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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17355A4601999-10-26026 October 1999 Forwards Revised Epips,Including Revs to 0-EPIP-1102, 0-EPIP-1212,0-EPIP-20110,0-EPIP-20111,0-EPIP-20132, 0-EPIP-20133 & 0-EPIP-20201,per 10CFR50.54(q) & 10CFR50, App E.Epip 0-EPIP-20107,has Been Deleted ML17355A4301999-10-0808 October 1999 Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included ML17355A4461999-10-0404 October 1999 Notifies NRC of Change in Commitment to Perform Periodic Testing of Critical Welds & Parts on Special Lifting Devices IAW NUREG-0612.Use of Ae Technology Will Provide Same Level of Testing Quality as Did NDE Methods Noted in ANSI Std L-99-208, Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included1999-10-0404 October 1999 Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included ML17355A4291999-10-0404 October 1999 Forwards Response to NRC Telcon Questions Re License Amend Request Dtd 990727,proposing Amend on one-time Basis to Modify TS 3.8.1.1 & TS 3.4.3 & 3.5.2 to Extend Allowed Outage Time for EDG from 72 H to 7 Days ML20212M1601999-09-28028 September 1999 Refers to 990908 Engineering Meeting Conducted at NRC Region II to Discuss Engineering Issues at Lucie & Turkey Point Facilities.List of Attendees & Copy of Presentation Handout Encl ML17355A4251999-09-22022 September 1999 Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820 ML17355A4111999-09-0909 September 1999 Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08 ML17355A4131999-09-0707 September 1999 Forwards Revised Relief Request 20 Re Requirement to Perform Exams as Required by IWL-2524 & IWL-2525,Table IWL-2500-1 for Exempt Tendon Insp,Per Recent Discussions with NRC ML17355A4141999-09-0202 September 1999 Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830 ML17355A4041999-08-23023 August 1999 Forwards Info to Support Assessment of Potential Risks Associated with Proposed Civil Aircraft Operations at Former Homestead Air Force Base to FP&L Turkey Point Nuclear Facility Units 3 & 4 ML17355A4071999-08-23023 August 1999 Informs That FPL Has Completed Review of Info Listed in Reactor Vessel Integrity Database,Version 2 & Found Listed Discrepancies,Re Closure of GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. ML17355A4061999-08-23023 August 1999 Forwards Semiannual FFD Performance Rept for Period of Jan- June 1999,for Turkey Point Units 3 & 4.List of Events Reported & Summary of Mgt Actions Taken,Included ML17355A4001999-08-20020 August 1999 Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance ML17355A3941999-07-27027 July 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01 ML17355A3871999-07-16016 July 1999 Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17355A3851999-07-14014 July 1999 Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of Rept ML17355A3711999-07-0606 July 1999 Forwards Revised EPIPs 0-EPIP-20201, Maintaining Emergency Preparedness - Radiological Emergency Plan Training & 0-EPIP-20126, Off-Site Dose Calculations. with Summary of Changes ML17355A3591999-06-30030 June 1999 Forwards Turkey Point,Unit 4 ISI Rept. Listed Repts Are Encl.No Eddy Current Exams Scheduled for Unit 4 Steam Generators ML17355A3661999-06-30030 June 1999 Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998 ML17355A3571999-06-28028 June 1999 Informs That Util Voluntarily Reporting Facility Readiness as Outlined in Suppl 1 to GL 98-01.Encl Is Y2K Readiness Disclosure for Units 3 & 4,reporting Status of Facility Y2K Readiness ML17355A3521999-06-18018 June 1999 Forwards Response to NRC 990415 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML17355A3491999-06-0404 June 1999 Forwards Summary of Corrective Actions Implemented by FPL Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions. ML17355A3441999-05-27027 May 1999 Modifies FPLs Consent to Confirmatory Order to Reflect Resolution of Four Issues Identified as Pending in L-99-031 ML17355A3451999-05-24024 May 1999 Requests Waiver of 520 Hours (13 Wks) Required Parallel Watchstanding in Control Room Prior to License Application Submittal for W Conley ML17355A2921999-04-22022 April 1999 Forwards Rev 35 to Turkey Point EP & Revised EPIP 0-EPIP-20101, Duties of EC, Per Requirements of 10CFR50, App E & 10CFR50.54(q).Summary of Changes,Encl.Implementation Date for Both Documents Was 990330 ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML17355A2891999-04-0909 April 1999 Forwards Relief Request 20, Exempt Tendon Insp, Requesting Relief from ASME Section XI Code,1992 Edition,Paragraph IWL-2521.1(c) Which Requires That Each Exempted Tendon Be Examined IAW IWL-2524 & IWL-2525.Approval Needed by 991001 ML17355A2861999-04-0505 April 1999 Forwards COLR for Turkey Point Unit 4,Cycle 18,IAW TS 6.9.1.7 ML17336A0681999-04-0101 April 1999 Expresses Support for FP&L Request for Waiver of Applicable Review Fees Upon FP&L Submittal of an Application for License Renewal for Turkey Point Units 3 & 4 ML17355A2751999-03-25025 March 1999 Informs NRC & Staff of Fp&Ls Plans to Submit License Renewal Application for Turkey Point Units 3 & 4 by End of Dec 2000 ML17355A2641999-03-19019 March 1999 Requests Changes to FPL Official Service List for Turkey Point,Units 3 & 4.Add s Franzone & Remove G Hollinger from All Correspondence ML17355A2651999-03-19019 March 1999 Forwards Annual Radioactive Effluent Release Rept for Jan-Dec 1998 & Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point,Units 3 & 4. ML17355A2621999-03-16016 March 1999 Forwards Special Rept as Result of Turkey Point Unit 3 End-of-Cycle 