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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
[Table view] |
Text
REGULAT INFORl'lATION DISTRIBUTI0 'YSTEl'l (R IDS)
ACCESSION NBR 8607210205 DOC. DATE: 86/07/15 NOTARIZED: NO DOCKET I FAC IL: 50-335 St. Lucie Plant> Unit ii Florida Power 8r Light Co. 05000335 50-389 St. Lucie Planti Unit 2> Florida Power Fc. Light Co. 0 AUTH. NAllE AUTHOR AFFILIATION WOODY> C. O. Florida Power i% Light Co.
REC IP. NANE RECIPIENT AFFILIATION 5000389'UBJECT:
TQURICNY, E. C PWR Prospect Directorate 8 Submits completed response to NRC 860428 ltr re inf o implementation of generic items as part of regulatorg trac lf 1ng sg 5, DIBTRIDUTION CODE: AOOID TITLE: OR COFiIEB RECEIVED: LTR Submittal: General Distribution 1 ENCL ~ BI ZE: ~if NOTES:
REClPIENT COPIES RECIP I ENT COPIES ID CODE/NANE LTTR ENCL ID CODE/MANE LTTR ENCL, PWR-B EB 1 PWR-B PEICSB 7 2
PWR-B FOB 1 1 PWR-B PD8 L* 0 PWR-B PD8 PD 01 5 5 TOURICNYA E 1 PWR-B PEICSB 1 1 PWR-B RSB 1 INTER NAL: ADN/LFI'lB 1 0 ELD/ DS2 1 0 NRR/GRAS 0 04 RCN2 1 EXTERNAL EC8cC BRUSKEA S 1 LPDR 03 1 1 NRC PDR 02 1 1 NSIC 05 1 TOTAL NUNBER OF COPIES REQUIRED: LTTR 22 ENCL 18
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IOX 14000, JUNO BEACH, FL 33408 FLORIDA POWER & LIGHT COMPANY JUL t 5 1886 L-86-290 Office of Nuclear Reactor Regulation Attention: Mr. E. G. Tourigny, Project Manager PWR Project Directorate II8 Division of PWR Licensing - B U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Tourigny:
Re: St. Lucie Units I and 2 Docket Nos. 50-335 and 50-389 Im lementation of Generic Items Florida Power & Light Company (FPL) letter L-86-239 of June 6, l986 provided a preliminary response to your letter of April 28, l986 and committed to a completed response by July I5, l986. The completed response is attached and supersedes L-86-239.
Very truly yours, 9,%0 C.~ O.~ Woody
~ ~ ~
Group Vice President Nuclear Energy CO W/MAS/gp A t tachment 8607210205,860715 PDR ADQCK'5000335 p PDR'j MAS3/03 I / I PEOPLE... SERVING PEOPLE
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208731-001 REGULATORY INFORMATION TRACKING SYSTEM PAGE NO.: 459 FACIL ITY IMP L EMENTATI ON 03/31/8'6
- ILITY: ST LUCIE 1 iNT LOCATION: 12 MI SE OF FT. PIERCEP FLA LICENSED POWER: 2700 MHT PROJECT MANAGER: D- SELLS
- KET NUMBER: 050-00335 DESIGN POWER: 0830 MHE BRANCH CHIEF: A. THADANI
- H/ENGINEER: EBASCO NSSS VENDOR: COMB LIC. ASSISTANT: P. KREUTZER INSPECTOR: R. CRLENJAK LIC ACT LICENSEE 0 PA ~CO PLET ~SATUS ~AT
>726 A-01 10 CFR 50.55 A(G) ISI 01/01/70C PRo ~TED n./sa
'043 A-01 10 CFR 50.55 A(G) ISI 02/01/78C PRo38cgED Q/84
)155 A-02 PENDIX I " ALARA 08/18/83C (:om PLG.TE, I') 83 r 044 A-03 SECURITY REVIEWS-MODIFIED AMENDMENT PLANS 02/28/79C Cotr) PL6TE.
i 392 A-09 PRESSURE VESSEL BELTLINE MATERIAL SURVEILLANCE 04/21/80C ComPLETE. t l8o
)623 A-10 CONTINGENCY PLANNING 09/18/80C C.orr4 PL Em )ceo"
)619 A-11 GUARD TRAINING PLANS 11r03/81C ConPLETE. )98) ~
)621 A-12 VITAL AREA ANALYSIS 04/14/82C (J)rr) pie.ye. lq 82."
