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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. L-90-128, Forwards Rev 26 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(a)(3))1990-04-17017 April 1990 Forwards Rev 26 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(a)(3)) 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 L-90-121, Forwards St Lucie Unit 2 Underwater Intrusion Detection Sys Safenet Barrier Conceptual Design, for Expeditious Review & Approval to Permit Sys Installation in Time Frame Discussed in 900228 Meeting1990-04-0202 April 1990 Forwards St Lucie Unit 2 Underwater Intrusion Detection Sys Safenet Barrier Conceptual Design, for Expeditious Review & Approval to Permit Sys Installation in Time Frame Discussed in 900228 Meeting 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. ML17223A5411990-02-26026 February 1990 Provides Addl Info Re Proposed License Amends Re Moderator Temp Coefficient Surveillance Requirements,Per 891026 & 900109 Telcons 1990-09-13
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ACCELERATED DINRIBUTION DEMONS TION SYSTEM
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REGULATORY INFORMATION DISTRIBUTION STEM (RIDS)
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ACCESSION NBR:9003080492 DOC.DATE: 90/02/26 NOTARIZED: NO DOCKET FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power a Light Co. 05000335 50-389 St. Lucie Plant, Unit 2, Florida Power 6 Light Co. 05000389 AUTH. NAME ~ AUTHOR AFFILIATION SAGER,D.A. Florida Powe'r & Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Provides addi info re proposed license amends re moderator temp coefficient surveillance requirements."
DXSTRXBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 NORRISiJ 5 5 INTERNAL: ACRS 6 6 NRR/DET/ECMB 9H 1 1 NRR/DOEA/OTSB11 1 1 NRR/DST 8E2 1 1 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 OC/LFMB 1 0 OGC/HDS2 1 0 X= 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 NCTE IO ALL "RIDS" KXZPXEFZS:
S PIZASE HELP US 1O REDUCE HASTE! CGNI'ACT.'lHE DOCUMEÃZ CXKQKL DESK, RQCN Pl-37 (EXT. 20079) IO EZZKQCGR YOUR MME FBCH DISTRIBUTION LIPIS P3R DCCGMEMIS YOU DGiN~T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 25
P.O. Box14000, Juno Beach, FL 33408-0420 FEBRUARY. 2 6 $ 990 L-90-69 10 CFR 50.90 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:
Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Additional Information on Proposed License Amendments Moderator Temperature Coefficient Surveillance Requirements TAC Nos. 66854 and 66855 On October 26, 1989, a conference call was held between Florida Power & Light Company (FPL) and the NRC to discuss questions the NRC Staff reviewer had pertaining to the St. Lucie Unit. 1 and St.
Lucie Unit 2 proposed license amendments entitled, "Moderator Temperature Coefficient Surveillance Requirements." Additionally, on January 9, 1990, further discussions were held between FPL and the NRC concerning these questions. Attached is FPL's response to all of the questions which have been raised during these discussions.
Should you have additional questions, please contact us.
Very truly yours, D. A. ger Vice esident St. Lu ie Plant DAS/MSD/gp Attachments cc: Stewart D. Ebneter, Regional Administrator, Region Senior Resident Inspector, USNRC, St. Lucie Plant II, USNRd gpOSOSOO~a 9oo~b
. PDP ADOCK P5000 PNU an FPL Group company
ATTACHMENT RESPONSE TO CONFERENCE CALL UESTXONS
- 1. What MTC value is assumed in the Main Steam Line Break (MSLB) analysis for St. Lucie Unit 1?
The St. Lucie Unit 1 Technical Specifications state that the MTC shall be less, negative than -28 pcm/degree F at, rated thermal power. This is used as the MTC value in the MSLB analysis for St. Lucie Unit 1.
- 2. Are the MTC values stated in the St. Lucie Unit. 1 and Unit 2 Technical Specifications given as >>ALL RODS OUT>> values at Rated Thermal Power?
The MTC limits given in the St. Lucie Unit 1 and Unit 2 Technical Specifications are given as Limiting Conditions for Operation. These MTC limits apply at any rod position.
- 3. Provide a comparison of predicted and measured MTC values for St. Lucie Unit 1 and Unit 2 at or near 300 ppm, as well as, the most negative predicted MTC values at Hot Full Power, All Rods Out for as many cycles as possible.
