclear Station, Unit 3, as though fully herein written.
The Application (10 CFR 550.33) is amended as follows:
- 1. On the cover sheet the words "for OCONEE NUCLEAR
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C STATION Units 1 and 2" are deleted and tha words "for OCONEE I # NUCLEAR STATION Units 1, 2 and 3", are inserted in lieu thereof.
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.( 2. On page 1 the word "two" appearing in the first s sentence of the second paragraph is deleted, and the word "three" is inserted in lieu thereof.
- 3. On page 7 the first line, which begins with the word " supply" and ends with the word " units", is deleted, and there is inserted in lieu thereof the following:
" supply the first two cores for each of the first two nuclear generating units, and the first core for the third nuclear generating unit" .
- 4. On page 7 the second sentence of the first complete paragraph beginning with the words "They will include" and ending with the words '" Units 1 and 2"' is deleted and there is inserted in lieu thereof the following:
"They will include three pressurized water reactors to be known as 'Oconee Nuclear Station Units 1, 2 and 3 ' " .
- 5. On page 7 the first sentence under section f begin-ning with the words " Applicant estimates" and ending with the words "approximately $197,828,000" is deleted and there isk inserted in lieu thereof the following:
" Applicant estimates that the total cost of the Oconee Nuclear Station, Units 1, 2 and 3, including the initial core for each unit, will be approximately $340,858,000".
- 6. The only paragraph under section h entitled "Com-pletion dates" on page 9 is deleted in its entirety and there is
, inserted in lieu thereof the following:
i (J
J O n- m i " Applicant's projected load requirements will necessi-tate full power operation of Oconee Nuclear Station, Unit 1, by May 1971; Unit 2, by May 1972; and Unit 3
- by June 1973. The earliest date for completion of construction of Unit 1 is estimated to be October 1, 1970, and the latest completion date is estimated to be February 28, 1971. Corresponding dates for Unit 2 are one year later. The earliest date for completion of construction of Unit 3 is estimated to be November 1, 1972, and the latest completion date is estimated to be August 1,1973" .
- 7. In the Agreement Limiting Access to Restricted Data ,
filed as Exhibit IV to the Application, the words " Units 1 and 2" A
() appearing on line 2 are deleted and the words " Units 1, 2 and 3" are inserted in lieu thereof.
B. Information requested in letter of Dr. Peter A. Morris , Director, Division of Reactor Licensing, to Applicant dated March 17, 1967.
By letter of March 17, 1967, the Director, Division of Reactor Licensing, requested information with respect to the financial qualifications of Applicant to construct Oconee Nuclear Station Units 1 and 2. Subsequent to the filing
. of the Application, the estimated cost of Units 1 and 2 has been revised. In addition, this Amendment No. 3 incorporates Unit 3 into the Application for Units 1 and 2. Reflecting the revised estimate for Units 1 and 2 and the addi-tion of Unit 3, the requested information is given as follows:
- 1. Copies of Duke Power Company Annual Report for 1966 were filed with Amendment No. I dated April 1,1967.
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- 2. Estimated costs of Oconee Nuclear Station are a
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$ 1,379,000 Site Acquisition y 278,366,000 Direct Cost of Plant b
$ 279,745,000 Subtotal C G 10,767,000 Allowance for additional inflation ;
18,900,000 Engineering, general overheads, and contingencies 1,387,000 Operator training - Carital portion 500,000 Licensing and special administrative ,
burdens l
,~
33,662,000 Interest during constr,1ction l 344,961,000 Total plant with substation l 63,000,000 Initial cores '
$ 407,961,000 Grand Total No separate breakdown is available of taxes and insurance
,- covered in this cost estimate. This revision to cost estimates is
occasioned by the inflation effect on the cost of equipment, labor and materials; increased interest rates; and the cost of items added !
l to meet licensing requirements. Applicant will own spent fuel from l l
the initial core of Unit 3, but not of Units 1 and 2.
- 3. The first core fuel for each unit will contain the following quantity, enrichment and dollar value (based on current AEC charge rates) of uranium:
Quantity Enrichment AEC Base Charges Ko-U Ko-U235 % Dollar Value 20,536 460 2.24 $ 3,529,727 25,546 631 2.47 5,021,322 34,657 960 2.77 7,940,958 80,739 co 2,051 S 16,492,007 l
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- 2. Estimated costs of Oconee Nuclear Station are as fouows: i Units 1 and 2 Unit 3 Total
\1,068,000$
146,732,000 0
79,194,000
$ 1,068,000 Site equisition 225,926,000 Direct cost of plant
$14 800,000 $ 79,194,000 $226,994,000 Su otal 8, 00,000 4,313,000 13,113,000 E ineering, general oderheads , and con-tingencies 403, 0 100,000 500, 00 Operator training -
Capital portion 400,000 100,000 500,000 Licensing and special administration burdens 14,166,000 371,000 22,53 000 Interest during construct-ion
$171, 566,000 $ 92,0 8,000 S 263,6 4,000 Total, without substation 5, 448,000 8,76 000 14 , 14,000 Step-up substation, in-cluding $1,174,000 interest during construction
$177, 014,000 S 100,844,00AS 2/7,858,000 Total plant with substation 36 , 290,000 26,710, 000 1 /63,000,000 Initial cores
$213 , 304,000 $ 127,554,000 40,858,000 Grand total No se'parate breakdow is a ilable of taxes and insur-ance included in Applica s' plant co truction estimates. Ap-plicant makes no speci c provision for calation in its plant estimates which are sed upon cost level obtaining as of the date of the estimat . Historically, contingen es included have been adequ e to cover escalation. Applica t will own spent fuel from e initial core of Unit 3, but not of nits 1 and 2.
