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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
s RKSULAiTQR>>Y INFORblAiTION D~ISTRIBUTiION SYSTE>>li (RIDS)
ACCESSIONi >>VBR 81'1'1 0 202B5s DOC ~ DA>>TEI~ 81/1 0/23'OTAR'IZED i NO DOCKEfTl IV FACIL>>:50: 250 Tur key Point'l anti Un>>it>> 3i. Florida>> Power and Lig5it C' 00 50:-251 Turkey Point: Pl anti Unit>> 4i, Florida Powe'r. and Lignit C 050 AUTH1 NAME[ AUTHOR>> AFFILIAT>>ION i
UHR IG R ~ E'~ Flor>>i de>> Power L L.igh,t C'o.
RE C IP' VA>>SKI REC>>IPI ENT AFF IL>>I Division of Licensing, AIT'IDN'IISE>>VHUTiiD',G, SUBJKCl1':: For wards cor rected Pagp 1 to'ttachment to util Bi 1 02'1> tr- 1 responding, to NRC 810821 1 tr>> re>> pressurized therma'l shbcki to>>
rebctor pressurei vessells; D~ISTRilBUTIQN CODE); A0498'- COPIES>> RECEIVED: LA'R ENCL(~'IZE.':-'
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FLORIDA POWER 8( LIGHT COMPANY October 23, 1981 L-81-465 Office of Nuclear 'Reactor Regulation Attention: Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Eisenhut:
Re: FPL Letter L-81-462 Dated October 21, 1981 ATTACHMENT CORRECTION By our letter referenced above, we responded to questions of your letter dated August 21, 1981 regarding Turkey Point Units 3 8 4 relating to pressurize'd thermal shock to reactor pressure vessels.
The attached corrected page replaces Attachment Page 1 of our letter referenced above.
Very truly yours, Robert E. Uhrig Vice President Advanced Systems 8 Technology REU:DAC:cf Attachment cc: Mr. James P. O'Reilly, Region II Mr. Harold F. Reis, Esquire f$ pic 8.% 1 0 2 0 g .
PEOPLE... SERVING PEOPLE
gt:
ll
Pressurized Thermal Shock to Reactor Pressure Vessel's uesti on 1):
Provide the RTNDT Values of the critical welds and;plates (or forgi ngs) in, your vessel for:
(a) Initial (as built)'onditions and ocati.on (e.g. 1/4T) and 1
(b) current conditions (include fluence level') at the RPV inside carbon steel surface.
Response 1):
Ini ti al Current Materi al ~RT gQ ~RT I1j ~RT ~
(a) Intermedi.ate Inner 123P481VA1 +50 F +35F +85F Forging*
Ci rcumf erenti al (Girth): Weld** SA 1101 +3 F +190 F +193F Lower Forging* 122S180VA1 +40 F +35F +75F
- Inner wall. The current RTNnT (1/4 T) = +168 F. Value is based on Unit 3 data .which has been sfiown to be more representative of Unit 4 than surveillance capsule removed fran Unit 4 (L-77-113, dated April
+
ll, 1977 and L-77-326, dated October 21, 1977).
Based on the slo e of prediction curves presented in proposed ASTM Standards "Pre icting Neutron Radiation Damage To Reactor Vessel Materi al."
(b) There have been 5.61 Effective Ful,l:Power Years (EFPY) of operation as of September 30, 1981 at Turkey Point Unit 4.
The total fluence on the inner wall is 1.1 X 10 9 n/cm2 and 6.6 X 1018 n/cm2 at 1/4 T.
(jues~tion 2:
At what rate is 'RTNDT increasing for these welds and plate material?
Res onse 2 :
RTNDT is increasing at the rate of 7'F/EFPY for the next 10 years;. for the remainder of life, 5'F/EFPY. The rate of change for the forgings i's 30F for the remaining design life of the vessel. These are based on the slo e of prediction curves presented in proposed ASTM Standards ".Predicti.ng eutron Radiation Damage To Reactor Vessel Material."
uestion 5:
Provide a listing, of operator actions which are required for your plant to prevent pressurized thermal shock and to ensure vessel integrity. Include a
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LEHIGH UNIVERSITY
)nsthu(e of Frac)use anC Solid Mechanics PacLard Lab. B}d8. N)9 BETHLEHEM, PEA.'CSYLVANIA,l8015 Telex Yo. Lehigh Univ. UD 7)0-670-)066 g ['(') fj):.