A comparison between predicted and measured MTC values is given in Table 1 for St. Lucie Unit 1 and Unit 2. The predicted end of cycle (EOC) MTC values are also included in Table 1 for each unit.
- 4. Briefly descxibe the technique used to determine the MTC at St. Lucie Unit 1 and Unit 2.
The following is a brief description of the technique used to determine the MTC at both St. Lucie Unit 1 and Unit 2.
Prere uisite The lead control rod assembly (CEA) bank is slowly diluted into the core (approximately 20% inserted) so as not to induce large axial offset disturbances and to allow xenon to reach equilibrium.
l
Method The MTC is determined in two parts, utilizing a reactor coolant system (RCS) cooldown and a RCS heatup.
RCS avera e tern erature cooldown The electrical generation output is increased by approximately 50 MW to affect a RCS average temperature cooldown of approximately 5 degrees F. Core thermal power is maintained constant by inserting either one CEA out of the lead CEA bank for Unit 1 or the lead CEA bank for Unit 2. Reactor power and RCS average temperature are then stabilized using the electrical generation output and either the single CEA or the lead CEA bank, depending on the unit.
RCS avera e tern erature heatu The electrical generation output is reduced by approximately 50 MW to return the RCS average temperature to approximately its original value (prior to the RCS cooldown). The CEA(s) inserted in the RCS cooldown is withdrawn to maintain thermal power constant. The reactor power and RCS average temperature are stabilized using the electrical generation output and either the single CEA or the lead CEA bank, depending on the unit.
The MTC is determined for each heatup and cooldown cycle by dividing the reactivity withdrawn/inserted by the CEA to maintain constant power by the change in the RCS average temperature over several RCS heatup/cooldown cycles. The MTC values for each heatup and cooldown cycle are then averaged and corrected for power drift.
- 5. Assume that during normal end of cycle (EOC) plant operation, plant conditions such as core average temperature, rod position, reactor coolant pressure, critical boron concentrations, etc., vary so as to change the MTC. Can these plant parameters vary within technical specification limits such that the MTC is more negative than the limit stated in the St. Lucie Technical Specifications?
The analysis in response to this question required three dimensional SIMULATE3 modeling of the St. Lucie Unit 1 and Unit 2 cores. The St. Lucie Unit 1 analysis consisted of full core modeling while that of Unit 2 consisted of quarter core modeling. Both predict the MTC adequately. St. Lucie Unit 1 Cycle 9 and Unit 2 Cycle 5 EOC conditions were modeled. It
should be noted that MTC values predicted by SIMULATE3 are:
1.) more negative at EOC than those that have been measured in past operating cycles at both St. Lucie Unit 1 and Unit 2, and 2.) SIMULATE3 MTC values are not biased.
The methodology used to analyze this question was to vary plant conditions about their nominal EOC values, beyond technical specification limits. The data was then examined to determine if any off-nominal operating conditions could exist within the bounds defined by the technical specifications such as to adversely affect the MTC (create a more negative MTC than that allowed in the technical specifications at EOC). The plant conditions investigated were:
- 1. Reactor coolant average temperature
- 2. RCS pressure
- 3. Core thermal power
- 4. Boron concentration
- 5. CEA position
- 6. Axial Shape Index (ASI)
Each parameter was varied about its nominal value (and in some cases outside the technical specification limits) while holding all other parameters constant. It should be noted that when varying the core thermal power, the core average temperature also varied. It should also be noted that the ASI could not be held constant while varying other operating parameters. All other parameters were held constant. In actual plant. operation these parameters will be coupled in that changing one parameter about its nominal value will cause another to change about, its nominal value.
The results of this analysis are presented in Tables 2 through 4 and Figures 1 through 5. The technical specification limits for a given operating parameter are included on each figure where applicable.
The results show that the EOC MTC is strongly dependent on the steady state coolant average temperature when all other parameters are held constant. Figure 1 shows this dependency.
The dependency was found to be -0.29 pcm/degree F per degree F for Unit 1 and -0.28 pcm/degree F per degree F for Unit 2.
For example, a 10 degree F increase in the average coolant temperature will lead to a 2.9 pcm/degree F decrease in the EOC MTC for Unit, 1 and a 2.8 pcm/degree F decrease in the EOC MTC for Unit 2.
