|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML17355A4601999-10-26026 October 1999 Forwards Revised Epips,Including Revs to 0-EPIP-1102, 0-EPIP-1212,0-EPIP-20110,0-EPIP-20111,0-EPIP-20132, 0-EPIP-20133 & 0-EPIP-20201,per 10CFR50.54(q) & 10CFR50, App E.Epip 0-EPIP-20107,has Been Deleted ML17355A4301999-10-0808 October 1999 Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included ML17355A4461999-10-0404 October 1999 Notifies NRC of Change in Commitment to Perform Periodic Testing of Critical Welds & Parts on Special Lifting Devices IAW NUREG-0612.Use of Ae Technology Will Provide Same Level of Testing Quality as Did NDE Methods Noted in ANSI Std L-99-208, Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included1999-10-0404 October 1999 Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included ML17355A4291999-10-0404 October 1999 Forwards Response to NRC Telcon Questions Re License Amend Request Dtd 990727,proposing Amend on one-time Basis to Modify TS 3.8.1.1 & TS 3.4.3 & 3.5.2 to Extend Allowed Outage Time for EDG from 72 H to 7 Days ML20212M1601999-09-28028 September 1999 Refers to 990908 Engineering Meeting Conducted at NRC Region II to Discuss Engineering Issues at Lucie & Turkey Point Facilities.List of Attendees & Copy of Presentation Handout Encl ML17355A4251999-09-22022 September 1999 Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820 ML17355A4111999-09-0909 September 1999 Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08 ML17355A4131999-09-0707 September 1999 Forwards Revised Relief Request 20 Re Requirement to Perform Exams as Required by IWL-2524 & IWL-2525,Table IWL-2500-1 for Exempt Tendon Insp,Per Recent Discussions with NRC ML17355A4141999-09-0202 September 1999 Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830 ML17355A4041999-08-23023 August 1999 Forwards Info to Support Assessment of Potential Risks Associated with Proposed Civil Aircraft Operations at Former Homestead Air Force Base to FP&L Turkey Point Nuclear Facility Units 3 & 4 ML17355A4071999-08-23023 August 1999 Informs That FPL Has Completed Review of Info Listed in Reactor Vessel Integrity Database,Version 2 & Found Listed Discrepancies,Re Closure of GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. ML17355A4061999-08-23023 August 1999 Forwards Semiannual FFD Performance Rept for Period of Jan- June 1999,for Turkey Point Units 3 & 4.List of Events Reported & Summary of Mgt Actions Taken,Included ML17355A4001999-08-20020 August 1999 Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance ML17355A3941999-07-27027 July 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01 ML17355A3871999-07-16016 July 1999 Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17355A3851999-07-14014 July 1999 Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of Rept ML17355A3711999-07-0606 July 1999 Forwards Revised EPIPs 0-EPIP-20201, Maintaining Emergency Preparedness - Radiological Emergency Plan Training & 0-EPIP-20126, Off-Site Dose Calculations. with Summary of Changes ML17355A3591999-06-30030 June 1999 Forwards Turkey Point,Unit 4 ISI Rept. Listed Repts Are Encl.No Eddy Current Exams Scheduled for Unit 4 Steam Generators ML17355A3661999-06-30030 June 1999 Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998 ML17355A3571999-06-28028 June 1999 Informs That Util Voluntarily Reporting Facility Readiness as Outlined in Suppl 1 to GL 98-01.Encl Is Y2K Readiness Disclosure for Units 3 & 4,reporting Status of Facility Y2K Readiness ML17355A3521999-06-18018 June 1999 Forwards Response to NRC 990415 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML17355A3491999-06-0404 June 1999 Forwards Summary of Corrective Actions Implemented by FPL Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions. ML17355A3441999-05-27027 May 1999 Modifies FPLs Consent to Confirmatory Order to Reflect Resolution of Four Issues Identified as Pending in L-99-031 ML17355A3451999-05-24024 May 1999 Requests Waiver of 520 Hours (13 Wks) Required Parallel Watchstanding in Control Room Prior to License Application Submittal for W Conley ML17355A2921999-04-22022 April 1999 Forwards Rev 35 to Turkey Point EP & Revised EPIP 0-EPIP-20101, Duties of EC, Per Requirements of 10CFR50, App E & 10CFR50.54(q).Summary of Changes,Encl.Implementation Date for Both Documents Was 990330 ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML17355A2891999-04-0909 April 1999 Forwards Relief Request 20, Exempt Tendon Insp, Requesting Relief from ASME Section XI Code,1992 Edition,Paragraph IWL-2521.1(c) Which Requires That Each Exempted Tendon Be Examined IAW IWL-2524 & IWL-2525.Approval Needed by 991001 ML17355A2861999-04-0505 April 1999 Forwards COLR for Turkey Point Unit 4,Cycle 18,IAW TS 6.9.1.7 ML17336A0681999-04-0101 April 1999 Expresses Support for FP&L Request for Waiver of Applicable Review Fees Upon FP&L Submittal of an Application for License Renewal for Turkey Point Units 3 & 4 ML17355A2751999-03-25025 March 1999 Informs NRC & Staff of Fp&Ls Plans to Submit License Renewal Application for Turkey Point Units 3 & 4 by End of Dec 2000 ML17355A2641999-03-19019 March 1999 Requests Changes to FPL Official Service List for Turkey Point,Units 3 & 4.Add s Franzone & Remove G Hollinger from All Correspondence ML17355A2651999-03-19019 March 1999 Forwards Annual Radioactive Effluent Release Rept for Jan-Dec 1998 & Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point,Units 3 & 4. ML17355A2621999-03-16016 March 1999 Forwards Special Rept as Result of Turkey Point Unit 3 End-of-Cycle 16 ISI of SG Tubes.Rept Summarizes Results of SG Tube ISI ML17355A2631999-03-12012 March 1999 Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit ML20204C6991999-03-10010 March 1999 Requests Amend to Turkey Point PSP to Modify Requirement to Post Security Officers to Provide Continuous Observation of Entire PA Perimeter in Event of Security Computer Failure. Change to Security Force Staffing Level Also Requested ML17355A2451999-03-0909 March 1999 Submits Info on FPL Current Levels of Nuclear Property Insurance,Per 10CFR50.54(w)(3) ML17355A2501999-03-0808 March 1999 Informs That Licensee Reviewed NRC 990228 Ltr Issuing Exemption Requested Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg.Tabulated Summary of Util Comments & Marked Copy of NRC Ltr & SER Encl ML17355A2441999-03-0101 March 1999 Provides Update to Util Written Notices,Dtd 961120 & 970627 of Claim Involving Alleged Bodily Injury Arising Out of or in Connection with Use of Radioactive Matl at Units 3 & 4 ML17355A2431999-02-25025 February 1999 Informs That FPL Does Not Have Any Candidates from Turkey Point Scheduled to Participate in 990407,Generic Fundamentals Examination (GFE) ML17355A2301999-02-18018 February 