- 3. The irst core fuel for each unit will contain e fol-lowing quar ity, enrichment and dollar value (based on c rrent AEC char rates) of uranium:
Quanti Enrichment AEC Base Ch rges Kg-If Kg- U23 5 % Dollar Valuh 20 36 460 2.24 $ 3,529,727 25,546 631 2.47 5,021,322 34,657 960 2.77 7,940,958 80,739 2,051 S16,492,007
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- 4. Excluding interest during construction, total funding requirements for Oconee Nuclear Station, Units 1, 2 and 3 are estimated as follows:
Station Initial Fuel 1966 $ 349,000 $ -
1967 2,404,000 -
1968 30,326,000 -
1969 88,465,000 -
1970 70,582,000 18,000,000 1971 43,399,000 32,190,000 1972 16 ,787,000 12,810,000 1973 1,835,000 -
- 5. As to source of funds for the construction of Units 1, 2 and 3, it is estimated that approximately 40% of the construct-ion funds will be generated internally from retained earnings and q depreciation. The balance will be obtained initially through short
)
term borrowings from commercial banks, and will thereafter be permanently funded by sale of securities. Due to changing market conditions, no definite statement can be made at this time as to the type of securities which will be sold or the date of their sale.
It is presently anticipated that the Company will issue first mort-gage bonds, cumulative preferred stock and common stock during this period.
C. Replacement and Supplementary pages for Preliminary Safety Analysis Report.
Filed herewith and made a part hereof are replacement and supplementary ,
pages for the Preliminary Safety Analysis Report containing'information on a revised design of control rod drives. This information is in addition to the material presented in Supplement 2 to the Preliminary Safety Analysis Report k- in answer to question 4.7 in letter of Dr. Peter A. Morris , Director, Division 1
of Reactor Licensing, to Applicant dated March 23, 1967.
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Other replacement pages are also filed herewith and made a part hereof indicating various minor changes to portions of the Preliminary Safety Analysis Report.
D. Errata Sheet.
Filed herewith and made a part hereof is an errata sheet indicating various minor changes and corrections to portions of the Preliminary Safety Analysis Report.
WHEREFORE, Applicant renews its request for the licenses specified in its original Application.
IN WITNESS WHEREOF, Duke Power Company has caused its name to be hereunto signed by W. S. Lee, its Vice President, and its corporate seal to be hereto affixed by James S. Sease, its Assistant Secretary, this 29th day of April,1967.
DUKE POWER COMPANY By Vice President Attest:
O h v h' istant Secretary
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s State of North Carolina )
County of Mecklenburg )
W. S. LEE, being duly sworn, states that he is Vice President of Duke Power Company; that he is authorized on the part of said Company to sign and file with the Atomic Energy Commission this Amendment No. 3 to its Applicaticri and documents appended thereto; that he has read all of the statements contained in such Amendment No. 3 and the documente ap-pended thereto and made a part thereof; and that all such statements made and matters set forth therein are true and correct to the beat of his know-ledge, information and belief.
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W. S. Lee SUBSCRIBED and sworn to before me, a Notary Public in and for the State and County above named, this 29th day of April,1967.
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.; Notary Public My coinmission expires: .
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'c 3 DOCKETS 50-269, 50-270 AND 50-(h DUKE POWER COMPANY OCONEE NUCLEAR STATION UNITS 1, 2 AND 3 Errata Filed With Amendment 3 Please make tha following notations in the Preliminary Safety Analysis Report to effect correction of errors and minor changes:
Note: These corrections should not be made until replacement pages have been substituted.
P_aage, Section Table of Contents Change page numbers for Sections 3.3 through 3.4 from in front of "3-78, 3-78, 3-79, 3-80, 3-86 and 3-87" to "3-75, 3-75, Volumes I and II 3-76, 3-77, 3-83 and 3-84," respectively.
1-111 List of Change title of Table 1-1 to " Engineered Safeguards Tables Equipment."