)292 A-14 10CFR 50.55 A(G) INSERVICE TESTING 04r02/85C Cc nlP LET'E.
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)094 A-15 QUALITY ASSURANCE REQUEST REGARDING DIESEL GENARAT 04/15/80C Co lr) pL,aTa.
A-16 QUALIFICATIONS OF EXAMINATIONP INSPECTION, TESTING 1 2/1 6/81 C C.omP<eth )$ 8) l 135 A-17 INSTRUMENTATION TO FOLLOW THE COURSE OF AN ACCIDEN 05/15/86 NRc, Ace)oA PF4)D)dg
$ 742 A-18 TECH SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-43) 12/06/85C Corn PL%.TE, g/8S
)144 A-20 10 CFR 50.62 OPERATING REACTOR REVIEWS 06/15/86 PgoSEcY<D )g 87
)985 A-21 10 CFR 50.61P PRESSURIZED THERMAL SHOCK RULE 04/30/86 hlRC. AC:AoV PLEAD)4)4
)783 B-02 FIRE PROTECTION 07/27/7 9 C corn P)-6.<E- )978
)813 B-03 PHR MODERATOR DILUTION 02/26/79C Co(OP).ETF )9 7 t
>826 B-Ori REACTOR-VESSEL OVERPRESSURE PROTECTION 09/16/83C ComP) CTE )$ 83 r251 B-07 STEAM GENERATOR FEEDWATER FLOW INSTABILITY 02r07r80C c.omPa ATE ) 98o 3171 B-08 PHR HPSI-LPSI FLOW RESISTANCE 06/19/79C Corn PL,E.rE.
~T)rr)ATES t)ATE.
i208731-001 REGULATORY I NFORMATI ON 'RACKI NG SYST EM .PAGE, NO.:- 460 FAG I L ITY IMP L EMENTATI ON 03/31/86 LUCIE 1 (CONTINUATION) 1305 B"08 PWR HPSI-LPSI FLOW RESISTANCE LIC
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ACT 06/19/79C LICENSEE E lcl79 2hZ'OP)PLET
'841 B-09 CHARGING SYSTEMS PIPE VIBRATIONS 12/29/78C Corn ec.el E I cl78
$ 913 B"14 CEA GUIDE TUBE WEAR 07/06/81C Corn pc-ET'6. I lB l B" 16 EMERGENCY PLA'NNING AND REVISIONS 04/01/81C Corn Pc-EvE- p38 l 3421 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 02/04/81C Corn pc-E~e. l l8 l 1685 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 10/14/81C Co rn pc.E.TE. i/8 l 3315 B-20 CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION 02/04/81C Comp c. EYE 1'l81 3377 B-21 LOSS OF 125-V DC BUS VOLTAGE WITH LOSS OF ANNUNCIA 02/28/82C Corn PLEX'. !982.
3422 B-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 02/04/81C e.e rnpc.Em, 1'981 i684 B"22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 10/14/81C Corn pa.a,vs. HSc 3052 B-23 DEGRADED GRID VOLTAGE 05/03/83C Corn PLETE- 883 2593 B-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW 05/27/83C CornPC.E.VE. Re3 3213 B-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW 01/01/70C CoPlpc.ETE- )981 1307 B-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW 02/09/81C C cnpLE.TE- l'>Bi 3252 B-26 INADVERTANT SAFETY INJECTION DURING COOLDOWN 03/17/81 C Cornpc.6ff 1981 5920 B-36 RESISTANCE TEMPERATURE DETECTOR (RTD) RESPONSE C 08/28/81C Cornpc.Er E. 1 lS2.
$ 319 B-37 STEAM GENERATOR TUBE DENTING AND SUPPORT PLATE MOD 02/02/81C Q) rn pt-E.TE, l lbl 0809 B-39 PWR PRESSURE TEMPERATURE LIMIT TECH SPECS 11/13/80C Cornpl EYE 1108 B"41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 07/11/84C C.ornPL E.v E. av/aq 3852 B-41 FIRE PROTECTION FINAL TECH SPECS (INCLUDES SER S 02/21/85C Compc.ErE. oa/BS 3853 B"4'1 FIRE PROTECTION FINAL TECH SPECS (INCLUDES SER 02/21/85C Com PLe.rE.