1999 Forwards Semiannual Fitness for Duty Performance Data for Period of 980701-981231 for Turkey Point Units 3 & 4 ML17355A2361999-02-18018 February 1999 Forwards Tabulation of 1998 Occupational Exposure Data for Turkey Point,Units 3 & 4,per TS 6.9.1.2.a.Reactor Coolant Specific Activity Limits of 100/E-bar Mci Per Gram of Gross Radioactivity Were Not Exceeded During 1998 L-99-042, Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3)1999-02-18018 February 1999 Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3) ML17355A2341999-02-18018 February 1999 Provides Response to RAI Re GL 97-01, Degradation of Crdm/ CEDM Nozzle & Other Vessel Closure Head Penetrations. ML17355A2231999-02-0808 February 1999 Informs That Util Will Comply with Commitment with Respect to Units 3 & 4,in Response to Ja Zwolinski 990129 Ltr.Util Also Agrees to Incorporate Commitment Into Confirmatory Order Modifying License Effective Immediately Upon Issuance ML17355A2031999-01-29029 January 1999 Forwards Rev 3 to Turkey Point Nuclear Plant Recovery Plan. Rev Does Not Decrease Effectiveness of Plan ML17355A2171999-01-20020 January 1999 Forwards Listed ISI Repts for Turkey Point Unit 3,in Accordance with Provisions of ASME Code,Section XI ML17354B2241999-01-0606 January 1999 Forwards Annual 10CFR50.46 Rept Re Changes To,Or Errors Discovered in ECCS Evaluation Models,Or in Application of Such Models That Effect Peak Clad Temp Calculation ML17354B2081998-12-15015 December 1998 Informs That Fpl,In Cooperation with State of Fl & County Emergency Response Agencies,Will Conduct Exercise of Turkey Point Radiological Emergency Plan on 990210.Scenario Package Forwarded to Emergency Preparedness Section Chief,Region II ML17354B2091998-12-15015 December 1998 Forwards Price Anderson Guarantees Annual Financial Rept,Per 10CFR140.21.Exhibit 1 Submitted to Satisfy Annual Financial Reporting Requirement of 10CFR50.71(b) 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17355A4601999-10-26026 October 1999 Forwards Revised Epips,Including Revs to 0-EPIP-1102, 0-EPIP-1212,0-EPIP-20110,0-EPIP-20111,0-EPIP-20132, 0-EPIP-20133 & 0-EPIP-20201,per 10CFR50.54(q) & 10CFR50, App E.Epip 0-EPIP-20107,has Been Deleted ML17355A4301999-10-0808 October 1999 Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included ML17355A4461999-10-0404 October 1999 Notifies NRC of Change in Commitment to Perform Periodic Testing of Critical Welds & Parts on Special Lifting Devices IAW NUREG-0612.Use of Ae Technology Will Provide Same Level of Testing Quality as Did NDE Methods Noted in ANSI Std L-99-208, Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included1999-10-0404 October 1999 Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included ML17355A4291999-10-0404 October 1999 Forwards Response to NRC Telcon Questions Re License Amend Request Dtd 990727,proposing Amend on one-time Basis to Modify TS 3.8.1.1 & TS 3.4.3 & 3.5.2 to Extend Allowed Outage Time for EDG from 72 H to 7 Days ML17355A4251999-09-22022 September 1999 Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820 ML17355A4111999-09-0909 September 1999 Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08 ML17355A4131999-09-0707 September 1999 Forwards Revised Relief Request 20 Re Requirement to Perform Exams as Required by IWL-2524 & IWL-2525,Table IWL-2500-1 for Exempt Tendon Insp,Per Recent Discussions with NRC ML17355A4141999-09-0202 September 1999 Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830 ML17355A4041999-08-23023 August 1999 Forwards Info to Support Assessment of Potential Risks Associated with Proposed Civil Aircraft Operations at Former Homestead Air Force Base to FP&L Turkey Point Nuclear Facility Units 3 & 4 ML17355A4071999-08-23023 August 1999 Informs That FPL Has Completed Review of Info Listed in Reactor Vessel Integrity Database,Version 2 & Found Listed Discrepancies,Re Closure of GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. ML17355A4061999-08-23023 August 1999 Forwards Semiannual FFD Performance Rept for Period of Jan- June 1999,for Turkey Point Units 3 & 4.List of Events Reported & Summary of Mgt Actions Taken,Included ML17355A4001999-08-20020 August 1999 Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance ML17355A3941999-07-27027 July 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01 ML17355A3871999-07-16016 July 1999 Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17355A3851999-07-14014 July 1999 Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of Rept ML17355A3711999-07-0606 July 1999 Forwards Revised EPIPs 0-EPIP-20201, Maintaining Emergency Preparedness - Radiological Emergency Plan Training & 0-EPIP-20126, Off-Site Dose Calculations. with Summary of Changes ML17355A3591999-06-30030 June 1999 Forwards Turkey Point,Unit 4 ISI Rept. Listed Repts Are Encl.No Eddy Current Exams Scheduled for Unit 4 Steam Generators ML17355A3661999-06-30030 June 1999 Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998 ML17355A3571999-06-28028 June 1999 Informs That Util Voluntarily Reporting Facility Readiness as Outlined in Suppl 1 to GL 98-01.Encl Is Y2K Readiness Disclosure for Units 3 & 4,reporting Status of Facility Y2K Readiness ML17355A3521999-06-18018 June 1999 Forwards Response to NRC 990415 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML17355A3491999-06-0404 June 1999 Forwards Summary of Corrective Actions Implemented by FPL Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions. ML17355A3441999-05-27027 May 1999 Modifies FPLs Consent to Confirmatory Order to Reflect Resolution of Four Issues Identified as Pending in L-99-031 ML17355A3451999-05-24024 May 1999 Requests Waiver of 520 Hours (13 Wks) Required Parallel Watchstanding in Control Room Prior to License Application Submittal for W Conley ML17355A2921999-04-22022 April 1999 Forwards Rev 35 to Turkey Point EP & Revised EPIP 0-EPIP-20101, Duties of EC, Per Requirements of 10CFR50, App E & 10CFR50.54(q).Summary of Changes,Encl.Implementation Date for Both Documents Was 990330 ML17355A2891999-04-0909 April 1999 Forwards Relief Request 20, Exempt Tendon Insp, Requesting Relief from ASME Section XI Code,1992 Edition,Paragraph IWL-2521.1(c) Which Requires That Each Exempted Tendon Be Examined IAW IWL-2524 & IWL-2525.Approval Needed by 991001 ML17355A2861999-04-0505 April 1999 Forwards COLR for Turkey Point Unit 4,Cycle 18,IAW TS 6.9.1.7 ML17336A0681999-04-0101 April 1999 Expresses Support for FP&L Request for Waiver of Applicable Review Fees Upon FP&L Submittal of an Application for License Renewal for Turkey Point Units 3 & 4 ML17355A2751999-03-25025 March 1999 Informs NRC & Staff of Fp&Ls Plans to Submit License Renewal Application for Turkey Point Units 3 & 4 by End of Dec 2000 