Figure 2 shows that the MTC appears to be dependent on the core thermal power. As was stated before, a change in the steady state core operating power will cause a change in the coolant average temperature. Table 3 and Figure 3 demonstrate the EOC MTC dependency when the core average temperature is corrected to the nominal core average temperature as the power is varied. The dependency of the EOC MTC on core power was found to be approximately -0.015 pcm/degree F per percent power change for both Unit 1 and Unit 2. The dependency of the EOC MTC is not significantly dependent on the core power, but rather on the change in the average coolant temperature that results from a change in the core power. The high power trip limits are 1074 for Unit 1 and 112% for Unit 2. If were to increase to the high power trip setpoints (assuming power that the average coolant temperature remains constant), the EOC MTC would decrease by 0.18 pcm/degree F for Unit 1 and 0.105 pcm/degree F for Unit 2.
It can be seen in Table concentration about. the 2 and Figure nominal EOC 4 that varying the boron value (41 ppm for Unit 1 and 21 ppm for Unit 2) will affect the EOC MTC. As the boron concentration decreases (with all other parameters held constant), the MTC becomes more negative. The dependency of the MTC on the boron concentration was found to be 0.022 pcm/degree F per ppm for Unit 1 and 0.019 pcm/degree F per ppm for Unit 2. For example, a 100 ppm decrease in the boron concentration would lead to a 2.2 pcm/degree F decrease in the EOC MTC for Unit 1 and a 1.9 pcm/degree F decrease in the EOC MTC for Unit 2.
Table 2 and Figure 5 show that the EOC MTC is dependent on the RCS pressure. A change in the RCS pressure causes a change in the coolant density (both water and boron). A change in the RCS pressure also leads to a change in the average coolant temperature in order to maintain critical operations at a new pressure. A temperature change also leads to a change in the coolant density (both water and boron). For a given change in RCS pressure, these two effects are coupled and tend to cancel out, leading to small changes in the EOC MTC. For example, as RCS pressure increases, the coolant density increases (positive MTC trend). However, the average coolant temperature will also increase (to maintain critical operation at a new pressure) causing a decrease in the coolant density (negative MTC trend). The EOC MTC remains essentially unchanged.
At EOC, the MTC is most negative with respect to the steady state operating pressure when the RCS pressure is between approximately 904 to 954 of its nominal operating value (2250 psia). It can be seen that at. its most negative condition with respect to pressure, the EOC MTC is not significantly
more negative than its nominal value (0.34 less for Unit 1 and 0.5% less for Unit 2). A change in the RCS pressure does not adversely affect the EOC MTC (create a more negative EOC MTC).
Table 4 demonstrates that the MTC is dependent on the ASI.
Shifts in the ASI cause the power and therefore, the temperature distributions within the core to deviate from their nominal EOC profiles. Changes in the temperature distribution about the nominal EOC profile will lead to changes in the global EOC MTC. The St. Lucie steady state power operating procedures limit the ASI to a band of plus or minus 0.05 units about the nominal value. The EOC MTC dependence on ASI is -2.9 pcm/degree F per unit ASI for Unit 1 and -2.3 pcm/degree F per unit ASI for Unit 2. An ASI unit is very large when compared to the operating band width of 0.1 ASI units about the nominal value. These values correspond to at the worst case steady state EOC ASI (0.05 units about the nominal value), a 0.64 decrease in the EOC MTC for Unit 1 and a 0.44 decrease in the EOC MTC for Unit 2. It should be noted that as operating parameters vary about their nominal EOC values, the ASI will also vary about its nominal value.
However, the dependency of the EOC MTC on the ASI is small and can be ignored.
Table 2 shows that the EOC MTC is not significantly dependent on whether CEAs are partially inserted or fully withdrawn when all other plant parameters are held constant. Table 2 shows that the EOC MTC is 1.14 less negative when CEAs are inserted for Unit 1 and Unit 2. This analysis was performed assuming that the boron concentration was constant at the nominal EOC value (41 ppm for Unit 1 and 21 ppm for Unit 2) while the CEAs were inserted into the core. However, in actual operation, as CEAs are partially inserted, the boron concentration would have to be reduced to maintain critical operation. This would cause the EOC MTC to decrease due to the decrease in the boron concentration, as is shown in Figure 4.
