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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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.FLORIDA.POWER.S.LIG~MPANY November 12, 1981 L-81-473 Office of Nuclear Reactor Regulation Attention: Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Eisenhut:
Re: Turkey Point Units 3 8 4 Docket No. 50-250, 50-251 Control of Heavy Loads As requested by an NRC letter, dated December 22, 1980, Florida Power 8 Light has conducted a review of controls for the handling of heavy loads at Turkey Point Units 3 8 4. This review was conducted in accordance with NUREG 0612, "Control of Heavy Loads at Nuclear Power Plants - Resolution of TAP A-36."
An update to our report of interim action taken on this subject and a report in response to Sections 2.2, 2.3, and 2.4 of Enclosure 3 to the December 22, 1980 letter are attached.
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Robert E. Uhrig Vice President Advanced Systems and Technology REU/PLP/Qbd 3
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PD~R PEOPLE... SERVING PEOPLE
ATTACHMENT Re: Turkey Point Units No. 3 and No. 4 Interim Actions for Control of Heavy Loads The NRC letter dated December 22, 1980 (subject: Control of Heavy Loads) requested implementation of interim actions for the training, qualification, and conduct of crane operators. Florida Power 5 Light will implement, at Turkey Point Unit No. 3 and 4, Section 2-3.1 (gualifications for and conduct of Operators) of Chapter 2-3 of ANSI Standard B 30.2-1976 with the following exceptions to the referenced paragraphs:
Paragraph 2-3.1.2. We will require an eye test of 20/40 in both eyes for new employees.
Paragraph 2-3. 1.7.f, g and h. Because of the power requirements of the crane motor heaters, we will meet the intent of these requirements by using the crane dead man switch instead of the main line disconnect devices.
Paragraph 2-3.1.7. We will test those controls necessary for the crane operations to be conducted.
Paragraph 2-3.1.7.n. Safety during maintenance work on cranes will be in accordance with the plant clearance procedure.
The remainder of Chapter 2-3 of the ANSI Standard (i.e.: Handling the Load, Attaching the Load, Moving the Load, Hoist Limit Device, Signals, ili scellaneous) will be met in a general manner in procedures or in cr ane operator training with the following exception:
Paragraph 2-3.2.4.a. At shift change, we will try out the upper limit device under no load unless a load is hanging from the hook at shift change or unless no crane operation in the area of the upper limit is anticipated.
TURKEY POINT UNITS 3 AND 4 RESPONSE TO NRC RE UEST FOR ADDITIONAL INFO%STION ON CONTROL OF HEAVY LOADS NUREG 0612 SECTIONS 2.2 2.3'ND 2.4 SPECIFIC R~EUIREMENTS'
TABLE OF CONTENTS Section Title ~Pa e Introduction Specific Requirements for Overhead Handling Systems Operating in the Vicinity of Fuel Storage Pools (Section 2.2)
Overhead Handling System Operating in the Containment (Section 2.3)
IV Overhead Handling Systems Operating in Plant Areas Containing Equipment
,Required for Reactor Shutdown, Core Decay Heat Removal, or Spent Fuel Pool Cooling (Section 2.4)
. Summary and Clarification of Response to 'General Requirements (Section 2.1)
VI References APPENDIX List of Fi ures
~Fi ures 1 Safe Load Path Turbine Gantry Cranes 2a ~ Safe Load Path Reactor Polar Crane Unit f33 2b. Safe Load Path Reactor Polar Crane Unit //4 Safe Load Path Spent Fuel Cask Handling Cranes Safe Load Path Intake Structure Bridge Crane ATTACHMENT
I. Introduction This report is submitted in response to the NRC generic letter "Control of Heavy Loads"'ated December 22, 1980. The NRC letter requests a two part response to the "Request for Addi'-
tional Information" (Enclosure 3 of the letter). The first part of the response, concerning the general requirements for overhead load handling systems, has been previously submitted.