ML17355A2641999-03-19019 March 1999 Requests Changes to FPL Official Service List for Turkey Point,Units 3 & 4.Add s Franzone & Remove G Hollinger from All Correspondence ML17355A2651999-03-19019 March 1999 Forwards Annual Radioactive Effluent Release Rept for Jan-Dec 1998 & Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point,Units 3 & 4. ML17355A2621999-03-16016 March 1999 Forwards Special Rept as Result of Turkey Point Unit 3 End-of-Cycle 16 ISI of SG Tubes.Rept Summarizes Results of SG Tube ISI ML17355A2631999-03-12012 March 1999 Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit ML20204C6991999-03-10010 March 1999 Requests Amend to Turkey Point PSP to Modify Requirement to Post Security Officers to Provide Continuous Observation of Entire PA Perimeter in Event of Security Computer Failure. Change to Security Force Staffing Level Also Requested ML17355A2451999-03-0909 March 1999 Submits Info on FPL Current Levels of Nuclear Property Insurance,Per 10CFR50.54(w)(3) ML17355A2501999-03-0808 March 1999 Informs That Licensee Reviewed NRC 990228 Ltr Issuing Exemption Requested Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg.Tabulated Summary of Util Comments & Marked Copy of NRC Ltr & SER Encl ML17355A2441999-03-0101 March 1999 Provides Update to Util Written Notices,Dtd 961120 & 970627 of Claim Involving Alleged Bodily Injury Arising Out of or in Connection with Use of Radioactive Matl at Units 3 & 4 ML17355A2431999-02-25025 February 1999 Informs That FPL Does Not Have Any Candidates from Turkey Point Scheduled to Participate in 990407,Generic Fundamentals Examination (GFE) ML17355A2341999-02-18018 February 1999 Provides Response to RAI Re GL 97-01, Degradation of Crdm/ CEDM Nozzle & Other Vessel Closure Head Penetrations. L-99-042, Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3)1999-02-18018 February 1999 Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3) ML17355A2361999-02-18018 February 1999 Forwards Tabulation of 1998 Occupational Exposure Data for Turkey Point,Units 3 & 4,per TS 6.9.1.2.a.Reactor Coolant Specific Activity Limits of 100/E-bar Mci Per Gram of Gross Radioactivity Were Not Exceeded During 1998 ML17355A2301999-02-18018 February 1999 Forwards Semiannual Fitness for Duty Performance Data for Period of 980701-981231 for Turkey Point Units 3 & 4 ML17355A2231999-02-0808 February 1999 Informs That Util Will Comply with Commitment with Respect to Units 3 & 4,in Response to Ja Zwolinski 990129 Ltr.Util Also Agrees to Incorporate Commitment Into Confirmatory Order Modifying License Effective Immediately Upon Issuance ML17355A2031999-01-29029 January 1999 Forwards Rev 3 to Turkey Point Nuclear Plant Recovery Plan. Rev Does Not Decrease Effectiveness of Plan ML17355A2171999-01-20020 January 1999 Forwards Listed ISI Repts for Turkey Point Unit 3,in Accordance with Provisions of ASME Code,Section XI ML17354B2241999-01-0606 January 1999 Forwards Annual 10CFR50.46 Rept Re Changes To,Or Errors Discovered in ECCS Evaluation Models,Or in Application of Such Models That Effect Peak Clad Temp Calculation ML17354B2081998-12-15015 December 1998 Informs That Fpl,In Cooperation with State of Fl & County Emergency Response Agencies,Will Conduct Exercise of Turkey Point Radiological Emergency Plan on 990210.Scenario Package Forwarded to Emergency Preparedness Section Chief,Region II ML17354B2091998-12-15015 December 1998 Forwards Price Anderson Guarantees Annual Financial Rept,Per 10CFR140.21.Exhibit 1 Submitted to Satisfy Annual Financial Reporting Requirement of 10CFR50.71(b) ML17354B2061998-12-0909 December 1998 Informs That Request for Exemption Specified in Section II.B.3 Will Not Be Needed Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg ML17354B1981998-11-25025 November 1998 Forwards Scope & Objective for 1999 Plant Annual Emergency Preparedness Exercise.Objectives Developed in Conjunction with State & Local Govts.Exercise Scheduled for 990210 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML17348A5661990-09-14014 September 1990 Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule. ML17348A5461990-09-0707 September 1990 Forwards 1990 Inservice Insp Refueling Outage Summary Rept of NDE Activities 900206-0404 First Refueling Outage Second Period Second Insp Interval. ML17348A5501990-09-0707 September 1990 Forwards Jul 1990 Integrated Schedule Regulatory Rept for Facilities ML17348A5521990-09-0606 September 1990 Forwards Matrix of Changes to Emergency Power Sys That Affect Revised Tech Specs Issued on 900828.Matrix Sent for Info & to Assist in NRC Review of No Significant Hazards Rept for Revised Tech Specs ML17348A5431990-08-31031 August 1990 Forwards Objectives for 901108 Emergency Plan Exercise. Exercise Will Involve Participation by Local Emergency Response Agencies & State Emergency Response Personnel & Will Not Be Evaluated by FEMA ML17348A5361990-08-27027 August 1990 Forwards Turkey Point Units 3 & 4 Semiannual Radioactive Effluent Release Rept,Jan-June 1990 & Health Physics Procedure HP-48, Process Control Program for Dewatering Radwaste Liners. ML17348A5171990-08-24024 August 1990 Forwards Ref Matl in Preparation for Operator License Exams Scheduled for Wk of 901029,per NRC 900628 Request ML17348A5041990-08-17017 August 1990 Forwards fitness-for-duty Program Performance Data for Jan-June 1990 ML17348A5051990-08-15015 August 1990 Forwards Monthly Operating Repts for Jul 1990 for Turkey Point Units 3 & 4 & Revise Rept for June 1990 for Unit 3 ML20059B0111990-08-14014 August 1990 Requests That Encl Intervenor Motion for Extension of Time to Appeal to Docketing & Svcs Branch Re Tech Spec Replacement Hearing Be Provided.Motion Inadvertently Omitted in Svc of Request on 900813 ML17348A4971990-08-10010 August 1990 Responds to Violations Noted in Insp Repts 50-250/90-18 & 50-251/90-18.Corrective Actions:Unit Stabilized in Mode 3, Operating Surveillance Procedures 3/4-OSP-089 Revised & Event Response Team Formed ML17348A4701990-07-27027 July 1990 Forwards Rept Detailing Investigative Analysis of Unsatisfactory Blind Specimen Results,Identification of Causes & Corrective Actions Taken by Lab to Prevent Recurrence,Per Unsatisfactory Performance Testing L-90-282, Forwards Rev 23 to Physical Security Plan.Plan Withheld (Ref 10CFR73.21 & 2.790)1990-07-25025 July 1990 Forwards Rev 23 to Physical Security Plan.Plan Withheld (Ref 10CFR73.21 & 2.790) ML17348A4281990-07-25025 July 1990 Forwards Decommissioning Financial Assurance Repts for Plants,Per 10CFR50.33(k) & 50.75(b) ML17348A4691990-07-23023 July 1990 Forwards Addl Info on Emergency Power Sys Enhancement Project Re Load Sequencer,Programmable Logic Controllers & Implementation of Sys in Plant,Per NRC 900705 Request ML17348A4191990-07-20020 July 