The above results show that. the EOC MTC is primarily dependent on the average coolant temperature and the boron concentration. However, it is not possible to vary these parameters within technical specification limits during normal plant operation so as to cause the EOC MTC to become more negative than that allowed in the technical specifications.
The manners in which to increase the average coolant temperature (and reduce the EOC MTC) are: 1. increase reactor power, and/or 2. increase the inlet temperature, and/or
- 3. decrease the coolant flow rate. The variability of these parameters within technical specification limits is listed below.
TECHNICAL SPECIFICATION LIMITS ON THE VARIABILITYOP PLANT PARAMETERS Inlet 535 deg. F (Unit 2 only) < Tin < 549 deg. F Temp.
Pressure 2225 psia < Pres < 2350 psia (Unit 2 only)
Coolant Flow > 37,000 gpm (Unit 1)
Flow 36,300 gpm (Unit 2)
Power; Power < 100%
The above limits on the inlet temperature (549 deg. F),
coolant flow rate, and reactor power are the nominal operating values for these parameters. None of these three parameters can be varied so as to raise the average coolant temperature above its nominal value. Therefore, the EOC MTC can not become more negative than the technical specification limit as a result of a change in the average coolant temperature.
The boron concentration can be reduced (and the EOC MTC reduced) while maintaining critical operation by either raising the average coolant temperature or inserting CEAs.
Since the average coolant temperature can not be increased above its nominal value, the boron concentration can not be reduced due to a change in the average coolant temperature.
It can be seen in Figure 4 that a change in the boron concentration alone (critical operations with CEAs inserted) will not cause the EOC MTC to become more negative than the technical specification limits.
In summary, plant parameters exist, primarily the average coolant temperature and the boron concentration, that affect the EOC MTC. However, these parameters can not vary about their nominal values within technical specification limits so as to cause an EOC MTC more negative that the limits given in the technical specifications.
Table 1 St. Lucie 300 ppm MTC Surveillance Requirement Comparison of Measured And Predicted MTC Values BOC 800 ppm 300 ppm EOC HZP HFP HFP HFP UNIT 1 Cycle 6 measured 4.20 -3.60 -12.10 predicted 4.90 -1.50 -15.00 -22.60 Cycle 7 measured 4.70 -2. 00 -12.90 predicted 4.50 -1.80 -15.00 -21.06 Cycle 8 measured 4.40 -1.60 -12.00 predicted 5.60 -1.40 -15.50 -21. 44 Cycle 9 measured 4 ~ 10 -3. 60 -12.06 predicted 4.50 -2. 70 -12.97 -18.26 UNIT 2 Cycle 2 measured 4. 10 3 ~ 11 -16.20 predicted 3.41 -5. 14 -14.82 -22.14 Cycle 3 measured 2.71 -6.05 -13.82 predicted 2.49 -8.30 -16.75 -24.20 Cycle 4 measured 2.45 -6. 68 -15.69 predicted 2.69 -8.78 -16.64 -23.81 Cycle 5 measured 3. 65 -7.75 NA predicted 3.37 -9.56 -16.80 -25.00 NA 300 ppm MTC measurement not yet performed for Unit 2 Cycle 5
Table 2 St. Lucie 300 ppm HTC Surveillance Requirement Unit 1 Unit 2 Condition HTC Job HTC Job (pcm/deg. F) (pcm/deg. F) ¹ Comnents Change in RCS temperatures EOC HTC is strongly dependent on the steady state core average
~ 101X nom. Tin -24.89 358 -27.09 1465 temperature. Hot e that a 1X
" 100.5X nom. Tin -24.18 366 -26.35 '1478 increase in Tin c orresponds 100X nom. Tin -23.34 5463 -25 '0 5356 to a 1X increase in Tavg.
99.5X nom. Tin -22.56 378 -24.67 1486 99X nom. Tin -21.82 386 -23.87 1490 UNIT 1 UNIT 2
-0.29 -0.28 (pcm/Deg. F)/Deg. F Change in RCS Pressure
- 110X ncm. Pressure -22.60 1329 -24.69 1492 Haximan decrease in HTC is 105X ncm. Pressure -23.09 1343 -25 '3 1498 approximately 0.3X for Unit 1 and 100X ncm. Pressure -23.34 5463 -25 '0 5356 0.5X for Unit 2. EOC HTC is not
- 95X nom. Pressure -23.37 1353 -25.62 1506 adversely affected by the RCS 90X nom. Pressure -23.41 1360 -25.54 1513 pressure.
