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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] |
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REGULATOR NFORMATION DISTRIBUTION 'EM (RIDS)
AOCE'SSION NBR: 8208170102 DOC ~ DATE: 82/08/10 NOTARIZED: NO DOCKET ¹ FACIL:50-250 Turkey Point P1 anti Uni t 3i Florida Power and Light C 05000250 50-251 Tur key Point Planti Unit 4i Florida, 'Power and Light BYNAME C 05000251 AUTH AUTHOR AFFILIATION UHRIGiR ~ E, Florida Power 8 Li'ght Co, GREC IP ~ NAME RECIPIENT AFFILIATION VARGAiS~A~ Operating Reactors Branch 1
SUBJECT:
Forwards addi info r e schedular commi'tments fot i tems in dr aft technical evaluation rept on control of heavy loads, DISTRIBUTION CODE: A033S COPIES RECEIVED:LTR ENCL . SIZE:,
TITLE: Conrtol of Heavy Loads Near Spent Fuel (USI A-36) Operating Reactor NOTES:
RECIPIENT iCOPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTiTR ENCL ORB ¹1 BC 7 7 NRR 'CLEMENSON01 INTERNAL: NRR REQUAiG 09 1 1 NRR/DL/ORAB 12 1 1 NRR/DSI/ADCCS11 1 1 AEB 1 1 NRR/DS I/RAB 10 1 1 0$ 1 RGN2 1 1 EXTERNAL: ACRS 13 10 10 L'P DR 03 1 1 NRC PDR 02 1 1 NSIC 06 1 1 NTIS 1 1 TOTAL NU~BER OF COPIES REQUIRED: LTTR 32 ENCL 32
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FLORIDA POWER & LIGHT COMPANY August 10, 1982 L-82-346 Office of Huclear Reactor Regulation Attention: ffr. Steven A. Varga, Chief Operating Reactors Branch II1 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Nr. Varga:
Re: Turkey Point Units 3 8 4 Docket Hos. 50-250 and 50-251 Control of Heavy Loads Draft Technical Evaluation Report We have reviewed the HRC letter dated flay 10, 1982, which requested our understandi ng of the resolution of the items in the Draft Technical Evaluation Report (TER) on Control of Heavy Loads.
The attachment to this letter provides additional information on schedular commitments for the items in the TER. Because the review work for lifting rigs and crane design is being done by contractors, we have provided our oest estimate for completion dates. We will notify you if these projectea completion dates change.
Very truly yours, Robert E. Uhrig Vice President Advanced Systems and Technology REU/PLP/mbd Attachment o3~
cc: J.P. O'Reilly, Region II Harold F. Reis, Esquire 820810 I 208170102 05000250, PDR ADOCK PDR~
P PEOPLE... SERVING PEOPLE
V
ATTACHMENT Re: Turkey Point Units 3 5, 4 Docket Nos. 50-250 and 50-251 Control of Heav Loads INTRODUCTION On December 22, 1980, the NRC issued a generic Tetter to Florida Power 8 Light Company requesting that FP8L review provisions for handling and control of heavy loads at Turkey, point, evaluate .these provisions with respect to the guidelines of NUREG-0612, and provide certain additional information to be used for a determination of conformance to these guidelines. On September 4, 1981, Florida Power 5 Light Company provided its response to this, request. On December 29, 1981, Franklin Research Center (FRC) as a consultant for the NRC issued a draft Technical Evaluation Report (draft TER) on the FPSL response. This draft TER and a subsequent .telephone conversation with the NRC and FRC indicated some areas where additional information would assist in their eval'uation of
,the FP8L response. The intent'f the following report is to clarify ana supplement the initial response by FPSL.
2.1 GENERAL GUIDELINES 2.1.2 Safe Load Paths Guideline 1, NUREG 0612, Article 5.1.1 1
- a. FRC Conclusions and Recommendations Turkey'Point Units 3 and 4 partially comply with Guideline
- 1. In order to comply with this guideline, the Licensee should perform the following:-
- 1. Define safe load paths wher e practical. The use of exclusion areas shoul'd be limited to miscellaneous maintenance areas'nd lifts where the designation of individual load paths is impractical.
- 2. Verify that heavy loads and their safeload paths have been identified in the plant procedure for controlling heavy loads.
- 3. Verify that the selection of load paths considers the location of structural members and beams.
- 4. Verify that safe load paths have been clearly marked on floors or structures.
- 5. Verify that devi ations from load paths require written alternatives approved by the plant's safety review committee (or equivalent).
- b. FPL Position The safe load path areas as defined in the initial response to the NRC generic letter have been revised in a subsequent response to HRC addressing the specific requirements of HUREG-0612. These .safe load path areas and restricted zones were developed by the FPL Power Plant Engineering Oepartment.