1990 Advises That Comments on NRC Safety Evaluation Re Implementation of Station Blackout Rule Will Be Provided by 900921 ML17348A4201990-07-20020 July 1990 Forwards Revised No Significant Hazards Determination for Proposed Tech Specs 1.17 & 3.0.5 & Bases,Per 890605 Ltr ML17348A4141990-07-20020 July 1990 Responds to Violations Noted in Insp Repts 50-250/90-14 & 50-251/90-14.Corrective Actions:Breakers Closed,Returning Monitoring Sys to Operable Level & Briefings Held to Explain Rvlms Sys Theory to Operations Control Room Personnel ML17348A4171990-07-19019 July 1990 Forwards May 1990 Integrated Schedule Regulatory Rept for Plant ML17348A4121990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. ML17348A4251990-07-17017 July 1990 Withdraws 900207 & 0424 Proposed Changes to Tech Specs Re Util Nuclear Review Board Composition IR 05000250/19900131990-07-16016 July 1990 Provides Info Re Plant Implementation of 10CFR50.44 & NUREG- 0737,Item II.E.4.1 Re Hydrogen Recombiners,Per 900518 Meeting & Insp Repts 50-250/90-13 & 50-251/90-13.Agreement Re Use of External Recombiners Will Be Reactivated ML20055G8641990-07-16016 July 1990 Informs ASLB That Petitioners Ref to Several Telephone Contacts Between J Butler & M Gutman,Of ATI Career Training Inst Is Inadvertent Misstatement & Should Be Changed to Telephone Contact. W/Certificate of Svc ML17348A4161990-07-16016 July 1990 Responds to Commitment Re Reverse Testing of Containment Isolation Valves Per Insp Repts 50-250/90-13 & 50-251/90-13. Corrective Action Plan Addresses Penetrations 16 & 53 for Unit 3 Only & Penetrations 11,47,54A & 54B for Both Units ML17348A4151990-07-16016 July 1990 Provides Info Re Plant Implementation of 10CFR50.44 & NUREG- 0737,Item II.E.4.1 Re Hydrogen Recombiners,Per 900518 Meeting & Insp Repts 50-250/90-13 & 50-251/90-13.Agreement Re Use of External Recombiners Will Be Reactivated ML17348A4041990-07-12012 July 1990 Forwards Addl Info Re Responses to NRC Questions on Piping Codes Used for Emergency Power Sys Enhancement Project ML17348A3921990-07-12012 July 1990 Summarizes Facility Performance Since Last SALP Evaluation Period Which Ended 890731.Util Pursued Aggressive self- Assessment Program,Including Significant Internal or Outside Assessments in Areas of Operator Performance & EOPs L-90-261, Forwards Rev 7 to Guard Training & Qualification Plan.Rev Withheld1990-07-11011 July 1990 Forwards Rev 7 to Guard Training & Qualification Plan.Rev Withheld L-90-259, Forwards Rev 22 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(a)(3))1990-07-11011 July 1990 Forwards Rev 22 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(a)(3)) ML17348A4321990-07-11011 July 1990 Forwards Rev 8 to Updated FSAR for Turkey Point Units 3 & 4. Rev Includes Activities Completed Between 890123 & 900122. Rept of Changes for Jul 1989 Through June 1990 Will Be Provided by 900901 ML17348A3941990-07-0909 July 1990 Forwards Requested Addl Info Re Emergency Power Sys Enhancement Project.Specific Detailed Changes Will Be Made to Procedures to Address Mods Affecting Equipment Relied Upon for Safe Shutdown ML17348A3881990-07-0505 July 1990 Requests Audit of NRC Records to Independently Verify Reasonableness of Charges Assessed Against Util,Per 10CFR170 Svcs ML17348A4311990-07-0505 July 1990 Documents Written & Verbal Request of Region II Personnel for Temporary Waiver of Compliance of Tech Spec 3.4.2.b.1 Re Allowable Out of Svc Time for One Emergency Containment Cooler from 24 H to 72 Hr W/Addl Reasons ML17348A3851990-07-0303 July 1990 Responds to NRC Ltr Re Violations Noted in Insp Repts 50-250/90-08 & 50-251/90-08.Corrective Actions:Training Dept Increased Emphasis on Radiological Postings in Radiation Worker Training ML17348A3711990-07-0303 July 1990 Responds to NRC 900524 Request for Addl Info on Emergency Power Sys Enhancement Project ML17348A3671990-07-0303 July 1990 Confirms Util Intentions Not to Operate Beyond Refueling Outage That Represents Last Outage Re NRC Bulletin 89-001 ML17348A3841990-06-29029 June 1990 Forwards LER 90-11 on 900609 Re hi-hi Steam Generator Water Level Turbine Trip & Subsequent Reactor Trip Due to Failure of Switch in Feedwater Valve Controller Hand/Auto Station. W/O Encl ML17348A3601990-06-29029 June 1990 Responds to Generic Ltr 89-04, Guidance on Developing Acceptable Inservice Testing Programs. Test Procedures Developed & Under Mgt Review Reflecting Revised Inservice Testing Program ML17348A3621990-06-28028 June 1990 Notifies That Senior Operator License SOP-20177-2 Will Be Terminated,Effective 900731 ML17348A3651990-06-28028 June 1990 Advises That Completion of safety-related motor-operated Valve Testing & Surveillance Will Be Completed by June 1990, Per Generic Ltr 89-10 Requirements ML17348A3591990-06-27027 June 1990 Responds to Violations Noted in Insp Repts 50-250/90-09 & 50-251/90-09.Corrective Actions:Specialist Counselled on Importance of Stopping Procedure When Steps Conflict W/ Condition of Plant & Procedure Use Guidelines Reviewed ML17348A3641990-06-27027 June 1990 Responds to Generic Ltr 90-04, Status of Licensee Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions. ML17348A3861990-06-27027 June 1990 Advises That New Date for Submittal of Response to Insp Repts 50-250/90-09 & 50-251/90-09 Is 900702 ML17348A3551990-06-21021 June 1990 Responds to NRC Bulletin 88-010, Nonconforming Molded Case Circuit Breakers. Five Untraceable Circuit Breakers Installed in Unit 3 safety-related Sys.All Five Breakers Replaced W/Traceable Breakers ML20055D9201990-06-20020 June 1990 Advises That Sp Frantz Will Represent Licensee in Argument Scheduled for 900710.Certificate of Svc Encl ML17348A3181990-06-19019 June 1990 Forwards Final Rept of Inservice Insp NDE of Unisolable Piping Sys & Components for Potential Thermal Stress Effects for Turkey Point Nuclear Power Plant, Per NRC Bulletin 88-008 ML17348A2981990-06-12012 June 1990 Forwards Rev 16 to Topical QA Rept. ML17348A2871990-06-0808 June 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor/Darling Model S350W Swing Check Valves or Valves of Similar Design. Bolt Replacement Performed ML17348A2861990-06-0808 June 1990 Advises That Info Re Operating History of Select Fuel Assemblies Sent to ORNL Between 900419 & 26,per 900510 Request ML17348A2781990-06-0404 June 1990 Forwards Emergency Power Sys Enhancement Project Repts, Reflecting Current Design Info 1990-09-07
[Table view] |
Text
REGULA 'RY INFORMATION'DISTRIBUTI SYSTEM (RIDSi ACC) SS ION NBR".80 1'2240430 DOC ~ DATE: 80/12/18 NOTARIZED; NO DOCKET FA$ 'fL:50-250 Turkey Point Pl anti Uni t 3R Fl or ida Power and Light C S0-2S1 BYNAME Turkey Point Planti Unit 4E Florida Power and Light 'C AUTH AUTHOR AFFILIATION UHRIGER.E. Florida Power 8 Light Co.