This report contains the second response providing information Section II, III and IV of this on the specific requirements.
report provides the information corresponding to Sections 2 2.3 and 2.4 of the "Request for Additional Information."
Section V p'rovides a summary with a clarification of the pre-vious response based upon findings in this report.
II. S ecific Re uirements for Overhead Handlin S stems Ooeratin Section 2.2 of Enclosure 3 of the December 22, 1980 NRC generic letter requests specific information concerning the design and operation of load-handling systems in the vicinity of stored, spent fuel. It requests that the information provided should demonstrate that adequate measures, have been taken to ensure that in this area, either the likelihood of a load drop which might damage spent fuel is extremely small, or that the consequences of such a drop will not exceed the limits set by the evaluation criteria of NURFG 0612, Section 5.1. The following discussion demonstrates how the above requirements are met in this area..
The following is a list of heavy load handling systems physi-cally capable (i.e., ignoring interlocks, moveable mechanical stops, or operating procedures) of carrying load's which .could, if dropped, land'r fall into the spent fuel pool.
Equipment
'Name ~Ca acit .
Spent Fuel Cask Crane 105 tons-main hook hhiting Company (1 serves both units) 15 tons-aux. hook Fuel Pool Bulkhead 2 tons American Chain and Cable Monorail (1 ea. unit)
The Spent Fuel Handling Machine and the New Fuel Monorail are not included above since these devices do not handle "heavy loads",'ce., loads weighing more than the weight of a spent fuel assembly with lifting tool. This exclusion is based upon Section 2.2.2 of Enclosure 3 of the NRC generic letter.
The S ent Fuel Cask Crane is used to transport the spent fuel cask in and out of the spent fuel storage pools of both .units.
Although the crane is rated for 105 tons, the Technical Specifi-cations prohibit the handling of loads larger than 25 tons in the pool. The Technical Specifications also prohibit movement of a spent fuel shipping cask over fuel assemblies stored in
,the spent fuel storage pool. To assure that this requirement will not be violated, FPSL has installed a shipping cask crane movement interlock system. The crane is s~itched into this re-stricted movement mode when the cask is being handled in the spent fuel pool. This is a requirement of Operating Procedure 16702.1 "Spent Fuel Shipment Using Model NFS-4 Shipping Cask."
Bypassing of the limit switches during cask handling operations is allowed only after the cask has been lowered to the bottom of the pool to allow trolley movement to facilitate unlatching of the crane hook from the cask lifting yoke. The operability of the restricted-zone interlocks is verified prior to their required use in accordance with ANSI B30. 2 "Overhead and Gantry Cranes."
Since the Technical Specifications and the interlock system prohibit the movement of a shipping cask over spent fuel, an accident resulting in a shipping cask falling upon stored fuel assemblies could only occur from the dropped cask tipping dur-ing its fall. The potential radiological consequences result-ing from such an accident were evaluated and found to be well within 10CFR100 limits assuming the spent fuel has decayed a minimum of 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />. Technical Specification 3.12 "Cask Handling" assures that this assumption remains valid.
The cask drop accident was reviewed by the NRC staff to deter-mine if Keff ff could be significantly affected by a change in fuel assembfy configuration resulting from the dropped cask im-pacting the fuel storage racks. Based upon the review (Reference
- 7) it was concluded that the required use of borated water at the refueling boron concentration in the spent fuel pools will assure that Keff remains less than 0.95 for all possible cask droP accidents.. A Keff of less than 0.95 satisfies NRC require-ments and assures that no undesirable criticality conditions will result from a dropped and tipped cask accident.
The fuel pool slab was evaluated for a vertical cask .drop assuming a 2 foot free fall and a water depth of 40 feet. The evaluation determined that the fuel pool integrity is main-tained in the event of a cask, drop accident.