, w G. C. Sih Di:ecto.'ctober l(~.
198'ttorney Yiartin H. Hodder 1131 N.E. 86th Street Niami, Florida 33138 RE: Turkey Point Nuclear Power Plant Unit No.': Reactor Vessel Lmbrittlement and Surveillance Program
Dear Attorney Hodder:
In response to your letter da.ed August 29, 1985 and the abnve referenced subject matter, I have read the package of documents on th<< RPV e::;t>.-i:tlement program at Turkey Point Unit No. 4. A number of supporting argu>>ants with ref-erence to the calculation of bRTNDT ale questionable If not invalid from the scientific view point. In what follows, the SMRI report and the FPL setter shall be referred to as $ 1]* and t2j**, respectively.
Prediction t'1 (1} Sn%I Based on the RPV material surveillance methodology, SM-.:! fl: estimated the shift in RTN>- for Turkey Point Unit No. 4. The results per;a'.):i:.'o wall ND) loca.ion 1/4T based on the data of Capsule T -in terms of L'FPY a. e sum= -ized graprically on the sheet attached to this letter. The shift in R;,,. ': found tc be*a -.oximately 324'F at 8 EFPY. This is beyond the NRC screef.',:" ialue of 300eF.
E. B. Norris, "Reactor Vessel Material Surveillance Prooram fo y Point Unit Nc. 4: Aralysis of "apsule T", Southwest Research Institute ;ical Re-port Nc. 02-4221, June 1976.
+*
Le ter, Ul io, FPL, to Eie,".l'ut, "Re: Turkey P .in. Unit <, Docs.~ :.s. 50-251, P:S to Reactor Pressure Vessels", January 21, 1982.
'2-(2) FPL Res onse 2 Mith reference to the material in Docket No. 50-:'51 on P1S of RPV as stated in [23, a lower aRTNDT value of 211'F was obtained for Unit No. 4. This result,'.however, was obtained by application of the survei'.lance data taken from Turkey Point Unit No. 3. The, justification was that the n~t".llurgica1 Properties of the beltline welds of the Turkey .Points Units No. 3 ard t'o. 4 are the same and that data on Unit No. 4 are not sufficient.
,(3) Comments The rate at which the beltline weld material deteriorates and/or em-brittles depends on the eomMned effects of irradiation and pressurized thermal shock. 'It is plant-specific in the sense that the influence differs inherently from one unit to another. In other words, the metallurgical properties alone
.. cannot determine the damage behavior of the welds. The ZocAno k'~.<one plays <
major role. Unless the rates of irradiation, fluctuations in thermal gradients and time variation in pressure are exactly the same for both Units No. 3 and No. 4, one is not justified to assume that data collected in Unit No. 3 could be applied to predict the behavior of Unit No. 4. Hence, conclusions drawn on tRTNDT for Unit No. 4 based on the da.a of Unit No. 3 cannot be considered valid.
I will not delve into the other details concerning the actual calculation of aRTNDT as they are beyond the scope o our imnediate concern.
Very sincerely vours,
'George C. Sih Professor of tiechanics GCS:bd *'='.
Enclosure
Oata Reproduced. from Table on Page 3 at Mall Los<<tion 1/4T, Report by E. B. Norris, "Reactor Vessel Naterial ."urveillance Program for Turkey Point Unit No. 4: Analysis u< Capsule T",
Southwest Research institute Technical Report Nn. 02-4221, June 1976, 500 400
~
tg 350 324'F 300 NPC Screening Criterion I
1 l
I 250 I I
I I
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t 8 10 15 . 20 E ect'.ve Full Po~er Year (EFPY)
r oc Dr. Geo. oe C. M. Sih Professor of Mechanics and Director of the Institute o Fracture and Solid Mecharics
~
Dr.. Si' . vrrently Professor of Mechanics and Director of the Institute of Fractur- a';"'olid Mechanics at Lehigh University, Bethlehem, Pennsylvania.
h{ lds the appoir.ment'of Adjunct Professor at The Hahnemann Medical Col-lege and H-.,spital of Philadelphia since 1972. He received his B.S. at the Uni-versity of Por'land; Oregon, 1953; .his M.S. at New York University, 1957; and ph.D. at Lehigh University, 1960; all of thee degrees in Mechanical Engineering.