RECI'P ~ NAME RECIPIENT AFFILIATION VARGApS,A,~ . Operating Reactors Branch 1
SUBJECT:
Forwards addi info re distribution sys vol tagesiin response to NRC 800819 tr.Since safety injection signal initiates 1
automatic fast transfer from auxiliary transformer to startup transformer<only connection via startup anal.yzed, DISTRIBUTION CODE: AO IBS COPIES:RECEIVED:LTR TITLE: Onsite Emergency Power Systems ENCL ~
~
SIZE:~ 'P NOTES:
RECIPIENT COPIES RECIPIENT COPIES Io CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENC'L ACTION: VARGA:E S ~ 04 7 7 INTERNAL: AEOD 1 GEN ISSUES BR13 1 1 I8,C SYS BR 09 1 1 I 8'E 06 2 2 MPA 18 1 1 NRC PDR 02 1 1 OELD 17 1 1 OP EX EVAL BRil 1 1 OR A SS BR 12 1 1 POlt(ER SYS BR 14 1 1 tR F ILt 01 1 1 EXTERNAL: ACRS 16 ib 16 LPDR 03 NSIC 05 1 1
'0 80 logy TOTAL NUMBER OF COPIES REQUIRED: LTTR 37 ENCL 37
FLORIDA POWER da LIGHT COMPANY December 18, 1980 L-80-411 Office of Nuclear Reactor Regulation Attention:. .Mr S. A. Varga, Chief Operating Reactors Branch IIIl Division of Operating Reactors U. S. Nuclear Regulatory Commission
.Washington, D. C. 20555
Dear Mr- Varga:
Re:. Turkey Points 'Units 3 8 4 Docket Nos. 50-250 .8 50-251 Adequacy of Station, Distribution S stem Volta es Florida 'Power 8 Light Company's response to a NRC letter dated August 19, 1980, requesting additional information on the above subject is attached.
Very truly yours, Robert E. Uhrig Vice President Advanced Systems 8 Technology REU/PLP/ras Attachment cc: J. P. O'Reilly, Region II Harold F. Reis, Esquire ll3i<'e'8'I 833lh83SHOll.":
38N SA
"'J Lf%5 53";fh%:.
tsol~ASi BESlQ G3AY~333 PEOPLE... SERVING PEOPLE
I'n response to NRC letter to FPL dated August 19, 1980 Y], e: Request for Additional Information, Tux'key Point Units 3 & 4 Adequacy of Station Electric Distribution System (dated July 1, 1980)
Reference:
- 1) NRC letter to FPL dated August 8, 1979
- 2) FPL letter to NRC dated November 9, 1979 This response addresses the NRC's request for Additional Information enclosed in the NRC letter to FPL dated August 9, 1980. Clarification of. assumptions and specific voltage analysis results are provided herein. Also provided is information requested concerning loading configurations that require greater than the minimum expected steady-state grid voltage in order to start all safety loads simultaneously.
Guideline 1 (Reference 1) requires that separate voltage analyses be performed, for each connection to offsite power" ...assuming the need for electric power is initiated by (1) an anticipated transient (e.g. unit trip) or (2) an accident, whichever presents the largest load demand situation." At Turkey Point, the largest load demand situation occurs under an accident condition wherein a safety injection signal starts all safety loads simultaneously. In accordance with Guidelines 3 and 5, all automatic actions by the electrical system are assumed to occur as designed. Therefore, since a safety injection signal initiates an automatic fast transfer 'from the auxiliary transformer to the start-up transformer, only the connection to offsite power via the start-up transformer was analyzed.
In order to obviate the need to repeatedly calculate the voltage at the terminals of each safety load for each case analyzed, as implied by Guidelines 6 and 7 (Reference 1), FPL chose to calculate the minimum voltage at each bus required to start each safety load. The highest minimum required voltages calculated for each bus are listed in Attachment A. If the voltage analysis results (above) are higher than those minimum values, then sufficient voltage would exist at the terminals of all safety loads to assure their successful start.
The requirements of Guideline 6 (Reference 1) were addressed in the second and third paragraph of page 2 of our November 9, 1979 response (Reference 2). As stated therein, the minimum expected steady-state grid voltage at Turkey Point is 235 KV and the maximum is 244 KV.
All low vol'tage AC (less than 480V) Class IE busses supplying power to vital instrument or control circuits at Turkey Point are powered by inverters supplied from the 125 VDC batteries. Being independent of offsite power, these busses are not included in the voltage analyses. The heat tracing system is the only safety related equipment powered from busses less than 480V. Since the heat tracing is a purely resistive load, voltage variations vill affect the heat output of the system. llowever, the voltages calculated in the analyses provided herein will have little or no effect on the performance of the heat tracing system because the voltages resulting from these. analyses are the worst momentary voltages that could occur upon start of all safety loads simultaneously. As the starting motors accelerate, the voltages would increase. On this basis, voltage variations due to motors starting is not considered to have any adverse impact on Class IE equipment powered from busses less than 480V.
though Turkey Point is a multi-unit station, the voltages analysis suggested by Guideline 2 (Reference 1) was not performed since the connections to offsite power for Units 3 and 4 are independent of each other and would, therefore, not be different from those provided herein.
In addition to the assumptions contained in the above discussion, the five assumptions listed in our November 9, 1979 response (Reference 2) apply to all cases analyzed. Also, in all cases, no manual load shedding was assumed.
In accordance with Guidelines 3 and 5, tripping of the Steam Generator Feedwater Pumps was assumed since this occurs automatically on a Safety Injection Signal. Unique assumptions for each case analyzed involve which Condensate Pumps, Component Cooling Water Pumps, and Intake Cooling Water Pumps are assumed running at the time of the accidents Two out of three of each of these pumps are normally running, but only the A and B pumps receive a start signal on safety injection actuation. This results in various combinations of starting and running loads as reflected in Attachment B. Attachment C provides the results of the voltage analyses for each case on each unit.
