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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
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I .V. t5VX 5 j81UVIVIIRIVII,t L 44 IQA FLORIOA POWER 5 LIGHT COMPANY r, 0/(
p g I April 3, 1981 L-81-153 II Mr. James P. O'Reilly, Director, Office of Inspection Region and Enforcement U.S. Nuclear Regulatory Commission
'QP//rp, 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 gpss~ Q~ +%I
Dear Mr. O'Reilly:
Re: Turkey Point Un s 3 &
Docket Nos. -25 and -25 18E Bulletin -11 Please find attached our final report. in response to ISE Bulletin 80-11.
Very trul yours, Robert E'. Uhrig Vice President Advanced Systems 5 Technology REU/JEM/mbd Attachment cc: Mr. Harold F. Reis., Esquire oR3 PEOPLE... SERVING PEOPLE
H
/
r II
FLORIDA. POWER &. LIGHT'OMPANY.
TURKEY POINT PLANT UNITS NO. 3 & 4 MASONRY MALL RE-EVALUATION (NRC IE BULLETIN 80-11)
BECHTEL PONER: CORPORATION GAITHERS BURG,, MARYLQg)
MARCH, 198 1'
ABLE OF CONTENTS I. INZRODUCTION & CONCLUSION II RESPONSES TO OUTSTANDING IE. BULLETIN 80-11 ITEMS A., Item 2b B. Item 3 III REFERENCES
FLORID POWER & LIGHT'OMPANY THUG'Y POINT'LANT UNITS NO. 3 & 4 MASONRY WALL RE-EVALUATION (NRC- IE BULLETIN 80-11)
I ... INTRODUCTION 6 CONCLUSION This. report is submitted to complete FPL's. response. to'NRC IE. Bull'etin 80-11.
It: specifically addresses items "2b" and. "3". Responses to items, "1"'nd "2a" of'he bulletin have been'rovided to the NRC via letter'>>80-234, dated. July 24, 1980.,
The July 24, 1980 submittal indicated that 99 walls were to be re-evaluated.
However, further. review indicated that 97 walls are in proximity to ox have attachments fxom safety-related piping or equipment. Also that submittal indicated. the inaccessibility of the Unit 3 containment which precluded E
a walkdown. However, during a'recent outage, a walkdown was completed by a survey team, and no concrete masonry-walls'ere found in the Unit, 3 containment.
All, 97'alls have, been re.-evaluated to meet their, intended function, under the appropriate. 1pads and. load. combinations associated with these walls, based. upon the: methods and. criteria provi'ded. in, Section IZ of- this submittal. Two of :
these- walls were determined. to be inadequate-to withstand jet. impingement loads only. Nuclear- safety related function(s) associated with the remaining 95 walls are not adversely impacted. The two walls that could potentially fail have associated. with them one reactor trip channel Failure of the circuit will trip the. channel,. i.e., the. circuit fails safe., Thus,. the potential. loss of either oC the: two walls is. considered, acceptable because the potential. impact.
oN the facility does not: affect: the ability to achieve and. maintain; a, safe shutdown condition
II., RESPONSES TO I;E'. BULIZTIN 80-11 ITEMS A. Item 2b Masonry walls, at; Turkey Point', Plant'nits 3 and 4 typically serve as- partition wall's, fire.- barriers,, water; barriers flood barriers shield. walls; load'earing. walls; or sound. barriers.. Documents indicating,l'ocation, and'. layout of masonry walls- are available at. the Turkey Point. site. for NRC, review. ~
The types and. strengths of. materials for construction typically were-as follows:
(1) Concrete. block conforming to ASTM C-90-66-T Grade A, with linear shrinkage limited to 0.05 percent-.
(2) Mortar conforming to ASTM C-270-64-T, using type "S" for un-reinforced masonry in contact. with. earth, type "N" elsewhere, and. type: "M".for.'reinforced masonry.,
(3) Grout for; filling*concrete block cells conforming to type "M"
-with. maximum size of aggregate: of'/8 inch.
'(0) Reinforcement Bars conforming t'o ASTM A-15-66, intermediate grade, deformed.
Joint Reinforcement: Approved standard product (Dur-0-Wall) conforming to ASTM-A82-66.
Five.- multi.-wythe, masonry walls were identified.. A total of 87'asonry wall's; were. reinforced. and. a total of. 10 masonry walls were unreinforced'.