16 ISI of SG Tubes.Rept Summarizes Results of SG Tube ISI ML17355A2631999-03-12012 March 1999 Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit ML20204C6991999-03-10010 March 1999 Requests Amend to Turkey Point PSP to Modify Requirement to Post Security Officers to Provide Continuous Observation of Entire PA Perimeter in Event of Security Computer Failure. Change to Security Force Staffing Level Also Requested ML17355A2451999-03-0909 March 1999 Submits Info on FPL Current Levels of Nuclear Property Insurance,Per 10CFR50.54(w)(3) ML17355A2501999-03-0808 March 1999 Informs That Licensee Reviewed NRC 990228 Ltr Issuing Exemption Requested Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg.Tabulated Summary of Util Comments & Marked Copy of NRC Ltr & SER Encl ML17355A2441999-03-0101 March 1999 Provides Update to Util Written Notices,Dtd 961120 & 970627 of Claim Involving Alleged Bodily Injury Arising Out of or in Connection with Use of Radioactive Matl at Units 3 & 4 ML17355A2431999-02-25025 February 1999 Informs That FPL Does Not Have Any Candidates from Turkey Point Scheduled to Participate in 990407,Generic Fundamentals Examination (GFE) ML17355A2301999-02-18018 February 1999 Forwards Semiannual Fitness for Duty Performance Data for Period of 980701-981231 for Turkey Point Units 3 & 4 ML17355A2361999-02-18018 February 1999 Forwards Tabulation of 1998 Occupational Exposure Data for Turkey Point,Units 3 & 4,per TS 6.9.1.2.a.Reactor Coolant Specific Activity Limits of 100/E-bar Mci Per Gram of Gross Radioactivity Were Not Exceeded During 1998 L-99-042, Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3)1999-02-18018 February 1999 Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3) ML17355A2341999-02-18018 February 1999 Provides Response to RAI Re GL 97-01, Degradation of Crdm/ CEDM Nozzle & Other Vessel Closure Head Penetrations. ML17355A2231999-02-0808 February 1999 Informs That Util Will Comply with Commitment with Respect to Units 3 & 4,in Response to Ja Zwolinski 990129 Ltr.Util Also Agrees to Incorporate Commitment Into Confirmatory Order Modifying License Effective Immediately Upon Issuance ML17355A2031999-01-29029 January 1999 Forwards Rev 3 to Turkey Point Nuclear Plant Recovery Plan. Rev Does Not Decrease Effectiveness of Plan ML17355A2171999-01-20020 January 1999 Forwards Listed ISI Repts for Turkey Point Unit 3,in Accordance with Provisions of ASME Code,Section XI ML17354B2241999-01-0606 January 1999 Forwards Annual 10CFR50.46 Rept Re Changes To,Or Errors Discovered in ECCS Evaluation Models,Or in Application of Such Models That Effect Peak Clad Temp Calculation ML17354B2081998-12-15015 December 1998 Informs That Fpl,In Cooperation with State of Fl & County Emergency Response Agencies,Will Conduct Exercise of Turkey Point Radiological Emergency Plan on 990210.Scenario Package Forwarded to Emergency Preparedness Section Chief,Region II ML17354B2091998-12-15015 December 1998 Forwards Price Anderson Guarantees Annual Financial Rept,Per 10CFR140.21.Exhibit 1 Submitted to Satisfy Annual Financial Reporting Requirement of 10CFR50.71(b) 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17355A4601999-10-26026 October 1999 Forwards Revised Epips,Including Revs to 0-EPIP-1102, 0-EPIP-1212,0-EPIP-20110,0-EPIP-20111,0-EPIP-20132, 0-EPIP-20133 & 0-EPIP-20201,per 10CFR50.54(q) & 10CFR50, App E.Epip 0-EPIP-20107,has Been Deleted ML17355A4301999-10-0808 October 1999 Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included ML17355A4461999-10-0404 October 1999 Notifies NRC of Change in Commitment to Perform Periodic Testing of Critical Welds & Parts on Special Lifting Devices IAW NUREG-0612.Use of Ae Technology Will Provide Same Level of Testing Quality as Did NDE Methods Noted in ANSI Std L-99-208, Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included1999-10-0404 October 1999 Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included ML17355A4291999-10-0404 October 1999 Forwards Response to NRC Telcon Questions Re License Amend Request Dtd 990727,proposing Amend on one-time Basis to Modify TS 3.8.1.1 & TS 3.4.3 & 3.5.2 to Extend Allowed Outage Time for EDG from 72 H to 7 Days ML17355A4251999-09-22022 September 1999 Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820 ML17355A4111999-09-0909 September 1999 Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08 ML17355A4131999-09-0707 September 1999 Forwards Revised Relief Request 20 Re Requirement to Perform Exams as Required by IWL-2524 & IWL-2525,Table IWL-2500-1 for Exempt Tendon Insp,Per Recent Discussions with NRC ML17355A4141999-09-0202 September 1999 Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830 ML17355A4041999-08-23023 August 1999 Forwards Info to Support Assessment of Potential Risks Associated with Proposed Civil Aircraft Operations at Former Homestead Air Force Base to FP&L Turkey Point Nuclear Facility Units 3 & 4 ML17355A4071999-08-23023 August 1999 Informs That FPL Has Completed Review of Info Listed in Reactor Vessel Integrity Database,Version 2 & Found Listed Discrepancies,Re Closure of GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. ML17355A4061999-08-23023 August 1999 Forwards Semiannual FFD Performance Rept for Period of Jan- June 1999,for Turkey Point Units 3 & 4.List of Events Reported & Summary of Mgt Actions Taken,Included ML17355A4001999-08-20020 August 1999 Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance ML17355A3941999-07-27027 July 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01 ML17355A3871999-07-16016 July 1999 Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17355A3851999-07-14014 July 1999 Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of Rept ML17355A3711999-07-0606 July 1999 Forwards Revised EPIPs 0-EPIP-20201, Maintaining Emergency Preparedness - Radiological Emergency Plan Training & 0-EPIP-20126, Off-Site Dose Calculations. with Summary of Changes ML17355A3591999-06-30030 June 1999 Forwards Turkey Point,Unit 4 ISI Rept. Listed Repts Are Encl.No Eddy Current Exams Scheduled for Unit 4 Steam Generators ML17355A3661999-06-30030 June 1999 Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998 ML17355A3571999-06-28028 June 1999 Informs That Util Voluntarily Reporting Facility Readiness as Outlined in Suppl 1 to GL 98-01.Encl Is Y2K Readiness Disclosure for Units 3 & 4,reporting Status of Facility Y2K Readiness ML17355A3521999-06-18018 June 1999 Forwards Response to NRC 990415 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML17355A3491999-06-0404 June 1999 Forwards Summary of Corrective Actions Implemented by FPL Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions. ML17355A3441999-05-27027 May 1999 Modifies FPLs Consent to Confirmatory Order to Reflect Resolution of Four Issues Identified as Pending in L-99-031 ML17355A3451999-05-24024 May 1999 Requests Waiver of 520 Hours (13 Wks) Required Parallel Watchstanding in Control Room Prior to License Application Submittal for W Conley ML17355A2921999-04-22022 April 1999 Forwards Rev 35 to Turkey Point EP & Revised EPIP 0-EPIP-20101, Duties of EC, Per Requirements of 10CFR50, App E & 10CFR50.54(q).Summary of Changes,Encl.Implementation Date for Both Documents Was 990330 ML17355A2891999-04-0909 April 1999 Forwards Relief Request 20, Exempt Tendon Insp, Requesting Relief from ASME Section XI Code,1992 Edition,Paragraph IWL-2521.1(c) Which Requires That Each Exempted Tendon Be Examined IAW IWL-2524 & IWL-2525.Approval Needed by 991001 ML17355A2861999-04-0505 April 1999 Forwards COLR for Turkey Point Unit 4,Cycle 18,IAW TS 6.9.1.7 ML17336A0681999-04-0101 April 1999 Expresses Support for FP&L Request for Waiver of Applicable Review Fees Upon FP&L Submittal of an Application for License Renewal for Turkey Point Units 3 & 4 ML17355A2751999-03-25025 March 1999 Informs NRC & Staff of Fp&Ls Plans to Submit License Renewal Application for Turkey Point Units 3 & 4 by End of Dec 2000 ML17355A2641999-03-19019 March 1999 Requests Changes to FPL Official Service List for Turkey Point,Units 3 & 4.Add s Franzone & Remove G Hollinger from All Correspondence ML17355A2651999-03-19019 March 1999 Forwards Annual Radioactive Effluent Release Rept for Jan-Dec 1998 & Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point,Units 3 & 4. ML17355A2621999-03-16016 March 1999 Forwards Special Rept as Result of Turkey Point Unit 3 End-of-Cycle 16 ISI of SG Tubes.Rept Summarizes Results of SG Tube ISI ML17355A2631999-03-12012 March 1999 Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit ML20204C6991999-03-10010 March 1999 Requests Amend to Turkey Point PSP to Modify Requirement to Post Security Officers to Provide Continuous Observation of Entire PA Perimeter in Event of Security Computer Failure. Change to Security Force Staffing Level Also Requested ML17355A2451999-03-0909 March 1999 Submits Info on FPL Current Levels of Nuclear Property Insurance,Per 10CFR50.54(w)(3) ML17355A2501999-03-0808 March 1999 Informs That Licensee Reviewed NRC 990228 Ltr Issuing Exemption Requested Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg.Tabulated Summary of Util Comments & Marked Copy of NRC Ltr & SER Encl ML17355A2441999-03-0101 March 1999 Provides Update to Util Written Notices,Dtd 961120 & 970627 of Claim Involving Alleged Bodily Injury Arising Out of or in Connection with Use of Radioactive Matl at Units 3 & 4 ML17355A2431999-02-25025 February 1999 Informs That FPL Does Not Have Any Candidates from Turkey Point Scheduled to Participate in 990407,Generic Fundamentals Examination (GFE) ML17355A2341999-02-18018 February 1999 Provides Response to RAI Re GL 97-01, Degradation of Crdm/ CEDM Nozzle & Other Vessel Closure Head Penetrations. L-99-042, Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3)1999-02-18018 February 1999 Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3) ML17355A2361999-02-18018 February 1999 Forwards Tabulation of 1998 Occupational Exposure Data for Turkey Point,Units 3 & 4,per TS 6.9.1.2.a.Reactor Coolant Specific Activity Limits of 100/E-bar Mci Per Gram of Gross Radioactivity Were Not Exceeded During 1998 ML17355A2301999-02-18018 February 1999 Forwards Semiannual Fitness for Duty Performance Data for Period of 980701-981231 for Turkey Point Units 3 & 4 ML17355A2231999-02-0808 February 1999 Informs That Util Will Comply with Commitment with Respect to Units 3 & 4,in Response to Ja Zwolinski 990129 Ltr.Util Also Agrees to Incorporate Commitment Into Confirmatory Order Modifying License Effective Immediately Upon Issuance ML17355A2031999-01-29029 January 1999 Forwards Rev 3 to Turkey Point Nuclear Plant Recovery Plan. Rev Does Not Decrease Effectiveness of Plan ML17355A2171999-01-20020 January 1999 Forwards Listed ISI Repts for Turkey Point Unit 3,in Accordance with Provisions of ASME Code,Section XI ML17354B2241999-01-0606 January 1999 Forwards Annual 10CFR50.46 Rept Re Changes To,Or Errors Discovered in ECCS Evaluation Models,Or in Application of Such Models That Effect Peak Clad Temp Calculation ML17354B2081998-12-15015 December 1998 Informs That Fpl,In Cooperation with State of Fl & County Emergency Response Agencies,Will Conduct Exercise of Turkey Point Radiological Emergency Plan on 990210.Scenario Package Forwarded to Emergency Preparedness Section Chief,Region II ML17354B2091998-12-15015 December 1998 Forwards Price Anderson Guarantees Annual Financial Rept,Per 10CFR140.21.Exhibit 1 Submitted to Satisfy Annual Financial Reporting Requirement of 10CFR50.71(b) ML17354B2061998-12-0909 December 1998 Informs That Request for Exemption Specified in Section II.B.3 Will Not Be Needed Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg ML17354B1981998-11-25025 November 1998 Forwards Scope & Objective for 1999 Plant Annual Emergency Preparedness Exercise.Objectives Developed in Conjunction with State & Local Govts.Exercise Scheduled for 990210 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML17348A5661990-09-14014 September 1990 Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule. ML17348A5461990-09-0707 September 1990 Forwards 1990 Inservice Insp Refueling Outage Summary Rept of NDE Activities 900206-0404 First Refueling Outage Second Period Second Insp Interval. ML17348A5501990-09-0707 September 1990 Forwards Jul 1990 Integrated Schedule Regulatory Rept for Facilities ML17348A5521990-09-0606 September 1990 Forwards Matrix of Changes to Emergency Power Sys That Affect Revised Tech Specs Issued on 900828.Matrix Sent for Info & to Assist in NRC Review of No Significant Hazards Rept for Revised Tech Specs ML17348A5431990-08-31031 August 1990 Forwards Objectives for 901108 Emergency Plan Exercise. Exercise Will Involve Participation by Local Emergency Response Agencies & State Emergency Response Personnel & Will Not Be Evaluated by FEMA ML17348A5361990-08-27027 August 1990 Forwards Turkey Point Units 3 & 4 Semiannual Radioactive Effluent Release Rept,Jan-June 1990 & Health Physics Procedure HP-48, Process Control Program for Dewatering Radwaste Liners. ML17348A5171990-08-24024 August 1990 Forwards Ref Matl in Preparation for Operator License Exams Scheduled for Wk of 901029,per NRC 900628 Request ML17348A5041990-08-17017 August 1990 Forwards fitness-for-duty Program Performance Data for Jan-June 1990 ML17348A5051990-08-15015 August 1990 Forwards Monthly Operating Repts for Jul 1990 for Turkey Point Units 3 & 4 & Revise Rept for June 1990 for Unit 3 ML20059B0111990-08-14014 August 1990 Requests That Encl Intervenor Motion for Extension of Time to Appeal to Docketing & Svcs Branch Re Tech Spec Replacement Hearing Be Provided.Motion Inadvertently Omitted in Svc of Request on 900813 ML17348A4971990-08-10010 August 1990 Responds to Violations Noted in Insp Repts 50-250/90-18 & 50-251/90-18.Corrective Actions:Unit Stabilized in Mode 3, Operating Surveillance Procedures 3/4-OSP-089 Revised & Event Response Team Formed ML17348A4701990-07-27027 July 1990 Forwards Rept Detailing Investigative Analysis of Unsatisfactory Blind Specimen Results,Identification of Causes & Corrective Actions Taken by Lab to Prevent Recurrence,Per Unsatisfactory Performance Testing L-90-282, Forwards Rev 23 to Physical Security Plan.Plan Withheld (Ref 10CFR73.21 & 2.790)1990-07-25025 July 1990 Forwards Rev 23 to Physical Security Plan.Plan Withheld (Ref 10CFR73.21 & 2.790) ML17348A4281990-07-25025 July 1990 Forwards Decommissioning Financial Assurance Repts for Plants,Per 10CFR50.33(k) & 50.75(b) ML17348A4691990-07-23023 July 1990 Forwards Addl Info on Emergency Power Sys Enhancement Project Re Load Sequencer,Programmable Logic Controllers & Implementation of Sys in Plant,Per NRC 900705 Request ML17348A4191990-07-20020 July 1990 Advises That Comments on NRC Safety Evaluation Re Implementation of Station Blackout Rule Will Be Provided by 900921 ML17348A4201990-07-20020 July 1990 Forwards Revised No Significant Hazards Determination for Proposed Tech Specs 1.17 & 3.0.5 & Bases,Per 890605 Ltr ML17348A4141990-07-20020 July 1990 Responds to Violations Noted in Insp Repts 50-250/90-14 & 50-251/90-14.Corrective Actions:Breakers Closed,Returning Monitoring Sys to Operable Level & Briefings Held to Explain Rvlms Sys Theory to Operations Control Room Personnel ML17348A4171990-07-19019 July 1990 Forwards May 1990 Integrated Schedule Regulatory Rept for Plant ML17348A4121990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. ML17348A4251990-07-17017 July 1990 Withdraws 900207 & 0424 Proposed Changes to Tech Specs Re Util Nuclear Review Board Composition IR 05000250/19900131990-07-16016 July 1990 Provides Info Re Plant Implementation of 10CFR50.44 & NUREG- 0737,Item II.E.4.1 Re Hydrogen Recombiners,Per 900518 Meeting & Insp Repts 50-250/90-13 & 50-251/90-13.Agreement Re Use of External Recombiners Will Be Reactivated ML20055G8641990-07-16016 July 1990 Informs ASLB That Petitioners Ref to Several Telephone Contacts Between J Butler & M Gutman,Of ATI Career Training Inst Is Inadvertent Misstatement & Should Be Changed to Telephone Contact. W/Certificate of Svc ML17348A4161990-07-16016 July 1990 Responds to Commitment Re Reverse Testing of Containment Isolation Valves Per Insp Repts 50-250/90-13 & 50-251/90-13. Corrective Action Plan Addresses Penetrations 16 & 53 for Unit 3 Only & Penetrations 11,47,54A & 54B for Both Units ML17348A4151990-07-16016 July 1990 Provides Info Re Plant Implementation of 10CFR50.44 & NUREG- 0737,Item II.E.4.1 Re Hydrogen Recombiners,Per 900518 Meeting & Insp Repts 50-250/90-13 & 50-251/90-13.Agreement Re Use of External Recombiners Will Be Reactivated ML17348A4041990-07-12012 July 1990 Forwards Addl Info Re Responses to NRC Questions on Piping Codes Used for Emergency Power Sys Enhancement Project ML17348A3921990-07-12012 July 1990 Summarizes Facility Performance Since Last SALP Evaluation Period Which Ended 890731.Util Pursued Aggressive self- Assessment Program,Including Significant Internal or Outside Assessments in Areas of Operator Performance & EOPs L-90-261, Forwards Rev 7 to Guard Training & Qualification Plan.Rev Withheld1990-07-11011 July 1990 Forwards Rev 7 to Guard Training & Qualification Plan.Rev Withheld L-90-259, Forwards Rev 22 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(a)(3))1990-07-11011 July 1990 Forwards Rev 22 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(a)(3)) ML17348A4321990-07-11011 July 1990 Forwards Rev 8 to Updated FSAR for Turkey Point Units 3 & 4. Rev Includes Activities Completed Between 890123 & 900122. Rept of Changes for Jul 1989 Through June 1990 Will Be Provided by 900901 ML17348A3941990-07-0909 July 1990 Forwards Requested Addl Info Re Emergency Power Sys Enhancement Project.Specific Detailed Changes Will Be Made to Procedures to Address Mods Affecting Equipment Relied Upon for Safe Shutdown ML17348A3881990-07-0505 July 1990 Requests Audit of NRC Records to Independently Verify Reasonableness of Charges Assessed Against Util,Per 10CFR170 Svcs ML17348A4311990-07-0505 July 1990 Documents Written & Verbal Request of Region II Personnel for Temporary Waiver of Compliance of Tech Spec 3.4.2.b.1 Re Allowable Out of Svc Time for One Emergency Containment Cooler from 24 H to 72 Hr W/Addl Reasons ML17348A3851990-07-0303 July 1990 Responds to NRC Ltr Re Violations Noted in Insp Repts 50-250/90-08 & 50-251/90-08.Corrective Actions:Training Dept Increased Emphasis on Radiological Postings in Radiation Worker Training ML17348A3711990-07-0303 July 1990 Responds to NRC 900524 Request for Addl Info on Emergency Power Sys Enhancement Project ML17348A3671990-07-0303 July 1990 Confirms Util Intentions Not to Operate Beyond Refueling Outage That Represents Last Outage Re NRC Bulletin 89-001 ML17348A3841990-06-29029 June 1990 Forwards LER 90-11 on 900609 Re hi-hi Steam Generator Water Level Turbine Trip & Subsequent Reactor Trip Due to Failure of Switch in Feedwater Valve Controller Hand/Auto Station. W/O Encl ML17348A3601990-06-29029 June 1990 Responds to Generic Ltr 89-04, Guidance on Developing Acceptable Inservice Testing Programs. Test Procedures Developed & Under Mgt Review Reflecting Revised Inservice Testing Program ML17348A3621990-06-28028 June 1990 Notifies That Senior Operator License SOP-20177-2 Will Be Terminated,Effective 900731 ML17348A3651990-06-28028 June 1990 Advises That Completion of safety-related motor-operated Valve Testing & Surveillance Will Be Completed by June 1990, Per Generic Ltr 89-10 Requirements ML17348A3591990-06-27027 June 1990 Responds to Violations Noted in Insp Repts 50-250/90-09 & 50-251/90-09.Corrective Actions:Specialist Counselled on Importance of Stopping Procedure When Steps Conflict W/ Condition of Plant & Procedure Use Guidelines Reviewed ML17348A3641990-06-27027 June 1990 Responds to Generic Ltr 90-04, Status of Licensee Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions. ML17348A3861990-06-27027 June 1990 Advises That New Date for Submittal of Response to Insp Repts 50-250/90-09 & 50-251/90-09 Is 900702 ML17348A3551990-06-21021 June 1990 Responds to NRC Bulletin 88-010, Nonconforming Molded Case Circuit Breakers. Five Untraceable Circuit Breakers Installed in Unit 3 safety-related Sys.All Five Breakers Replaced W/Traceable Breakers ML20055D9201990-06-20020 June 1990 Advises That Sp Frantz Will Represent Licensee in Argument Scheduled for 900710.Certificate of Svc Encl ML17348A3181990-06-19019 June 1990 Forwards Final Rept of Inservice Insp NDE of Unisolable Piping Sys & Components for Potential Thermal Stress Effects for Turkey Point Nuclear Power Plant, Per NRC Bulletin 88-008 ML17348A2981990-06-12012 June 1990 Forwards Rev 16 to Topical QA Rept. ML17348A2871990-06-0808 June 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor/Darling Model S350W Swing Check Valves or Valves of Similar Design. Bolt Replacement Performed ML17348A2861990-06-0808 June 1990 Advises That Info Re Operating History of Select Fuel Assemblies Sent to ORNL Between 900419 & 26,per 900510 Request ML17348A2781990-06-0404 June 1990 Forwards Emergency Power Sys Enhancement Project Repts, Reflecting Current Design Info 1990-09-07
[Table view] |
Text
ACCELERATED DI< UTION DEMONSTR TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9006060118 DOC.DATE: 90/05/30 NOTARIZED: NO DOCKET g FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION HARRXS.K.N. Florida Power & Light Co.
RECXP.NAME RECIPIENT AFFXLIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards Relief Request 6/7 A from code required volumetric
& visual exam of RCP casing welds & interior surfaces.
DISTRIBUTXON CODE: A047D COPIES RECEIVED:LTR i /ENCL X SIZE:
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 0 PD2-2 PD 5 5 EDISON,G 1 1 XNTERNAL: AEOD/DSP/TPAB 1 1 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 9H 1 1 NUDOCS-ABSTRACT 1 1 OC LF 1 0 OGC/HDS2 1 0 EG 01 1 1 RES/DSXR/EIB 1 1 EXTERNAL: EG&G BROWN,B 1 1 EG&G RANSOME, C 1 1 LPDR 1 1 NRC PDR 1 1 NSIC 1 1 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL 17
~
~
pp P.O. Box14000, Juno Beach, FL 33408-0420 NAY 3O jggp L-90-156 10 CFR 50.55a(g)(5)(iii)
U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:
Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Request for Relief Inservice Ins ection Pro ram Pursuant to 10 CFR 50.55a(g)(5)(iii), Florida Power 6 Light Company has determined that conformance with certain code requirements is impractical for Turkey Point Units 3 and 4.
Requests for relief from the code required volumetric and visual examination of reactor coolant pump casing welds and interior surfaces (Attachment 1 and 2), and the basis for such relief, are attached.
Your approval is requested by September 15, 1990 so that we may plan for the upcoming outages, beginning November 1990 for Unit 4 and December, 1990 for Unit 3.
If you should have any questions, please contact us.
Very truly yours, K. N. Harris Vice resident Turkey Point Plant Nuclear KNH/TCG/gp Attachments cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant 9006060ii8 900530 PDR AGOCK 05000250 I 9 PDC an FPI. GrouP comPany
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t:B't U i Yl'l"i
ATTACHMENT. 1 TURKEY POINT UNIT 3 SECOND INSPECTION INTERVAL RELIEF REQUEST RELIEF REQUEST NO. 6/7 A A. COMPONENT IDENTIFICATION:
EXAM CATEGORY ITEM NO.
B-L-1 B12.10 - VOLUMETRIC EXAMINATION, to include 100% of the pressure retaining welds on one pump in each group of pumps performing similar functions in the system.
B-L-2 B12.20 VISUAL EXAMINATION of the internal pressure boundary surfaces on one pump in each group of pumps performing similar functions in the system.
C. FUNCTION:
Turkey Point Plant Unit No. 3 has three (3) reactor coolant pumps. These pumps function during normal reactor operation to provide forced recirculation through the core.
D RELIEF REQUESTED:
Relief is requested from the Code volumetric and visual examinations of the Reactor Coolant Pump Casing welds and interior surfaces during the inspection interval.
E. BASIS FOR RELIEF:
Volumetric examination is not feasible due to the coarse grain structure inherent in thick stainless steel castings, that precludes the use of conventional 'ultrasonic examination techniques.
The pump casing is fabricated from cast. stainless steel (ASTM A381, Grade CF8M) material.
Configuration of the pump design requires~disassembly of the pump (including internal parts) to perform radiographic examination.
TURKEY POINT UNIT 3 SECOND INSPECTION INTERVAL RELIEF REQUEST RELIEF REQUEST NO. 6/7 A CONTINUED Visual examination is not practical since it requires total disassembly of ,the pump.
Radiographic examination is not possible without the complete disassembly of the pump (see Figure 1). To perform this examination, large expenditures of man-hours and manrem are required with essentially no compensating increase in plant safety. Based on actual data compiled No.' from the radiographic examination of the Turkey Point Unit Reactor Coolant Pump casing welds and the visual examination of the internal boundary surface of one pump, in excess of 5900 man-hours and 46 man-rem exposure was expended in the disassembly, examinations and reassembly of the pump.
There is a very low probability, based upon industry experi-ence, to disassemble pump(s) solely for maintenance'purposes.
There is no requirement by the pump manufacturer (Westing-house) to disassemble the pump(s) as part of normal mainte-nance or inspection. Accordingly, Florida Power & Light Company's procedures do not require disassembly of the pump(s) for maintenance or inspection purposes. There are no reported failures within the pump casings with these model pump(s) .
Adequate safety margins are inherent in the basic pump de-sign. The structural integrity afforded by the existing pump casing material will not significantly degrade over its lifetime. The Reactor Coolant Pump casing material, cast stainless steel (ASTM A351-CF8m), is widely used in the Nuclear Industry and has performed extremely well.
Satisfactory inspection results achieved in February 1982 coupled with the same inspections conducted by other utility company's and employing the same manufacturing model pumps, provides additional assurance as to the pumps'asing integ-rity.'lorida Power & Light Company through the Westinghouse Owners'roup has submitted to the ASME Code, Code case N-481, Titled "Alternate Examination Requirements for Cast Austenitic Pump Casings" This Code case was approved on
~
March 5, 1990.
TUEL"Y POINT UNIT 3 SECOND INSPECTION INTERVAL RELIEF REQUEST I
RELIEF REQUEST NO. 6/7 A CONTINUED F. ALTERNATIVE EXAMINATIONS:
Perform a VT-2 visual examination of. the exterior of all pumps during the Hydrostatic pressure tests required by Table IWB-2500-1, Category B-P.
,Perform a VT-1 visual examination of the external surfaces of the weld of one pump casing.
Perform a VT-3 visual examination of the internal surfaces whenever a pump is disassembled for maintenance.
The alternate examination and tests provide assurance of an acceptable level of quality and safety.
G. IMPLEMENTATION SCHEDULE:
At or near the end of the Inspection Interval Inspection Interval 22 February 1984 to 21 February 1994 Inspection Period 22 February 1991 to 21 February 1994 H. ATTACHMENTS TO RELIEF REQUEST NO. -6/7 A Fig-. No. 1 ,. Reactor Coolant Pump detail 003-V13A Reactor Coolant Pump drawing 003-V20 Reactor Coolant Pump Interior and weld identification & location The need for this exemption was recognized by FP&L during the First Inspection Interval. FP&L submitted and received NRC approval for this request for relief.
FP&L resubmitted this request for relief at the beginning of our Second Inspection Interval and received partial approv-al as denoted below.
SUBMITTED- 23 February 1984 (under Request 6/7 APPROVED TAC NOS.: 49936 Category B-L-2 only DENIED: Category B-L-1 AMENDED: Amendment 6/7A supplements Request for Relief No. 6/7 originally submitted in 1984.
RE-SUBMITTED'EASON FOR AMENDMENT: Relief from the ASME Code requirements is still required for this interval.
TURKEY POINT UNIT 3 SECOND INSPECTION INTERVAL RELIEF REQUEST RELIEF REQUEST NO. 6/7 A
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~%N FIGURE NO. 1 REACTOR COOLANT PUMP DETAIL 4
RCP-(i)-24 RCP-(i)-23 RCP-(i)-1 RCP-(R)-22
~ RCP-(i)-2 RCP-(i)-21
~ t RCP-(i)-20 RCP-(R)-19 ~
~ I ~ R~ (.) .
RCP-(R)-4 RCP-SPA-L2 RCP-SPA-L3 RCP-(i)-5 RCP-(P)-18~
RCP-(i)-17 RCP-(R)-16
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~RCP-( )-9 RCP-( )-1S RCP-( )-14 +
RCP-(i)-13 g i )(
l~ RCP-(i)-10 RCP-( ~ )-11 RCP-(R)-12 RCP-SPA-L1 ~
MAIN COOLANT PUMP LOOP SUPPORT LOCATIONS A
HOKE THE IDENTIFICATION OF APPLICABLE STUDS. NUTS, AND LIGAMENTS SHALL SUPPORT DETAIL BE MADE BY INSERTING THE FOLLONNG DESINATIONS IN PLACE OF THE ( ) FROM ABOVE MAIN COOLANT PUMP LOOP "A" STUDS (FSA)
MAIN COOLANT PUMP LOOP A NUTS - (FNA)
MAIN COOLANT PUMP LOOP, A" UGAMENTS - (FLA)
REFERENCE, DRAWINGS PRESSURE I)c TEMPERATURE STATS SIZE MATERIAL SPECS SCH TYPE PP) ~e CODES k PROGRAMS GROUP TURKEY POINT UNIT 3 DESIGN PSIG: TEMP(F): TITLE: REACTOR COOLANT PUMP 3PZOOA OPERATING PSIG: TEMP(F): 10-12-89 DATE: ZONE: 056 HYDROSTATIC PSIG: TEMP(F): REVISION APPROVED BY: DRAI))ING NUMBER:
UT CALIBRATION BLOCK: UT-18. UT-19 3,. I. I. ANf)FRRÃitl 003-VI 3A
44.0 WELD "A 1 8.69 44.5 0" 0" I
i 67.81 WELD "8 74.0 T'.50 1
65 . 7 PREPRATION FOR EXAMINATION
/ 1. REMOVE INSULATION
- 2. CLEAN 0.0. SURFACE
/ 28.0 3. REMOVE INTERNALS
/ 4. OECON OUTSIDE FLANGE
/ 5. CLEAN ID SURFACE
/ 6. HP SURVEY (LEAD BLANKE'TS)
- 7. SCAFFOLD WHEN REQUIRED NOTES:
MANUFACTURER WESTINGHOUSE WELD C" CODE CASE N-481 "ALTERNAllVE EXAMINATION REQUIREMENTS FOR CAST AUSTENITIC PUMP CASINGS RELIEF REQUEST 6/7 REFERENCE DRAWINGS PRESSURE Ec TEMPERATURE STATS SIZE MATERIAL SPECS SCH TYPE ~~ alkyd CODES k PROGRAMS GROUP TURKEY POINT PLANT UNIT 3 CASTING SA-351, GR. CFBM TITLE: REACTOR COOLAN'T PUMP (TYPICAL ALL 3 )
DESIGN PSIG: TEMP(F):
OPERATING PSIG: TEMP(F): DATE: 16 APRIL 1990 ZONE: 56.57.58 HYDROSTATIC PSIG: TEMP(F): REVISION APPROVED BY: DRAWING NUMBER:
UT CALIBRATION BLOCK: N/A n r I Arrnlrr~nrr nn3 v7n
ATTACHMENT 2 TURKEY POINT UNIT 4 SECOND INSPECTION INTERVAL RELIEF REQUEST RELIEF REQUEST NO. 6/7 A A. COMPONENT IDENTIFICATION:
EXAM CATEGORY ITEM NO.
B-L-1 B12.10 VOLUMETRIC EXAMINATION, to include 1004 of the pressure retaining welds on one pump in each group of pumps performing similar.
functions in the system.
B-L-2 B12.20 VISUAL EXAMINATION of the internal pressure boundary surfaces on one pump in each group of pumps performing similar functions in the system.
C. FUNCTION:
Turkey Point Plant Unit No. 4 has three (3) reactor coolant pumps. These pumps function during normal reactor operation to provide forced recirculation through the core.
D. RELIEF REQUESTED:
Relief is requested from the Code volumetric and visual examinations of the Reactor Coolant Pump Casing welds and interior surfaces during the inspection interval.
E. BASIS FOR RELIEF:
Volumetric examination is not feasible due to the coarse grain structure inherent in thick stainless steel castings, that precludes the use of conventional ultrasonic examination techniques.
The pump casing is fabricated from cast stainless steel (ASTM A351, Grade CF8M) material.
Configuration of the pump design requires disassembly of the pump (including internal parts) to, perform radiographic examination.
Visual examination is not practical since disassembly of the pump.
it requires total
TURKEY POINT UNIT 4 SECOND INSPECTION INTERVAL RELIEF REQUEST RELIEF REQUEST NO. 6/7 A CONTINUED Radiographic examination is not possible without the complete disassembly of the pump (see Figure 1). To perform this examination, large expenditures of man-hours and manrem are required with essentially no compensating increase in plant safety. Based on actual data compiled from the radiographic examination of the Turkey Point Unit No. 3 Reactor Coolant Pump casing welds and the visual examination'f the internal boundary surface of one pump, in excess of 5900 man-hours and 46 man-rem exposure was expended in the disassembly, examination, and reassembly of the pump.
There is a very low probability, based upon industry experience, to disassemble pump(s) solely for maintenance purposes. There is no requirement by the pump manufacturer (Westinghouse) to disassemble the pump(s) as part of normal maintenance or inspection. Accordingly, Florida Power & Light Company's procedures do not require disassembly of the pump(s) for maintenance or inspection purposes.. There are no reported failures within the pump casings with these model pump(s).
Adequate safety margins are inherent in the basic pump design.
The structural integrity afforded by the existing pump casing material will not significantly degrade over its lifetime.
The Reactor Coolant Pump casing material, cast stainless steel (ASTM A351-CF8m), is widely used in the Nuclear Industry and has performed extremely well.
Satisfactory inspection results achieved in February 1982 coupled with the same inspections conducted by other utilities and employing the same manufacturing model pumps, provides additional assurance as to the pumps'asing integrity.
Florida Power & Light Company through the Westinghouse has submitted to the ASME Code, Code case N-481, Titled Owners'roup "Alternate Examination Requirements for Cast Austenitic Pump Casings". This Code case was approved on March 5, 1990.
F. ALTERNATIVE EXAMINATIONS:
Perform a VT-2 visual examination of the exterior of all pumps during the Hydrostatic pressure tests required by Table IWB-2500-1, Category B-P.
Perform a VT-1 visual examination of the external surfaces of the welds of one pump casing.
Perform a VT-3 visual examination of the. internal surfaces whenever a pump is disassembled for maintenance.
TURKEY POINT UNXT 4 SECOND INSPECTION INTERVAL RELIEF REQUEST RELIEF REQUEST NO. 6/7 A CONTINUED Perform a VT-3 visual examination of the" internal surfaces whenever a pump is disassembled for maintenance.
The alternate examination and tests provide assurance of an acceptable level of quality and safety.
G. IMPLEMENTATION SCHEDULE:
At or near the end of the Inspection Interval Inspection Interval 15 April 1984 to 14 April 1994 Inspection Period 15 April 1991 to 14 April 1994 H. ATTACHMENTS TO RELIEF REQUEST NO. 6/7 A Fig. No. 1 Reactor Coolant Pump detail 4-V13A Reactor Coolant Pump drawing 004-V20 Reactor Coolant Pump Xnterior and weld identification & location The need for this exemption was recognized by FP&L during the First Inspection Interval. FP&L submitted and received NRC approval for this request for relief. FP&L resubmitted this request for relief at the beginning of our Second Inspection Interval and received partial approval as denoted below.
SUBMITTED: 23 February 1984 (under Request 6/7)
APPROVED: TAC NOS.: 49936 Category B-L-2 only DENXED: Category B-L-1 AMENDED Amendment -6/7A supplements Request for Relief No. 6/7 originally submitted in 1984.
RE-SUBMITTED REASON FOR AMENDMENT: Relief from the ASME Code requirements is this interval.
still required for
l TURKEY POINT UNIT 4 SECOND INSPECTION INTERVAL RELIEF REQUEST RELIEF REQUEST NO. 6/7 A CONTINUED
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4
4-RCP-(e)-24 4-RCP-(o)>>23 4-RCP-(i)-I 4-RCP<<(t)-22 4-RCP-(e)-2 4-RCP-(o)-21 4-RCP-( )-20 4-RCP-(a)-3 4-RCP-SPA-L2
~ ~ 4-RCP-SPA-L3 0 000~ 0 4-RCP-(a)-4 4-RCP-(o)-19 4-RCP-(i)-5 0 0 4-RCP-(o)-8 REACTOR COOLANT PUMP 0 0 LOOP A 4-RCP-(o)-18 0 0 0 4-RCP-(t)-7 4-RCP-(i)-17 4-RCP-(o)-8 4-RCP-(o)-I 8 ooo 4-RCP-(o)-IS ~4-RCP-(i)-9 4-RCP-(o)-14 4-RCP-(o)-IO RCP-(o)-13 4-RCP-(i)-I I SUPPORT LOCATIONS 4-RCP-(o)-12 HAZIER QK IDENTIFICAllON OF STUDS, NUTS, AND FLANGE SURFACE AREAS SHALL BE MADE 8Y NSERTIHG THE FOLQWNG DESGNATIONS 81 PLACE OF THE (i)
MAIN COOLANT PVLIP LOOP A STUDS FSA MAIN COOLANT PUMP LOOP A NUTS FHA MAIN COOLANT'VLIP LOOP A FLANGE RHFACE AA SUPPORT DETAIL FROM ABOVE REFERENCE DRAWINGS PRESSURE 4 TGAPERATURE STATS SIZE MATERIAL SPECS SCH TYPE ~p) Q CODES Jt PROGRAMS GROUP lURKEY POINT UNIT 4 DESGH PSG: TEMP(r): lllLE: REACTOR COOLANT PULIP LIAIN FLANGE STUDS, NUTS AND PVLIP SUPPORTS (4P200A)
OPERAllNG PSG: TEMPS (r): DATE: 4/28/90 ZONE: 055 HYDROSTATIC PSIG: TEMP(F): REVISON APPROVED BY: DRANNG NVLIBER; UT CKIBRAllON BLOCK: UT-18, UT-19 0 R. L. TURNER 4-VljA
44.0 WELD "A 44.5 0" 44.5 I-I I
i 67 81 WELD B 74 0" j'.50" l65'. 7 PREPRATION FOR EXAMINATION
- 1. REMOVE INSULATlON
- 2. CLEAN O.D. SURFACE
/ 28.0
- 3. REMOVE INTERNALS
/ 4. OECON OUTSIDE FLANGE
/ 5. CLEAN ID SURFACE
- 6. HP SURVEY (LEAD BLANKETS)
- 7. SCAFFOLD WHEN REQUIRED
'OTES:
MANUFACTURER WESTINGHOUSE N-481 "ALTERNATIVE EXAMINATION REQUIREMENTS FOR WELD C" CODE CASE CAST AUSTENITIC PUMP CASINGS RELIEF REQUEST 6/7 REFERENCE DRAWINGS PRESSURE dr, TEMPERATURE STATS SIZE MATERIAL SPECS SCH TYPE ~~ Igloo CODES IL PROGRAMS GROUP TURKEY POINT PLANT UNIT 4 TITLE: REACTOR COOLANT PUMP (TYPICAL ALL 3 DESIGN PSIG: TEMP(F): CASTING SA-351, GR. CFBM )
OPERATING PSIG: TEMP(F): DATE: 17 Ma 1990 ZONE: 56,57,58 HYDROSTATIC PSIG: TEMP(F): REVISION APPROVEO BY: DRAWING NUMBER:
UT CALIBRATION BLOCK: N/A 0 F. I ANDERSON 004-V20
0 0 1