BOX nom. Pressure -23.10 2626 -25.09 2613 Change in Thermal Power A change in the thermal power
- 115X nom. Power -24.79 2631 .26.92 2620 results in a change in the core
- 110X nom. Power -24.34 1368 -26.47 1517 average tesyerature. The HTC 105X nom. Power -23.86 1374 -26.00 1527 dependency on the power is 100X nom. Power -23.34 5463 -25.50 5356 primarily dependent on the 95X nom. Power -22.80 1379 -24.95 1537 core average temperature.
90X nom. Power -22.29 1389 -24.41 1539 (See Table 3 for temp. correction)
Change in Boron Concentration OX nom. boron 0 ppm -24.2 92 0 ppn -25.91 1575 HTC dependent on boron concentration.
50X nom. boron 20 ppm -23.8 102 10 ppm -25.63 1581 100X nom. boron 41 ppm -23.3 5463 21 ppm -25.50 5356 150X nom. boron 60 ppm -22.9 115 30 ppm -25.33 1591 UHIT 1 UIIIT 2 200X nom. boron 80 ppm -22.5 128 40 ppm -25.12 1600 -0.022 -0.019 (pcm/Deg. F)/ppm
- - Beyond Limit given in Technical Specifications
Table 2 St. Lucie 300 ppm HTC Surveillance Requirement Unit 1 Unit 2 Condition HTC Job HTC Job (pcm/deg. F) ¹ (pcm/deg. F) ¹ Caments Insertion of Lead CEA Bank 100X withdrawn -23.34 5463 -25.50 5356 The dependence of the HTC 95X withdrawn -23 F 57 7831 -25.78 7804 on CEA insertion is minimal.
90X withdrawn -23.60 7834 -25.76 7809 1.1X decrease for Unit 1 85X withdrawn -23 '6 7838 -25.60 7811 1 'X decrease for Unit 2 BOX withdrawn -23.54 7842 -25.56 7815 75X withdrawn -23.56 7848 -25.72 7817 NOTE: In all cases ASI changes, however, effect on HTC is negligible Unit 1 Unit 2 Depletion given in Job ¹ 5049 Depletion given in Job ¹ 9696 Depleted to 16.5 Gwd/HTHH = 11,870 EFPN Depleted to 15.2 Gwd/HTNH = 11, 193 EFPN Boron Concentration = 41 ppm Boron, Concentration = 21 ppm Nom. Pressure = 2250 psi Nom. Pressure = 2250 psi Nom. Tavg "- 575.1 Nom. Tavg >>- 574.7 Nom. Tin = 548 degrees F. Nom. Tin = 548 degrees F~
Nom. Power = 2700 Hw Nom. Power ~ 2700 Hw
Table 3 St. Lucie 300 ppm HTC Surveillance Requirement EOC NTC PoMer Dependency Correction Unit 1 Unit 2 Rau Corrected RaM HTC Corrected Tavg HTC HTC Tavg HTC HTC X Pmer (deg. F) (pcm/deg. F) (pcm/deg. F) (deg. F) (pcm/deg. F) (pcm/deg. F)
- 115 579.6 -24.79 -23.49 579.3 -26.92 -25.63
- 110 578.1 -24.34 -23.47 577.8 -26.47 -25.60
- 105 576.6 -23.86 -23.43 576.2 -26.00 -25 '8 100 575.1 -23.34 -23.34 574.7 -25.50 -25.50 95 573.7 -22.80 -23.21 573.2 -24.95 -25.37 90 572.2 -22.29 -23.13 571.7 -24.41 -25.25 Beyond limits given in Technical Specifications NTC Tavg Dependency HTC Tavg Dependency pcm/deg. F. per Deg. F pcm/deg. F. per Deg. F
-0.29 -0.28 The EOC NTC dependency on poMer is actually a dependency on the average coolant tesperature associated Mith a given poMer level. SlHULATE3 cannot hold average coolant temperature constant Nile changing pcwer.