In order to provide assurance that no safety loads could experience excessive voltage (Guideline ll, Reference 1) calculations were performed assuming one-half normal load on the 480V busses, minimum pumps running on the 4KV busses, and maximum voltage (244KV) on the grid. The results are presented in Attachment D.
Since no calculated voltage is in excesses of 10% of the equipment nameplate (460V or 4000V), the results are considered satisfactory.
In accordance with the subject NRC Request, additional voltage analyses were performed assuming all safety loads have started and are running, and the largest non-Class IE motor is started. (Motor operated valves are assumed to have completed their action} Because the 7000 HP Steam Generator Feedwater Pumps it
~
are tripped off on a Safety Injection Signal, is possible that an operator could re-start a pump after the safety loads are running (although such action in not per procedure) and is not required for safe shutdown). Only two cases for each unit were analyzed:
Case 2 (Attachment B), which results in the highest load on the "A" train, was assumed when starting the "A" Steam Generator Feed-water Pump.
Case 13 (Attachment B) which results in the highest load on the "B" train, was assumed when starting the "B" Steam Generator Feedwater Pump.
The results of these analyses are tabulated in Attachment E. Also tabulated are the bus voltages required to maintain minimum guaranteed starting voltages at the running safety equipment terminals. (These voltages are based on voltage drops due to full load current. Attachment A voltages are based on voltage drops due to starting currents). Only in the case where the 38 Steam Generator Feedwater Pump is started does an analyzed voltage fall below the required voltage. In this case, HCCD is less than 1.8. volts low. Since the equipment is capable of starting and running at the required voltage, it is reasonable to assume that running equipment will continue to run at the analyzed voltage during the starting of the Steam Generator Feedwater Pump.
In any event, the voltages do not decrease sufficiently to cause starters or contactors to drop out. On this basis, the results of these analyses are considered satisfactory.
1;) order to verify the accuracy of the voltage analyses, voltage and current measurements were made at all Class IE busses. A voltage analyses was then performed using the measured loads and'he resulting voltages compared with the measured voltages. The close correlation between the measured and calculated values (less than 3% difference) provides assurance that the mathematical model used in the voltage analyses is accurate.
In response to Items 5 and 6 of the subject NRC request for Additional Information, the loading configurations that require greater than the cases 13 and 14 in and result in the calculated'us voltages provided for those cases in Attachment C for Unit 3 only. The operators at Turkey Point have been instructed to avoid operation under these loading configurations. If, due to equipment malfunction, the plant is required to be operated in one of these configurations, the operators have been instructed to ensure that the switch-yard voltage remains above that .which analyses indicate is sufficient to safely start all safety equipment. If, while operating in one of these loading configurations, the switchyard voltage decreases below the analyzed safe voltage for, that configuration, the operators are instructed to,decrease the unit's output and thus lower the demand on the electrical system. Such "reduction of loading" as quoted in Item 6 of the subject:NRC request does not imply manual load shedding in that no motor or, equipment is shutdown,.
The reduction of load on the electrical auxiliary system is due to lower power required by the various process pumps in the plant. However, as stated in our letter of November 9, 1980, a design modification is in progress,to add undervoltage relay protection to the 4160V and 480V load center. This modification, will eliminate the need for administrative restrictions on operation of the plant.
In response to Item 4 of the subject NRC request, please refer to our response to NRC letter to FPL dated July 26, 1979 attached to FPL letter to NRC dated November 9, 1979 (Reference 2).
The review requested by Item 2 of the subject NRC request is contained in Chapter 8 of the Turkey Point FSAR.
A tachment A Page 1 of 1 HIGHEST iilININUllVOLTAGES RE UIRED TO START SAFETY LOADS Unit 3 4KV Bus 3A 3214.4V 4KV Bus 3B 3213.5V 480V Load Center 3A None starting 480V Load Center 3B None starting 480V Load Center 3C None starting 480V Load Center 3D None starting 480V HCC 3A 381.4V 480V iICC 3B 392.2V 480V i~lCC 3C 399.9V 480V >jcc 3D . 398.3v Unit 4 4KV Bus 4A '215.8V 4KV Bus 4B 3213.4V 480V Load Center 4A None starting 480V Load Center 4B None starting 480V Load Center 4C. None starting 480V. Load Center 4D None starting 480V >1CC 4A 402.9V 480V i~lCC'4B 396.7V 480V;lCC 4C 393.1V
Attachment B Page 1 of 1 L ADING CONFIGURATIOiVS In all loading configuration cases listed below, the Safety Injection Pumps and RHR Pumps (1 each per 4KV bus) are assumed to start and the Heater Drain Pumps (1 per bus), Turbine Plant Cooling Mater Pumps (1 per bus), circulating Mater Pumps (2 per bus), and the Reactor Coolant Pumps (1 on A bus, 2 on B bus) are assumed to be running. The Steam Generator Feedwaeer Pumps are tripped off upon Safeey Injection Signal. The running and starting loads on the 480V load centers and motor conerol centers do not vary between, cases analyzed. The cases listed below apply equally to Unit 3 and Unit 4.
Case Condensate A B Pumps C
+ Comp. Cooling Water Pumps +
B~: C Ai'i'c Intake Cooling Water
'
Pumps +
OFF RUN RUN START RUN RUN START',., .:,.RUN,!;,RUN, ;,
. .
RUiV OFF RUN START RUN RUN START RUN RUN OFF RUiN RUN RUN START RUVi START RUN RUN RUN OFF RUN RUVi START RUN START RUN RUN OFF RUN RUN RUN RUN OFF START RUN RUN RUN OFF RUiN RUN RUN OFF START RUN RUiV OFF RUN RUN START RUiN RUiV RUN START RUN RUN OFF RUiV START RUN RUN RUN START RUiV OFF RUiV RUiV RUN START RUN RUN START RUN 10 RUN OFF RUN RUiV START RUN RUN START RUN OFF RUiN RUN RUN OFF RUN START RUN 12 RUN OFF RUiV RUN RUiV OFF RUiV START RUiV OFF RUN RUiV 'TART RUN RUN RUN RUN OFF 14 RUN OFF RUN START RUN RUN RUN RUiV OFF OFF RUiV RUN 'UN START RUN RUN RUN OFF 16 RUVi OFF RUN RUiV START RUN RUN RUN OFF OFF RUN RUiV RUN RUiV OFF RUN RUiV OFF 18 RUN OFF RUiV RUN RUiN OFF RUN RUiV OFF
+ Two out of three normally running Pumps start automatically on S.I.S. if not already running.
