|
---|
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
-.ACCELERATED DISTRIBUTION DEMONSTPWTION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)CCESSION NBR:9002070202 DOC.DATE: 90/01/29 NOTARIZED:
NO DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C.05000251 AUTH.NAME AUTHOR AFFILIATION HARRIS,K.N.
Florida Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Responds to.NRC ltr re violations noted in Insp Repts 50-250/89-203
&50-251/89-203.
DISTRIBUTION CODE: IE01D COPIES RECEIVED:LTR ENCL SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice of VioIation Response NOTES: RECIPIENT ID CODE/NAME PD2-2 PD INTERNAL: AEOD AEOD/TPAD NRR SHANKMAN,S NRR/DOEA DIR 11 NRR/DREP/PRPB11 NRR/DST/DIR 8E2 NUDOCS-ABSTRACT OGC/HDS2 RES MORISSEAU,D TERNAL: LPDR NSIC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1'1 1 1 1 1 1 RECIPIENT ID CODE/NAME EDISON,G AEOD/DEIIB DEDRO NRR/DLPQ/LPEB10 NRR/DREP/PEPB9 D NRR/DRIS/DIR NRR/PMAS/ILRB12 0 ErIEjBERMAN, J RGN2 FILE Ol NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 24
P.O.Box14000, Juno Beach, F1.33408-0420 I=PL JAN 2 9 1990 L-90-36 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen:
Re: Turkey Point Units 3 and 4 Docket Nos.50-250 and 50-251 Re 1 to Ins ection Re ort 89-203 Florida Power&Light Company has reviewed the subject inspection report.The response to the unresolved items identified in the report is attached.Should you need any additional information, we would be glad to discuss the response with you.Very truly yours,)Vice/President Turkey Point Plant KNH/GRM/tbj Attachment cc: Stewart D.Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant 9p0207 gpp0250 2 900129 PDP ADOCK 0@DC O an FPL Group company.
Re: Turkey Point Units 3'and 4 Docket Nos.50-250 and 50-251 Re 1 to Ins ection R ort 89-203 DEFICIENCY 89-203-10:
REPLACEMENT CCW HEAT EXCHANGER SHELL-SIDE NOZZLE LOAD Discussion:
.ZP&L engineering package PC/M 88-263 was written for replacement of the Unit 4 heat exchangers.
FP&L prepared purchase order C88658 90314 to procure the replacement heat exchangers.
Appendix C of the purchase order required that the replacement heat exchangers be qualified by the response spectrum approach for the SSE depicted in Figure 1 of that Appendix.The Bechtel calculation C-SJ-183-02 CCW Heat Exchanger Support Pedestal Load Evaluation, included an evaluation of the heat exchanger fundamental frequency.
The Bechtel calculation computed a fundamental frequency greater.than 33 Hz for the heat exchangers, and concluded that the heat exchangers were rigid.The calculation therefore used the Zero Period Acceleration (ZPA)values of the SSE spectrum to compute the seismic reactions of the heat exchangers.
However, the Bechtel calculation did not consider the transverse flexibility of the concrete pedestals supporting the heat exchangers.
If the heat exchanger and the supporting concrete pedestals were analyzed as a single mathematical model, the fundamental frequency of the heat exchanger along its longitudinal axis drops to about 10 Hz.This would increase the magnitudes of the seismic loads for which the heat exchangers must be qualified.
The replacement heat exchangers were qualified for piping thrust, dead loads and seismic loads by Target Technology Ltd.Bechtel recommended that Target compute the heat exchangers fundamental frequency and use ZPA loads both to qualify the heat exchangers and to compute the heat exchanger support reaction.Like Bechtel, Target computed the heat exchanger fundamental frequency without considering the transverse flexibility of the concrete pedestals and concluded that the heat exchanger was rigid.As a consequence, Target qualified the replacement heat exchanger with respect to the ZPA seismic loads.Since the heat exchangers and concrete pedestal corifiguration is flexible, the Target stress report does not adequately qualify the replacement heat exchangers for the governing seismic loads.This item is Unresolved (89-203-10)
R88POIls8:
The determination that the heat exchanger pedestal supports are flexible (approximately 5 Hz)"'n the longitudinal axis affects the qualification of the CCW and ICW piping attached to the heat exchangers, the heat exchangers and the support pedestals themselves.
