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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
REQfj.ATINFORMATIONDISTRIIOSTEM(RIDS)ACCESSIQNNBR:8708310039DOC.DATE.:87/08/25NOTARIZED:NOFACIL:59-389St.LuciePlantiUnit2iFloridaPower5LightCo.AUTH.NAMEAUTHORAFFILIATIONWQODYiC.O.FloridaPowerZrLightCo.RECIP.NAME.RECIPIENTAFFILIATIONDocument'ontrolBranch(DocumentControlDesk)
SUBJECT:
ForwardsrevisedlargebrealLOCAEGCSperformanceresultsforlimitingbreaksizeforfacilitywhichgustifiesincresedsteamgeneratortubeplugginglimitofupto1430Tubes.DISTRIBUTIONCODE:A001DCQPIESRECEIVED:LTRENCL'IZE:TITLE:QRSubmittal:GeneralDistributionNOTES:DOCKET005000389RECIPIENTIDCODE/NAMEPD2-2LATOURIQNYiECOPIESRECIPIENTLTTRENCLIDCODE/NAME0PD2-2PD1COPIESLTTRENCL5INTERNAL:ARM/DAF/LFMB~NRR/DEBT/CEBNRR/DEBT/RSBNRR/PMAS/ILRB01EXTERNAL:EQSQBRUSKE,8NRCPDR01111111111h!RR/DEST/ADSNRR/DEBT/MTBh!RR/DOEA/TSBQQC/HDS2RES/DE/EIBLPDRNSIC11111110111111TOTALNUMBEROFCOPIESREQUIRED:LT1R21ENCL18
-4I'I4"1Jttftf'4<<'<<.4<<4Il]EK')J'r4))"I>IJ'IJi1tl44l'LTCJ/'<<,fl"4t'4I4)~/~IJ"JP"7,4,g,4LfJ41~1jf1),IIII)~l4tt),'I)+I<<'44IIi'4/lyg't"j"<<44K'1JJrt.*wg",4<<)t,)t)t/4IJ/.LI"4<<)/III<<4eelyI~1t4'IKJ,l<<g"41"4III),$4I'/444~
P.X14000,JUNOBEACH,FL334080420>y9l/6,AUGUSTJ251987L-87-327U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555Gentlemen:Re:St.LucieUnitNo.2"DocketNo.50-389LareBreak'LOCAAnalisisFloridaPower&-LightCompany(FPL)hasreanalyzedtheSt.LucieUnit2LargeBreakLOCAAnalysis.ThenewLOCAAnalysissupersedestheanalysisofrecordsubmittedbyFPLletterL-86-37,datedJanuary3,l986,whichsupportedasteamgeneratortubeplugginglimitofl250averagelengthtubespersteamgenerator.TheattachedrevisedLargeBreakLOCAAnalysisjustifiesanincreasedsteamgeneratortubeplugginglimitofuptol430tubes.Thisre-analysiswasperformedusingtheNRC-approvedJunel985versionoftheCombustionEngineering(CE)LargeBreakLOCAevaluationmodel.Otherplantparameterchangeswereincorporatedinthisanalysisinanefforttoboundfuturecyclesandpossibleplantchanges.Theresultsoftheanalysisdemonstrateapeakcladtemperature(PCT)of2I07F,apeaklocalcladoxidationpercentageof7.62%andapeakcorewideoxidationpercentageoflessthan0.70%.TheseresultsdemonstratecompliancewithIOCFR50.46acceptancecriteriaof2200oF,l7%andI%,respectively.There-analysispredictsIFhigherPCTthanthePCTpredictedinthecurrentReferenceAnalysis.AlthoughthischangeinPCTdoesnotrequiresubmittaloftherevisedanalysistotheNRC,itisbeingsubmittedtojustifyanincreasedsteamgeneratortubeplugginglimitandtocalltothestaff'sattentiontheuseoftheJunel985versionoftheCELargeBreakLOCAevaluationmodelforSt.LucieUnit2.Verytrulyyours,C.O.WooGroupViresidentNuclearEnergyCOW/EJW/gcAttachmentcc:Dr.J.NelsonGrace,RegionalAdministrator,RegionII,USNRCSeniorResidentInspector,USNRC,St.LuciePlant8708$t0039BQP00+8970826pDRADO~pDRPEJWI/02I/IanFPLGroupcompany I,Id-~~~444~4v~Ilf~I'Ithl4~4NMA~4II!<<A~"~dt'~l444VIVII~"I4I'"IIt'ld4At!'LL'VV4I4IdlthI,NI,!~I!~14~'4i'II44~'~l4'=414I~*<<4I'14ItId~',If.~4ILV~h)44<<~~I4LA!'v4\ItlI!I4N,IUd~44('dI'4'.4LL'I(I'4I!4NU~/N41~Iht.dv,-IAC4-VUt!