Attachment C Page 1 of 18 VOLTAGE ANALYSIS RESULTS CASE 1 UNIT 3 UNIT 4 BUS VOLTAGES (Grid at 235'V) 4KV Bus A* 01 4KV Bus A** q q. s8tq 4KV Bus B'+
4KV Bus B:"~ 3851 3861 480V LC A 432 417 480V LC B 422 423
'80V LC C 419 432 480V LC D 430 428 480V NCC A 430 480V /ICC 403 407 430 B'80V NCC C 480V NCC D 405
~High - side of current limiting reactor
- Low-side, of current limiting reactor
+Not on Unit 4
Attachment C Page 2 of 18 VOLTAGE ANALYSIS RESULTS CASE 2
'k UNIT 3 UNIT 4 BUS VOLTAGES (Grid at 235 KV) 4KV Bus A* 3 03 38 8 4KV Bus A** . 3786 3781 F,
i 4KV Bus B* 3944 3953 4KV Bus B** 3876 3888 480V LC A 429 415 480V LC B 425 426 480V LC C 416 480V LC D 433 432 480V HCC A 427 408 480V HCC B 406 418 480V'CC C 404 427 480V'?ICC D 409
<<High side of current limiting reactor
- Low-side. of current limiting reactor
+Not on Unit 4
Attachment C Page 3 of 18 VOLTAGE ANALYSIS RESULTS CASE 3 UNIT 3 UNIT 4 BUS VOLTAGES (Grid at 235 KV) 4KV Bus A* 3953 3951 4'us A** 3864 3862 4KV Bus B* 3894 3901 4KV Bus B** 3797 3807 480V LC A 438 480V LC B 480V LC C 42 4 480V LC D 423 422 480V Mcc A 436 480V MCC B 397 409 480V >>CC C 413 436 480V MCC D 399
- High side of current limiting reactor
- Zaw-side of current limiting reactor
~ +Not on Unit 4
Attachment C Page 4 of 18 VOLTAGE ANALYSIS RESULTS cAsE 4 UNIT 3 UNIT 4 BUS VOLTAGES (Grid at,235 KV) 4KV, Bus A* 3 36 4KV Bus A** 3839 3837 4KV Bus B* 3913 3919 4KV Bus B** 3823 3833 480V L 'A 435 421 480V LC B 419 420 480V LC C 422 436 480V LC D 4 480V'CC A 433 480V HCC B 400 412 480V HCC C 410 433 480V HCC D 402
- High side of current limiting reactor
- Low-side. of current limiting reactor
+Not on Unit 4
Attachment C Page 5 of 18 VOLTAGE ANALYSIS RESULTS cASE 5 UNZT 3 UNIT 4 BUS VOLTSXKS (Grid at 235 KV) 4KV Bus A*
4'us A** 3872 387o q+ ~ jul gu ee'~ )
~ P p I 4KV Bus B* 3931 3939 4KV Bus B** 3855 3865 480V LC A 439 425 480V LC B 423 423 480V LC C 426 44o 480V LC D 43o 428 48OV IICC A 437 418 480V NCC B 4o4 480V HCC C 414 480V i~ICC D 4o6
- High side of current limiting reactor
- low-side, of current limiting reactor
+Not on Unit 4
Attachment C Page 6 of 18 VOLTAGE ANALYSIS RESULTS CASE 6 UNIT 3 UNIT 4 BUS VOLTAGES (Grid at 235 KV) 4KV Bus A* 3 43 3 40 4KV Bus A** 3847 3844
>>>>
}
%>> k )<}r 4/>>} ~}'}
~
~ >> -(>>
4KV Bus 3948 '957 B*'KV Bus B~* 3880 3892
.480V LC A 436 422 480V LC B 426 426 480V LC C 423 480V LC D 4S2 480V MCC A 434 415 480V MCC B 406 418 480V MCC C 480V MCC D 409
- Efigh side of current limiting reactor
- Low-side. of current limiting reactor
+Not on Unit 4
Attachment C VOLTAGE ANALYSIS RESULTS CASE 7 UNIT 3 UNIT 4 BUS VOLTAGES (Grid at 235 KV) 4KV Bus A*
4KV Bus A** 3853 38 o 4KV Bus B* 3901 4KV Bus B** 3809 3818 480V LC A 437 422
'18 480V LC B 418 480V LC C 480V LC D 425 423 480V HCC A 435 416 398 41o 480V HCC B 411 435 480V HCC C 480V HCC D 4oo
~High side of current limiting reactor
'**Low-side, of current limiting reactor
+Not on Unit 4
Attachment C Page 8 of 18 VOLTAGE ANALYSIS RESULTS CASE 8 UNIT 3 UNIT 4 BUS VOLTAGES (Grid at 235 ZV) 4KV Bus A*
4KV Bus A** 3827 824
~
(Vv' 1 ~ V p,? r p q' 4KV Bus B* 3918 3 26 4KV Bus B*~ 3834 384'2o 480V LC A 480V LC B 42o 421 480V LC C 421 43C?
480V LC D 428 427 480V MCC A 432 413 480V MCC B 4ol 413 480V 409 432 MCC C 480V MCC D 4o4
- High - side of current limiting reactor
"*Low-side. of current limiting reactor
+Not on Unit 4
Attachment C Page 9 of 18 VOLTAGE ANALYSIS RESULTS CASE UNIT 3 UNIT 4 BUS VOLTAGES (Grid at 235'V) 4KV Bus A* 78 4KV Bus A** 3 o6 3905
/'ll %
(gA;~ 1A' .;F 0 f) Cwf ~ ~ $ 4g') h )+pl)l",(i i ~ II 4KV Bus B* 3867- '3874 4KV Bus B~* 3755 3764 480V LC A 429 480V LC B 411 480V LC C 4 480V LC D 41 4a 480V NCC A 441 422 480V HCC B 3 2 4o4 480V NCC C 441 480V lICC D 394
- High - side of current limiting reactor
- Low-side, of current limiting .reactor
+Not on Unit 4
Attachment C P~e 10 of 18 VOLTAGE AHALYSIS RESULTS CASE 10 UNIT 3 U!NIT 4 BUS VOLTAGES (Grid at 235'V) 4KV Bus A*
4KV Bus A** 3881 3880 I
@i yW t W'V ~ <<g r>f~ )'W le~q a ~
4 4KV Bus B* 3884 3892 4KV Bus B."" 3780 3790 480V LC A 440 426 480V LC B 415 480V LC C 427 480V LC D 422 420 480V HCC A 438 480V NCC B 395 407 480V HCC C 438 480V IICC D 397
- High - side of current limiting reactor
<*Zow-side of current limiting reactor
+Not on Unit 4
'E Attachment C Page 11 of 18 VOLTAGE ANALYSIS RESULTS CASE ll UNIT 3 UNIT 4 BUS VOLTAGES (Grid at 235 Ã1) 4KV Bus A* o 4 4'us A**
/i~ p~
'I
~ '4 i~ i ~ 'li ~ 1 1
~ ~ Q s g', p P log% I 4KV Bus '3* Ro12" 4471 Bus B*" 3812 3822 480V LC A 429 480V LC B 418 419 480V LC C 431 480V LC D 425 423 480V 'HCC A 442 423 480V HCC B 399 411 418 442 480V HCC C 401 480V HCC D