S7 ce/ss'981 31 B-42 TMI FOLLOW UP ALL PLANTS 01/19/81C Cornpc En 1794 B-43 PWR FEEDWATER LINE CRACKS 01/04/80C Com pc.ETE. ilTI
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208'7 LUCIE l52 366 387 500 729 31-001 1
B-43 B"44 B-45 B"46 B"47 PWR REGULATORY I NFORMATION TRACKING SYSTEM (CONTINUATION)
FEEDHATER LINE CRACKS LESSONS LEARNED IMPLEMENTATION WASH FACI L ITY IMPLEMENTATION 1400 EVENT Vz "PRIMARY COOLANT SYSTEM PRESSUR ANALYSIS OF TURBINE DISC CRACKS ECCS) CLAD SHELLING AND RUPTURE LIC ACT COP~P~T 05/25/82C 06/02/80C 04/20/81C 08/28/81 09/10/80C C
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)00 B-59 MASONRY HALL DESIGN 06/26/85C Corn pl aVE. al
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492 B"60 .ENVIRONMENTAL QUALIFICATION 1 1/1 5/84C ComPLCTE-107 B-61 LOSS OF NON CLASS IE I&C POWER 07/28/82C Com PLOTS l fB<
178 B-62 ESF RESET CONTROL DESIGN DEFICIENCY 04/05/82C CompLETE. ll8 l 252 B-66 NATURAL CIRCULATION COOLDOHN 04/26/83C Comp Lgq E. l'l 83 560 B-69 IEB 80-4 MAINSTEAM LINE BREAK WITH CONTINUED FEEDH 0'l/17/83C Core PLE.VE- l't B3 760 B-72 NUREG 0737 TECH SPECS (GENERIC LETTER 82-16) 03/02/84C Com PLS,V E. p/~
325 B-74 THERMAL SHIELD FOLLOW UP ANALYSIS 03/14/84C &rr) pLETE. o3lw
$ 02 B-76 ITEM 1.1 POST TRIP REVIEHs PROGRAM DESCRIPTION & 12r17r85C Corri PL CTE. n-!sr 383 B-77 ITEM 2.1 EQUIPMENT CLASSIFICATION & VENDOR INTER 04r15r86 ACC. A<T'log P~c rug 964 B-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 12/23/85C Corn PLEBE. n/ss $ o+/a, 045 B-79 ITEM 3.1.3 POST MAINTENANCE TESTING CHANGES TO 10/25/85C Corn PLY@, lo/~
l 00 B-80 ITEM 4.1 REACTOR TRIP SYSTEM RELIABILITY VENDO 12r17r85C CornpLETE.
o/es'S/aS l53. B-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROG FOR R 05r15r86 CoN P LET'E E5T(MAT'E.D PgT'E.
208731-001 REGULATORY INFORNATION TRACKING SYSTEN PAGE NO.: -462 FACILITY INPLENENTATION 03/31/86 LUCIE 1 ( CONTINUATION)
~0. ~4 LIC ACT
~COMPLE ~QUS LICENSEE
~A 571 B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83- 06/21/85C htII.C ACT'IM PER>I4%
635 B-85 SALEN ATHS 1.2 DATA CAPABILITY 04/15/86 Co% pLETE- og/ga 718 B-86 SALEN ATHS 2.2 S-R CONPONENTS 12/01/86 f'RoT~TEb n./ss 801 B-87 SALEN ATHS 3.2.1 & 3.2.2 S-R CONPONENTS 12/17/86 CowPI CfE. tz,/~
SS4 B-88 SALEN ATHS 3.2.3 T.S. S-R CONPONENTS 10/25/85C Com Pt-a,~a, to/Sg 940 B-89 SALEN ATWS 4.2.3 & 4.2.4 LIFE CONPONENTS 1 2/31/86 ARt'CTIoP PE.Ht Ia)4g 111 B"92 SALEN ATHS 4.5.1 DIVERSE TRIP FEATURES 12/17/85C CnPL Pt.EVE.
n/es'./sa 028 B"93 SALEN ATHS 4.5.2 & 4.5.3 TEST ALTERNATIVES 12/01/86 Pg.o+ac+E,>
250 C-01 PHR SECONDARY HATER CHENISTRY NONITORING REQUIRENE 04/16/82C ComPI.CVE. llBL 924 C-06 PUNP SUPPORT-LANELLAR TEARING 04/1 7/81 C COMPLETE.