Dr. Sih has engaoed in research in the in.eraction of mechanical deforma.ion and heat flow (1960) supported by the Koppers Foundation, in Fracture Mechanics (1950 and 1961) for the Boeing Company Transport Division and (1962 to 1965) for the -National Science Foundation, and as a member of the Technical Staff, Bell Te'.ephone Laboratory (Surfer 1961). He has been engaoed as Principal Investigator in more than fifty projects at Lehigh University sponsored by the Office of Naval Research, Naval Research Laboratorv, the National Aeronautics and Space Adminis-tration, the Air Force, the Arry, etc.,'ll of which are concerned with opti-mizing the use of high performance material with design, a discipline that has r
beer freq~e:tl.> referred to as "Fracture Mechanics". 'Much of his work has been concerned with es:imating the remaining life of material and structural components dar aged by yielding ar.".or fracture. He specializes in developing co:@uter soft-ware for predicting th~ mecI arical behavior of structures and the stability of objects moving through fluid media. his more recent activities are concerned'ith the influence of moisture and te >perature ln co;.-,osite ma ellals laser glazing tech;iques a~d no."-destru tive testing methods involving higt'-voltage electrophotography.
.0 Fror.: 1953 to 1957, Dr. Sih was e-. ioyed by
~
Pa"io Corporation O'. America as a project and re:eiirch engineer. He worked on the research ard developnent of input and output d..vices for the first generation "Bizmark" computer system.
Among 1..
2.
Adju~
.Autor h
the sigr<i'.'cant patents he obtained were:
optical system for line printing.
'.:: " 'gnetic disc printing device for the 0
Xerox process.
In 1957 ~-." 19'. 8, Dr. Sih returned to the academic life and served at the City College of Ne~ York as Lecturer in Mechanical Engineering. He came to Lehi gh Uni vers i ty in 195B as In..tructor in Engineering Mechanics and was appointed Assistant Prc '.e's-. af er comp'c tion of his doctorate. From 1965 to 1966, Dr.. Sih held the positior of Visiting Professor in Aeronautics at the California Institu'e of Technology and participated in an Air Force research project on the dyramics of crack propagation and size effects in the fracture of plates.
Dr.:Sih assumed in 1970 the du"..es of Regio'nal Editor, International Journal of Fracture Mechanics, a~ d the responsibilities of soliciting and reviewing papers in the field of fracture Mechanics. From 1971 to 1975, he served as an Associate Editor .of the ASM: Journal of Applied Mechanics. 'He is also on the Editorial Ad-visory Board of the Journal of Engineering Fracture Mechanics. He is also Ed~tor-in-Chief of an Interrati~'l Journal of Theoretical and Applied Fracture Mechanics.
Dr. Sih is a Fe'ow of tie American Society of Mechanical Engineers and Honorary Fellow""of the Internatir>> al Congress of Fracture. He is also a foundino member of the Ir+erra',ional C:::, era+ive Fracture Institute, an organization established to promote the interc~.'e of ideas and information among active researchers in
'fracture m chanics.
i Dr.. Sih is'lso a me".; of the fol'oi irig societies:
1 ~ Society of Signa Xi
- 2. AS'on-..ittee E-24 on Fracture Testing of Y<a+erials
- 3. International Society of Engineering Science
- 4. American Society of Civil Engineering
- 5. American Society of Hechanical Engineering
- 6. Interriatioral Society for the Interaction of He;! anics aric'. 1'<1hematics Dr. Sih is the Editor of three book series. Seven volumes on thr <echanics of Fracture series have been or are about to be published:
Volume I - Methods of knalysis and Solutions to Cra~k Problems, 1973 Volume II - Three-Dimensiorial Crack Problems, 1974 Volume III - Plates ard Shells with Cracks, 1976 Volume IV - Elas+odynamic Crack Problems, 1976 Volume V - Stress kralysis of Notch Problems, 1976 Volume VI - Cracks in Composite Yiaterials, 1980 Volume VII - Experimenal Evaluation of Stress Corcentration and Intensity Factors, 1980 The two other series are Fati ue and Fracture:
Volume I - Fatigue and Fracture, S. Kocanda, 1978 Volume II - Fracture t'icromechanics of Polymer Na:erials, V. 5. >:i:,shenko and V. P. Tamuzh, 1980 and Enoineerinri k" lication of Fracture He Ianics:
Vol um I - Fracture %chanics Yiethodol ogv: Eve 1 ua. ion of St i.u:; ural lo:-:~:
nents Integrity, edited by G. C. Sih a-d L. Faria
,.-~c II
~
MsxeC Miode Crack Enter sior
~
by E. E. Gdouto.
