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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
.
U.S. NUCLE AD REOULATORY AMIS $ 4CN OOM ' ' """ E R NRC
- veau 195 tz m fa.2 c o J 2* )/ 2 r NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL TO: FROM: DATE OF OOCUMENT
~]ute Power Co:r)any 11/13/7S
- r. Benard C. '.usche Charlotte, l' orth Carolina OATE RECEIVED
'!r. Jillina 0 Parker, Jr. 11/13/76 KE TrE n ONOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED CORICINAL kUNC L AS$1FIE D One si;.ed co,y KCoPy DE SCRIP TION ENCLOSU RE l l
Ltr. r our 3/12/76 ltr. . . . trans the f o l louine,: Concerns susceptability Of station operation and equipment to degraded ; rid volta;;e l condi tions . I t> 1
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(L-P) (13-P)
A.-
PIANT NAME:
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Oconee Units 1 '!-3 av .v _ . . . . _
SAFETY
~
FOR ACTION /INFORMATION ENVTRn l l / L , / 7 UL l lIEIEED AD: '
ASSIGNED AD!
g BRANdH CHIEF: Sch"encer BRANCH cifTEF?
PROJECT MANAGER: Cech '
PROJECT MANAGER!
'LIC. ASST.: Shevard LIC. ASST.!
. INTERN AL DISTRIBUTION NkG FIIF) SYSTEMS SAFETY PT. ANT SYSTEMS SITE SAFETY &
Y NRC PDR _
HEINEMAN TFnpsen ENVIRO ANALYSIS
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SCHROEDER BENAROYA DENTON & MUT T.FR
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~X GOSSICK & STAFF ENGINEERING IPPOLITO ENVIRO TECH _
MIPC MACCARRY f KIRKV00D FRNST CASE KNIGitT I BALLAPB
_.}MNAUER SIlMEIL OPERATING REACTORS SPANCLER
_JMRLESS PAWLICKI STELLO 9TTP TFf'ff .
PROJECT MANAG_EMENT REACTOR SAFETY OPERATING TECH. CAMMILL !
~BOYD ROSS X. EISENHUT
~
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X P. COLLINS NOVAK SHA0 HULMAN HOUSTON ROSZTOCZY X BAER - -
PETERSON CHECK M BUTLER (3) SITE ANALYSIS i MELTZ V QRJ"ES VOLIliElt
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SKOV110LT K J. COLLIN3 .i iRUTRERG MRFCFR l EX TEHNAL DISTRillUTION CONTHOL NUMBER X 1.PDR : 'a l ,a t : a , .; . c. . _ NA r IAB: BR00VitAENj%T LAB '
TIC: REG. VIE ULRMSON(ORNL) g)(NSIC:_ LA PDR ggg ASLB CONSilLTANTS ,
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er DUKE POWER COMPANY Powen Detto No 422 Socin Cuence Srazzi, Cuant.oTTE. N. C. asa42 w i t u ^u o. a^ a a t a. a a. November 15, 1976
'/'Cr Pots.ctut TE Ep*ONE:Anta 704 SrCa Pocowc':o= 373-4083 Mr. Benard C. Rusche, Director
\ ,4 \ \ ; a Office of Nuclear Reactor Regulatit.1 $
U. S. Nuclear Regulatory Commission I, Washington, D. C. 20555 km -
Attention: Mr. A. Schwencer P I i
Re: Oconee Nuclear Station Docket Nos. 50-269, -270, -287 gc
Dear Sir:
In response to your letter dated August 12, 1976, a study of the Oconee
- 7uclear Station has been conducted to determine the susceptability of station operation and equipment to degraded grid voltage conditions. A summary of the results of this study which specifically address those concerns described in your letter is attached.
Ver truly yours, N C._4 U . hML --
William O. Parker, Jr.
]
MS f: ge ,
Attachment a
/
Z'?g 1.;. .se
E OCONEE NUCLEAR STATION i OEPTABILITY 10 DEGRADED GRID VC AGE I. I NTRODUCT I ON In response to the Request for Information relative to the potential implications of the events which occurred at the Millstone Unit No.
2, July 5, 1976, the Oconee Class IE electrical distribution system has been evaluated to determine if the operability of safety-related equipment, including associated control circuitry and instrumentation, can be adversely affected by short term or long term degradation in
- grid system voltage. Our evaluation has been directed toward identifying all possible voltage conditions (i.e., normal and degraded) that can exist on the plant auxiliary system and to comparing equipment operating limits to these voltage conditions.
