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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 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 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 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 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 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 ML20107K5361996-04-18018 April 1996 Forwards Rev 4 to Util Security & Contingency Plan 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
[Table view] |
Text
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,s REGULATORYINFOhdbTIONDISTRIBUTIONSYSTEM' IDS)
-DISTRIBUT10N FOR XNCOMINO MATERIAL ._io - 2 0 '70/287 4
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,UB. JECT: LTR 1 ENCL 1
' 5PON:E TO ?RC"S LTR DTD 12/09/77.
FURNISHING INFO CONCERNING TEAM GENERATCR OPERATING HISTORY.
_1NT NAME: OCONEE - UNIT 1 REVIEWER INITI AL: XJM OCONEE - UNIT 2 DISTRIBUTER INITI AL:
OCONEE - UNIT 3
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(DISTRIBUTION CODE AOO1)
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DUKE POWER COMPANY Powsm Bt:sto No 4a2 SocTn Caracu STazzT. CitAHLOTTE. N. C. 28242 wiwau o. maa ca.sa. February 16,1978 s.cr p=cs.ocar *tttewowc: Aaca 704 src = paoovcoom f
, 73-4083 Mr. Edson G. Case, Acting Director , ,;~<- ~
Office of Nuclear Reactor Regulation } c-
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U. S. Nuclear Regulatory Commission Washington, D. C. 20555 3
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QC O' A
RE: Oconee Nuclear Station sj g Docket Nos. 50-269, -270, -287 An %-
Dear Sir:
In response to your letter of December 9, 1977 concerning steam generator operating history, please find attached the information requested with regard to the Oconee Nuclear Station.
Very truly yours, ,
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William O. Parker, Jr.
KRW:ge Attachments o\
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I780530010 u.___ - _ _ ______ -
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9 8 AIfACHMENT 1 OCONEE NUCLEAR STATION UNIT 1 STEAM GENERATOR HISTORY l
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OCONEE NUCLEAR STATION ,
UNIT 1 1
- 1. BASIC PLANT INFORMATION Startup Date: July 15, 1973 Utility: Duke Pcwer Company Location: Seneca, South Carolina Thermal Power Level: 2568 MWt NSSS Supplier: Babcock and Wilcox (B & W)
Number of Loops: 2 Steam Generator Supplier, Model No., Type: B & W, 177 FA, Once Through Steam Generator (OTSG)
Number of tubes per Generator: 15,530 Tube Size, Material: Alloy 600; 0.625" OD; 0.557" ID If, STEAM GENERATOR OPERATING CONDITIONS Normal Operation Inlet Temperature: 602.8'F Primary Pressure: 2200 psi Secondary Pressure: 925 psi Allowed Leak Rate: 0.3 gpm 6
Primary Flow Rate: 65.66 x 10 lb/hr Accidents
. Design Basis LOCA; Maximwn Delta-P: 925 psi Main Steam Line Break; Maximum Delta-P: 2200 psi y - -
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III. STEAM GENERATOR SUPPORT PLATE INFORMATION j = '
Material: SA 212 B Carbon Steel Design Type: Broached 1
5 Design Code: AS)2 III (through 1967) i Dimensions: 58.7" R, thickness 1.5" 6
Steam Flow Rate: 5.3 x 10 lb/hr i
j Tube Dimensions: 5/8" D (nominal) .
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IV. STEAM GENERATOR BLOWDOWN INFORMATION Oconee Nuclear Station's Once Through Steam Generators (OTSG) are not designed to perform normal blowdowns. There is no operational requirement to perform normal blowdownc. The steam generator sample line, however, i can provide a limited blowdown capability of 1 GPM during power operation.
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V. WATER CHEMISTRY SPECIFICATIONS A. Feedwater (Normal Power Operation)
J 10 ppb (max)
Total Solids Cation Conductivity 0.5 pmho/cm (max) l Dissolved Oxygen as 02 7 ppb (max) i Hydrazine as N 2Hg 1-25 ppb Silica-as SiO2 20 ppb (max)
Total Iron as Fe 10 ppb (max)
Total Copper as Cu 2 ppb (max) pH @ 77'F 9.3-9.6 Lead as Pb 1 ppb (max)
Feedwater (Startup*)
Total Iron as Fe 100 ppb (max)
Cation Conductivity 1.0 pmho/cm (max)
Dissolved Oxygen as 02 100 ppb (max)
Hydrazine 300% of stoichiometric 02
- Established prior to f a.eding OTSGs.
B. OTSG Water (Less Than 102 Steaming) pH 9.0-10.5 Cation Conductivity 10 umh em (mar)
Chloride 1.4 Jt. ~ .* pt )
Sodium 2.0 ppm (max)
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OTSG Water (Layup) 4 Ammonia as NH3 10 ppm (nominal) 2 ppm-20 ppm range ph @ 77'F 9.5-10.5 Hydrazine 200 ppm initial 50 ppm (min)
Sodium 1.0 ppm (max)
Cation Conductivity 10 pmho/cm (max)
C. Condenser Cooling Water Condenser Cooling Water is obtained from Lake Keowee. There are no demineralizers or cooling towers installed. The following is a table of representative chemistry values:
Calcium 2.2 ppm Magnesium 0.7 ppm Sodium 1.7 ppm Potassium -0.9 ppm Bicarbonate Alkalinity 13.6 ppm Sulfates 1.1 ppm l
Chlorides 0.6 ppm Phosphates <0.2 ppm Nitrates 0.1 ppm Free Carbon Dioxide .11.0 ppm
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Silica 6.1 ppm Total Iron 0.05 ppm Manganese 0.12 ppm
_pH 6.5-7.0 kN i
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9 VI. TURBINE STOP VALVE TESTING Turbine Stop Valve Testing had been performed on a daily basis from initial startup until February 1974, when weekly testing was initiated.
In July 1975, the testing frequency was returned to a daily basis for stop valves and weekly for the control valves. In March 1977 when it appeared that stop valve testing might possibly contribute to steam generator tube failure, the frequency was citanged back to monthly.
Frequency Actual: Monthly (maximum time between tests is 6 weeks)
Recommended: Daily (turbine vendor)
Monthly (steam generator vendor)
Pcwer Level Actual: 65 percent full power, or 94 percent full power if power reduction not desirable Recommended: 65 percent full power (steam generator vendor)
No recommendation (turbine vendor)
Testing Procedures Actual: Stroke Length - full - 8.5 inches
- to trip - 8.0 inches Stroke Rate - open to closed - 13 sec.
- closed to open - 27 sec.
Recommended: same as actual
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VII. STEAM GENERATOR TUBE DEGRADATION HISTORY INSERVICE INSPECTION RESULTS November 1974 A.
Initial Refueling Inservice Inspection Steam Generator 1A:
- umber of Tubes Inspected
- 573 (3.69%)
Number of tubes plugged: 0 Metalurgical Exam Results: No evidence of degradation in excess of 20%
Steam Generator 13:
Number of Tubes Inspected: 493 (3.171) 2 Number of Tubes plugged: 0 Metalurgical Exam Results: No evidence of degradation in excess of 20%.
B. March 1976 - 293 Effective Full Power Days (EFPD) since last refueling inspection r
Steam Generator lA Number of tubes inspected: 469 (3.02%)
Number of tubes plugged: 0 Metalurgical Exam Results: No evidence of degradation in excess of 20%
Steam Generator 1B Number of Tubes Inspected: 495 (3.19%)
Number of tubes plugged: 0 Metalurgical Exam Results: No evidence of degradation in.
excess of 20%
9-s C. August 1977 - 308 EFPD since last refueling inspection Steam Generator lA 4 4 Number of tubes inspected: 2500 (16.10%)
Number of tubes plugged prior to this ISI: 2 (.01%)
Number of tubes plugged this ISI: 5 (.03%)
Metalurgical Exam Results: All 5 tubes were in periphery region and exceeded degradation limits. All five tubes showed localized OD degradation with a maximum wall thinning of 60%. The defect area was at the 14th support plate. The tubes were 8-5, 117-107, 146-14, 147-11 and 7-4.
Steam Generator 1B Number of tubes inspected: 5004 (32.22%)
Number of tubes plugged prior to this ISI: 19 (0.1%)
Number of tubes plugged this ISI: 34 (0.22%)
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Metalurgical Exam Results:
'Al tubes were in the periphery region.
All tubes plugged showed localized OD degradation with a maximum wall thinning of almost 100%.
The defect area was at the 14th support plate except as noted:
88-122 (9th)64-125(1)99-125 138-68 68-127 37-4 100-124 51-123 75-121 (12th) 8-49 101-120 68-131(1)76-122 (12th)60-114 (12th) 101-122 43-108( }- 100-122 (13th)93-110 41-110 75-113 (14th) 62-11 16-71 9-51 (12th) 61-12 17-79 (13th) 8-48 7-32 (between 12th-13th)60-127 76-111 7-53 (11th)61-123 83-117 133-56 (11th)
(1)not plugged this ISI
( ) removed for further study Tubes 22-92, 133-57, and 79-2 were also plugged during this ISI for reasons other than exceedance of degradation limit.
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REGION IDENTIFICATION Region # Tubes Within Region
' Periphery of Bundle (1) 6806 (43.82%)
Tube Lane (2) 636 (4.09%)
Interior 8088 (52.08%)
Total 15,530 Allowed wall thinning before plugging = 40%
(1) Defined as tubes outside a 12 sided polygon connecting support rod positions (~20 rows)
(2) Within 5 rows of open tube lane i
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. A. October 31, 1976 R0-269/76-17 OTSG 1 A Number of tubes leaking 1 Number of additional tubes inspected 15 Total number plugged / removed 2 Summary a) Tube 77-17 plugged due to leakage b) Tube 77-18 also plugged B. December 8, 1976 R0-269/ 76-19 OTSG 1 B Number of tubes leaking 1 Number of additional tubes inspected 139 Number of tubes plugged / removed 4 Summary a) 114-109 plugged due to leakage at 14th support plate (SP) b) Tubes 113-110, 75-18, 113-115, also plugged C. January 15, 1977 R0-269/77-2 OTSG 1 B Number of tubes leaking 1 Number of tubes additional inspected 140 i
Number of tubes plugged / removed 2 Summary 4
a) Tube 75-12 plugged due to crack at upper support U
' plate b) . Tube 81-128 also plugged
. . . ) 9 D. February 28, 1977 R0-269/77-8 OTSG 1 B Number of tubes leaking 1 Number of additional tubes inspected ~3%
Number of tubes plugged / removed 6 Summary a) Tube 32-13 plugged due to leakage at 14th SP b) Tubes also plugged: 101-4, 33-14, 2-7, 77-25, 2-8.
c) Tube removed: 77-25 E. March 22, 1977 R0-269/77-17 OTSG 1 B Number of tubes leaking i Number of additional tubes inspected 100 Number of tubes plugged / removed 5 Summary a) Tube 77-25 identified as leaker (weld failure in old plug) b) Tubes also plugged: 77-3, 77-5, 77-8, 77-22, 77-29 F. May 7, 1977 R0-269/77-16 OTSG 1 B Number of tubes leaking 1 Number of additional tubes inspected 507 Number of tubes plugged / removed 3 Summary a) Tube 77-15 identified as leaker with crack 1/4" belou upper tube sheet b) Tube 17-5 also plugged c) Tube 75-18 removed
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-IX. CONDENSER INFORMATION As stated earlier in Section V of this report,-water from Lake Keowee is used to provide condenser cooling. Condenser tubes are made of 304 Stainless Steel. During operation, tube leakage is detected by secondary chemistry analysis for silica; a maximum of 20 ppb is allowed.
A search for a tube leak occurs whenever the silica concentration in the' secondary begins to increase.
Condensor tube leakage:
Date Remarks November 1974 2 tubes plugged
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X. RADIATION EXPOSURE WITH RESPECT TO STEAM GENERATORS Date Generator Dose (Exam & Repair) ( Comment:
11/74 A&B 44 First Refueling ISI 3/76 A&B 28.3 Second Refueling ISI 10/76 A 22 OTSG A leak 12/76 B 25 OTSG B leak 1/77 B 18.7 OTSG B leak 2/77 B 25.4 OTSG B leak 5/77 B 18 OTSG B leak 8/77 A&B 25.7 (exam) Third Refueling ISI 20.4 (repair)
Total A&B 391 (1) Dose in man-rem; testing and repair were not always separable.
XI. DEGRADATION GROWTH OTSG 1B Tube Number Location 2/76 1/77 5/77 9/77 90-124 14th S.P. -- --
20-30% 25-30%
113-112 14th S.P. -- --
30% 30%
81-128 14th S.P. 60%(l) 80% -- --
98-128 14th S.P. -- --
0% 35%
No evidence of real degradation growth in tubes90-124 and 113-112.
Tube 81-128 was plugged 1/77 and tube 98-128 is still in service.
EFPD between 2/76 - 1/77 is approximately 179.
EFPD between 5/77 - 9/77 is approximately 63.
(1) Computer evaluation techniques not available at time but tube was backchecked when 80% indication was observed.
There are no tubes with a degradation history in Steam Generator lA.
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J A ATTACIO!ENT 2 OCONEE NUCLEAP. STATION UNIT 2 STEAM GENERATOR HISTORY
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.J OCONEE NUCLEAR STATION-UNIT 2
- 2. BASIC PLANT INFORMATION Startup Date: September 9, 1974 Utility: Duke Power Company Location: Seneca, South Carolina Thermal Power: 2568 MWt NSSS Supplier: Babcock and Wilcox (B & W)
Number of Loops: 2 Steam Generator Supplier, Model No. , Type: B&W, 177 FA, Once Through Steam Generator (OTSG)
Number of tubes per Generator: 15,530 Tube Size, Material: Alloy 600; 0.625" OD; 0.557" ID II. STEAM GENERATOR OPERATING CONDITIONS Normal Operation Inlet Temperature: 602.8*F 6
Primary Flow Rate: 65.66 x 10 lb/hr Primary Pressure: 2200 psi Secondary Pressure: 925 psi Allowed Leak Rate: 1 gpm Accidents Design Basis LOCA; Maximum Delta-P: 925 psi Main Steam Line Break; Maximum Delta-P: 2200 psi
III. STEAM GENERATOR SUPPORT PLATE INFORMATION Material: SA 212 B Carbon Steel Design Type: Broached Design Code: ASME III (thru 1967)
Dimensions: 58.7"R, thickness 1.5" 6
Steam Flow Rate: 5.? x 10 lb/hr Tube Hole Dimensions: 5/8" D (nominal)
IV. STEAM GENERATOR BLOWDOWN INFORMATION Oconee Nuclear Station's Once Through Steam Generators (OTSG) are not designed to perform normal blowdowns. There is no operational requirement to perform normal blowdowns. The steam generator sample line, however, can provide a limited blowdown capability of 1 GPM during power operation.
V. WATER CHEMISTRY SPECIFICATIONS
- Water chemistry specifications for Unit 2 are the same as Unit 1, and are contained in Attachment 1,Section V.
VI. TURBINE STOP VALVE TESTING Turbine stop valve testing procedures for Unit 2 are the same as those for Unit 1 and are contained in Attachment 1,Section VI.
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. VII. STEAM GENERATOR DEGRADATION HISTORY INSERVICE INSPECTION RESULTS A. April 1976 - Initial Refueling Inspection Steam Generator 2A Number of tubes inspected: 479 (3.08%)
Number of tubes plugged prior to this ISI: 0 Number of tubes plugged this ISI: 0 Metalurgical Exam Results: No evidence of degradation in excess of 20%
Steam Generator 2B Number of tubes inspected: 476 (3.07%)
Number of tubes plugged prior to this ISI: 0 Number of tubes plugged this ISI: 0 Metalurgical Exam Results: No evidence of degradation in excess of 20%
B. August 1977 - 277 EFPD since last refmaling inspection Steam Generator 2A Number of tubes inspected: 506 (3.26%)
Number of tubes plugged prior to this ISI: 0 Number of tubes plugged this ISI: 0 Metalurgical Exam Results: No evidence of degradation in 1
excess of 20% l Steam Generator 2B Number of tubes inspected: 987 (6.36%)
i Number of tubes plugged prior to this ISI: 3 (.02%)
Number of tubes plugr,ed this ISI: 4 (.03%)
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- o Metalurgical Exam Results: Three tubes plugged were in-the lane region and one in the interior. Maximum degrada-tion was in excess of 40%. All were degraded at the 15th SP except the interior tube, which ras at the 12th SP.
The plugged tubes were: 75-5 uane 75-9 Lane 78-2 Lane 112-29 Interior REGION IDENTIFICATION Region # Tubes with Region Periphery of Bundle (1) 6806 (43.82%)
Tube Lane (2) 636 (4.09%)
Interior 8088 (52.08%)
Total 15,530 Allowed wall thinning before plugging = 40%
i (1) Define as tubes outside a 12 sided polygon connecting support rod positions ('20 rows) l (2) Within 5 rows of open tube lane.
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VIII. ABNORMAL OPERATIONAL EVENTS
. December 4, 1976 R0-270/76-15 OTSG 23 Number of tubes leaking 1 Number of additional tubes inspected 133 Number of tubes plugged / removed 3 Summag a) Tube 77-23 plugged due to leakage at upper tube sheet b) Tubes also plugged: 77-27, 124-42
, c) Tubes removed: 77-27, 77-23 IX. CONDENSER INFORMATION As stated earlier in Section V of this report, water from Lake Keowee is used to provide condenser cooling. Condenser tubes are made of
- 304 Stainless Steel. During operation, tube leakage is detected by secondary chemistry analysis for silica; a maximum of 20 ppb is allowed. A search for a tube leak occurs whenever the silica concen-tration in the secondary begins to increase.
Condenser tube leakage:
Date Remarks January 1975 2 tubes plugged i
X. RADIATION EXPOSURE WITH RESPECT TO STEAM GENERATORS Date Generator Dose (Exam & Repair)( Comments 4/76 A&B 2.1 First Refueling ISI 12/76 B 25 OTSG B leak
- j. 8/77 A&B 13.5 (exam) Second Refueling ISI 36.5 (repair) SOAK Instrumentation insertion 1 (2) and OTSG repair 1/78 B 11 OTSG B leak and SOAK removal 10/77 B 18 (exam) OTSG B leak Total A&B 106.1 (1) Dose in man-rem; examination and repair dosages could not always be separated.
l (2) SOAK (Second-Of-A-Kind) Flow-vibration instrumentation added for 1
additional information on possible causes of OTSG leakage.
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i XI. DEGRADATION GROWTH OTSG 2B Tube Number Location 12/76 6/77 75-5 15th S.P. 60% 85%
i 75-9 15th S.P. 40% 60%
75-14 15th S.P. 20% 20%
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- EFPD between 12/76 - 6/77 is approximately 180.
i Tube 75-5 has since been stabilized, tube 75-9 has been removed and 4
1 tube 75-14 is still in service.
There are no tubes with a degradation history in Steam Generator 2A.
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e ATTACHMENT 3 OCONEE NUCLEAR STATION LTIT 3 STEAM GENERATOR HISTORY l
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O D OCONEE NUCLEAR STATION UNIT 3 I. BASIC PLANT INFORMATION
-Startup Date: December 10, 1974 Utility: Duke Power Company Location: Seneca, South Carolina Thermal Power: 2568 MWt NSSS Supplier: Babcock & Wilcox (B & W)
Number of Loops: 2 Steam Generator Supplier, Model No. Type: B & W, 177 FA, Once Through Steam Generator Number of tubes per Generator: 15,530 Tube Size, Material: Alloy 600; 0.625" OD; 0.557" ID II. STEAM GENERATOR OPERATING CONDITIONS Normal Operation Inlet Temperature: 604*F 6
Primary Flow Rate: 65.66 x 10 lb/hr Primary Pressure: 2200 psi Secondary Pressure: 925 psi Allowed Leak Rate: 1 gpm Accidents Design Basis LOCA; Maximum Delta-P: 925 psi Main Steam Line Break; Maximum Delta-P: 2200 psi
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III. STEAM GENERATOR SUPPORT PLATE INFORMATION
. . Material: SA 212 B Carbon Steel
. Design Type: Broached Design Code: ASME III (thru 1967)
Dimensions: 58.7"R, thickness 1.5" 6
Steam Flow Rate: 5.6 x 10 lb/hr Tube Hole Dimensions: 5/8" D (nominal)
IV. STEAM GENERATOR BLOWDOWN INFORMATION Oconee Nuclear Station's Once Through Steam Generators (OTSG) are not designed to perform normal blowdowns. There is no operational requirement to perform normal blowdowns. The steam generator sample line, however, can provide a limited blowdown capability of 1 GPM during power operation.
V. WATER CHEMISTRY SPECIFICATIONS Water chemistry specifications for Unit 3 are the same as Unit 1 and are contained in Attachment 1,Section V.
VI. TURBINE STOP VALVE TESTING PROCEDURES Turbine Stop Valve Testing Procedures for Unit 3 are the same as those for Unit 1 and are contained in Attachment 1,Section VI.
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VII. STEAM GENERATOR DEGRADATION HISTORY A. November 1976 - Initial Refueling Inspection Steam Generator 3A Number of tubes inspected: 586 (3.77%)
Number of tubes plugged prior to this ISI: 0 Number of tubes plugged this ISI: 0 Metalurgical Exam Results: No evidence of degradation in excess of 20%.
Steam Generator 3B Number of tubes inspected: 489 (3.15%)
Number of tubes plugged prior to this ISI: 3 (0.02%)
Number of tubes plugged this ISI: 0 Metalurgical Exam Results: 4 tubes had degradation between 20-30%. No other tubes showed evidence of degradation in excess of 20%
B. October 1977 - 289 EFPD since last refueling inspection Steam Generator 3A Number of tubes inspected: 1090 (7.00%)
Number of tub 2s plugged prior to this ISI: 0 Number of tubes plugges this ISI: 0 Metalurgical Exam Results: No evidence of degradation in excess of 20%
Steam Generator 3B Number tubes inspected: 1090 (7.00%)
Number of tubes plugged prior.to this ISI: 20 (0.13%)
Number of tubes plugged this ISI: 0 Metalurgical Exam Results: 6 lane tubes had evidence of degradation between 20%-40% at the 15th SP but' were not plugged.
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. REGION IDENTIFICATION Region # Tubes With Region
- Periphery of Bundle (1) 6806 (43.82%)
Tube Lane (2) 636 (4.09%)
interior 8088 (52.08%)
Total 15,530 Allowed wall thinning before plugging 40%
(1) Defined as tubes outside a 12 sided polygon connecting support rod positions (~20 rows)
(2) Within 5 rows of open tube lane i
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l VIII. ABNORMAL OPERATIONAL EVENTS A. July 21, 1976 R0-287/76-10 OTSG 3B Number of tubes leaking 1 Number of other tubes inspected not available Number of tubes plugged / removed 3 Summary a) Tube 77-11 was plugged due to leakage about 10 feet below tube sheet.
b) Tubes 81-63, 37-6 were also plugged.
B. February 14, 1977 R0-287/77-2 OTSG 3B Number of tubes leaking 1 Number of other tubes inspected 142 Number of tubes plugged / removed 11 Summary a) Tube 77-19 was plugged due to leakage from crack at 15th SP b) Tubes 75-2 and 77-12 thru -21 were also plugged.
C. June 10, 1977 R0-287/77-8 OTSG 3B Number of tubes leaking 1 Number of other tubes inspected 133 Number of tubes plugged / removed 1 Summary a) Tube 78-1 was plugged due to leakage at 15th SP b) Leak rate was approximately doubled by mainsteam stop value test conducted while leak was monitored
I D. - ' July 14, 1977 R0-287/77-10 OTSG 3B Number of tubes leaking 1 Number of other tubes inspected 120 Number of tubes plugged / removed 2 Summary a) Tube 77-2 was plugged due to leakage at bottom of upper tube sheet b) Tube 77-1 was also plugged 1X. CONDENSER INFORMATION As stated earlier in Section V of this report, water from Lake Keowee is used to provide condenser cooling. Condenser tubes are made of 304 Stainless Steel. During operation, tube leakage is detected by secondary chemistry at.alysis for silica; a maximum of 20 ppb is allowed. A search for a tube leak occurs whenever the silica concen-tration in the secondary begins to increase.
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Condenser tube leakage:
, ,, , Date Remarks August 1976 Two tubes plugged october 1976 Identified cause of previou leakage as a broken bypass line support member causing steam to impinge directly on condenser tubes. Plugged approximately 150 tubes that were bent February 1977 One tube plugged April 1977 One tube plugged May 1977 Three tubes plugged December 1977 One tube plugged i
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