911 C-07 FUEL HANDLING ACCIDENT INSIDE CONTAINNENT 04/27/79C Con% Pl.+YE. R19 083 C-10 CONTROL OF HEAVY'OADS OVER SPENT FUEL POOL (PHASE 03/04/85C C,c apt.e.<< os/es 469 C-12 BORON SOLUBILITY DURING LONG TERN COOLING FOLLOHIN 03/29/82C Cc nl PI-Sea. 1'lBQ-648 C-14 AUXILIARY FEEDWATER SEISNIC QUALIFICATION 1 1/08/82C CaMPI.EYE. I'l82-273 C-15 CONTROL OF HEAVY LOADS - PHASE II (FOLLOHUP OF NPA 06/28/85C C.om PLS.~ ok/85lan%
091 C-16 UTILITY RESPONSES TO STAFF RECOMNENDATIONS CONCERN 12/11/85C Com pc.e TE. [o/Q5 915 D-06 PEAKING NODEL CHANGE FOR CE REACTOR CORE 05/26/78C Coept.E~ l le 923 D-10 ASYNNETRIC LOCA LOADS 06/15/86 Pgo5KcT'E > I'/ $7 101 D-11 FISSION GAS RELEASE 10/13/78C ComPa.6<E. I'178 319 D-15 HIGH ENERGY LINE BREAK & CONSEQUENTIAL SYSTEN FAIL 01/31/84C QvnPLE.Va lpga<"
034 D-17 DEFINITION OF OPERABLE 05/28/81 C CompLam l l8 l 905 D-19 DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15) 03/1 5/86 NRC, ACT'Iog PEhlb 306 E-03 CORE RELOADS REQUIRING PRIOR NRC APPROVAL 05/27/79C Co< pt.ETE 1979 DATE.
1208731-001 REGULATI)RY INFORMATION TRACKING SYSTEH PAGE NO 063 FACIL ITY IMP L ENENTATION 03/51/86 LUCIE 1 (CONTINUATION)
LIC ACT LICENSEE
~OREG! ~A~US 8918 E-06 CEA POSITION INDICATION FAILURES CE 0 CE/27/82C CoePL6:f E. lRM 1308 E-07 REACTOR PROTECTION SYSTEH lOGIC CE 03/31/82C CoRPLETE. l98~
CI05% F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR 01/26/82C ~PLE,V-ECompL:TE- l9B<
4125 F-02 I.A.1.3 SHIFT MANNING 06/30/83C 1~/aS 6196 F-03 I.A.2.1 UPGRADING OF RO AHD SRO TRAINING 03/26/82C Co&P LE;IK- l98~
F4267 F-06 I.C.1.2/3.A ENERGENCY OPERATING PROCEDURES GENERIC 06/07/81C CcelPxE TE. ai/aa 6337 F-05 I.C.1.2/3.B PROCEDURES GENERATION PACKAGES (NUREG 05/15/86 PRo~GTE.D i~(e 7250 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 02/04/82C ComPLETE. IQB2.
7322 F" 07 I, C.6 CORRECT PERFORMANCE OF. OPERATING ACTIVITI 02/04/82C Cc>mpxETE. l98<
1205 F-08 I.D.1.1 DETAILED CONTROL ROON DESIGN REVIEW PROGRA 10/10/86C CoN PL@.TE. -lo/H 1285 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM 06/11/85C PRoSEc TE, D 19a7 F-10 II.B.1 RCS HIGH POINT VENTS 09/1 6/83C Coh0pxE,TE. oS/8f 7973 F-11 II.B.2 PLANT SHIELDING 01/14/83C CoRPLETE- l983 4675 F-12 II.B.3 POST ACCIDENT SANPLING 09/28/83C CoRPaETE. ~ R83 6516 F-13 II.B.G TRAINING FOR MITIGATING CORE DAHAGE 03/26/82C 4omP LE;TE. l9e~
6617 F-11 I I . D. 1 RV AND SV 7%&tiitt8-T~STr~g 06/15/86 HRc Ac.&lo&
6667 F-15 II.E.1.1 AFW SYSTEM EVALUATION 09/1 I/82C f CorAPLE. E. l96 2 I. E.
PEP>IN'bmpL 3378 F-16 I 1 . 2. 1 AFW SYSTEM INITIATION 09/16/82C ComPLETE 1982.