II. EVALUATION !
l The following evaluation of the Oconee Class IE electrical distribution system addresses items I through 3 of the Request for Information. The
)
item numbers referred to in our response are identical to the item numbers in your Request for informatson.
Response to item 1.a: Plant auxiliary systems (safety-related and non-safety related) will be supplied by of fsite power during plant refueling, plant startup, plant shut-down, and abnormal trip of the )
unit. The estimated fraction of normal plant operating time in '
which plant auxiliaries arc supplied by offsite power is approximately 16 %.
Response to item 1.b: Offsite power is supplied by Duke's 230KV transmission system. The normal operating range for the grid system voltage at Oconee is between 227KV and 217KV. The corresponding operating range at the 4.16KV safety-related buses is between 4240V and 3940V. It should be noted that these voltage ranges were established on t he basis of observed voltages over a period of several months under various plant / system operating conditions.
Response to item 1.c: Figure i shows a one-line diagram of the Oconee Unit 3 auxiliary system and was the basis of our analysis of voltage profiles throughout the auxiliary system. Since the auxiliary systems for Units 1 and 2 are similar to Unit 3, the results of our analysis are also applicable to these units. Under offsite power conditions transformer CT3 supplies 4)60V Main Feeder Buses I and 2 which in turn supply 4I60V Engineered Safeguard Switchgear Buses 3TC, 3TD, and 3TE. These safeguard buses supply non-safety related loads (i .e.,
Load Centers 3XI, 3X4, 3X2, 3X5, 3X3, and 3X6) and the three safety-related Load Centers 3X8, 3N1, and 3X10. Since the normal operating range (i.e., 227KV to 217KV) for the grid system voltage is below the nominal 230KV system voltage, startup transformer CT3 is set on the 218,500 volt tap in order to optimize voltage profiles throughout the auxiliary system. All load center transformers as shown in Figure I are set on nominal taps. In order to determine the voltage profiles at the safety-related buses for full load and no load conditions and the range of normal grid voltages defined above, computer studies were run for the following two cases:
CASE 1: With the grid voltage assumed operating at 227KV and the auxiliary system under minimum loading conditions, the voltage profiles for the safety-related buses were calculated.
This case provides the highest expected voltages of 4252/613/212V.
on the safety-related buses for the highest normal operating grid voltage. It should be noted that since the no load condition does not practically exist on the auxiliary system the condition of minimum loading during cold shut-down has been used instead.
Figure 2 sunnarizes the results of this case.
CASE 2: With the grid voltage assumed operating at 217KV and the auxilia ry system under maximum loading (i .e., full load) conditions, the voltage profiles for the safety-related buses were calculated. This case provides the lowest expected voltages of 3802/548/189V. on the safety-related buses for the lowest normal operating grid voltage. Figure 2 summarizes the results of this case.
For all other possible auxiliary system loading conditions with the 230KV grid system operating between 227KV and 217KV, the voltage profiles for the safety-related buses will be within the range established by Case I and Case 2 defined above.
Response to item 1.d-Under normal conditions the Oconee Unit 3 auxiliary loads are carried by the Unit 3 generator through transformer 3T as shown in figure 1. Under this condition, transformer 3T supplies 4160V Main Feeder Buses 1 and 2 in the same manner as transformer CT3 described in response to item 1.c. The normal operating range for the generator terminal voltage is 18.94KV to 17.68KV. In analyzing the voltage profiles at the safety-related buses, computer studies were run for normal generator operating voltages D.e., Cases 3 and 4) as defined above and for degraded conditions (i.e., Cases 5 and 6) requi ring generator trip. The case studies are as follows:
CASE 3: With the generator voltage at its normal maximum value of 18.94KV and the auxiliary system under minimum loading conditions corresponding to the condition of the unit tied to the transmission system and urider load, the voltage profiles for the safety-related buses were determined. This provides the highest expected voltages of 4397/633/219V on the safety-related buses for the highest normal generator operating voltage. Figure 3 summarizes the results of this case.
CASE 4: With the generator voltage at its normal minimum value of 17.68KV and the auxiliary system under maximum loading conditions, the voltage profiles for the safety-related buses were determined. This provides the lowest expected voltages of 3978/573/198V on the safety-related buses for the lowest normal generator operating voltage. Figure 3 sunmarizes the results of this case.