Copies of these safe load path drawings are attached. These drawings indicate certain areas where the handling of loads greater than 1760 pounds is restricted. In some areas the handling of loads greater than 5 tons is restricted. The bases for these restrictions are the different capabilities of the structures in the area to withstand a dropped load and the potential for damage to irradiated fuel and safe shutdown equipment.
Florida Power 5 Light Company does not concur that marking the safe load paths on the floors or structures is a practical or necessary means of informing the operator of the safe areas.
The sketches which are readily available to the operator at the hoist controls, are easy to understand and serve the same purpose as floor markings. Also, floor markings can be obstructed by equipment and are not feasible in certain areas (e.g. the refueling pool).
The- plant Maintenance Procedure 0736""Keavy Load Handling" requires written alternatives for deviations from the safe load paths. These alternatives are approved by the Haintenance Superintendent. The Plant Nuclear Safety Review Committee (PNSC) approved this procedure and has delegated this authority to the Maintenance Superintendent. The Maintenance Superintendent is a member of the PHSC and is responsible for all. maintenance activities at the nuclear power plant. It is our judgment that the individual filling this senior maintenance position can determine when a safe load path variation requi res full review by the. PHSC, and as a member of that group he would bring the situation to the attention of that group.'he NRC reviewer found this position acceptable during our phone conference.
2.1.3 Load Kandlin Procedure Guideline 2 NUREG-0612, Article 5.1.1 2
- a. FRC Conclusions and Recommendations FPL partially complies with Guideline 2. The following is required for full compliance.
- 1. identify all loads which are or could be (i.e., without .
credit for interlocks, technical specifications, operating procedures or detailed structure analysis) carried in the vicinity of irradiated fuel or safe shutdown equipment.
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- 2. prepare procedures containing the information identified in Guideline 2 for those loads not identified in 2.1.3.a above {i.e., Reference 4, Table 2).
- b. FPL Position Florida Power 8. Light Company's Power Plant Engineering Department has analyzed the potential consequences of load drops in the vi ci nity of i rradi ated fuel and safe shutdown equipment. The analysis:has enveloped all possible;,
configurations, sizes and weights of potential dropped loads. The safeload path areas and restricted zones have been developed as a result of this analysis and consider the capabilities of the structures beneath the load. The plant Maintenance Procedure 0736 "Heavy Load Handling" r equi res the operators to confine the loads within these areas. Compliance with this procedur e assures compliance with Gui'deli ne 2.
A complete listing of loads which could be carried in these areas is not pr act'ical. Almost every plant component within the reach of each crane would have to be listed. Since Engineering's analysis envelopes all loads such a listing is not necessary.
A li sti'ng of significant heavy loads which are periodically handled in the vicinity of i rradiated'uel has been prepared along with the procedures used for handling of these loads and is given in Table 2 of the FPL report (3).
2.1.4 Crane 0 erator Training Guideline 3 NOREG '0612, Article 5. 1.1 3
- a. FRC Conclusions 8 Recommendations Conclusions and recommendations covering Guideline 3 must be deferred until a comprehensive response is received. The Licensee should ensure that the response addresses operator selection and conduct as well as training.
- b. FPL Position The final response to NUREG-0612 Request for Information (4) was submitted, on November 12, 1981. This report states tnat:
"A training program in accordance with ANSI 830.2-1976 has been developed and our standard company physical for new employees meets or exceeds the physical requirements of the ANSI standard. Some minor exceptions to the ANSI standard have been taken and are listed in the attachment at the end of .this report. These training programs and procedures will be ava'i-lable at the site for review."
The exceptions. to ANSI B30.2-1976 are also listed at the end of this report.
2.1.5 Special Lifting Devices Guideline 4, NUREG-0612, Article 5.1.1 4 a ~ FRC Conclusions,and Recommendations Insufficient information has been provided to allow a determination of compliance with respect to Guideline 4. The Licensee should provide an evaluation concerning compliance with ANSI 14.6 for all special lifting devices (e.g., reactor vessel head and internal lifting rigs, fuel cask lifting device). Further, in performing their evaluation, the
'Licensee should address the imposition, of static and dynamic loads when assessing design stresses.
- b. FPL Position We have contracted with our NSSS vendor to review the design of the reactor vessel internals and head lifting rigs, load cell, load cell linkage and reactor coolant pump motor lifting rig, to determine.the acceptability of these components to the criteria of ANSI 14.6 - 1978 as supplemented by NUREG 0612, section 5.11.4. We expect to receive .the results of these evaluations by the end of September 1982.
2.1.6 Liftin Devices Not S ecially Designed Guideline 5.f NUREG-0612, Artie e 5;1.1 5 a ~ FRC Conclusions & Recommendations FPL partially complies with Guideline 5. The Licensee.
selection and marking of slings should .be evaluate'd.
- b. FPL Position The program for sling use and maintenance at Turkey point Units 3 and 4 meets the requirements of ANSI 830.9. The ANSI standard requires a 5:1 safety factor for sling strength based upon the breaking strength of the sling divided by the rated capacity.'ccording to the standard', the sling is selected based upon the weight of the load; i.e. the rated capacity
.should be greater than the actual load weight. There is no requirement for consideration of a "dynamic load factor" ana it is presumed that sufficient margin is present from the 5:1 safety factor.
FP8L does not feel that it is practical in tne field to account for a dynamic load factor or that such a factor is necessary. Presumably if such a factor was a real safety concern the universally accepted ANSI standard would require one. In any event, the hoisting speeds at Turkey Point are relatively slow and any contribution from a dynamic effect would not be significant. Also, any'ritical lifts {e.g.
reactor head lift, reactor missile shield, etc.,) are always done at very slow speeds.
Superimposing a dynamic load factor in addition to the 5:1 existing safety factor for the slings would not be consistent with other safety factors used in crane design. for example, the hoisting rope requires on a 5:1 safety factor with no dynamic contribution. (Crane Nanufacturers Association of America, Specification f70, Section 4.2).
The rated capacity is marked on the slings. These slings are inspected yearly by an outside contractor, and worn slings are replaced. New slings are tagged with their capacity. prior to receipt by FPL.
2.1.7 Cranes, Inspection, Testing and Maintenance Guideline 6, NUREG-0612, Article 5.1.1 6
- a. FRC Conclusions and Recommendation FPL will comply with Guideline 6. Associated procedures
-should be readily available for NRC staff review when completed.
- b. FPL Position The Turkey Point crane inspection, testi:ng and maintenance program complies with the requirements of ANSI 830.2-1976 with the exception that tests and inspections are performed prior to use where it is not practical to meet that frequencies of ANSI B30.2 for periodic inspetion and test, or where frequency of crane use is less than the specified inspection and test frequency (e.g. the polar crane i.s used every 12 to 18 months during refueling operations and is generally not accessible during,power operation).
2.1.8. Crane Desi n Guideline 7, .NUREG-0612, Article 5.1.1(7))
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- a. FRC Conclusion Turkey Point Units 3 and 4 comply with Guideline 7, to a substantial degree, on the basis'f compliance with EOCI-61 criteria. However, insufficient, information has been made available to verify that the following CMAA-70 requirements have been satisfied for cranes subject to this review. The Licensee should make this information available or provide suitable justification for concluding that the requirements.of CHAA-70 have been satsisfied by equivalent means.
- 1. Hoist lifting speeds do not exceed 30 feet per minute;
- 2. Nonsymmetrical girder secti'ons were not, used in crane construction.
- 3. Any longitudinal stiffeners in use conform to the requirements of CtlAA-70, and allowable h/t rations in box girders using these stiffeners do not exceed ratios specifi ed in CMAA-70.
4~ Girders with b/c ratios in excess of 38 were not used.
Fatigue failure was considered in crane design and the number of design loading, cycles at or near rated load is less than 20,000 cycles.
- 6. 'Maximum crane load weight, plus the weight of the, bottom block, divided by the number of parts of rope does not exceed 205 of the manufacturer's published breaking strength.
- 7. Drum design calculations were based on the combination of crushing and bending loads.
- 8. Drum groove depth and pitch conform to the recommendations of CMAA-70.
Gear horsepower ratings were based on design allowables and calculation methodology equivalent to the incorporated in CMAA-70.
- 10. A cab-control, cab-on trolley configuration was not used.
Mechanical load brakes or hoist holding brakes with torque ratings of appr oximtely 125$ of the hoist motor torque were used..
- 12. Crane operation under load near the end of bridge or troll'ey travel is not allowed or is compensated for by bumpers and stops which satisfy the .intent of CMAA-70.
- 13. Any static control -systems in use conform to the requirements of CMAA-70.
- 14. Controllers in use are the spring-return or.momentary-contact pushbutton type or are equipped with a device which, disconnects all motors on power failure and will not permit restart until controller handle is brought to the OFF position.
- b. FPL Position lie are reviewing the comments of the reviewers concerning crane design. We expect to provide a response to this item by the end of September, 1982.
~ 2.2 INTERIM PROTECTION MEASURES" 2.2. 1 Technical Specifications ( Interim Protection Measure 1 NUREG-0612, Artcc e 5.3 1
- a. FRC Conclusions 8 Recommendations The Licensee made no statements or conclusions regarding this interim protection measure..
- b. FPL Positi'on This interim measure was not included in the NRC letter dated December 22, 1980 {Control of Heavy Loads) 2.2.3 Special Reviews for Heavy Loads Over the Core Interim Protection Measure 6 NUR G-0612, Artcc e 5.3. 6
- a. FRC Conclusions 8t Recommendations c%
Insufficient information has been provided for Turkey Point Units 3 and 4 to evaluate compliance with interim Protection Measure 6. The intent of this interim mesure was to provide, on the basis of a one-time detailed inspection, assurance of a high degree of load handling system reliability during the peri od when certain hardware-associated guidelines (Guidelines 4., 5, and 7) were being .evaluated. A general review of crane operations to establish procedure improvements may not meet the intent of tni s i nterim measur e. In oroer to allow a finding of compliance, the Licensee should provide sufficient information for FRC to verify that the extent of this review',
was comparable to that identified for this interim protection measur e.
- b. There was no request for a written response to this Interim Action item in- the December 22, 1980 NRC letter. Me did however, provide a brief response saying that the requested review had been conducted and that operations over the core were addressed in the plant, maintenance procedure.
REFERENCES NUREG-0612 "Control of Heavy..Loads at Nuclear Power Plants", NRC, July 1980
- 2. NRC Letter to all Licensees
Subject:
Contro'1 of Heavy Loads, December 22, 1980
- 3. R.E. Uhrig (FPL) letter to D.G. Eisenhut (NRC)
Subject:
Control of Heavy, Loads, Turkey Point Units 3 5 4 4~ R. E. Uhrig (FPL) letter to D.G. Ei senhut (NRC)
Subject:
Control of Heavy Loads {L-81-473), November 12, 1981 Draft Technical Evaluation Report Control of Heavy Loads, Turkey Point Units 3 5 4 FRC, December 29, 1981 ATTACHMENTS E
Safe Load Paths {as revised in final response) 24 Exceptions to ANSI 830.2-1976 for Crane Operator Training
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~ L-,81-.473< dated November 12, *1981 A 1:,TACill:iE.V r Re: Turkey l'oint Units No. 3 and No. 4 interim) Actions for Control of )leavy Loads Tlie IIRC letter date.l December 22, I980 (subj< "t: Control o. Heavy Loads) r!~quested im:,)':erne!!tation of interiim ac'ions fur tl',. trodi)ii>>g, quahification, arid conduct of crane operators. Florid~ Powe) 5 l.ight wii i):.pie;;; nt at 1
Turkey Point Unit ho.. 3 and 4), S<<cti<<n 2-3.1 (I;ual il'icatio>>s for and conduct of Operators) of Cha,)ter 2-3 of MSI Standard B 30.2-I)75 wi th the.al'lowing exceptions to the re-erenced paragraplis:
Paragraph 2-'3.1.2. he ilail 1'equire an eye t<<st of 2U/4U in both eyes for oew employees.
Paragraph 2-3.1.7.f, g and h. Because or tiie l)ower requireinents ot tlie crane motor li aters, we will meet the intent ot these .requireiments by using tiie crane dead mian switch instead ot the miain line disconnect devices.
Paragraph 2-3.'..7. He wi 11 test tliose controls necessary for the crane .
operations to bu conducted.
Paragraph 2-3. 1.7.n. Safety dur ing inaintenance work on cranes wi 1'1 be ln accordance witli tlie plant clearance proceduie.
The remainder of Chapter 2-3 o tlie ANSI Standard (i.e.: llandl ing the Load, Attaching the Load, Yioving the Load, 'rloist Limit 0 vicl., Signals, f~iscellaneous) w',l l be met in a gener 1 imanner in procedures or in crane operator tra Ill llg wi th tlie f o 1 1 1'owl ilg excl.",)' 0'1:
Paragrapli 2-3.2.4.a. At stiilt cliangu, we wi l l try out tiie upper limit device uiider no load unless a load is nanging tron the hook at shift change or Unless io era)le Oper tiuil 1n th.'rea of tile ul)Per l.imit is antici oated.
0 RFCElQED FLORIOA POWER & LIGHT COMPANY AUG 6 8@
!NTER-OFFICE CORRESPONDENCE Nuclear Licensing LOCATION Nuclear Energy TO R.E. Uhrig DATE AUG 5 i982 FROM J.W. Williams, Jr. COPIES TO R.J. Acosta D.W. Jones
SUBJECT:
TURKEY POINT UNITS 3 8 4 C.S. Kent CONTROL OF HEAVY LOADS H.N. Paduano/910.27 TP DRAFT TER H.E. Yaeger/J.K. Hays J.A. Yespica PNS-LI-S2-237 The subject information is attached for your review and forwarding to the NRC. The attachment was prepared in accordance with the requi rements of iiP 2. 13 for a submittal not ~re ui ri n an affidavit.
Except for the following, the attachment is fully responsive to the NRC requirements or differences are clearly noted in the attached: None The information- in the attachment, except for a few minor items, was provided by EPP.
J.W. Williams, Jr.
PLP/mbd Attachment PEOPLE... SERVING PEOPLE Form 1008 (Stoclsed) Rev.
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