4768 F-17 II.E.1.2.2 AFW SYSTEM FLOW INDICATION 09/14/82C l 982.
4814 F-18 II.E.4.1 DEDICATED HYDROGEN PENETRATION 10/20/81C 6TE. [QBl 4885 F-19 I I. E. I. 2 CONTAINMENT ISOLATION DEPENDABILITY 05/27/83C Compxr TE f983 4956 F-20 II.F.1.1 NOBLE GAS MONITOR 12/09/81C eonnpxE,TE RS l 5027 F-21 II.F. 1. 2 IODINE/PARTICULATE SAMPLING 12/09/81C ComPLETE. AS l
.1208731-001 RE'GULATORY INFORNATI ON TRACKING SYSTEM PAGE NO.: I'46/
FACILITY INPL ENENTATI ON 03/31/8i f LUCIE 1 (CONTINUATION)
A@A'~US LIC ACT LICENSEE A~CO ~A~ ~CO ~DA 45098 F-22 I I.F.1.3 CONTAINMENT HIGH RANGE MONITOR 01/07/82C h mPLETE. 19 82 476344 F-23 II.F.1.I4 CONTAINNENT PRESSURE INSTRUMENT 08/23/83C CeolPL E:TE- l 9 83 47705 F-2I4 II.F.1.5 CONTAINMENT WATER LEVEL INSTRUNENT 08/23/83C Qo<PC.ETE J9 B3 47776 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 08/23/83C ~mPl.E.TE i9S3 o5168 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 06/20/85C Co%PI-E.TE- ae/SS 96905 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 06/06/8I4C CoII1 p LE.TE- or./Bq I47816 F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 10/05/83C Coe pLSTE- l98$
%5266 F-36 II.K.3.1 AUTO PORV ISOLATION 10/06/83C C rnPLETE- IZ BS 45312 F-37 II.K.3.2 REPORT ON PORV FAILURES 10/06/83C CD K PL E.TE 1183 I45378 F-38 II.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE OI4/06/82C ComPWE.<E l9e<
I45 4433 F-39 II.K.3.5 AUTO TRIP OF RCPS 02/08/83C CO441PLE TE. l 983 I4566I4 F-447 II.K.3.17 ECCS OUTAGES 08/08/83C Ca~PLEve F-53 II.K.3..25 POWER ON PUMP SEALS 09/30/82C C.o &PLE.TE. l9 82.
I45861 F-57 II.K.3.30 SB LOCA METHODS 06/26/85C Cc DEPLETE aS/85 II.K.3.31 06/26/85C (98'f I48200 F-58 COMPLIANCE WITH 10 CFR 50.I%6 C.CN pl-E.TE. olo
/e5'&lbl445 I'45980 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER 07/15/86 HRc. ACT'low I46 051 F-644 III.A.1.2 OPERATIONAL SUPPORT CENTER 07/15/86 HRC. ACTlo4l PEgp I46123 F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 07/15/86 H44.C AcTlo~
ID'EADIQ 0
I46195 F-66 III.A.1.2 NUCLEAR DATA LINK 07/30/82C Can pt.E,T E lqe2.~
I46267 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 05/11/83C CO<PL E. TE 883 446339 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 07/15/86 plRc. AcTtod PMblQQ I46441 0 F-69 I I I . D.3. 3 IMPLANT RADIATION MONITORING 02/23/82C ComPl.E.T E AW-I464479 F-70 II I. D. 3. 44 CONTROL ROON HABITABILITY 03/11/82C COI41PLET E l982 ESTWQT E b be E.