The. typical masonry wall. reinforcement. detail shows 84 or 85 verticaL reinforcing, bars, spaced. at 16 inches on center: and horizontal. masonry reinforcement of Dur>>O-Wall (or equal) spaced at either 16 inches or J
32 inches. on, center.. No masonry ties between the-wythes are shown on design drawings f'r multi-wythe walls.
TypicaI construction practices associated with these walls follow:
(1) Concrete"blocks'ere= stacked.'nder: cover oe protected from.
exposure" to~ the.. weather or from. contact. wi'th soi,l Use; oC damaged'l'ocks was not permitted.
(2) Mortar was prepared in batches of the volume that was to be used before initial set took place, and was placed within one hour after'mixing.
(3) Grout was mixed. in a. clean mechanical mixer. with only sufficient water added to produce a. plastic mix which would flow readily into place without segregation.
(4) Vertical reinforcing steel typically consisted of rebar dowels in. a. base. slab or. footing, lap spliced to vertical rebar in a grout. filled block cell.. The masonry blocks were placed. in a staggered pattern over the d'owels,. vertical rebar lap spliced to the. dowels, and horizontal. reinforcing placed at. specified l spacing; All. cells. including; those. containing vertical, bars
,were. grout. filled with the. reinforcing bars adequately. anchored in place until the grout had set sufficiently to support the bars.
(5) Unreinforced masonry blocks were placed. in a staggered pattern.
(6) Grout: was",=poured. in lifts. not, exceeding 16 inches. Each pour was, rodded to insure compaction" and bond to the proceeding pour and.'o prevent. the; development" of voids.
The construction practices employed adequately prevent. any significant.
voids. or: other. weaknesses in the materials of construction.,
All 97 masonry walls were re-evaluated. for their intended function based upon appropriate Turkey Point Units 3 & 4. FSAR loads and load.
combinations using conventional analytical methods prescribed by the Vorking Stress Design method with a load factor of. unity. The. loads.
considered included. those. produced from. safety and non.-safety-related attachments", interstory. drift: (differential, floor displacement),, thermal.
effects, and'he- effects of potential cracking. under dynamic loads The FSAR does not. specify the use of any particular. code for. the design.
of the masonry walls For: normal. design loading conditions the re-evaluation was based on the American Concrete Institute "Building Code Requirements for Concrete Masonry Structures" (ACI 531-79). For.
loading conditions not. directly covered. by this- code, supplemental allowable stresses and alternative design techniques were used as discussed hereinafter.
Calculated wall stresses were first compared against an allowable stress criteria. If allowable stresses were exceeded, then wall.
stability was checked using inelastic design approaches.
Design allowable stresses were used for- loads'ormally encountered, during plant- operation or shutdown (such as normal operating. thermal, effects and pipe. reactions) and. infrequently encountered loads (such, as operating basis earthquake (OBE) and'ind loads).. A. 30/: stress.
increase; was permitted for load combinations containing normal operating thermal effects or.. displacement limited loads. The factor of safety against failure of the masonry for cases where the 30% stress increase is utilized reduces from 3.0 to 2.3,. still well within the elastic range.
Allowable stresses utilized, in the re.-evaluation follow:
Masons~
All'owable working- stresses as per Table 10..1. of'CI'31-79.
Cell Grout Allowable tension stresses equal to 2.5 .
Reinforcin Steel Stresses in steel reinforcement not: to exceed the following limits: (ACI: 531-79):;,
ln: Tension:
Grade. 40 bars ...............,......,. 20,000 psi Joint. wire, reinforcement 50 percent of minimum ASTM speci, fied yield strength, but not to exceed ................... 30,000 psi In Compression:
40 percent of ASTM specified yield. strength, but not, to exceed ...............,.............. 24,000 psi In>>. plane. effects due. to interstory drift were either determined by.
analysis. or. in-. plane strains (A/H). They were limited t'o 0.00012, where His the relative displacement: between the. top and. bottom. of:
the: wall. and H is the height. of'he wall. A totally confined. wall was limited to a strain of 0.0008'or. walls where (a) the structural shear.
resisting elements bounding each vertical side of the wall had a shear, resisting capability larger than the wall and (b) the wall width to height ratio was at least 0.5.,
In-, plane: strain allowables for. interstory. drift. effects for non-shear walls were established below- the- level of: strain. required. to initiate.
significant. cracking. The. allowable: strain for. a confined wall was based. on the equivalent. compressi'on strut. model discussed in. Reference. 1 and modified. by a safety. factor of 3.0 against crushing. Test data.
(References. 1. through 7) associated with cracking strains for confined
/
masonry walls subjected to in-plane displacements confirms the predicted strain as given by the equivalent strut model.