The foregoing discussion and evaluation of the cask handling system and potential cask drop accidents has been previously-submitted and accepted by the NRC staff (Reference 8) and is reiterated here for the sake of completeness. It has been demonstrated that a cask drop accident over the spent fuel assemblies is unlikely due to the design of the cask handling system and that, in .the event of such an accident, the consequences are within- acceptable limits. In addition, in order to achieve maximum practicable "defense-in-depth" the interim requirements and general guidelines of NUREG 0612 are being implemented for the operation of the Spent Fuel Cask Crane. This includes a safe load path which is shown on Figure 3.
The Fuel Pool Bulkhead Monorail is used to lift and move the pool gate bulkhead from the normal location on the inside face of the spent .fuel pool to the designated storage loca-tion. The monorail is located directly above the inside face of the wall and does not travel over the spent fuel racks. A special procedure MP 1407.23 "Removal and Installa-tion of the Spent Fuel Pit Keyway Gate" has been prepared for the handling of the bulkhead which delineates steps and the proper sequence to be followed.
III. R ecific Re uiremenrs for Overhead llandlin S seems 0 sr~aria in the Containment Section 2.3 of Enclosure 3 of the December 22, 1980 NRC generic letter requests specific information concerning the design and operation of load-handling systems in the vicinity, of the reac-tor core. It requests that the information provided should demonstrate that adequate measures have been taken to ensure that, in this area, either the likelihood of a load drop which might damage spent fuel is extremely small, or that the conse-quences of such a drop will not exceed the limits set by the evaluation criteria of NUREG 0612, Section 5.1. The following d'iscussion demonstrates how the above requirements are met.
The following crane is physically capable (i.e., ignoring inter-locks, moveable mechanical stops,, or operating procedures) of carrying heavy loads over the .reactor vessel.
Equipment Name ~Ca acicy Desi natbr Polar Crane 135 tons Main Hook f~hiting Company 35 tons-Aux Hook 3.
The Manipulator Crane is not listed since it does not handle "heavy loads", i.e., loads weighing more than the weight of a spent fuel assembly with lifting tool.
The Turkey Point Plant Maintenance Procedure 0736, "Heavy Load Handling" defines a safe load path (Figures 2a and 2b) which prohibits hook travel over the reactor vessel without prior special approval. However, during plant maintenance and refueling operations it is sometimes necessary to carry heavy loads over the reactor vessel. Special procedures have been prepared for those loads which are handled periodically over the reactor vessel and have been referenced in FP&L's first phase response (Reference 5). These proce-dures identify the required equipment; inspection and acceptance criteria required before movement of the load; the steps and proper sequence to be followed'n handling the load; the load path and any special precautions. Any load lifts not covered by a special procedure are controlled generically by the Plant Maintenance Procedure 0736 previously mentioned. This proce-dure requires that approval from the Maintenance Superintendant be obtained prior to movement of these loads over the reactor vessel. The Maintenance Superintendant will assure that the proper controls are present.
In addition to these procedures, which are available at'he site for review, safe operation of the cranes is assured by the crane maintenance and operator training and qualification
'programs whi'ch 'follow'ANSI; B30.2".-1976 guidelines., Based upon FP&L's review of the procedures, equipment and personnel used in load handling operations over the core, we believe that the likelihood of the load drop in the area is extremely small.
IV. ~S ecific Re uirements for Overhead Handlin S stems 0 eratin in Plant Areas Containin E ui ment Re uired for Reactor Shut-down, Core Deca Heat Removal or Spent Fuel Pool Coolin Section 2.4 of Enclosure 3 of the December 22, 1980 NRC generic letter requests specific information concerning the design: and operation of load-handling systems in the vicinity of equipment or components required for sa'fe reactor shutdown and decay heat removal. It requests that the information provided should demonstrate that adequate measures have been taken to ensure that in these areas, either the likelihood of a load drop ->which might prevent safe reactor shutdown- is extremely small, or that damage to such equipment from load drops vill be limited in or-der not to result in the loss of their safety-related functions.