-1208731-001 REGULATORY I NFORNATI ON TRACKING SYSTEM PAGE NO.~ - 665 FACILITY IMPLEMENTATION 03/51/8<
I'UCIE 1 (CONTINUATION)
LIC ACT LICENSEE 0C NO. @PA~ ~CO ~QUS ~A 56167 F"71 I.D.1.2 DETAILED CONTROL ROON REVIEH (FOLLOHUP TO 05/15/86 PRo3'EcTK.D pfg7
<9693 G-01 REACTOR COOLANT PUMP TRIP (D660 II.K.3.5) 06/15/86 F'Ao/Ecfgb )'f87
-1208731-001 REGULATORY I NFORMATI ON TRACKING SYSTEM PAGE NO:. -
FACILITY IMPLEMENTATION 46'3/31r8 AGILITY'T LUCIE 2 "LANT LOCATION: 12 MI SE OF FT. PIERCEP FLA LICENSED POWER: 2700 MHT PROJECT MANAGER: D. SELLS
~OCKET NUMBER: 050-00389 DESIGN POWER: 0830 MHE BRANCH CHIEF: A. THADANI RCH/ENGINEER: EBASCO NSSS VENDOR- COMB L IC. ASSISTANT: P . KREUTZER E INSPECTOR: R. CRLENJAK LIC ACT LICENSEE
~CO. ~COOPT T ~Sip US ~DA 151136 A-17 INSTRUMENTATION TO FOLLOW 1HE COURSE OF AN ACCIDEN 05/15/86 8Qc ACT'IoPJ Pe,ADIIJQ 155743 A-18 TECH SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-43) 12/06/85C CoITIPI-e-Te- l2/85 159145 A-20 10 CFR 50.62 OPERATING REACTOR REVIEWS 06/15/86 pao3'e,CVXD lqaa 159986 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE 04/30/86 NRC ACglOP PE,HDIIJg ll52803 B-76 ITEM 1.1 POST TRIP REVIEWP'ROGRAM DESCRIPTION & 12/17/85C Co~l a c~e e/e5 l52884 B-77 ITEM 2.1 EQUIPMENT CLASSIFICATION & VENDOR INTER 04/15/86 WRY. AcT'<od PEunlaG 1152965 B-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 12/23/85C CoIT1 P Le.T'e. z/Bsg o0/86 1530446 B-79 ITEM 3.1.3 " POST MAINTENANCE TESTING CHANGES TO 10/25/85C C.on pt.e.Te. lo/85 1531 01 B"80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY VENDO 12/17/85C C,om p~e.v.E. l2/85 l53154 B-81 ITEMS 4.2.1 & 4.2.2 "PREVENTATIVE MAINT PROG FOR R 05/15/86 c,ompl.e<e os/e6 154572 B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83- 06/21/85C
- Ngc hcTloA PEADIHc 153636 B-85 SALEM ATHS 1.2 DATA CAPABILITY 04/15/86 Com PLET+ o'B/e6
'53719 B-86 SALEM ATWS 2.2 S"R COMPONENTS 12/01/86 pRo3Ec Te,D 12/86 153802 B-87 SALEM ATWS 3.2.1 & 3.2.2 S-R COMPONENTS 12/17/85C Com PLe, Ye, iZ/B5 153885 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 10/25/85C ~~PLE.TF- lo/~
1539 4I1 B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS 12/31/86 NRc Ac7 IoIJ PEAP tAg l54112 B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 12/17/85C compI-ev e ]485 1544029 B-93 SALEM ATHS 4.5.2 & 4.5.3 TEST ALTERNATIVES 12/01/86 PRo3 e,c T eD t2/86 II (FOLLOHUP 1
I52274 C-15 CONTROL OF HEAVY LOADS PHASE OF MPA 06/28/85C ComPL.E~ O6/85 l58092 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN 12/11/85C C,ornPLE,TE. lo/g5
'.-1208731-001 REGULATORY INFORMATION TRACKING SYSTEM PAGE NOxi 467 FACIL ITY IMP L EMENTATI ON 03/34/5 T LUCIE 2 (CONTINUATION)
.LIC ACT LICENSEE Kh > ~~EERIE ~sv >us usa 155906 D-19 DIESEL GENERATOR RELIABILIlYTECH SPECS (GL 84-15) 05/15/86 PIRC ACT'log P6PDIAG 151 206 F"08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRA 10/10/80C C,o me~av a. 1o/8<
I51286 F-09 I.D.2. SAFETY PARAMETER DISPLAY SYSTEM 06/1 1/85C paoZmV a.e 1987 l51605 F 16 II D.1 RV AND SV ~HRt6- Tesv'iaq
~ 06/15/86 HRc AC.T le PKPPlPC 150982 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 06/06/84C ~mpaata- ol /8+
157576 F-58 II.K.3.31 COMPLIANCE WITH 10 CFR 50.66 06/26/85C c + p(.a.ve. e~laS'Ac I59275 F-68 II I. A. 2. 2 METEOROLOGICAL DATA UPGRADE 07/1 5/86 ACV'to4 pep>i45 156168 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEW (FOLLOWUP TO 05/15/86 PgoskcTE> lQB7 I59I411 G-01 REACTOR COOLANT PUMP TRIP (D660 II.K.3.5) 06/15/86 pgoyGcTE,D lg 87