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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
[Table view] |
Text
(. ..
(J; DUKE POWER GOMPANY 9-P.O. BOX 33180 CHARLOTTE, N.C. 28242 HALB. TUCKER Turmenown vsos resernest (704) 3M534 suas4a emosemenom
{'
July 22, 1986 bc:
g..
.Dr. J.. Nelson Grace, Regional Administrator l U.S. Nuclear Regulatory Commission - Region II p l 101 Marietta Street, NW, Suite 2900 m Atlanta, Ga. 30323 -
e.a
\
Subject:
Oconee Nuclear Station Docket Nos. 50-269 ] , Unit 1
Dear Dr. Grace:
Pursuant to Oconee Nuclear Station Technical Specification 4.17.6(b), Duke Power !
Company (Duke) is providing the following information concerning the Oconee Unit I steam generator inservice inspection. The inservice inspection and tube plugging l operation for the current Unit I refueling outage was completed on March 7, 1986.
There were approximately 3,188 tubes inspected in the Unit 1 OTSG "A". For Unit 1 OTSG "B", there were approximately 8,012 tubes inspected. The eddy current testing was conducted from the inlet end of the generator and covered the entire length of the tube.
Please find attached (Attachments 1 and 2) lists of tubes located in Oconee Unit 1 OfSGs "A" and "B" respectively which have eddy current indications of tube wall degradation greater than or equal to 20% but less than 40%. Also attached (Attach-ments 3 and 4) are lists d tunes from the same OTSGs which have eddy current indications of tube wall degradation greater than or equal to 40% (the limit for plugging) and which have been plugged.
Very truly yours,
/P Hal B. Tucker PJN/48/jgm Attachments xc: Document Control Desk Ms. Helen Pastis U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. J.C. Bryant NRC Resident Inspector Oconee Nuclear Station 8611100414 860722 [Ig PDR g
ADOCK 05000269 PDR
O f*1C13*
1 1 wepmf i _ _ - - - - - - - - -
., , g Arv iiENT 1 OCONEE-1 A-OTSG i ALL TUBES WITH OD INDICATIONS 220% TW, BOBBIN COIL '
2/86 REFUELING OUTAGE !
l l
l ROW-COL OUTAGE ELEVATION INDICATION 7. TW i l
4- 4 2/06 RFO 14 OD (general) 43 47- 5 2/06 RFO 10 -
- 3. 40"' OD (general) 26 60- 2 2/06 RFO 14 00 (general) 30 66- 3 2/06 RFO 14 + '9.60" OD (general) 28 72- 9 2/06 RFO 14 OD (gwner al ) 41 72- 11 2/06 RFO 14 + 0.50" OD (general) 69 72-126 2/86 RFO 11 + 0.00" OD (general) 24 73- 9 O/86.RFO 14 -
W.59" OD (general) 41 136- 4 2/06 RFO 14 OD (general). 33 4
o i
_ ,. .,._m- .r..-.m. , _ _ . . - - _ . _ _ -
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, m
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k j HMENT 2 OCONEE-1 B-0TSG PAGE 1 OF 2 ALL TUBES WITH OD INDICATIONS >20% TW, BOBBIN COIL 2/86 REFUELING OUTAGE ROW-COL OUTAGE ELEVATION INDICATION 7. TW (7 3- 30 O/06 RFO 10 -
1.10" .OD (
(general) 22 4- 5 O/86 RFU 14 OD (general) 51 5- 7 O/06 RFO 13 OD general) 53 5- 26 O/86 RFO 10 OD (general) 53 7- 49 2/06 RFO 14 OD (general) 82 7- 52 2/06 RFO 14 OD (general) 60 8- 15 O/86 RFO 14 -
0.20" OD (general) 53 8- 17 2/06 RFO 10 -
1.30" OD (general) 42 9- 53 2/86 RFO 9 OD (general) 52 11- 3 O/86 RFO 8 OD (general) 71 13- 5 2/06 RFO 14 OD (general) 54 13- 72 O/86 RFO 14 OD (general) 66 14- 31 O/86 RFO O -
0.10" OD (general) 33 15- 69 2/06 RFO 14 + 0.40" OD (general) 44 17- 80 O/86 RFO 14 + 0.30" OD ( 32 18- 15 O/86 RFO 14 + 0.60" OD (general) 34 01- 50 O/86 RFO 10 OD (general) 59 OO- 28 O/86 RFO 14 + 0.40" 00 (general)
' general) 52 25- 89 O/86 RED 1_4 + 0. Stil" OD ~~2' 1 Eb 08- 72 2/86 RFO 14 OD (5eneral) 44 f08-72 2/06 RFO 14 OD (general) 60 34-101 2/06 RFO 14 + 0.50" OD (ganeral) 37 35- 88 O/86 RFO 14 + 0.10" OD (general) 53 37- 2 O/86 RFO 14 0D (general) 58 41-113 2/86 RFO 14 + 0.00" OD ( 32 1- 3 2/86 RFO 10 OD (general) 55 52-107 2/06 RFO 7 OD (general) 30