The following discussion demonstrates how the above requirements are met.
The following is a list of cranes from which a load drop .may result in damage to any system required for plant shutdown or decay heat removal, taking no credit for any interlocks, tech-nical specifications, operating procedures or detailed struc-tural analysis. This list includes those cranes of this type
in Group I of Table 1 of the initial response to the NRC generic letter.
Equipment Name ~ca acit (tons) Desi nator Charging Pump Mono- American Chain and Cable rails Safety Injection American Chain and Cable Pump Monorails Main Steam Platform American Chain and Cable Spent Fuel Cask 105 Main Hook Whiting Company Bridge Crane 15 Aux. Hook Turbine Building 145 Main Hook Whiting Company Gantry Crane 35 Aux. Hook Units 3 & 4 Turbine Building 70 Main Hook Harnischfeger Gantry Crane 15 Aux. Hook Units 1 & 2 Intake Structure 25. Whiting Company Bridge Crane Reactor Polar 135 Main Hook Whiting Company Cranes 35 Aux Hook listed since a load drop from these monorails could potentially damage a safe shutdown system. In every case, however, the component which could potentially be damaged from a load drop would be inoperative for maintenance purposes. These monorails are used for maintenance of these pumps only and are not required to carry heavy loads over operational safety related equipment to reach the laydown area. The Technical Specifications require that one redundant system must be operational in order to remove the other train from service for maintenance. Therefore, plant safe shutdown capability would not be defeated by a load drop on a component which is being serviced, since a backup system will be operational.
The Hain Steam Platform Monorails are used to remove safety related valves. However, these valves can only be removed when the plant is shut down and their safety related function not required. These monorails handle no other heavy loads.
The Spent Fuel Cask Brid e Crane is located on the Reactor Auxiliary Building roof and serves both units. The principal function of this crane is the movement of the spent fuel cask as described in Section II of this report. Under normal conditions this is the heaviest load handled by the crane in the vicinity of safety related equipment or fuel. Cask drop analyses along the cask travel path were performed (see Reference 8) wherein it was determined that postulated accidents can be acceptably accomodated and unit safe-shutdown capability is maintained. The crane is also used to handle relatively light loads over the Reactor Auxiliary Building roof.
There is no safety related equipment within the operating envelope of the crane hook which could be directly impacted by a load drop.
Safety related components within the Reactor Auxiliary Building are protected from potential load drops by a reinforced concrete roof with a minimum thickness of one foot supported by structural steel framing. The Component Coolin'g Mater equipment under the crane operating envelope is similarly protected by steel framing and heavy duty grating. In order to assure that only light loads are handled in these areas, the plant Maintenance Procedure 0736 "Heavy Load Handling" restricts the handling of loads greater than 5 tons over the concrete roof area and 1760 pounds over the Component Cooling. Mater area grating (refer to Figure 3). Also, as mentioned previously, the interim requirements and general guidelines of NUREG 0612 are being implemented for the operation, maintenance and qualification of operators for this crane to minimize the possibility of a load handling accident and to achieve maximum "defense-in-depth".
The Unit No. l and 2 (fossil) and Unit No. 3 and 4 Turbine ~Uantr Cranes can operate over the Unit No. 3 and 4 Turbine Building. Two reinforced concrete enclosed switchgear rooms, one for each unit, are located within the range of Turbine Gantry Crane operating envelope. Although it is considered highly unlikely that a heavy load drop could penetrate the two foot thick concrete roof and cause sufficient damage to equipment located in this room that would result in defeating plant safe shutdown capability or decay heat removal, the handling of heavy loads is restricted in this area. A safe load path has been defined for this crane (refer to Figure 1) which prohibits the handling of loads in excess of 5 tons in this area. In addition to the safe load path, in order to achieve maximum practicable "defense-in-depth", the interim requirements and general guidelines of. NUREG 0612 have been adopted for. the operation, maintenance and qualification of operators for this crane.