CASE 5: With the generator voltage assumed at the overvoltage setpoint of 19.91KV requiring generator trip and the auxiliary system under minimum loading conditions corresponding to the condition of the Unit tied to the transmission system and under load, the voltage profiles for the safety-related buses were dete rmi ned. This provides the highest possible operating voltages of 4626/667/250V on the safety-related buses with the generator voltage at the overvoltage setpoint of the Volts /
Hertz protective relaying. Figure 4 summarizes the results of this case.
CASE 6: With the 230KV transmission system operating at its normal minimum value of 217KV and with the generator assumed operating in a degraded loading condition (i .e., under-excited condition) corresponding to the loss-of-excitation relay setpoint, the vol tage profiles (i .e. 3952/569/197v) for the safety-related buses were determined. Figure 4 summarizes the results of this.
Response to item 1.e: Figure i shows the sensor locations for the undervoltage relaying for switching power to the safety-related buses, in addition, the 230KV switchyard is equipped with redundant undervoltage and underfrequency logic designed to detect severe system undervoltage and underfrequency conditions.
The undervoltage trip setpoints for the safety-related switching systems are as follows:
UV Point Trio Setpoint 1 68% voltage (Time Delay = 5.0 sec.)
2 68% voltage (Time Delay = 5.0 sec.)
3 68% voltage (Time Delay = 5.0 sec.)
4 68% voltage (Time Delay = 5.0 sec.)
5 68% voltage (Time Delay = 5.0 sec.)
6 68% voltage (Time Delay = 5.0 sec.)
7 55% voltage (Time De lay = 5.0 sec.)
8 55% voltage (Time Delay = 5.0 sec.)
The setpoints for the 230KV switchyard system are as follows:
Undervoltage: 68% voltage (Time Delay = 6.0 sec.)
Underfrequency: 57 Hertz (Time Delay = 15 cycles)
The basis for the above undervoltage settings is to detect sudden and complete loss of power conditions with sufficient time delay to ride over voltage transients.
Response to item 1.f: The maximum 230KV system voltage of 227KV is normally attained when all three Oconee generators are running and supplying MVARS to the 230KV transmission system. Steady-state transmission voltages in excess of 227KV cannot exist at the Oconee switchyard without a significant change in our system generation MVAR output. Therefore, the 227XV system voltage and auxiliary system loading defined in Case 1 (see response to item 1.c. and Figure 2) provide the maximum safety-related bus voltages under of fsite power conditions. There is no overvoltage trip when the auxiliaries are operating on offsite power through the startup transformers.
As could be concluded from our response to item 1.e., the relay undervoltage setpoints can theoretically allow line voltages below 68% to exist on the safety-related buses. However, studies of our 230KV transmission system have indicated that sustained steady-state voltages at 68% are impossible because the Duke system would have experienced load-shedding and system separation at voltages {
considerably higher than 68% resulting in the switchyard under- )
frequency relays isolating the switchyard and starting the Keowee emergency units to supply power to the safety-related buses. Our minimum steady-state 230KV system voltage of 217KV is normally
- experienced when all three Oconee generators are disconnected from ,
the transmission system. The 217KV system voltage and auxiliary i system loading defined in Case 2 (see response to item 1.c. and Figure 2) provide the minimum safety-related bus voltage under j offsite power conditions. l l
Response to item 1.q: The following is a definition of the voltage i
ranges over which safety-related and non-safety related components !
can operate continuously in the performance of their design function:
Component Limiting Voltage Range Motors' 4000 V 4400/3600V.
575 V 633/518V.
200 V 220/180V.
Limitorque Values 575 V 633/518V.
200 V 220/180V.
Motor Controllers 600 V 185% (510V.) ,
208 V > 85% (177V . )
As can be seen, the voltage ranges defined for motor continuous operation are the most restrictive operating conditions and, therfore, establish the bounds of continuous system operation. As defined in Cases 1 through 4 (see Figures 2 and 3) the maximum and minimum auxiliary system voltages are within the operating bounds established by the voltage ranges defined above. Therefore, all safety-related loads, including related control circuitry and instrumentation, will perform their safety functions as required.
Response to item 1.h: The voltage monitorinj and voltage alarms available in the control room for the Oconee Class IE Power Distribution System are as described below:
- 1. 4KV Distribution System (See Figure 6 for identification of monitor points)
A. Annunciators Annunciators alarming undervoltage conditions are provided for the following:
1 Normal Source .
- 2. Start-up Source
- 3. Standby Bus #1 4 Standby Bus #2
- 5. Main Feeder Bus #1
- 6. Main Feeder Bus #2
- 7. Standby Source from Keowee
- 8. Standby Source from Lee B. Computer Digital Computer points monitoring undervoltage conditions are provided for the following:
- 1. Normal Source
- 2. Start-Up Source
- 3. Standby Bus #1
- 4. Standby Bus #2
- 5. Main Feeder Bus #1
- 6. Main Feeder Bus #2 Analog computer points indicating voltage conditions are provided for the following:
- 1. Main Feeder Bus #1
- 2. Main Feeder Bus #2
- 3. Switchgear Group ITC 4 Switchgear Group ITD
- 5. Switchgear Group ITE C. Voltmeters Control room voltmeters are provided to monitor voltage on the following:
- 1. Normal Source
- 2. Start-Up Source
- 3. Main Feeder Bus #1 4 Main Feeder Bus #2 S. Standby Source from Keowee l
- 6. Standoy Source from Lee
- 2. 600V Essential Load Centers A. Annunciators Annunciators are provided which will alarm an undervoltage condition on any of the 600V Essential Load Centers.
- 3. 600/208V E:sential Motor Control Centers i
A. Annunciators Annunciators are provided which will alarm on loss of power to any of the 600 or 208 volt Essential Motor Control Centers.
Response to item 2: The load shedding feature of the Oconee Emergency Power System was designed to shed non-essential loads from the 4KV essential power system prior to the initiation of automatic transfers to the standby buses. Whenever an automatic transfer to the standby buses is initiated the load shed logic sheds non-essential loads by means of redundant logic circuits which actuate redundant trip coils of the breakers to be shed.
Because of the ample capacity of the standby sources at Oconee, no sequencing of Engineered Safeguards loads is requi red. Since sequencing is not required, no shedding of essential loads is necessary. The re fore ,
the load shed feature sheds only non-essential loads and is maintained l throughout the event.
l in summary, since the load shed feature has no direct interface with '
the essential loads, there is no potential for a condition similar to that experienced at Millstone 2.
Response to item 3: The Oconee switchyard is protected by the ;
redundant undervoltage and underfrequency logic system. This system j provides blackout and underfrequency protection by automatically j separating the generating units from the transmission system in the event of adverse system conditions. The setpoints for this system are defined in our response to item 1.e.
The three generating units are each rated for 1038 MVA at a .90 power factor. However, the maximum output power is 886 MW. The generating units at Oconee are dispatched to maintain the 230KV switchyard within the normal range of 217KV and 227KV.
Plant operating procedures and controls and instrumentation are provided to assure the facility is being operated as required by system conditions.
III. CONCLUSIONS Study of Cases I through 6 Indicate that all except Case 5 provide acceptable operating voltages on both safety and non-safety related buses. However, Case 5 and Case 6 represent degraded generator
, operating conditions that would require a malfunction I . the generator exciter-regulator system in order to be realized. The resulting abnormal generator MVAR loading would be quickly detected by station operators and steps taken to correct these operating conditions.
All pertinent combinations of operating conditions have been evaluated for the Oconee auxiliary system. Voltage conditions similar to that which occurred at Millstone are not typical of or applicable to our Occ.iee Station.
IV. PROPOSED ACTIONS Although an event similar to that which occurred at Millstone is not !
credible at Oconee, the undervoltage relays on the Emergency Power i System will be set at 88% (3660V) to ensure that minimum voltage required for continuous operation of non-safety and safety-related equipment under any postulated degraded condition. This action will be l completed by March 1, 1977 As discussed in our response to item 1.e.,
the time delay for these relays is approximately five seconds. This will eliminate short duration voltage transients from causing spurious trips and ensure that degraded undervoltages are detected before they can ad-versely affect safety-related loads. l l
Figure 5 shows the results of Case 7 which provides the voltage profiles on the safety-related buses under degraded offsite power conditions corresponding to the proposed undervoltage relay setpoints of 88% (3660V).
This Case demonstrates that voltages below the continuous operating limits of the safety-related loads cannot exist without causing a trip and assumption of all essential loads by the emergency standby buses.
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FIGURE 2 - CASE 1 AND 2 Voltage Profiles on Safety-Related Buses under norraal of fsi te power condi tions o
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FIGURE 3 - CASE 3 AND 4 Vol tage Profiles on Safety-Related Buses under normal unit power conditions
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HOTE: The dotted lines represent the bounds of continuous equipment operation, a FIGURE 4 - CASE 5 AND 6 Voltage Profiles on Safety-Related Buses under degraded unit .ower conditions
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FIGURE 5 - CASE 7 Voltage Profiles on Safety-Related Buses under degraded offsi te power conditions corresponding to undervoltage trip setpoint.
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