The analyses for each of these components have been revised/reviewed as described below: The piping stress analyses for both the CCW and ZCW piping have been revised, taking into account the pedestal flexibility"'"'.
The revised analyses showed that both systems, including the pipe supports, remain within Updated Final Analysis Report allowable stresses.New heat exchanger nozzle loads were also determined from these analyses.The heat exchanger qualification is being reviewed in order to determine the effect of the new nozzle loads and the pedestal flexibility.
With respect to nozzle loadings, no adverse effect on heat exchanger qualification is anticipated; a preliminary comparison of the new nozzle loads against the allowable stresses documented in the original heat exchanger qualification report has indicated that the increase in nozzle loads falls within the margin between actual and allowable nozzle stresses.Upon further review of the seismic input provided in the specification to the heat exchanger vendor"', it was found that the response spectra used was a conservatively amplified enveloping response spectra curve.The Zero Period Acceleration (ZPA)for the enveloping spectra provided in the specification is greater than the acceleration corresponding to 5 Hz on the ground response spectra which actually corresponds to the base of the'support pedestals (0.4 g's versus 0.37 g's respectively)
"'.Accordingly, the seismic loading on the heat exchangers will be reduced, even when the pedestal flexibility is considered.
FPL is working with Target Technologies to obtain a revised final stress report by June 30, 1990.This report will include a consideration of the effects of the correct pedestal flexibility, the new nozzle loads, and the ground response spectra which correspond to the heat exchanger location.This report will be incorporated into the heat exchanger replacement engineering documentation package within 60 days of receipt, but no later than August 29, 1990.
This item will be considered complete once the report has been incorporated into the documentation package as discussed above.
References:
1)Bechtel Calculation 18712-183-C-SJ-183-02 Revision 8,"CCW Heat Exchanger Support Pedestal Load Evaluation" 2)Teledyne Calculations 6961C-1 Revision 4,"Stress Problem 025" and.6961C-3 Revision 6,"Stress Problem 038/CCW-24" 3)Bechtel Calculations 18712-M12-183-02 Revision 5, and 18712-M12-183-04 Revision 2,"XCW Piping Stress Analysis" 4)Purchase Order No.C88658-90314 for CCW Heat Exchanger Replacement 5)Bechtel Calculation 18712-183-C-SJ-183-12 Revision 1,"CCW Heat Exchanger Pedestal Stiffness Analysis" DEFICIENCY 89-203-13:
REPL2KXMENT CCW HEAT EXCHANGER SHELL-S1DE NOZZLE LOAD Discussion:
FPL engineering package PC/M 88-263, was written for replacement of the Unit 4 heat exchangers.
The heat exchangers were qualified for the imposed dead loads, nozzle loads, and seismic loads in a Target Technology report.~'echtel calculation M12-183-01 tabulated shell-side nozzle loads that were substantially higher than the nozzle loads which Bechtel originally transmitted to Target and which were used in the Target qualification report.Bechtel transmitted the revised nozzle loads to Target on November 23, 1988.Bechtel and Target discussed these nozzle loads on December 1, 1988 and Target informed Bechtel that the increased nozzle loads were acceptable.
However, Target never revised and reissued the CCW heat exchanger qualification report to document the qualification of the heat exchangers for the revised nozzle loads.This item is unresolved (89-203-13).
FPL Response: Subsequent to this increase in nozzle loads, the piping stress analyses for the CCW and ZCW piping have been revised.New heat exchanger nozzle loads were determined from these analyses.FPL is working with Target Technologies to obtain a revised final stress report by June 30, 1990, This report will include a consideration of the effects of the newly revised nozzle loads.Since the stress report is being resubmitted to address revised nozzle loads, and is being tracked as part of Deficiency 89-203-10, this item is considered complete.
DEFICIENCY 89-203-14:
CCN REL1EF VALVE REPLACEMEBFV Discussion:
FPL engineering package PC/M 86-238 was written for replacement of Unit 4 relief valves RV-1423 through 1431.Teledyne prepared calculation 6548-1 to qualify these 1-1/2 inch or 1 inch diameter cantilever branch lines for both units.Teledyne technical report TR-5322-1 requires that safety-related piping be qualified to the appropriate loading combinations and stress limits.However, the Teledyne calculation does not address: o The effects of valve thrust;o The need to support valve RV-3-1431 with a tieback from the 3-inch run pipe, since the branch line is not rigid;o A stress check at.the root of each branch line for the combined effects of pressure, dead load, valve thrust, and seismic loads;or o The effects of lumped mass of the branch line and relief valve.If this lumped mass is considered, the fundamental frequency of the branch line will drop.This item is Unresolved Item (89-203-14)
.FPL Response: The calculation which supported the replacement of CCW relief valves (RV-1423 through 1431)installed per PC/M 86-238 was revised to include the following:
The effects of valve thrust A stress check at the root of each branch line The'ffects of lumped mass of the branch line and relief valve During the determination for the need to support RV-3-1431, the hand calculation for the branch line containing RV-3-1431 was revised using a dynamic analysis and it was determined that the branch line actually has a frequency greater than 33 Hz and as a result there was no need to support the valve with a tieback from the 3-inch run.
P, This.review determined that the existing configuration for the relief valves continues to meet the Turkey Point UPSAR stress criteria, Appendix 5A.These reviews are documented in the Teledyne calculation"'.
This item is considered complete.Reference 1)Teledyne calculation 6548-1, Revision 1, associated with PC/M 86-238.
DEZICIENCY 89-203-15:
COMPONENT COOLING WATER OPERATING PROCEDURES Discussion:
The inspection team reviewed operating procedure 3/4-OP-030 for the CCW system to determine if valve lineups were consistent with approved design drawings and if lineup changes for various operating evolutions were properly established and restored.The team found the following deficiencies when comparing the procedures to system drawings 5610-T-E-4512, Sheet 1 and 2: o Procedure 4-OP-030, page 25, Step 7.5.2.7, directs the operator to makeup the CCW surge tank as required by manipulating valves MOV-4-832, 4-711B and 4-710B.Valve 4-737C was not referenced as requiring manipulation; however, it is shown as a normally closed valve on the system drawing and would inhibit makeup flow if not opened.o Procedures 3-OP-030 and 4-0P-030, page 27, step 7.3.2.15 specify that valve.4-711B be left open although drawing 5610-T-E-4512 indicates normal position as closed.Step 7.6.2.15 specifies the positions of valves 3-711A and 4-711A as being left open although the referenced drawing indicates closed as the normal position.o Procedures 3-OP-030 and 4-0P-030, Attachments 2 and 3, for CCW valve alignment inside and outside containment, contained the following deficiencies:
Valves 3-10-681, 3-10-682, and 3-10-683 were specified as having a normal position of open in the valve lineup as opposed to closed as indicated on they system drawing.Valve 4-10-689 was specified as being closed in the valve lineup as opposed to closed and capped as indicated on the system drawing.Valves 3-10-749, 4-10-692, 4-10-1009, 4-10-1010, 4-1181, 4-1182, and 4-769D were shown on the system drawings but were not included in the valve lineup.These deficiencies if not corrected, could have resulted in failure to adequately verify system integrity or could have placed the system in a condition where valves were left opened instead of closed, resulting in a loss of system integrity.
With the exception of the makeup valves (4-737C, 4-711B, 3-711A, and 4-711A)the valves noted were vent and drain valves.
The.licensee agreed to make the identified corrections to the procedures.
The item is unresolved (89-203-15).
FPL Response: Procedure Corrections have been completed as follows:.Procedure 4-OP-030 Infrequent Operations Section 7.0, has been modified to indicate valve 4-737C requires manipulation for alternate CCW surge tank fill.Procedures 3-OP-030 and 4-0P-030, Infrequent Operations Section 7.0, has been modified to indicate valve 4-711B as closed in step 7.5.2.15 and valves 3-711A and 4-711A as closed in step 7.6.2.15.Procedures 3-OP-030 and 4-OP-030 valve lineups have been modified to show: Valves 3-10-681, 3-10-682, and 3-10-683 as closed.Additionally, investigation of the improper valve positions listed in 3-OP-030 for valves 3-10-681, 3-10-682, and 3-10-683 showed incorrect positions resulted from a procedure change error and that a valve lineup had not been performed using this procedure with these incorrect positions listed.We are confident that had a valve lineup been performed, the"On-The-Spot-Change" process would have been used to correct this procedural error.Way Valve 4-10-689 Q closed and capped.Valves 3-10-749, 4-10-692, 4-10-1009, 4-10-1010, 4-1181, 4-1182, and 4-769D as shown on system drawing 5610-T-E-4512 An additional concern raised by the resident inspector involves 3/4-ONOP-030, Loss of Component Cooling Water.The area of concern involved emergency hoses and included: 1)Physical Fit-up of hoses (fittings) 2)Hose Length (to allow reaching all three pumps)3)Designated storage FPL RESPONSE Item 1-Physical Fit-up has been verified and is complete.Item 2-Hose length has been verified and the length allows reaching all three pumps.Item 3-Permanently designated storage is presently being investigated by the Operations Department.
DEFICIENCY 89-203-16:
CCW PUMP AND SURGE TANK SEISMIC QUALIFICATION AND ANCHORAGE CHECK Discussion:
Westinghouse Equipment Specification 676428 included the seismic qualification criteria for the CCW pumps.Section 3.2.12 of the specification stated that the pumps shall be designed to resist earthquake forces in the horizontal and vertical directions, as specified by the data sheets.The Westinghouse centrifugal pump data sheet APCC-532 specified a horizontal design acceleration of 1.0 g and a vertical design acceleration o&0.67 g.FPL could not access the seismic qualification documents for the CCW pumps.FPL additionally could not access any seismic criteria fo'r the CCW surge tank, or any seismic qualification documents.
The equipment anchorage should be checked for the combined effects of piping thrusts, dead load and seismic load.However, FPL could not access the anchorage calculations for the CCW pumps and surge tanks.The audit team was informed that an essential calculation program is planned for the facility.The licensee will determine which calculations are required and will verify that the calculations are retrievable.
This item is unresolved item (89-203-16)
..FPL Response: As indicated in the above discussion, no seismic qualification documents have been found for either the CCW pump or the CCW surge tank.This situation is not uncommon for power plants of Turkey Point's vintage.In order'o assess the need to recreate the qualification documents for this type of equipment,.FPL commissioned a review of the Turkey Point seismic design.This review was conducted by Westinghouse and completed in July 1989.The Westinghouse report"'ompared the seismic capacities of equipment documented in various NUREGs and other published literature to similar, if not identical, equipment found at Turkey Point.This report concluded that the Turkey Point safety related equipment, including the CCW pumps and surge tanks, have high generic seismic capacities.
If properly anchored, the equipment is seismically adequate due to Turkey Point's location in a low seismicity region.In addition to the Westinghouse effort discussed above, the issue of equipment seismic qualification-is being addressed under Generic Letter 87-02,"Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, Unresolved Safety Issue (USI)A-46".FPL has submitted a program to the NRC for resolution of this generic issue.10
An analysis of the CCW pump anchorage has been performed to evaluate the effects of nozzle loads, dead loads, and seismic loads"'.This analysis showed that the pump anchorage is satisfactory to withstand all postulated loads.Similarly, analyses of the CCW surge tank anchorages (including structural steel supporting members)have been performed to evaluate the effects of nozzle loads, dead loads, and seismic loads"'.The structural members and connections have been shown in this calculation to adequately withstand all postulated loads and to remain-within UFSAR allowable stresses.The expansion anchors used to attach the supporting members to the concrete walls have been shown to be acceptable for functionality; however for Unit 4, modifications will be required to bring the safety factors up to the values required by current standards.
The anchor modification discussed above will be implemented by the end of the next Unit 4 refueling outage, currently scheduled to start in November 1990.FPL is proceeding with developing an enhanced Calculation Control Program.This program includes a revised calculation procedure and a FPL mainframe computer indexing system that will accept FPL and contractor calculations.