Design.allowables. we increased for loads which are ghly improbable such. as. the safe, shutdown earthquake (SSE). Code allowable stresses for masonry in tension, shear and. bond were'increased by a factor of 1.67'hich provides a factor of safety against failure of 1.8. Masonry compression stresses were increased by a factor of 2.0 for axial stresses. and. 2 5 for; flexura1 and bearing stresses which provides a safety- factor; against: fail'ure oE 1..2; Allowable reinforcing steel.
stresses were<< 90%, of.'inimum ASTM specified yield. strength provided.
lap splice lengths. and, embedment: (anchorage) could devel'op this stress level.. Allowable, bond. stresses in determining. splice. and.. anchorage.
lengths were permitted to. be increased by a factor of 1.67..-.In-plane strains. due. to interstory drift were limited to 1.67 times the values previously stated..
Damping for uncracked walls was set't 2% for OBE and SSE corresponding to stress levels ranging from approximately 0.3 to 0.6 of ultimate.
Damping for reinforced walls which are expected to crack due to out-of-plane seismic inertia loading were set at 4% for OBE and 7% for SSE.
The modulus of rupture of concrete, grout and mortar was assumed to vary by 20%5, therefore, a lower bound modulus of rupture was determined by applying. a. reduction factor of 0.8 to the theoretical concrete modulus of'upture of T.5 ~f'c. For mesoury,. th.e modu.lus of. rupture:
was approximated. by* increasing the. code. allowable flexural. tensile.
stress'y the factor. of safety of. 3 and then. applying the 20% reduction to arrive at a lower bound value of 2.4 Ft, where Ft is the. code allowable tensile stress.
Where. the bending due to out-of-plane loading caused flexural. stresses in the." wall to exceed the-. previously stated. design allowables,, the wall was evaluated by alternate methods. including the following:
Ener Balance Techn e Masonry walls (a) that were not relied upon to provide strength'f the structure as a whole, and (b) that were subjected to out.-of-plane. seismic inertia loading causing flexural stresses in excess; of design, allowables were evaluated by means of: the "energy balance; technique:" fom reinf'orced. wall's.
Reinforced: masonry wall's evaluated. by the "energy balance technique-"
(References. 8 and. 9) must: have sufficient'apability to preclude brittle failure an'd allow relatively large ductile flexural deformations. Tests (Reference 13) indicate that when flexure is the dominant. action,, ductilities are in excess of 25. Other:
tests (Reference 14) show that. when compression failures occur, ductilities in excess of 5 can be achieved.
When reinforced masonry has adequate shear and compression capability, its behavior is expected to parallel that of reinforced concrete where. allowabl'e. ductilities for predominately non-structural elements are normally set. at 10. 'hus, for out-of-plane seismic loading on. non-shear: wall's constructed. of masonry where brittle failures are. precluded,, a ductility of' was considered acceptable if:.the function of the safety system(s) associated. with. the wall are: not, jeopardized. by wall deflection.
The, deflection. of a fully cracked reinforced wall subj'ected to seismic loading was determined by the '"energy balance technique".
If the, predicted. displacement exceeded three times the yield displacement' the resulting displacement was multiplied by a factor.- of 2.. The resulting displacement was utilized to evaluate the: potential impact. on the function. of safety related system(s) attached. and/ox" adjacent. to, the..wall In; a11'ases- the= midspan displacement. was limited; to fi've times the, yield'isplacement, and the masonry compression stresses were limited. to 0.85f'm
Archin Action Masonry walls confined within a rigid frame or, structure can develop substantial resistance to out-of-plane loadings, after.
flexural cracking. These walls may be evaluated by use of the arching theory (References 10 through. 12).
The; resistance of the- wall to out-of<<plane: forces were, that: a;- three-hinged: arch'."'is: formed. after flexural determined'y'ssuming; cracking Due. consideration was given to the rigidity of the-supporting elements and their ability to restrict rotation of the wall about the supports. The effects of a gap at, the. supports were considered The maximum allowable uniform load used was the lesser. of.:
a) One third of the predicted load based on a maximum masonry compression of 0.85f'm b) Two thirds of the. predicted load based. on a, maximum tension stress of. 6 'm. along the 4.5 diagonal failure plane and.
one inch. bearing wi'dth at 0.85f'm'n the vicinity of'the hinge
-The: deflection at. the. interiom hinge: oK the. arch. after fulL contact.
with the, support: was-. limited". to- 0.3 times. the. thickness of the wall..
A. displacement. of. 2 times the calculated. displacement was utilized to evaluate. the potential, impact on the function of, safety related system(s) attached and/or, ad]acent to the wall.
The structural response of the. masonry walls subjected: to out-of-plane, sei'smi'c: i'nertia. loads'as. based. on, a. constant. value of. gross. moment of inerti'a" along"the. span, of the.. wall for. the. elasti'c (uncracked) condition..
If'he wall. was- cracked', the moment oE'nertia. was. obtained. by using the ACI-318 formula for effective moment. of inertia used, Sn calculating immediate. deflections (Reference. I 15).
To determine: the out- -plane frequencies oF masonry lls, the uncracked behavior and, capacities of. the. walls and, iF applicable, the cracked behavior and capacities of the walls were considered.
Uncracked Condition The equivalent moment= of inertia oF an. uncracked wall (It) was obtained from: a- transformed', section consisting" of the block, mortar, and ce11 grout".. Al'ternatively, the cell grout,, neglecting block and mortar. on the. tension side, was used..
Cracked Condition If the applied moment due to all loads in a load combination exceeded the uncracked moment capacity, the wall was considered.
to be cracked. In this event,. the equivalent moment of inertia was computed as follows:
Ie M cr M cr cr M M a<< a M
cr' t.
Y.
where, Ie, = Equivalent. moment, of 'inertia M = Uncracked. moment capacity cr M = Applied maximum moment on the wall I' Moment of inertia of transformed uncracked section Icr. ='oment of inertia of'he cracked section Fr = Modulus; oF rupture Y = Distance of neutral plane= from- tension; face.
If the use. of an equivalent moment 'of inertia, resulted in an applied'oment less than the uncracked moment capacity, then the wall was verified for the uncracked. capacity.
The efFect of modes vibration higher than the fun entaL mode was- considered. For this purpose, a modaL'nalysis was,performed or.- alternatively,, the inertia. load on the wall due to its own weight for. the fundamental mode was'onsidered as the uniform load in lieu of, determining an effective. mass.. The, corresponding bending moment and. reaction account: fom the higher mode effects.
Vncertainties in; structural frequencies. of. the: masonry walL due. to variations in structural properties and mass were- taken into. account.
The lower.- bound'requency was utilized if it was, on, the higher,- frequency side of the peak response, spectrum. If the lower bound frequency was. on. the lower frequency side. of the peak, the peak acceleration was used.. If'he response spectra for a wall spanning between two floors were of the same shape, the average spectra was used. If they were different, the enveloping spectra was used corresponding to the walL's natural frequency.
Boundary conditions were determined considering one-way spans with hinged, fixed or free edges as appropriate. Two-way spans were not used.,
Load transfer. at the boundary was evaluated based on boundary anchorage 1
capacities.. Fixed. end. conditions were justified for. walls (a) built into thicker, walls or, continuous across walls and slabs, (b) that, have the. stxength to resist. the. fixed end moment, and (c) that have sufficient.
support rfgidity to. prevent rotation. Otherwise, the wall edge: was considered simply supported or free depending on the shear carrying.
capability of the. wall and support..
Distribution. of concentrated loads are affected by the bearing area under. the. load, hori'zontal and vertical wall stiffness,. boundary conditions'. and. proximity-. of: load to wall. supports~ For predominantly one-way action,, an effective beam width of 6 times the- wall, thickness for: distribution: of, concentrated'oads was" conservatively used, for.. the following, condi,tions:
Concentrated, load at midspan;- simple supports:
~ LP 9.6T Concentrated load on a. cantilever: h
+2.4T'.+4.8T Couple at midspan;, simple. supports:
Couple near a support,. simple supports'. a+ Z.4T L'
where.- beam., length h:. 'istance= from~ the- fi'xed. end to the. point. of load application.
- a. = distance between: the concentrated loads producing a couple T = thickness of the wall Interstory drift'alues were derived from the dynamic analysis. Strain allowables depending on the degree of confinement were applied for in-plane drift effects on non-shear walls. They were set based on in-plane effects in a manner that ensures that a reasonable margin remains for. out-of-plane loads. Out-of-plane drift effects were considered if some degree of fixity.existed at the top and/or. bottom of the wall.
Local loadings, resulting from items such as piping and equipment support. reactions, were included.. The evaluation included. transfer.
oE the 1'oads" into the: wall by consideration of, punching shear. effects to:-ensure that. failure; due. to. local. effects, (X..e., block pullout) would," not occur.
The're-evaluation of multi-wythe masonry walls was based on. the absence of composite action between the two wythes.
B., Item' The. methods and. assumpti'ons- utilized, in. the.. masonry- wall. re-evaluation.
were.. based. on. conservative. acceptance criteria and referenced literature which provide adequate. support'. for the propriety of the evaluation methodoIogy., Therefore;. there=- is no need; to. conduct. a= masonry wall test: program; to support: the. re-evaluation. conducted pursuant to NRC Bulletin 80-11;,
REFERENCES Klingner,, R. E. and Bertexo, V. V., "Infilled Frames in Eaxthquake Resistant Construction,." Report No., EERC 76<<32, Earthquake, Engineering Research Center,. University of. California, Berkeley, CA, December.;, 1976.
Mali,, R and,"Salgado,, G.. "Comportamiento. de muxos de. mamposteria. sujetos a cargas 1'aterales,," (Behavi'or of." Masonry Wall. Under. Lateral. Loads.
Second-Report ) Instituto>> de: Ingenieria, UNAM,. Informe No. 237, September;,
1969..
MeH; R , Zeevart;, W'.. and.'Esteva L' "Comportamiento de muros de. mamposteria hueca ante cargas alternades," (Behavior. of Reinforced Masonry Loads), Instituto de Ingeniexia, UNAM, Informe No.156, July, Undex'lternating 1968.
Chen, S. J., Hidalgo, P. A., Mayes, R. L., Clough, R. W., McNiven, H. D "Cyclic Loading Tests of Masonry Single Piers, Volume 2 - Height to Width .
Ratio of. 1," Report'o. EERC 78-28, Earthquake Engineering Reseax'ch Center, University of California, Berkeley, CA, November, 1978.
Mainstone, R. J., "On the. Sti.ffnesses and Strengths of Infilled Frames,"
Proc.. I.C.E , 1971.
Hidalog, P. A., Mayes, R . L,, McNiveny H D p Clough' W p Cyclic Loading., Tests of Masonry. Single Piers, Volume. L - Height: to Wi.dth Ratio of. 2,." Report. No.. EERC 78/27, Earthquake Engineering;Research Center,. University of California, Berkeley, CA, 1978.
Hidalog,. P'. A, MayesR L McNiven, H'. D.Clough, R W, "Cyclic Loading Tests of. Masonry Single. Piers, Volume;= 3 Height: to Width Ratio of 0 5 .'eport No EERC- 79/12 Earthquake. Engineering. Research Center, Univexsit~ oE C'alifornia, Berkeley;. CA, 1979..
BlumeJ.. A,. N M'ewmark, and L. H. Corning,, "Design of Multi;story Reinforced Concrete Buildings for Earthquake Motions," Portland. Cement Association, IL. 1961 Newmark, N.. M ,. "Current. Trends in the. Seismic; Analysis and Design of'igh-Rise Structures," Chapter 16, Earthquake: Engineering,. Edited by R'. L., Wiegel, McGraw-Hill',, 1970.
Gabri.elson;, B;. L'.. and; K; Kaplan,. "Arching. in: Masonry. Walls Subjecte*
to; Out-of.>>Plane Forces,." Earthquake. Resistance. of. Masonry Construction, National Workshop NBS 106;, 1976;. pp 283.-313.,
McDowell,. E.. L., K E.. McKee; and. E'avin"Arching Action Theory.
of Masonry Walls,," journal. of the Structural Division,. ASCE Vol 82',
No ST2March,.1956',Paper No .. 91'5'..
-12>>
. 12. McKee,, K'., E. and'., Savin~esign of Journal', of the Structural ~ision,.
Masonry Walls for, ASCE.
B~ Loading;"
Transactions, Pro~eding Paper 1511,. January, 1958.
13.. Scrivener, J.. C;., "Reinforced. Masonry-Seismic Behaviour and Design,"
Bulletin. of New Zealand Society for Earthquake Engineering, Vol. 5, No., 4-,, December, 1972.
14.. Scrivener, J.. C , "Face. Load, Test's on Reinforced. Hollow.-brick. Non-.
loadbearing. Walls," New Zealand. Engineering, July 15, 1969.
15- Branson,. D.. E , "Instantaneous'nd; Time-Dependent" Deflections on; Simple and. Continuous. Reinforced Concrete Beams,," HPR Report. No. 7, Part 1', Al'abama.,Hi'ghway Department, Bureau of Public. Roads, August 1965, pp.. 1-78.