-- III - Fracture Nechanics of Concrete: Material Characterization and Testing, edi ted by A. Carpinteri and A. Ingra ffea Volure IV Fracture Mechanics'f Concrete: Numeric~1 Analysis and Struc.ural Application by G. C. Sih anC Ii. DiTommaso Volume V Bonded Repair of Aircraft Structure by I b. Balt r arid R. Jor es Volume YI Crack Grouch and Material Damage iri Coi <
i < tc'. Lin:i'. Load arid Bri t tl e Frac ture by A. Ca r pinteri Dr. Sih has also served as principal organizer and editor of proceedings of several conferences:
- 1. International Conference on "Dyniamic Crack Prop,<;ation", (1972), Lehigh University
- 2. Internatiorial Corference on "Prospects of Fracture Mechaf lies", (1974';,
The Netherlands 3.. Conference on "Linear Fracture Mechanics", (1975), Lehigh University 4; Interriational Corference on "Fracture Mechanics and Technology", (1976),
Hong Kong 5.=" 14th Annual Meeting of the Society of Engir merino Science, (l977), '.e-high University 6; First USA-USSR Symposium on "Fracture of Composite Match la s', (1975'),
USSR
- 7. International Conference on "Fracture Mechanics in Engii .-:
"' " Applica-tions", (1979), India
- 8. International Coriference ori "Analytical and Experimen+a ~ fi~cture N=-
chanics", (1980), Italy
- 9. International Con.erence on Defects arid Fractu e", (.9;-'.:), Po'.and
- 10. International Conference on "Yixed Yiode Crack I'ropagation", (1980),
Greece
- 11. International Conference on "Absorbed Energy arid/or Specific Strall'i En-ergy Density Cri ter ion", (1980), Hungary
- 12. International Coriference on "Defects, Fractur~ and Fatigue", (1982),
Cariada
- 13. International Conference on "Fracture Yiechanics 7echnnlogy Applied to Yaterial Evaluatiori and Structure Design", (1982), Australia
- 14. International Conference on "Application of Fracture Hechanics to Na-terials and Structures", (1983), Germany Dr. Sih has approximately two hundred publications principally in the area of solid and fracture mechanics. He has authored and co-authored a total of three books.
Handbook of Stress Intensity Factors, 1973
- 2. Three Dimensional Crack Problems (with Yi. K. Kassir), 1974
- 3. Cracks in Composite ¹terials (v ith E. P. Chen), 1980 Dr. Sih received the 1975 Achievement Award from the Chinese Institute of Engineers in the United States and the 1984 Achievement Award from the Chinese Engineers and Scientists Association of Southern California for his accomplishments ir research and teaching in fracture and solid mechariics.
Dr. Sih has also beer active in serving as members of riatic ~
=.':~ittees.
Among ther are the National Yiaterials Advisory Board conicernina ~ .i the Dyraric Response of Y~terials Subjected to High Strair Rate koadira; Shii t'~!erials Fab-ri:ation arid Inspection; and other cow;ittees concerrinc Nu lear hf'c:ctor Compo-nf nts Cf A Cox Newspaper Friday Afternoon. October 25. 19ffb 40 Pages Make I eectcr vv alms CBllled 'embff'ittted't TUrkey Point Srn said he could not discuss KI.LEM HAMPTON whether Unit Four ls potentially Snulhwcst Rci<<iirch Industries AW+4 items 8 eeettor dangerous because of the many filrd an ad<lllin>>al riliort fn 1979 factors that contribute to safety at equaling sevr>> rf f<<c rive full pow-A metals engineer who re- a nuclear power plant. But he safd er years at Turkry Point to 10 cal-viewed a 1976 Florida Power & the information in the FP&L re- endar years. It suggested that an-Bght Co. report on two nuclear port called for further study. other brittleness test be conducted reactors at Turkey Point maintains "They should seriously re-evalu- in seven full-power years. Unit that the walls of one of the reac- ate the situation," Sih said. "Ac- Four, currently in ils eighth full tors has "..gone Into embrlttle- cording to their assessmertt, it has power year. was scheduled tor a inent" and should be promptly ln- passed beyond the limits. The pub- brittleness inspection this year.