The revised calculation procedure was issued in December 1989.The loading of the new calculation index data will be a continuing process and the loading of the historical data will be handled through the normal budget process.
References:
1)"Turkey Point Units 3&4, Fragility Analysis for Quantification of Seismic Capabilities of Buildings, Structures and Equipment, WCAP-12051", Westinghouse Electric Corporation, July 1989 2)Bechtel Calculation 18712-183-C-SJ183-11 Revision 1,"CCW Pump Pedestal Analysis" 3)Bechtel Calculation 18712-183-C-SJ183-10 Revision 1,"CCW Surge Tank Platform Analysis" 11
DEFICIENCY 89-203-18:
CCW PZPE SUPPORT CALCUI~ZONS Discussion:
The team reviewed the calculations for approximately twenty four pipe supports which were documented in the following Teledyne stress packages: Teledyne calculation TR-5322-93, USNRC I&E Bulletin 79-14 Analysis, Turkey Point Unit 4 Nuclear Power Plant, Component Cooling Water System (Outside Containment)/Stress Problem CCW-14, Revision 1, dated November 21, 1984;Teledyne calculation 6961C-1, Analysis of Stress Problem 025 Unit 4, Turkey Point, for Replacement of CCW Heat Exchangers, Revision 3, dated November 30, 1988;and o Teledyne calculation 6961C-3, Analysis of Stress Problem 038-Unit 4, Turkey Point, for Replacement of CCW, Revision 5, dated October 28, 1988.The team compared these calculations against the applicable Teledyne engineering procedures and identified the following calculational and procedural deficiencies:
o Teledyne re-qualified a number of stanchion supports to resist uplift.However, the Teledyne baseplate procedure does not appear applicable to the qualification of these supports.Pipe support 4-ACH-267 is an example of such a stanchion support.o Some anchor bolt tension and shear loads, such as for support SR-703, were not computed in accordance with the Teledyne procedure.
For example, baseplate edge distance amplification factors were not applied to compute bolt tension loads, and the shear loads were distributed to all, rather than half, of the anchor bol'ts.The allowable bolt tension used to qualify pipe support 4-ACH-211 exceeded the bolt tension allowed by the Teledyne design guide.Bending stresses in single-angle supplementary steel were not correctly computed.Examples included the supplementary steel for pipe supports 4-ACH-14 and 4-ACH-46.o Some supplementary steel was checked using assumed cross-sectional dimensions that were not field verified.Examples included the supplementary steel for pipe supports 4-ACH-190 and 4-ACH-191.
o Spring hanger 4-ACH-207 tops and bottoms out, but was accepted as-is without analysis.12 o The Teledyne stress packages indicated that ZPA and seismic inertia loads should be combined absolutely, however,, these values were actually calculated by the SRSS method within the stress package.o The AISC web crippling check was not performed to determine if beam stiffeners are required.This item is unresolved item (89-203-18)
.FPL Response: The responses to the individual deficiencies are as follows: Teledyne reviewed pipe support 4-ACH-267 for uplift and determined that based on the thickness of the plate-.the prying factor is 1.0;while examples in the Teledyne base plate procedure do not represent the actual support configuration, the procedure is still applicable.
Teledyne reviewed SR-703 and determined that the baseplate edge distance amplification factor was 1.0 and therefore the engineering procedure was not required to be used;The calculation.
originally considered shear loading on all four anchor bolts.Upon further review, an arithmetic error was identified in the shear load calculation.
The calculation was revised to distribute the shear load to half the anchor bolts.Teledyne reviewed support 4-ACH-211 and determined that the calculation referenced an incorrect revision to the Teledyne design guide.The allowable bolt tension to qualify the support was bounded by the bolt tension in the later revision of the design guide.Teledyne revised calculations for supports 4-ACH-14 and 4-ACH-46 to correctly compute bending stresses in single angle supplementary steel.Supports 4-ACH-190 and 4-ACH-191 are currently on the punchlist for discrepancies identified during the development of their respective drawings.Therefore these supports will be walked down to verify the dimensional assumption in the calculation.