The Intake Structure Brid e Crane could potentially carry heavy loads over the Intake Cooling Mater (ICM) pumps. However, a review of the loads handled by this crane has identified no heavy loads which are normally carried over the ICM pumps, Also, if a heavy load drop is postulated it is considered un-likely that such an event could cause sufficent damage to the
redundant ICW systems to defeat safe shutdown and decay heat removal. To assure that no heavy loads are carried over the pumps a safe load path has been defined which restricts load handling in this area (refer to Figure 4). Also, the interim requirements and general guidelines of NUREG 0612 have been implemented for this crane.
The Reactor Building Pol'ar Crane is operated during plant cold shutdown and refueling modes. During these modes the residual heat removal (RHR) system is required to remain functional to remove decay heat from the reactor core. Since the piping for thi's system is within the hook envelope of the reactor polar crane, heavy load drops are reviewed.
The majority of the RHR piping in the containment is located within the confines of the reinforced concrete internal struc-ture. The piping within this area is considered to be adequately protected from load drops. On the one side of the buil'ding the piping exits the internal structure and follows the containment wall to the piping penetration area.
Although there is .structuxal steel framing between the piping and the crane which will provide some protection, load handling will be restricted in this area. This area is indicated on the safe load path sketches on Figure 2a and 2b.
As previously stated in Section III of this report, the NUREG 0612 general guidelines and interim requirements have been adopted for the operation of the Reactor Building Polar Crane.
V. Summar and Clarification of Res onse to General Re uirements This report documents the final phase of FPL&L's revi'ew of the controls for the handling of heavy loads at Turkey Point Units 3 and 4 as requested by the NRC generic letter dated December 22, 1980. As a result of the findings in this report, the safe load path sketches presented in the first phase response have been changed' complete set of the new safe load path sketches are presented in Figures 1 through 4.
The results of Florida Power and Light Company's review of NUREG 0612 finds no equipment modifications required to meet the NUREG 0612 specific requirements. New proceduxes, training programs and other actions necessary to comply with the interim requirements and general guidelines are being implemented and have been addressed in the previous response. A training program in accordance with ANSI B 30. 2-1976 has been developed and our standard company physical for new employees generally 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 available at the site for review.
VI References
- 1. NUREG 0612 "Control of Heavy Loads at Nuclear Power Plants"
- 2. NRC Generic Letter "Control of Heavy Loads" dated December 22, 1980.
- 3. Enclosure 2 of Generic Letter "Staff Position Interim Actions for Control of Heavy Loads"
- 4. Enclosure 3 of Generic Letter ":Request for Additional Information on Con'trol of Heavy Loads"
- 5. FPL letter L-81-382 to. Mr. Eisenhut of NRC dated September 4, 1981, "Co'ntrol of Heavy Loads" (First Phase response).
- 6. Plant Maintenance Procedure 0736 "Heavy Load Handling"
,7. Safety Evaluation by the Office of Nuclear Reactor Regulation
-Supporting Amendment No. 23 to License No. DPR-31 and Amendment No. 22 to License No. DPR-41.
- 8. FPL letter L-78-324 to Mr. Stello of NRC dated October 4, 1978 "Control of Heavy Loads"
APPENDIX L
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STATE OF FLORXDA )
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John A. DeMastry, being first duly sworn, deposes and says:
That he is Manager, Nuc1ear Licensing of Florida Power S Light Company, the Licensee herein; That he has executed the foregoing document; that the state-ments made in this said document are true and correct to the best of his knowledge,.information, and belief, and that he is authorized to execute the document on behalf of said Licensee.
John A.'eHastry Subscribed and sworn to before me this
~ day of
-->>NOTARY PUBLXC, and fo" the County of Dade, fS tate,,'o f;,.'"F 1 or i Notary Public. Stato of Florida at Largo My commission expires: