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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17241A5001999-10-21021 October 1999 Forwards Rev 3 to Emergency Response Data Sys (ERDS) Data Point Library for St Lucie Unit 1.Rev Provides Replacement Pages & Follows Format Recommended by NUREG 1394, ERDS Implementation, Rev 1,App C ML17309A9981999-10-19019 October 1999 Forwards Revised Epips,Including Rev 3 to EPIP-10 & Rev 25 to HP-202.EPIP-10 Added Onsite Monitoring Points,Made Administrative Changes & Incorporated New Attachments & HP-202 Added Red Team Survey Points ML20217F6171999-10-0808 October 1999 Forwards Insp Repts 50-335/99-11 & 50-389/99-11 on 990827 & 990907-09.No Violations Identified.Matl Encl Contained Safeguards Info as Defined by 10CFR73.21 & Disclosed to Unauthorized Individuals Prohibited by Section 147 of AEA ML17241A4811999-10-0101 October 1999 Reports Number of Tubes Plugged During Unit 1 Refueling Outage SL1-16,per TS 4.4.5.5.a 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 ML17241A4701999-09-25025 September 1999 Forwards Info Requested by NRC Staff During 990916 Telcon to Complete Staff Review of Request for risk-informed Extension of Action Completion/Aot Specified for Inoperable Train of LPSI Sys at Plant ML17241A4721999-09-24024 September 1999 Forwards Rev 1 to Plant Change/Mod (PCM) 99016 to St Lucie Unit 1,Cycle 16 COLR, IAW TS 6.9.1.11.d.Refueling Overhaul Activities Are Currently in Progress & Reactor Operations for Cycle 16 Are Scheduled to Commence in Oct 1999 ML17241A4681999-09-22022 September 1999 Requests Restriction Be Added to Senior Operator License SOP-21093 for TE Bolander.Nrc Forms 369,encl.Encl Withheld Per 10CFR2.790(a)(6) ML17241A4671999-09-20020 September 1999 Forwards Completed NRC Form 536, Operator Licensing Exam Data, for St Lucie Units 1 & 2,as Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams. ML17241A4581999-09-13013 September 1999 Forwards Info Requested by NRC Staff During 990630 & 0816 Telcons,To Complete Review of Proposed License Amend for Fuel Reload Process Improvement Program ML17241A4531999-08-31031 August 1999 Informs That No Candidates from St Lucie Plant Will Be Participating in PWR Gfes Being Administered on 991006 ML17241A4521999-08-31031 August 1999 Withdraws Relief Request 16 & Suppl Relief Request 15 with Info Requested During 990526 Telephone Conference Re ISI Insp Plan,Third 10-yr Interval ML17241A4501999-08-26026 August 1999 Informs That FPL Has Reviewed Reactor Vessel Integrity Database,Called RVID2,re Closure of GL 92-01,rev 1,suppl 1. Requested Corrections & Marked Up Pages from Rvid 2 Database Summary Repts That Correspond to Comments,Attached ML17241A4371999-08-13013 August 1999 Forwards fitness-for-duty Program Performance Data for six- Month Period Ending 990630,per 10CFR26.71(d) ML17241A4461999-08-11011 August 1999 Requests That W Rept Entitled, Evaluation of Turbine Missile Ejection Probability Resulting from Extending Test Interval of Interceptor & Reheat Stop Valves at St Lucie Units 1 & 2, Be Withheld from Public Disclosure L-99-171, Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3)1999-07-29029 July 1999 Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3) ML17309A9911999-07-26026 July 1999 Forwards Revised EPIPs & Revised Procedures That Implement Emergency Plan as Listed.Procedures Provides Instruction for Operational Support Ctr (OSC) Chemistry Supervisor to Establish Remote Labs at Locations Specified ML17241A4471999-07-22022 July 1999 Requests That Rev 1 to WCAP-14732 & Rev 1,Add 1 to WCAP-14732 Be Withheld from Public Disclosure ML17241A4221999-07-22022 July 1999 Forwards List of Proposed Licensing Actions for St Lucie Units 1 & 2,planned During Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. ML17241A4151999-07-22022 July 1999 Forwards Revised Relief Request 25 for Second 10-yr ISI Interval for Unit 2 ML17241A4101999-07-16016 July 1999 Forwards FP&L Supplemental Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17309A9881999-07-0707 July 1999 Forwards Rev 5 to EPIP-03, Emergency Response Organization Notification/Staff Augmentation. Rev 5 to EPIP-03 Was Revised to Transfer EP Responsibilities from Training Manager to Protection Svcs Manager ML20209F1541999-07-0606 July 1999 Informs That NRC in Process of Conducting Operational Safeguards Response Evaluations at Nuclear Power Reactors. Plant Chosen for Such Review Scheduled for Wk of 990823-26 ML17241A4011999-06-30030 June 1999 Forwards Info Copy of Florida Wastewater Permit (FL0002208) (Formerly NPDES Permit) Mod,Which Was Issued by Florida Dept of Environ Protection on 990604 ML17241A3971999-06-30030 June 1999 Forwards Suppl Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, as Requested in 990317 Ltr 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 ML17241A3951999-06-29029 June 1999 Provides Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants, Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl ML17241A3731999-06-17017 June 1999 Supplements Relief Requests 4,11 & 13 for Third ten-year ISI Interval with Info Requested During 990526 Telcon.Expedited Review Is Requested by 990730 to Avoid Negatively Impacting Upcoming St Lucie Unit 1 Refueling Outage (SL1-16) ML17241A3641999-06-14014 June 1999 Submits Supplement to Relief Request 24 with Info Requested by Nrc.In Addition Relief Request 24 Is Identical to St Lucie Unit 1 Relief Request 4 for Third ISI Interval Being Supplemented by FPL Ltr L-99-139 ML20195F3871999-06-11011 June 1999 Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5) IA-99-247, Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5)1999-06-11011 June 1999 Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5) L-99-129, Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3)1999-06-0909 June 1999 Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3) ML17241A3561999-06-0707 June 1999 Forwards Rept Containing Brief Description & Summary of SEs for Changes,Tests & Experiments Which Were Approved for Unit 3 During Period of 970526-981209 ML17241A3601999-06-0707 June 1999 Forwards Correction to Annual Radiological Environ Operating Rept for CY98.Util Has Identified Transcription Error on Last Page of Attachment C of Rept,Results from Interlaboratory Comparison Program 1998 ML20195F3941999-05-27027 May 1999 FOIA Request That Memo from J Calvo to Fl Lebdon Re TIA - St Lucie,Unit 1 Environ Qualification of Woodward Governor Controls Be Placed in PDR ML17241A3461999-05-24024 May 1999 Forwards Revised Relief Request 22 to Clarify Several Areas of Relief.Nrc Action Is Requested to Be Complete by Aug 1999 to Support Planning for Spring 2000 Unit 2 Refueling Outage ML17241A3391999-05-20020 May 1999 Forwards Notification of Change to Small Break LOCA ECCS Evaluation Model Used for St Lucie Unit 1.Anomaly Was Discovered & Corrected That Resulted in Reducing Calculated PCT for Limiting SBLOCA by More than 50 F ML17241A3371999-05-20020 May 1999 Forwards Util Suppl to GL 95-07 Response Re pressure-locking & Thermal Binding of safety-related power-operated Gate Valves,In Response to NRC Second RAI Dtd 990225 ML20207C7531999-05-17017 May 1999 Discusses Issue Identified by FPL in Feb 1998 Involving Potential for Fire to Cause Breach of Rc Sys High/Low Pressure Interface Boundary & NRC Decision for Exercise of Enforcement Discretion ML17241A3301999-05-17017 May 1999 Forwards LER 99-004-00 Re as Found Cycle 10 Psv Setpoints Outside TS Limits,Which Occurred on 990415.Root Cause Determination Not Yet Complete.Suppl to Include Root Cause & Corrective Actions Will Be Submitted ML17309A9821999-05-10010 May 1999 Forwards Rev 36 to St Lucie Emergency Plan, Per 10CFR50.54(q).Executive Summary & Summary of Changes Incorporated by Rev,Encl IR 05000335/19980141999-04-29029 April 1999 Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated ML17241A3221999-04-29029 April 1999 Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated ML17229B1071999-04-28028 April 1999 Forwards 1998 Annual Environ Operating Rept for St Lucie Unit 2. Rept Includes Discussions of 5-inch Barrier Net Maint & Taprogge Condenser Tube Cleaning Sys Ball Loss,As Agreed at First Biennial Sea Turtle Meeting Held on 980120 ML17229B1051999-04-22022 April 1999 Requests That Listed Individuals Be Placed on Official Serve List for Nuclear Matl Safety & Safeguards Info Notices ML17229B1061999-04-21021 April 1999 Notifies NRC of Change in Medical Status of Licensed Operator Pf Farnsworth (Docket 55-21285,license SOP-21094). NRC Form 3996, Medical Exam Certification, Encl.Encl Withheld Per 10CFR2.790(a)(6) ML17309A9851999-04-15015 April 1999 Requests That NRC Review Denial of Appeal from Assessment of Fees Assessed in 981101 Invoice RS0062-99 & Assessment of Fees in Invoice RS0182-99 Which Was Also Denied in 990305 Ltr.Both Invoices Are for Fees Re Inspector GG Warnick ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML17229B0951999-04-0808 April 1999 Requests Approval of Encl Revised Relief Request 6,in Response to 990322 Telcon with NRC & 10CFR55.55a(a)(3). Request States That Visual VT-3 Exams Will Be Conducted IAW IWA-2213 & Repairs Will Be IAW Util ASME Section IX Program ML17229B0821999-04-0707 April 1999 Requests Approval of Interim Relief Request 26 Re Repair Requirements for Class 2 ECCS Piping,Per 10CFR50.55a(a)(3) & 50.55a(g)(iii).Alternative Actions Apply Guidance of GLs 91-18 & 90-05 & ASME Code Case N-513.Evaluation,encl 1999-09-28
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17241A5001999-10-21021 October 1999 Forwards Rev 3 to Emergency Response Data Sys (ERDS) Data Point Library for St Lucie Unit 1.Rev Provides Replacement Pages & Follows Format Recommended by NUREG 1394, ERDS Implementation, Rev 1,App C ML17309A9981999-10-19019 October 1999 Forwards Revised Epips,Including Rev 3 to EPIP-10 & Rev 25 to HP-202.EPIP-10 Added Onsite Monitoring Points,Made Administrative Changes & Incorporated New Attachments & HP-202 Added Red Team Survey Points ML17241A4811999-10-0101 October 1999 Reports Number of Tubes Plugged During Unit 1 Refueling Outage SL1-16,per TS 4.4.5.5.a ML17241A4701999-09-25025 September 1999 Forwards Info Requested by NRC Staff During 990916 Telcon to Complete Staff Review of Request for risk-informed Extension of Action Completion/Aot Specified for Inoperable Train of LPSI Sys at Plant ML17241A4721999-09-24024 September 1999 Forwards Rev 1 to Plant Change/Mod (PCM) 99016 to St Lucie Unit 1,Cycle 16 COLR, IAW TS 6.9.1.11.d.Refueling Overhaul Activities Are Currently in Progress & Reactor Operations for Cycle 16 Are Scheduled to Commence in Oct 1999 ML17241A4681999-09-22022 September 1999 Requests Restriction Be Added to Senior Operator License SOP-21093 for TE Bolander.Nrc Forms 369,encl.Encl Withheld Per 10CFR2.790(a)(6) ML17241A4671999-09-20020 September 1999 Forwards Completed NRC Form 536, Operator Licensing Exam Data, for St Lucie Units 1 & 2,as Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams. ML17241A4581999-09-13013 September 1999 Forwards Info Requested by NRC Staff During 990630 & 0816 Telcons,To Complete Review of Proposed License Amend for Fuel Reload Process Improvement Program ML17241A4531999-08-31031 August 1999 Informs That No Candidates from St Lucie Plant Will Be Participating in PWR Gfes Being Administered on 991006 ML17241A4521999-08-31031 August 1999 Withdraws Relief Request 16 & Suppl Relief Request 15 with Info Requested During 990526 Telephone Conference Re ISI Insp Plan,Third 10-yr Interval ML17241A4501999-08-26026 August 1999 Informs That FPL Has Reviewed Reactor Vessel Integrity Database,Called RVID2,re Closure of GL 92-01,rev 1,suppl 1. Requested Corrections & Marked Up Pages from Rvid 2 Database Summary Repts That Correspond to Comments,Attached ML17241A4371999-08-13013 August 1999 Forwards fitness-for-duty Program Performance Data for six- Month Period Ending 990630,per 10CFR26.71(d) ML17241A4461999-08-11011 August 1999 Requests That W Rept Entitled, Evaluation of Turbine Missile Ejection Probability Resulting from Extending Test Interval of Interceptor & Reheat Stop Valves at St Lucie Units 1 & 2, Be Withheld from Public Disclosure L-99-171, Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3)1999-07-29029 July 1999 Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3) ML17309A9911999-07-26026 July 1999 Forwards Revised EPIPs & Revised Procedures That Implement Emergency Plan as Listed.Procedures Provides Instruction for Operational Support Ctr (OSC) Chemistry Supervisor to Establish Remote Labs at Locations Specified ML17241A4221999-07-22022 July 1999 Forwards List of Proposed Licensing Actions for St Lucie Units 1 & 2,planned During Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. ML17241A4471999-07-22022 July 1999 Requests That Rev 1 to WCAP-14732 & Rev 1,Add 1 to WCAP-14732 Be Withheld from Public Disclosure ML17241A4151999-07-22022 July 1999 Forwards Revised Relief Request 25 for Second 10-yr ISI Interval for Unit 2 ML17241A4101999-07-16016 July 1999 Forwards FP&L Supplemental Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17309A9881999-07-0707 July 1999 Forwards Rev 5 to EPIP-03, Emergency Response Organization Notification/Staff Augmentation. Rev 5 to EPIP-03 Was Revised to Transfer EP Responsibilities from Training Manager to Protection Svcs Manager ML17241A4011999-06-30030 June 1999 Forwards Info Copy of Florida Wastewater Permit (FL0002208) (Formerly NPDES Permit) Mod,Which Was Issued by Florida Dept of Environ Protection on 990604 ML17241A3971999-06-30030 June 1999 Forwards Suppl Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, as Requested in 990317 Ltr 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 ML17241A3951999-06-29029 June 1999 Provides Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants, Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl ML17241A3731999-06-17017 June 1999 Supplements Relief Requests 4,11 & 13 for Third ten-year ISI Interval with Info Requested During 990526 Telcon.Expedited Review Is Requested by 990730 to Avoid Negatively Impacting Upcoming St Lucie Unit 1 Refueling Outage (SL1-16) ML17241A3641999-06-14014 June 1999 Submits Supplement to Relief Request 24 with Info Requested by Nrc.In Addition Relief Request 24 Is Identical to St Lucie Unit 1 Relief Request 4 for Third ISI Interval Being Supplemented by FPL Ltr L-99-139 L-99-129, Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3)1999-06-0909 June 1999 Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3) ML17241A3601999-06-0707 June 1999 Forwards Correction to Annual Radiological Environ Operating Rept for CY98.Util Has Identified Transcription Error on Last Page of Attachment C of Rept,Results from Interlaboratory Comparison Program 1998 ML17241A3561999-06-0707 June 1999 Forwards Rept Containing Brief Description & Summary of SEs for Changes,Tests & Experiments Which Were Approved for Unit 3 During Period of 970526-981209 ML20195F3941999-05-27027 May 1999 FOIA Request That Memo from J Calvo to Fl Lebdon Re TIA - St Lucie,Unit 1 Environ Qualification of Woodward Governor Controls Be Placed in PDR ML17241A3461999-05-24024 May 1999 Forwards Revised Relief Request 22 to Clarify Several Areas of Relief.Nrc Action Is Requested to Be Complete by Aug 1999 to Support Planning for Spring 2000 Unit 2 Refueling Outage ML17241A3371999-05-20020 May 1999 Forwards Util Suppl to GL 95-07 Response Re pressure-locking & Thermal Binding of safety-related power-operated Gate Valves,In Response to NRC Second RAI Dtd 990225 ML17241A3391999-05-20020 May 1999 Forwards Notification of Change to Small Break LOCA ECCS Evaluation Model Used for St Lucie Unit 1.Anomaly Was Discovered & Corrected That Resulted in Reducing Calculated PCT for Limiting SBLOCA by More than 50 F ML17241A3301999-05-17017 May 1999 Forwards LER 99-004-00 Re as Found Cycle 10 Psv Setpoints Outside TS Limits,Which Occurred on 990415.Root Cause Determination Not Yet Complete.Suppl to Include Root Cause & Corrective Actions Will Be Submitted ML17309A9821999-05-10010 May 1999 Forwards Rev 36 to St Lucie Emergency Plan, Per 10CFR50.54(q).Executive Summary & Summary of Changes Incorporated by Rev,Encl ML17241A3221999-04-29029 April 1999 Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated IR 05000335/19980141999-04-29029 April 1999 Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated ML17229B1071999-04-28028 April 1999 Forwards 1998 Annual Environ Operating Rept for St Lucie Unit 2. Rept Includes Discussions of 5-inch Barrier Net Maint & Taprogge Condenser Tube Cleaning Sys Ball Loss,As Agreed at First Biennial Sea Turtle Meeting Held on 980120 ML17229B1051999-04-22022 April 1999 Requests That Listed Individuals Be Placed on Official Serve List for Nuclear Matl Safety & Safeguards Info Notices ML17229B1061999-04-21021 April 1999 Notifies NRC of Change in Medical Status of Licensed Operator Pf Farnsworth (Docket 55-21285,license SOP-21094). NRC Form 3996, Medical Exam Certification, Encl.Encl Withheld Per 10CFR2.790(a)(6) ML17309A9851999-04-15015 April 1999 Requests That NRC Review Denial of Appeal from Assessment of Fees Assessed in 981101 Invoice RS0062-99 & Assessment of Fees in Invoice RS0182-99 Which Was Also Denied in 990305 Ltr.Both Invoices Are for Fees Re Inspector GG Warnick ML17229B0951999-04-0808 April 1999 Requests Approval of Encl Revised Relief Request 6,in Response to 990322 Telcon with NRC & 10CFR55.55a(a)(3). Request States That Visual VT-3 Exams Will Be Conducted IAW IWA-2213 & Repairs Will Be IAW Util ASME Section IX Program ML17229B0821999-04-0707 April 1999 Requests Approval of Interim Relief Request 26 Re Repair Requirements for Class 2 ECCS Piping,Per 10CFR50.55a(a)(3) & 50.55a(g)(iii).Alternative Actions Apply Guidance of GLs 91-18 & 90-05 & ASME Code Case N-513.Evaluation,encl ML17229B0851999-04-0505 April 1999 Requests Approval of Encl Relief Request 25 Which Proposes to Use Alternative Requirements of ASME Code Case N-613 in Lieu of Requirements of ASME Section XI Figures IWB-2500-7(a) & IWB-2500-7(b).Action Requested by Aug 1999 ML17309A9791999-03-31031 March 1999 Forwards Revised EPIPs Including Rev 2 to EPIP-00,rev 2 to EPIP-09,rev 2 to EPIP-10 & Rev 10 to HP-207.Summary of Revs Listed ML17309A9761999-03-23023 March 1999 Forwards Revised Epips,Including Rev 4 to EPIP-03, Er Organization Notification/Staff Augmentation, Rev 3 to EPIP-05, Activation & Operation of OSC & Rev 14 to HP-200, HP Emergency Organization. Changes to Epips,Discussed ML17229B0691999-03-19019 March 1999 Transmits TS Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity,Per Soluble Boron Credit ML17229B0721999-03-16016 March 1999 Requests Approval of Enclosed Relief Requests 23 & 24 Re ISI Plan for Second ten-year Interval.Nrc Action Is Requested to Be Complete by Aug 1999 to Support Planning for Spring 2000 Unit 2 Refueling Outage 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 ML17229B0481999-03-10010 March 1999 Informs That Util Delivered Matls Requested in Encl 1 of NRC Ltr by Hand on 990308,as Requested by NRC Ltr Dtd 990218 1999-09-25
[Table view] Category:UTILITY TO NRC
MONTHYEARML17223A9401990-09-13013 September 1990 Forwards Evaluation of Potential Safety Impact of Failed Control Element Assemblies on Limiting Transients for Facility ML17223A9341990-09-10010 September 1990 Forwards Addl Info Re Generic Implications & Resolution of Control Element Assembly (CEA) Failure at Facility,Per NRC Request.Description of Testing Program for Old Style CEAs in Unit 1 Core Encl L-90-315, Advises That Util Has Completed Evaluation of NUREG-0737, Item II.D.1,SER Item 81990-08-30030 August 1990 Advises That Util Has Completed Evaluation of NUREG-0737, Item II.D.1,SER Item 8 ML17223A9201990-08-28028 August 1990 Forwards Forms NIS-1 & NIS-2, Owners Rept for Inservice Insps as Required by Provisions of ASME Code Rules, Per 900725 Ltr ML17223A8911990-08-20020 August 1990 Forwards Corrected Monthly Operating Repts for Jul 1990 for St Lucie Units 1 & 2 & Summary of Operating Experience ML17348A5041990-08-17017 August 1990 Forwards fitness-for-duty Program Performance Data for Jan-June 1990 L-90-301, Discusses Generic Implications & Resolution of Control Element Assemblies Failure at Plant1990-08-16016 August 1990 Discusses Generic Implications & Resolution of Control Element Assemblies Failure at Plant ML17223A8751990-08-0909 August 1990 Responds to Violations Noted in Insp Rept 50-335/90-14. Corrective Actions:Rcs Flow Determination by Calorimetric Procedure Repeated W/Supervisor of Individual Observing & Individual Counseled by Supervisor IR 05000335/19900141990-08-0909 August 1990 Responds to Violations Noted in Insp Rept 50-335/90-14. Corrective Actions:Rcs Flow Determination by Calorimetric Procedure Repeated W/Supervisor of Individual Observing & Individual Counseled by Supervisor 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 ML17223A8621990-07-25025 July 1990 Advises That NIS-1 & NIS-2 Forms,As Part of Inservice Insp Rept,Will Be Submitted by 900831 ML17348A4281990-07-25025 July 1990 Forwards Decommissioning Financial Assurance Repts for Plants,Per 10CFR50.33(k) & 50.75(b) ML17223A8631990-07-25025 July 1990 Submits Addl Info Re Implementation of Programmed Enhancements Per Generic Ltr 88-17, Loss of Dhr. All Mods for Unit 1 Completed & Operational.Mods for Unit 2 Schedule for Upcoming Refueling Outage L-90-271, Responds to NRC Ltr Re Violations Noted in Insp Repts 50-335/90-09 & 50-389/90-09.Corrective Actions:Procedural Expectation Re Hanging & Removal of Deficiency Tags Will Be Reemphasized to Personnel Generating Work Orders1990-07-20020 July 1990 Responds to NRC Ltr Re Violations Noted in Insp Repts 50-335/90-09 & 50-389/90-09.Corrective Actions:Procedural Expectation Re Hanging & Removal of Deficiency Tags Will Be Reemphasized to Personnel Generating Work Orders ML17223A8581990-07-19019 July 1990 Forwards Implementation Status of 10CFR50.62 Mod at Facility Re Requirements for Reduction of Risk from ATWS Events for Light Water Cooled Nuclear Power Plants ML17223A8491990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. No Rosemount Transmitters Models 1153 Series B,1153 Series D & 1154 Mfg Prior to 890711 Supplied by Different Vendor ML17223A8521990-07-17017 July 1990 Forwards Addl Info Requested Re Generic Implications & Resolution of Control Element Assembly Failure at Plant.Encl Confirms Util Intent to Follow C-E Regulatory Response Group Action Program IR 05000335/19900131990-07-0909 July 1990 Responds to Violations Noted in Insp Repts 50-335/90-13 & 50-389/90-13.Corrective Actions:Maint Personnel Counseled & Aware of Importance of Verifying Design Configuration Requirements ML17223A8421990-07-0909 July 1990 Responds to Violations Noted in Insp Repts 50-335/90-13 & 50-389/90-13.Corrective Actions:Maint Personnel Counseled & Aware of Importance of Verifying Design Configuration Requirements ML17348A3881990-07-0505 July 1990 Requests Audit of NRC Records to Independently Verify Reasonableness of Charges Assessed Against Util,Per 10CFR170 Svcs ML17223A8391990-07-0303 July 1990 Forwards Results of Beach Survey Procedure & Reduction of Field Survey Data,Per Tech Spec 4.7.6.1.1.Unit 1 Updated Fsar,Section 2.4.2.2,concluded That Dune Condition Acceptable Per Tech Spec 5.1.3 ML17223A8381990-07-0202 July 1990 Requests Termination of Operator License for s Lavelle.Util Also Requests That Ltr Be Withheld (Ref 10CFR2.790) L-90-239, Forwards Rev 6 to Guard Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21)1990-07-0202 July 1990 Forwards Rev 6 to Guard Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21) ML17223A8371990-06-27027 June 1990 Provides Details of Implementation Plan Re Recommendations & Schedular Requirements in Generic Ltr 89-10,per 891228 Ltr.Design Basis Review of safety-related motor-operated Valves & Determination of Switch Settings in Progress ML17308A4981990-06-27027 June 1990 Responds to Generic Ltr 90-04 Re Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions ML17223A8341990-06-19019 June 1990 Forwards Corrected Proposed Tech Spec Figure 3.4-2 Per 900207 Application for Amend to License NPF-16,incorporating Revised Pressure/Temp Limits & Results of Revised Low Temp Overpressure Protection Analysis Into Tech Specs ML17223A8241990-06-18018 June 1990 Forwards Revised Combined Semiannual Radioactive Effluent Release Rept for Jan-June 1988. ML17223A8271990-06-18018 June 1990 Forwards Ma Smith 900601 Ltr to WR Cunningham of EPA Requesting Mod to Plant NPDES Permit to Permit Cleaning of Facility & to Establish Discharge Limits for Chemical Cleaning Wastes ML17348A2981990-06-12012 June 1990 Forwards Rev 16 to Topical QA Rept. ML17223A6761990-05-31031 May 1990 Advises That Air Operated safety-related Components Will Perform All Design Basis Events,Per 881227 Ltr.All Actions Required by Generic Ltr 88-14 Complete for Plant ML17348A2651990-05-29029 May 1990 Submits Rept Detailing Investigative Analysis of Unsatisfactory Blind Specimen Results,Identification of Causes & Corrective Actions Taken by Lab to Prevent Recurrence,Per 10CFR26,App A.2.8(e)(4) ML17223A6741990-05-22022 May 1990 Forwards Info Re Status of 10CFR50.62 Mods to Meet ATWS Requirements as of 900515.Plant Change/Mod Package Necessary for Installing ATWS Will Be Issued by 900630.Hardware Procurement for Diverse Scram Sys Approx 90% Complete ML17223A6361990-05-0808 May 1990 Forwards Final Response to NRC Bulletin 88-010, Nonconforming Molded-Case Circuit Breakers. One Untraceable Circuit Breaker Installed in Unit 2 Qualified SPDS & Replaced W/Traceable Breaker ML17223A6281990-04-21021 April 1990 Forwards St Lucie Unit 2 Annual Environ Operating Rept, Vol 1 1989. ML17223A6081990-04-13013 April 1990 Responds to Violations Noted in Insp Repts 50-335/90-02 & 50-389/90-02.Corrective Actions:Nuclear Plant Supervisor Required to Remain in Control Room During Significant Changes in Power Operation & Preventive Maint Upgraded ML17223A6071990-04-0505 April 1990 Responds to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs. Removal & Replacement of Cold Leg Side Plugs of Heat Number 3513 for Unit 1 Completed During Refueling Outage ML17308A4911990-04-0202 April 1990 Forwards Description & Summary of Safety Evaluations of Plant Changes/Mods Reportable Per 10CFR50.59.Repair &/Or Replacement of Protective Coatings on Surfaces Inside Bldg Pose No Unreviewed Safety Question ML17223A5931990-03-30030 March 1990 Forwards Status of 10CFR50.62, Requirements for Reduction of Risk from ATWS Mods at Plant as of 900315.Diverse Scram Sys Module Prototype Fabrication in Progress ML17223A5921990-03-27027 March 1990 Forwards Addl Info on Proposed License Amend Re Increased Max Allowable Resistance Temp Detector Delay Time,Per 891219 Telcon & Advises That Util Request to Increase Plant Resistance Temp Detector Response Time Remain Unchanged ML17223A5831990-03-19019 March 1990 Forwards Response to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implications of Control Sys in LWR Nuclear Power Plants,' Per 10CFR50.54(f) ML17347B6191990-03-13013 March 1990 Provides Listing of Property Insurance Programs ML17223A5531990-03-0909 March 1990 Submits Results of Investigation of Error Detected in Dose Assessment During 900124 NRC Evaluated Exercise at Plant. Operator Error Caused Keyboard Hangup Requiring Computer Restart ML17223A5451990-03-0808 March 1990 Forwards Revised Tech Specs Re Steam Generator Tube Repairs, Per 890602 Telcon & Subsequent Discussions W/Nrc ML17308A4871990-03-0707 March 1990 Forwards Response to Eight Audit Questions & Licensing Bases Criteria to Resolve Station Blackout Issue.Util Currently Has Procedures to Mitigate Effects of Hurricanes & Tornados Which Meet or Exceed NUMARC 87-00 Guidelines ML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML17347B6031990-02-27027 February 1990 Requests Approval to Use Code Case N-468 at Plants ML17223A5321990-02-26026 February 1990 Forwards CEN-396 (L)-NP, Verification of Acceptability of 1-Pin Burnup Limit of 60 Mwd/Kg for St Lucie Unit 2. ML20012A0011990-02-26026 February 1990 Notifies That Followup Actions Completed on Schedule & Incorporated Into Rev 25 to Plant Physical Security Plan,Per NRC 890605 Request ML17223A5411990-02-26026 February 1990 Provides Addl Info Re Proposed License Amends Re Moderator Temp Coefficient Surveillance Requirements,Per 891026 & 900109 Telcons IR 05000335/19890241990-02-22022 February 1990 Responds to Violations Noted in Insp Repts 50-335/89-24 & 50-389/89-24.Corrective Actions:Applicable Procedures Changed to Clarify Which Spaces & Blocks Required to Be Completed on Plant Work Order & QC Supervisor Counseled 1990-09-13
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REGULATOR INFORMATION DISTRIBUTION, 'EM (RIDS)
ACCESSION NBR 8709160129 DQC. DATE: 87/09/10 NOTARIZED: YES DOCKET FACIL: 50-..335 St. Lucie Planti Unit ii Florida PoUJer h Light Co. 05000335 50-389 St. Lucie Planti Unit 2i Florida Poeer 5 Light Co. 05000389 AUTH. NAME AUTHOR AFFILIATION WOODY) C. O. Flor ida Power h Light Co.
REC IP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Foreard s response to NRC Hul le tin 87-001'Thinning of Pipe Walls in Nuclear Poeer Plants. " Scope 5 extent of program includes all moderate 5 high energy carbon steel piping sgsi both nuclear saf et'-related 5 nonsa f etg-related.
DISTRIBUTION CODE: IE11D COPIES RECEIVED: LTR TITLE: Bulletin Response (50 DKT)
L ENCL + SIZE:7 +
NOTES RECIPIENT COPIES RECIPIENT COPIES'TTR ID CODE/NAME LTTR ENCL ID CODE/NAME ENCL PD2-2 LA 0 PD2-2 PD 1 1 TOUR I GNY> E 1 INTERNAL: AEOD/DOA 1 1 AEOD/DSP 1 AEOD/DSP/TPAB 1 1 NRR/DEST/ADE 1 NRR/DEST/ADS 1 1 NRR/DEBT/MEB 1 1 NRR/DOE*/EAB 1 1 NRR/DOEA/GCB 1 1 NRR/ /EPB 1 . 1 NRR/PMAS/ ILRB 1 1 E FILE 02 1 1 RES/DE/EIB 1 1 RG 2 FILE 01 1 1 EXTERNAL'PDR 1 NRC PDR NSIC 1 1 TOTAL NUMBER OF CQP I ES REQUIRED: LTTR 19 ENCL 18
P. O. BOX 14000, JUNO BEACH, FL 33408 0420
.0 SEPTEtiIBXR 1 0 1987 L-87-376 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:
Re: St. Lvcie Units I and 2 Docket Nos. 50-335 and 50-389 NRC Bulletin NO. 87-0 I Thinnin of Pi e Walls in Nuclear Power Plants By the subject Bulletin, the NRC staff requested information concerning programs for monitoring the wall thickness of pipes in condensate, feedwater, steam, and connected high-energy piping systems.
Attached is the response to this Bulletin for St. Lvcie Units I and 2.
The attached information is provided pursuant to Section I82a of the Atomic Energy Act of l954, as amended. If further information is required on this topic, please contact us.
Very truly yours, C. O. Woo Group Vi resident Nuclear Energy COW/E JW/gp Attachments cc: Dr. J. Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant 8709160229 870910 PDR ADQCK 05000335 8 PDR an FPL Group company
, E JW3/038/I
0 ~l ~ l STATE OF FLORIDA )
) ss.
COUNTY OF PALM BEACH )
~C.O.W That he is d 1 i fi d l,d
'a Grou Vice President d
of Florida Power & Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this 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.
C. O. Woody Subscribed and worn to before me this g,day of , 19~.
NOTARY PUBLIC, in and for the County of Palm Beach, State of Florida
>> ~OB~EC $ Z)g
'.'ORE) g 1 1
~offqgS>0 My Commission expires: ~0'tf<> 4av jaj>>, ,. '"'
NRC BULLETIN 87 THINNING OF PIPE lVALLS IN NUCLEAR POPOVER PLANTS Information Re uest 1:
Ideptify codes or standards to which the piping was designed and fabricated.
~Res ense 1 St. Lucie Unit 1 Non-nuclear safety related piping: ANSI B31.1.
Nuclear safety related piping: ANSI B31.7.
St. Lucie Unit 2 Non-nuclear safety related piping: ANSI B31.1.
Nuclear safety related piping: ASME Section III.
Information Re uest 2 Describe the scope and extent of your programs for ensuring that pipe wall thicknesses are not below the minimum allowable thickness. Include in the description the criteria you have established for:
A. Selecting points at which to make thickness measurements.
B. Determine how frequently to make measurements, C. Selecting methods used to make thickness measurements.
D. Making repair/replacement decisions.
~Res onse 2 St. Lucie Unit 1 R 2 In general, the scope and extent of the St. Lucie program includes all moderate and high energy (i.e., above 200oF) carbon steel piping systems, both nuclear safety related and non-nuclear safety related. Inspection locations are established in accordance with accepted industry methods such as those provided by EPRI for single and two phase systems. within specific piping systems, locations for inspections are selected based upon such factors as fluid velocity, piping geometry, moisture content (for steam) and chemistry. Areas which are subjected to flow disturbances such as elbows, branch connections, piping and fittings downstream of control valves or flow orifices are preferred locations for inspections.
Pg. 2 Res onse 2 (cont'd)
Frequency of inspection is based upon the rate of erosion/corrosion. Each operating cycle, inspection data is reviewed to determine which locations, based upon measured maximum erosion/corrosion rates, may be approaching code minimum wall thickness values. Locations which may violate code minimum wall thickness within the next operating cycle require corrective action.
The method of examination is selected based upon the ability to accurately'rovide a profile of wall thickness readings over the entire area of the piping or fitting expected to experience significant erosion/corrosion. In general, ultrasonic devices have been used for this purpose.
Decisions to take corrective action for piping and fittings which have suffered erosion/corrosion damage are based upon the ability of the piping or fitting to satisfy code minimum wall thickness requirements during the subsequent operating cycle. If the lowest wall thickness reading in a piping section subtracted from the erosion/corrosion expected during the subsequent operating cycles is less than the minimum value required by the applicable code, the piping section must be repaired or replaced.
Information Re uest 3 For liquid-phase systems, state specifically whether the following factors have been considered in'stablishing your criteria for selecting points at which to monitor piping thickness:
A. Piping material B. Piping configuration C. pH of water in the system D. System temperature E. Fluid bulk velocity F. Oxygen content
~Res onse 3 St. Lucie Units I 2 2 The initial 'single-phase inspection programs for St. Lucie Units I R 2 were developed soon after the Surry pipe rupture incident. The major factors used to select inspection locations were similar to those accepted for two-phase flow systems and included material composition, temperature, flow path geometry, fluid velocity, fluid pH and oxygen content. Inspection planning tools such as EPRI's "CHEC" Computer Program for single-phase erosion/corrosion were not available during initial St. Lucie single-phase systems such as feedwater, heater drain, condensate and blowdown. within these systems, geometry was considered the most important selection factor. Closely spaced fittings, branch connections, elbows and piping/fittings downstream of control valves were given highest priority for inspections.
Pg. 3 Information Re uest 0 Chronologically list and summarize the results of all inspections that have been performed, which were specifically conducted for the purpose of identifying pipe wall thinning, whether or not pipe wall thinning was discovered, and any other inspections where pipe wall thinning was discovered even though that was not the purpose of that inspection.
A. Briefly describe the inspection program and indicate whether it was specifically intended to measure wall thickness or whether wall thickness meausrements were an incidental determination.
B. Describe what piping was examined and how (e.g., describe the inspection instrument (s), test method, reference thickness, locations examined, means for locating measurement point (s) in subsequent inspections).
C. Report thickness measurement results and note those that were identified as unacceptable and why.
1 D. Describe actions already taken or planned for piping that has been found to have a nonconforming wall thickness. If you have performed a failure analysis, include the results of that analysis, indicate whether the actions involve repair or replacement, including any change of materials.
St. Lucie Unit 1 During the 1983 refueling outage, the turbine cross under piping was inspected for wall thickness loss. The results are contained in Attachment D.
As a result of the Surry incident and general concerns regarding erosion/corrosion in two-phase systems, a comprehensive inspection program was developed. The program was specifically intended to collect data on the wall thickness profiles of several high energy pipe(fittings to detect erosion/corrosion degradation. For two-phase systems such as extraction steam, an EPRI methodology (EPRI HP-3900) for predicting erosion/corrosion rates was utilized. For single-phase systems, such factors as flow geometry, temperature, fluid chemistry as previously discussed were utilized in selecting inspection points. The program was designed to first
'inspect the most likely points for erosion/corrosion and to collect "baseline" data on other locations, with program expansion required if wall thinning in any location was more severe than anticipated.
Ultrasonic examination was used to determine wall thickness. "Zone maps", as shown in the attachments, were used to specify the extent of examination required at each selected inspection point. The ultrasonic probes were moved along each circumferential line of the zone map, the data was fed to a strip chart recorder.
The ultrasonic instrumentation was of the pulse echo-type with cathode ray tube display. Carbon steel incremental step blocks were utilized to provide reference thickness to calibrate the instrumentation.
Res onse 0 (cont'd)
A total of 52 locations were selected based on anticipated erosion/corrosion rates; of these,02 locations were in the extraction steam systems, and 10 locations were in single-phase systems. For each of these locations, a "screening criteria" was provided to indicate when engineering evaluation of the thinning was required. The screening criteria was conservatively defined as the minimum wall thickness for the piping plus the maximum possible erosion/corrosion which could occur during the subsequent cycle of operation. A copy of the inspection program document is provided as Attachment A.
The 1987 refueling outage inspections revealed that significant erosion/corrosion degradation was limited to the extraction steam piping and the moisture separator reheater shell side drains. In the case of the extraction steam systems, and piping segments required replacement. All measurements in single-several'itting phase piping systems revealed that the piping is all still within manufactureres tolerances for wall thickness (i.e., nominal wall thickness plus or minus 12'%).
Based on single-phase piping inspection results, erosion/corrosion rates appear to be very low, and encroachment on minimum wall thickness values is not expected for several operating cycles. Attachment B is a summary report which provides the results of all Unit 1 wall thickness inspections and describes corrective actions which were required.
St. Lucie Unit 2 St. Lucie Unit 2 has been operating for less than half the time that St. Lucie Unit 1 has operated. Since the plants are virtually identical in terms of configuration and erosion/corrosion parameters, pipe wall thinning location-for-location is expected to be generally 50% or less of the Unit 1 values. A program has been developed for Unit 2 which is modeled after the Unit 1 program. Inspection points have been selected based upon Unit 1 inspection results. The first Unit 2 wall thickness measurements to detect erosion/corrosion will be conducted during the 1987 refueling outage in October and November. Attachment C is a copy of the Unit 2 inspection program document.
Information Re uest 5 Describe any plans either for revising the present or for developing new or additional programs for monitoring pipe wall thickness.
~Res ense 5 St. Lucie Units 1 R 2 Florida Power R Light Compan'y is satisfied with the program as a whole and in particular the inspection method. The "ultrasonic zone mapping" technique proved adequate in providing the information necessary to make sound decisions on corrective actions. The methods for determining "screening values" are logical and ensure that code requirements for minimum wall thickness are satisfied.
MCI1:5
Pg.5 St. Lucie Units 1 R 1 (cont'd)
IVith respect to selection criteria, the EPRI methodology for two-.phase erosion/corrosion proved to be an excellent tool for determining, on a relative basis, where to concentrate inspection resources.
Future program inprovement is expected in the single-phase inspection location selection technique. Future programs (beginning with the 1988 Unit 1 inspection) will have single-phase locations selected with assistance from EPRPs "CHEC" computer program. This program will provide a prioritized selection of inspection points based on consideration of piping material, flow rates, configuration, water chemistry, etc.. In addition, we will continue to monitor the inspection results from the nuclear industry, particularly in the single-phase flow areas.
Modifications to the inspection program will be made to reflect new findings elsewhere as considered appropriate.
MCI1:5