Teledyne revised the calculation for spring hanger 4-ACH-207 including the stiffness of the spring hanger in the dynamic analysis to limit seismic travel and as a result, the support did not top or bottom out.13 The ZPA loads are those which result from the response of the piping system in the rigid range.These loads are combined with the seismic inertia loads which result from the piping stress analysis.The ZPA and seismic inertia loads are correctly combined using the square root sum of the squares (SRSS)method in the calculation.
However, the computer code used to support the Teledyne stress packages does not presently have the capability of combining the ZPA and seismic inertia loads using the SRSS method;it combines them absolutely.
Therefore, Teledyne currently"per forms the SRSS combination o f the ZPA and seismic inertial loads by hand.Teledyne's computer program will be modified to perform this function.Teledyne revised the affected stress packages to address the AISC'eb crippling check.For all identified deficiencies, the revised calculations resulted in confirming that the existing configuration continues to meet the Turkey Point UFSAR stress criteria, Appendix 5A..This is documented in Teledyne calculations"'.
To avoid recurring deficiencies, the pipe support criteria will be revised to address baseplate uplift, single angle bending and the AISC web crippling check.The Teledyne computer code will be revised to eliminate the need to perform hand calculations using the SRSS method.These two documents will be revised by March 1, 1990.
Reference:
(1)Teledyne Calculations 6961C-1, Revision 4"Stress Problem 025" and 6961C-3, Revision 6"Stress Problem 038/CCW-24" 14
DEFICIENCY 89-203-20:
CDR VERIFICATION Discussion:
The CDRs for the RPS, CCW, and electrical distribution systems were reviewed.The CDRs were found to contain erroneous and unnecessary information, as follows: o The CCW chemical mixing pot was inferred to have been replaced when it had only been moved to a different location on the system.o The CCW pump start sequence description was incomplete.
o The CCW containment isolation valve stroke times were not consistent with the TS requirements.
o The instrument voltage tolerances were improperly specified.
o The methodology for cable short circuit calculations was inconsistent with actual practice.o The discharge profile was ambiguously defined.These.concerns led to the conclusion that the CDR had not been appropriately verified.The licensee has agreed to perform some additional verification of the CDR information.
The licensee also issued a directive which restricted the use of CDR information in the design process.This item is unresolved (89-203-20)
FPL Response: FPL has committed to perform a Component Design Requirements (CDR)verification.
In the interim, a directive has been issued which restricts the usage of CDR information.
The verification will take place in several stages.First, the accuracy and reliability of CDR information will be improved in a"CDR Repair" project.The main objective will be to provide true component requirements in a clear, concise and verifiable format.Upon completion of"CDR Repair" for the 18 select systems,"CDR Verification" will be performed.
This effort will include a verification/validation of CDR information.
The scope of this verification will be finalized in procedures, and is expected to focus on key design requirements (attributes) that demonstrate the functional capability of the components.
The"CDR Verification" effort is scheduled for completion by June 30, 1991.15 I DEFZCZENCY 89-203-23:
ACCEPTABILITY OF THE MINIMUM BATTERY TERMINAL VOLTAGE Discussion:
The minimum end-of-service-life battery terminal voltage is 105 Volts Di,rect Current (VDC).There is no evidence that the terminal voltage is adequate to power all safety-related devices.The licensee has performed individual voltage drop calculations for load addition or modification.
The li.censee has not performed a bounding calculation to show that all devices located remotely from the battery bus will be able to operate successfully.
While some tests have been performed, certain components were bypassed during the testing and were therefore not verified to operate at the low battery terminal voltage.Adequate assurance does not exist that the combination of the minimum battery terminal voltage and system voltage drop considerations will yield sufficient equipment voltages to maintain equipment functionality.
This is unresolved item 89-203-23.
FPL Response: A bounding calculation as described above is not a licensing requirement for Turkey Point.Individual voltage drop calculations for load additions and modifications have been performed as necessary.
However, to provide additional assurance that all equipment required to operate will do so at the minimum battery terminal voltage of 105 volts, a bounding calculation will be performed..
This calculation will demonstrate the acceptability of the DC equipments'oltage ratings of 105 volts.This work is scheduled for completion by December 31, 1990.16 0,