The temperature affect can be corrected out by the folloMing relation:
Corrected HTC = RaM NTC - Tavg dependency * [ Tavg(P) - Tavg(P=100X) ]
MBERE Tavg(p) -- the coolant average temperature for a given power level Tavg(Pi100X) -- the nominal average coolant temperature RaM HTC -- the HTC output by SIHULATE3 for given poMer level and associated average coolant tesperature Tavg dependency -- the dependency of the EOC HTC on Tavg Parer dependency for constant temperature = -0.015 pcm/degree F per X po~er change
Table 4 St. Lucie 300 ppm HTC Surveillance Requirement Dependence on Axial Shape Index (ASI)
Unit 1
-- Job 1993 Unit 2 -- Job 7824 Table 4 St. Lucie 300 ppm HTC Surveillance Requirement Dependence on Axial Shape Index (ASI)
Unit 1 -- Job 1993 Unit 2 " Job 7824 ASI HTC ASI HTC 0.066 -23.55 0.069 -25 ~ 73 0.040 -23.60 0.049 -25.76 0.012 -23.67 0 '25 -25.80
-0. 015 -23.75 0.000 -25.86
-0.041 -23.81 -0.027 -25.90
-0.080 -23.96 -0.072 -26.01
-0.091 -23.99 -0.089 -26.07
-0 '95 -24.01 -0.099 -26.10
-0.102 -26.12
-0. 101 -26.12 Unit 1 HTC = -2.9 (pcm/Deg. F)/(Unit ASI)
Unit 2 HTC = -2.3 (pcm/Deg. F)/(Unit ASI)
NOTE: ASI unit is large, change in ASI is small The ASI change was generating by inducing a xenon transient and determining the HTC at various times within the transient.
ASI = (Pbottom - Ptop)/(Pbottom + Ptop)
-ASI -- power in top half of core
+ASI -- power in bottom half of core The ASI band from the Operating Procedures is plus or minus 0.05 ASI units from the nominal value. Thus, the corresponding HTC band is plus or minus 0.145 pcm/deg. F for Unit 1 and 0.115 pcm/deg. F for Unit 2.
This corresponds to 0.6X decrease in the EOC HTC for Unit 1 and a 0.4X decrease in EOC HTC for Unit 2.
Figure 1 St. Lucie EOC MTC Behavior Analysis MTC vs. RCS Temperature
-20 21 ol'<Hvou wivH 7-~
No~iuy i GR6'ATer. %4 < Tea
+Ave . QOINIILPAI VOLZ i 4<~<60
-22 bu6 zo SPec<e'iud ~
<< i<<$ <> rcv power 23 4MO Fi os.
Unit 1 24 NDlhlQQL r4vc .
25 Unit 2 26 27 Unit 2 Technical Specification Limit 28 Unit 1 Technical Specification Limit 29 568.0 570.0 572.0 574.0 576.0 578.0 580.0 RCS Average Temperature (Deg. F)
Figure 2 St. Lucie EOC MTC Behavior Analysis MTC vs. Power
-20 21 8 oMi Ilail Po V4CL i evei. Beyond Technical
-22 Specification Limits z Unit 1
-24 25 Unit 2 26
-27 Unit 2 Technical Specification Limrt 28 Unit 1 Technical Specification Limrt 29 90% 94% 98% 1 02% 1 06% 1 10% 1 14%
% Nominal Thermal Power
l' Figure 3 St, Lucie EOC MTC Behaviour Analysis Corrected MTC vs. Power 22 Unit 1 gbwiWL.
pc w~
QEV6'L Beyond Technical Specification Limits 25 Unit 2 26 27 V
28 Unit 1 Technical Specification Limit 29 94K 1 02K~ 1 06K 11' Nominal Thermal Power
Figure 4 St. Lucie EOC MTC Behavior Analysis MTC vs. Boron Concentration 20 21
-22 Unit 1
-24 25 26
-27 Unit 2 Technical Specification Limit 28 Unit 1 Technical Specification Limit
-29 30 20 40 60 80 Boron Concentration (ppm)
Figure 5 St. Lucie EOC MTC Behavior Analysis MTC vs. RCS Pressure 20 I BbYOHD TtQ4.
l &Pic Liest'5, 21 I I F>N. <HlT 'z oH!!r I
Beyond Technical .1 Specification Limits I
I Unit 1 h
8
'U E Unit 2 Q.
26 I-I
~Unit 2 Technical Specification Limit l
28 !
>Unit i Technicai Specification Limit I
I 30 1.80 2.00 2.20 2.40 (Thousands)
RCS Pressure (psia)
.0