.50-107 2/86 RFO 7 + 0.90" OD (general) 50 53- 3 O/06 RFO 13 OD (generall 35 53- 4 O/06 RFO 13 + 0.10" OD (general) 71 58-107 O/06 RFO 12 OD (general) 56 58-107 O/86 RFO 14 + 0.50" OD (general) generall 53 60-128 O/06 RFO 14 + 0.30" OD (general) 44 61- 1 2/06 RFO 13 + 0.30" 00 (general) 08 63- 28 O/86 RFO 15 + 44.90" OD (general) 31 67- 7 O/86 RFO O + 0.40" OD (general) 31 68- 4 2/06 RFO 13 OD (general) 36 68- 7 O/86 RFO 13 OD (general) 62 71- 3 2/06 RFO 14 + 0.30" OD (general) 22
,71-108 O/86 RFO 14 OD (general) 53 72- 3 2/86 RFO 11 -
1.30" OD (general) 41
'. 7 2- 3 2/86 RFO 14 + 0.30" OD (general) 54 74-119 2/06 RFO 13 + 0.20" OD (general) 54 74-100 2/86 RFO 13 OD (general) 30 78-116 O/06 RFO 14 OD (general) 48 80-!!0 2/86 RFO 14 OD (general) 52 81-109 2/86 RFO 11 OD ( 51 86-126 2/06 RFO 14
.93-102 O/86 RFO 14 OD (general) general) 44 94- 10 2/86 RFO 14 + 0.30" OD (general) 31 94-126 2/86 RFO 14 00 (general) 43 95- 12 O/86 RFO 14 OD (general) 33 95- 13 O/06 RFO 14 OD (general) 29 104-117 O/06 RFO 10 -
1.50" OD (general) 33 105-120 O/86 RFO 14 + 0.30" OD (general) 55 106- 10 O/86 RFO 14 OD (general) 61 107- 9 O/86 RFO 14 OD (general) 33 109- 5 O/86 RFO 9 -
1.00" OD (general) 33 110-111 O/86 RFO 10 OD (general) 45 111- 1 2/86 RFO 12 OD (general) 24 116- 1 2/86 RFO 14 + 7.50" OD (general) 31 116- 5 2/86 RFO 5 OD (general) 29 116-105 2/86 RFO 9. OD (generall 30 It06-111 2/86 RFO 11 -
0.70" OD Wear / Thin 66
'106-111 2/06 RFO 13 -
0.70" OD Wear /Than 43 "196-110 O/06 RFO 11 -
0.80" OD Wear /Than 38 106-112 2/06 RFO 10 -
0.80" OD Wear /Than 45 s 106-112 2/86 RFO 13 -
0.80" OD Wear /Than 45 108-111 O/86 RFO 13 -
0.60" OD Wear /Than 31' 100-113 2/06 RFO 13 -
0.50" OD Weer/Than 37 ig8-114 '/86 RFO 13 -
0.60" OD Wear / Thin 37 1 0- 4 '5 / 8 6 F D - 14 OD (geneeel) 24 100- 57 2/06 RFO 7 OD (general) 4!
l 1
d .'
ATTACHMENT 2 CONT'D. .
OCONEE-1 B-OISG .
PAGE 2 OF 2 ALL TUBES WITH OD INDICATIONS 120% TW, BOBBIN COIL 2/86 REFUELING OUTAGE ROW-COL OUTAGE ELEVATION INDICATION 7. TW 122- 2 2/06 RFO 13 + 0.49" UD (
123- 4 2/06 RFO 3 OD (general) 24 24 135- 17 2/06 RFO 13 + 0.99" OD (general) general) 45 137- 17 2/86 RFO 10 + 9.7p" OD (general) 34 137- 18 2/86 RFO 19 OD ( 29 138- 29 2/06 RFO 9 -
1.60' OD (general) general) 52 141- 52 2/86 RFO 10 -
1.50" OD (general) 43 141- 65 2/86 RFO 3 + 0.29" OD (general) 43 142- 52 2/06 RFO 19 OD (general) 27 143- 14 2/86 RFO 9 OD (general) 26 145- 3 2/86 RFO 14 + 0.49" OD (general) 31 146- 5 2/86 RFO 15 + 45.49" OD ( 23 148- 34 2/06 FFO 14 + 9.80" OD (general) general) 25
p 0* ,
g CHtiENT 3 OCONEE-1 A-OTSG ALL TUBES REMOVED FROM SERVICE 2/86 REFUELING OUTAGE NO. -ROW COL
- 1. 4- 4
- 2. 72- 9
- 3. 72- 11
- 4. 73- 9 S
0
.-,r-- , - - . . - . . _ . - .,-.._y - , . . , . _ _ . . , ,
. - . . - . . __, , m,,,. .,. , _ _ _ _ , , , , _ , , ,
r:
J w D
krsACHHENT 4 o
OCONEE-1 B-OTSG ALL TUBES REMOVED FROM SERVICE 2/86 REFUELING OUTAGE NO. ROW COL
- 1. 4- 5
- 2. 5- 7
- 3. 5- 26
- 4. 7- 49
- 5. 7- 52
- 6. 8- 15
- 7. 8- 17
- 8. 9- 53
- 9. 11- 3
- 10. 13- 5
- 11. 13- 72
- 12. 15- 69
- 13. 18- 15
- 14. 21- 59
- 15. 22- 28
- 16. 25- 89
- 17. 28- 72
- 18. 35- 88
- 19. 37- 2
- 20. 51- 3
- 21.52-107
- 22. 53- 3
- 23. 53- 4
- 24.58-107
- 25.58-127
- 26.60-128
- 27. 68- 7
- 28.71-128
- 29. 72- 3
- 30. 72- 9
- 31.74-119
- 32.78-116
- 33.80-130
- 34.81-129
- 35.86-126
- 36.93-122
- 37.94-126
- 38. 95- 12
- 39. 105-122
- 40. 106- 10
- 41. 109- 5
- 42. 110-111
- 43. 120- 57
- 44. 135- 17
- 45. 138- 20
- 46. 141- 52
- 47. 141- 65 N