\
~Eiigh side of current limiting reactor
- Low-side. of current limiting eactor
+Not on Unit 4
Attachment C Page 12 of 18 VOLTAGE ANALYSIS RESULTS CASE 12 UNIT 3 UNIT 4 BUS VOLTAGES (Grid't 235 KV) 4KV Bus A*
4KV Bus A**
4)1)1(4$ ~ Alp ~
~ F J)&tggl
'J'
~ gf' kJ 4KV Bus B* 3922 4KV Bus B** 3838 q84 480V LC A 441 427 480V LC B 421 421 480V LC C 428 442 480V LC D 429 427 480V MCC A 439 42o 480V MCC B 4ol 413 480V MCC C 416 43'80V MCC D 404
- High - side of current limiting reactor
~*Low-side of current limiting reactor
+Not on Unit 4
Attachment C Page 13 of 18 VOLTAGE ANALYSIS RESULTS CASE 13 UNIT 3 UNIT 4 BUS VOLTAGES (Gria at 235 KV) 4KV Bus A* 3949 3945 4KV Bus A** .3856 3852 4KV Bus B* 3933 3941 4KV Bus B** 3857 3868 480V LC A 423 480V LC B 423 480V LC C 438 480V LC D 431. 429 435 416 480V 11CC A 480V ailCC B 404 416 480V NCC C 412 480V NCC D 406
- High side of current limiting reactor
- Low-side of current lim'ting reactor
+Not on Unit 4
0 Attachment C Page 14 of 18 VOLTAGE ANALYSIS RESULTS CASE 14 UNIT 3 UNIT 4 BUS VOLTAGES (Grid at 235 KV) 4KV Bus A*
4KV Bus A** 383o 3827 1 I
~ w il g y g~
4KV Bus B* . 3950 - '3959 4KV Bus B** 3883 3895 480V LC A 434 42o 480V LC B 426 427 480V LC C 421 435 4SOV LC D 434'32 '432'13 480V lICC A 4oY 419 480V HCC B 409 432 480V lICC C 480V lICC D 41o
'I
- High side of current limiting reactor
- low-side. of current limiting reactor'Not on Unit 4
Attachment C Page 15 of 18 VOLTAGE ANALYSIS RESULTS CASE 15 UNIT 3 UNIT 4 BUS VOLT&DES (Grid at 235'V) 4KV Bus A* 3982 3 81 4KV Bus A** 3909 3908 i lw <<<
4'us il < i< P << '< P < t ~ ~ ~ < ~,
P
< ? I~ '
<
B* 3899 3906 4):V Bus B."* 3803 3813 480V LC A 443 429 480V LC B 417 480V LC C 43P
'424 423 480V LC D 422 480V NCC A 398 41P 480V HCC B 418 480V i~ICC C 400 480V HCC D
- High side of current limiting reactor
- m~ N-side. of current limiting reactor
+Not on Unit 4
Attachment C Page 16 of 18 VOLTAGE ANALYSIS RESULTS.
CASE 16 UNIT 3 UNIT 4 BUS VOLTE~ (Grid at 235 KV) 4KV Bus A*
4KV Bus A** 3883 3882
)f ~
I ~
~,"r ' ~ l&l Vigol (1'4(i t
~ ~ (% ~ I 4KV Bus B* " 3916- 3924 4KV Bus B~* 3828 384o 480V LC A 440 426 480V LC B 42o 42o 480V LC C 428 . 441
" 428
426 480V LC D 480V MCC A 438 42o 4oo 412 480V NCC B 415 439 480V NCC C 480V HCC D 4o3
- High side of current limiting reactor
- Low-side. of current limiting. reactor
+Not on Unit 4
Attachment C Page 17 of 18 VOLTAGE ANALYSIS RESULTS CASE 17 UNIT 3 'UNIT 4 BUS VOLTAGES (Grid at 235 KV) 4KV Bus A*
4KV Bus A** 3 1 16 4KV Bus B'>> 3936 3 44 4KV Bus B** 3861 . 3871 480V LC A 430 480V LC B 480V LC C 431 '445 480V LC D 431 4z9 480V NCC A 423, 404 480V HCC B 419 442 480V iXCC C 480V NCC D 407
- High side of current limiting reactor
- Le~-side, of current limiting reactor
+Not on Unit 4
Attachment C Page 18 of 18 VOLTAGE ANALYSIS RESULTS CASE 18 UNIT 3 lJNIT 4 BUS VOLTAGES (Grid at 235'V) 4KV Bus A* 3 2 s 6 4KV Bus A** 3891 3890 4KV Bus B* 3953 3962 4KV Bus B"* 3887 3898 480V LC A 441 427 480V LC B 426 427 480V LC C 428 442 480V LC D 435 433 480V hlcc A 439 42o 4o7 419 480V -hlCC B 416 439 48OV hlCC C 41o 480V hlcc D
- High - side of current limiting reactor
- Low-side. of current limiting reactor
+Not on Unit 4
Attachment D Page 1 of 1 VOLTAGE ANALYSIS RESULTS ASSPiflifG lfINIBIUi~f LOAD & MXI!'fUi~f SWITCHYARD VOLTAGE UNIT 3 UNIT 4 BUS VOLTAGES (Grid at 244 KV) 4KV Bus A* 4326 4326 4KV Bus A** 4312 4312 4KV Bus B* 4325 4328 4KV Bus B** 4311 480V LC A 494 494 480V LC B 494 494 480V LC C 494 480V LC D F06 498 480V HCC A 493 493 480V HCC B 491 493 480V HCC C 493 493 480V l1CC D 500
- ffigh side of current limiting reactor
- Low-side of current limiting reactor
+Not on Unit 4
Page 1 of 2
~'OL~AG- hN" L~STS B" SUL' Uil"" 3 ASSU?~iING SAFE'Y LOAD HUlli?ZNG AllD STAR ZNG OF LARGEST llOH-CLASS lE LOAD BUS VOL~KG=S (Gr'd at 235 KV)
BUS REQUIRED CASE 2 CASE 13
~ 5 A IW NONE 3537 4OO8 32O4 34 2 3 70 4-'qt NONE 3 82 35O4
" 'Vi Bus 32O4 3 3 346 3'0; 38O l:80V ' 448 ~33
)~ 8Pq ~ rs C NONE 3 6 48 "V ..C D 4 6 480V:!".C NONE 44o 48OV:'CC 442 48Or i:.CC C 86 48O'! iiCC D 442
- bligh side of current limiting reactor
- *.-'Low-side of current limiting reactor
Att"chment E Page 2 of 2 VOLTAGE ANALYSiS B" SULTS - UIIIT -",
ASSUMING SAFETY OADS BUNNZNG AIID STABTiNG OF LARGEST HON-CLASS IE LOAD BUS VOLTP GES (Grid at 2 g Kv)
REQUIRED CASH 2 'CAS" 13 4'us s ~
' ~ < ~
A'"'KV Nol'1E. 8 4 Bus A~~ 3203 3474' 7 4I:V Bus B~ NONE 4 3go6 4kà Bus B-+ 32o4 3968 4 2 480V LC A 393 4zo 48OV LC B 4co 480V LC C NONE 48ov LC D 4 6 48ov:.cc A '88 44 48ov I.ICC B 40ov I:cc c NOPE 4
- High side of current limiting reactor
>>'Low-side of current 1initing reactor