pected. lic deserves an answer on that ba- But FPgiL requested permlssfon But an FP&L spokesman said the sis from the NRC to delay the teston conditions of the reactor walls are Brittle walls can become dan- its request, FP&L said ft wanted to within federally set safety stan- gerous during sudden changes ot begin an integrated program of 4ar'ds and do not warrant immedi- testing between Unit Three and ate inspection. an assessment the temperature. If a minor accident Unit Four, thus reducing employee Nuclear Regulatory Commission were to occur and Unit Four had exposure to radiation and avoiding agrees with, aa NRC spokesman to be cooled down quickly with possible power outages.
said. water, the walls could shatter. A
'he fssue of the reactor's em-cracked reactor would result in a meltdown, Lorion said, and NRC The NRC approved the delay and FP&L's plan to test material brittlement, or lack of ductility sdentlsts agree. from Unit Three to evaluate condi-pliability) caused by age and And a meltdown at Turkey tions in Unit Four based on several etress, was raised at a press con- Pofnt, according to a report by criteria. Among them, the NRC ference yesterday by Joette Lo- Sandia Labs for the NRC, could be said, the units must be "sufHcient-rioa, a freelance writer-researcher expected to cause immediate death ly similar to permit accurate com-who founded and serves as the to anyone within a 20-mile radius parisons" and there must be "sub-sole member of, the Miami-based of the plant and radioactive con-, stantial advantages" to personnel Center for Nuclear Responsibility, and power clients in reduced radi-
~
a nuclear watchdog group.
tamination to a 70-mile radius.. ation exposure and outages.
Lorioa obtained the FP&L report Turkey Point's just north of FP&L responded that Units Homestead in deep South Dade., Three and Four are identical in de-the NRC Ia August and sent 'rom Wolverton said that Unit Four I
ft to Dr. George Sih, director of the walls have not become dangerous- sign. modifications and materiel Institute of Fracture and Solid Me- ly embrittled. He said there is l and are operated under the same chanics at Lehigh University in embrittlement of the walls, 'ome conditions. FP&l. acknowledged a Ifethfehem, Pa., for analysis. but that lt has not exdeeded feder- difference in emb..':llement be-Sih said fn a telephone intervfew al safety standards. tween the two units r>>d attributed that after reviewing the FP&L re- "We contend that the plant is it to different lev<<ls of usage.
port, he concluded that the walls sate or we wouldn't run it," Wol- The Southwest Rrscarch Indus-on the Unit Four reactor at Turkey verton said. tries Inc. tests shnwrd considera-Point reached a condition ot em- . bly lower ernbririlrr cnt levels for brfttlement in 1981. NRC spokesman Frank Ingram Unit Three than .'i "nit Four, Sih "According to the report. the arateriaf has gone fnto embrittle-rnent," Sih said. ~
aafd his agency had studied the po-tential for embrittlement at Tur-key Point and was satisfied that not expectc ':i said. Unit Thirr. li r example, was
~ ceed federal safety standaiui r.i '. after 10 full Sih. who was named a feBow of "embrlttlement would not be a power years.
the American Society of Mechani- problem for either reactor for Martin Hod:;i; i "orney for Lo-cal Engineers in 1973 for distin- some time, possibly even up to the rion's group, s:.i', i'.~t with the ap-guished work, said he pioneered end of its 40-year life span. proved delay i:.:irittlement of said the NRC currently fs re- Unit.Four's vi >>lli ~ ould not be ex-
'e the field of assessing the life span wrrd strength ot metals and has viewing FP&L's 1976 report as amined for arii".l i l4 years. Wol-
~
conducted many assessments on part ot a hearing request by Lo- verton said lir i "uldn't say how nuclear plants nationwide in the rion's group on the embrfttfemi;nt long the ext'>>."i >> is for iri re-past decade. issue. Thc report, based on a 1975 quired testing FP&L spokesman Dave Wolver- test by Southv, est Research Indus- Litigation 1!i i<>cli nr Responsibility and "we have found his assess- Four would exceed federally set began in 198'. << lien Lorior. co~-
ment was a limited assessment safety standards for brittleness be- plained to tl. NRC about Turkey with a lin:ited "amount of informa- tween its fifth and tenth "effective Point.
tion. Some of it in fact was old. It full power year," which is mea-was not a comprehensive study of sured in time at full operating the u:hole situation." power. ~