2-10 2.6 Third paragraph, add the following sentence to end oi paragraph: "The structural design criteria for the maximum hypothetical earthquake are 0.10g and 0.15g for Class I structures founded on-bedrock and over-i t .
( burden, respectively."
i Figure 2 Change elevation of 500 kv Switchyard from "730" to 2-2 "735."
3-1 Table of Change the page number for each of Sections 3.3, Content's 3.3.1, 3.3.1.1 and 3.3.1.2 from "3-78" to "3-75."
s i % 3-111 List of Change the page number for Tables 3-19 and 3-20 from l h '\ Tables' "3-68" and "3-76" to "3-67" and "3-73," respectively.
y rf 4 3 Delete page 3-82 (front), 3-83 (back) and page 3-84 y (front), 3-85 (back); change page numbers 3-86, 3-87, Yl t . 3-88, 3-89 and 3-90 to 3-83, 3-84, 3-85, 3-86 and
, 9 3-87 respectively.
5-1 5.1 Second paragraph, second line, change vertical wall
' thickness from "3-1/2 feet" to "3 ft-9 in."; third 1
Line, change dome thickness from "3 feet" to "3 ft-3 in."
5-12 5.1.2.7.2 First paragraph following Table 5-2, second line, i change "3-1/2 foot Reactor Building wall" to "3 ft-9 in. Reactor Building wall."
,q-4 1 (4- 29 -67)
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-- Filed With Amendment 3 g Section .
5-12 5.1.2.7.3 Fourth paragraph, second line, change "3-1/2 foot Reactor Building wall" to "3 f t-9 in. Recctor Building wall."
5-22 5.4 Fifth full paragraph on page, change the first sen-tence to read, " Provisions will . . . these penetra-tions, except for the main steam lines, may be pres-sure . . . operation."
7-5 7.1.2.1 Third full paragraph on page, first line, delete "three phase"; second line, change " drive assemblies" to read " drive clutch assemblies"; second line, change
" drive power supply" to read " drive clutch power sup-ply"; fifth line, change " drive power supplies" to ret.d " drive clutch power supplies"; last line, delete "three phase."
7-11 7 Delete all material on page 7-11, but retain sheet for page 7-12 on reverse side.
r' Figure 8 Change elevation of 500 kv Switchyard from "730" to (y] 8-2 "735."
~4-7 14.1.2.4.1 First paragraph following c., change the second sen-
,, % tence to read, "There are two additional pumps per
,0 unit."
4-26 14.2.2.2.3 Eighth line on page, change " valves" to " values."
SC-4 Appendix Fifth paragraph, third, fifth and sixth lines, change SC, 3.5 "
3f'"and"g6f'"to"3gf c "and"6pc,"
respeci0ely.
5D-14 Appendix After first sentence, first paragraph, add the follow-SD, 4.2 ing sentence: "The tensile strength of the splices will equal or exceed 125 per cent of the minimum yield strength for each grade of reinforcing steel as speci-fied in the appropriate ASTM standard."
5D-15 Appendix First full paragraph, last line, delete "of the appro-5D, 4.2 priate ASTM standard" and substitute "es stated above."
8.1-1 Supplement Change third paragraph to read, "The response spectra No. I curves for the maximum hypothetical earthquake are Question showt as attached Plates 1 through 4 of answer to 8.1 quest. ion 8.5 in Supplement No.1."
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Errata
[]./ Filed With Amendment 3 Page Section 9.7-2 Supplement In Table 1, Concrete Cover Over Reinforcing, change No. I the cover provided by Duke for the ducts for pre-Question stressed steel in the Cylinder Haunch and Cylinder 9.7 from (10" min.) and (12-1/2") respectively to (6")
, in both cases.
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DUKE POWER COMPANY AMENDMENT NO. 3 TO APPLICATION FOR LICENSES DOCKET NOS. 50-269 50-270 50-Additional information is submitted as Supplement 3 for the pur-pose of amending the Preliminary Safety Analysis Report to include Oconee Nuclear Station, Unit 3:
Front Back 3 -1 3-2 3-3 3-4 (3
.) 3-5 3-6 a
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' DUKE POWER COMPANY AMENDMENT NO. 3 TO APPLICATION FOR LICENSES DOCKET NOS. 50-269 50-270 50-Errata sheets and substitution and supplementary pages to portions of the Preliminary Safety Analysis Report.
Errata sheets , pages 1-3, for PSAR.
Substitution and supplementary pages as listed below:
Front Back Fig 1-6 -
Fig 1-9 -
2-3 2-4 3 -11 -
3-vi -
3-5 3-6 3-66 3-67 3-68 3-69 3-70 3-71
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3-73 3-74 3-75 3-76 3-77 3-78 3-79 3-80 3-81 3-82 Fig 3-51 Fig 3-52 Fig 3-57 Fig 3-58 Fig 3-59 Fig 3-60 Fig 7-2 -
SF-1 SF-2 SF-3 -
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