~I44'.MV!4I>>,<<A'"';4IhAl~~I,I!I.4t,",..41!f,I4IIL,'lt.4,4:.l"..VVC4UI~letdtII4=<<NII4d44I!.V!3I~41V1I14'~NLAUlAV!44I'~t'Md!c4".!L<1~I!'4!!Vt',d1hl~~~I LargeBreakLOCAECCSPerformanceResultsfortheLimitingBreakSizeforSt.Lucie2 Large8reakLOCAECCSPerformanceIntroductionandSummarAnECCSperformanceanalysiswasperformedforSt.LucieUnit2todemonstratecompliancewithlOCFR50.46whichpresentstheNRCAcceptanceCriteriaforEmergencyCoreCoolingSystemsforlightwater-cooledreactors(Reference1).TheanalysisevaluatesvariousplantchangesutilizingtherecentlyapprovedC-EJune1985version(Reference2)ofthelargebreakloss-of-coolant(LOCA)evaluationmodel.ThismodeldiffersfromtheevaluationmodelappliedinlicensingSt.Lucie2CycIe3(Reference3).TherevisedlargebreakLOCAevaluationmodelapprovedbyNRCincludes,changesto:(1)thecladdingdeformation/rupturemodelsbasedonNUREG-0630,(2)thesteamcoolingmodelsappliedatandabovetherupturelocationforrefloodratesbelowoneinchpersecond.(3)COMPERC-IIallowingsafetyinjectionpumpdeliverybeforethesafetyinjectiontankshaveemptied,(4)CEFLASH-4Anumericalmethods,(5)thestagnationpropertiesusedintheMoodybreakflowmodel,(6)thenodalizationschemeusedinCEFLASH-4A,and(7)theaxialpowershapeusedintheanalyses.Ofthesechanges,items(1)and(2)introducebeneficialeffectsonthecalculatedresultsatandabovethecladrupturelocation.Items(3)through(6)haveanegligibleorsmallbeneficialimpact.Theaxialpowershapehasanadverseimpactonresults;however,theCycle3analysisalreadyincorporatedthenewshape.ThecurrentanalysiscomplieswiththeconditionsforNRCapprovaloftherevisedmodel.Theseconditionsrequirethatapplicationofthemodelinclude:abreakspectrumstudyutilizingtheadverseaxialpowershapetodeter~incthe limitingbreaksize;adeterminationofwhethernosinglefailureisworsethanassumingtheworstsinglefailure;andassurancethattherevisedsteamcoolingheattransferisnotallowedtoexceedheattransferpredictionsbasedontheFLECHTcorrelation.Abreakspectrumanalysiswasperformedtodeterminethelimitinglargebreak.Inaddition,theanalysisassumed1430pluggedtubespersteamgenerator,fuelparameterswhichboundcurrentandexpectedconditions,augmentationpenaltyofunity,aninitialsafetyinjectiontank(SIT)gaspressureof200psig,reducedRCSvesselandcorebypassflow,andanend-of-cycletemperaturecoastdown.Theanalysisjustifiesanallowablepeaklinearheatgenerationrate(PLHGR)of13.0kw/ft.'ThisPLHGRisequaltotheexistinglimitforSt.LucieUnit2.Themethodofanalysisanddetailedresultswhichsupportthisvaluearepresentedherein.MethodofAnalsisThemethodofanalysisisbaseduponC-E'sJune1985largebreakLOCAECCSevaluationmodelwhichisdescribedinReferences4through10andwasapprovedbytheNRCinReference2.TheReferenceCycle,St.Lucie2Cycle3analysis(Reference3)utilizedthepreviouslyapprovedlargebreakLOCAevaluationmodel.Exceptforthemodelandvariousplantparametersdiffer-encesdescribedabove,themethodofanalysisisidenticaltotheReferenceCyclelargebreakLOCAECCSperformanceanalysis.Blowdownhydraulics,refill/refloodhydraulicsandhotrodtemperaturecalculationswereperformedwithfuelparameterswhichboundthecurrentfuelcycleandexpectedconditionsforfuturecyclesatareactorpowerlevelof2754Mwt.Theblowdownhydraulicscalculations'ereperformedwiththeCEFLASH-4Acode(Reference7)whiletherefill/refloodhydraulicscalculationswereperformedwiththeCOMPERC-IIcode(Reference8).ThehotrodcladtemperatureandcladoxidationcalculationswereperformedwiththeSTRIKIN-II
~~
andPARCHcodes(Reference11and12,respectively).Fuelperformancecalcu-lationswereperformedusingtheFATES-3AversionoftheC-E'sNRCapprovedfuelperformancecode(Reference13and14)withthegrainsizerestrictionasrequiredbytheNRC(Reference15).MostoftheECCSanalysisinputparametersarethesameasthoseoftheReferenceCycle(Reference3).1nparticularthelimitingaxialshapeusedisthesameasthatusedintheReferenceCycleandisconsistentwiththeselectionproceduredocumentedinReference9andapprovedbytheNRCinReference2.AsummaryofthesignificantinputparametersandinitialconditionsforthepresentandthereferenceanalysisareshowninTablel.ThemajordifferencesandtheirimpactonthePeakCladTemperature(PCT)arediscussedbelow.ThisanalysisaccountsforsteamgeneratorU-tubepluggingofupto1430averagelengthtubespergeneratorcomparedto1250fortheReferenceCycle(Reference3).Inaddition,thisanalysisusedaninitialsafetyinjectiontankpressureof200psigandanaugmentationpenaltyofunitycomparedtovaluesof570psigand1.01,respectively,fortheReferenceCycle.BasedonReference16afavorableincreaseintheinitialcontainmentwalltemperatureof90F(comparedtoavalueof60FfortheReferenceCycle)wasused.Abreakspectrumanalysiswasperformedincorporatingtheabove.Toboundfuturefuelcycles,thelimitingbreakdeterminedfromthebreakspectrumanalysiswasreanalyzedwithalimitingsetofradiationenclosuredata.Anassessmentwasmadeoftheimpactofreducingthecorebypassflowsuchthatvesselflowcanbereduced(from363,000gpmto359,700gpm)whilemaintainingthesamecoreflow.Anevaluationofatemperature.coastdownto520Fattheendofthecyclewasalsoperformed.
Steamgeneratortubepluggingincreasestheresistancetoflowpassingthroughtheprima'rysideofthesteamgenerator,therebyinhibitingsteamventingfromthecoreoutletplenumtothebreak.Thisreducestherefill/refloodratesandincreasesthepeakcladdingtemperature.Thisanalysisassumes1430pluggedtubespergenerator;however,italsoconservativelyboundspluggingfewerthan1430tubesineitherorbothsteamgenerators,sincethiswouldreducetheflowresistanceandreducethepeakcladtemperature.ThereductionintheaugmentationpenaltyresultsinanincreasehotassemblyaveragechannelPLHGR.Thehotassemblyaveragechannelinfluencestheradiationheattransferbetweenthehotrodofthehotandtheaveragerodofthehotassembly.HigherpoweroftheaveragethehotassemblyresultsinreducedheattransferfromthehotrodtosurroundingrodsresultinginahigherPCT.ofthePLHGRassemblyrodofitsReducingtheSITinitialgaspressureresuItsinaslightincreaseintherefilltime.Increasedrefilltimemeansalongerperiodofadiabaticheatup.ThisconsequentlyresultsinahigherPCT.IncreasingtheinitialcontainmentwalItemperatureresultsinanincreaseinrefloodflowintothecore.Thishelpstolowerthepeakcladtemperature.Reducingthevesselflowratebylessthan1%withaco~respondingdecreaseincorebypassflowhasaminimalimpactonthePCT.StudiesperformedforotherC-Eplantshaveshownthat~educingthevesselandcoreflowratesby16%increasesPCTbylessthan10F.Thisslightsensitivitywouldbefurtherreducedifthecoreflowremainsthesame.
Temperaturecoastdown-.atEOCdoesnotadverselyaffectPCT.ExplicitphysicscalculationsforEOCcoastdownconditionsconfirmedthattheReferenceCyclecoreparameters(e.gesaxialandradialpowerdistributfons,andPLHGR)conservativelyboundEOCcoastdownconditions.TheonlyadverseimpactofEOCcoastdownistheeffectwhichthereducedcoolanttemperaturehasontheblowdownhydraulics.However,previousstudieshaveshownthistobeasmalleffect,andonewhichisoffsetbythesignificantlylowerfuelstoredenergyatEOCburnuprelativetothelimitingburnupusedinthecurrentanalysiz.ResultsTable2providestheresultsofthebreakspectrum.Double-EndedSlotatPumpDischarge(DES/PD)b~eakswerejudgedtobenon-limitingbasedonfuelaveragetemperaturesatTAD(TimeofAnnulusDownflow)whichdefinestheendofblowdownportionofthetransient.Asexpected,thebreakspectrumanalysisdeterminedthe0.6DEG/PDbreaktobethelimitingbreak.ThepreviouslyapprovedevaluationmodeldemonstratedaweaksensitivitytoPCTduetotheva~iousbreaksizes.ThisisalsotruefortheJune1985evaluationmodelasshowninTable2.However,thenewleakflowmodelincorporatedintheJune1985evaluationmodelintroducesashiftfnthelimitingbreaksizeduetothesmallchangeintheleakflowcharacteristics.ThisisconsistentwithotherC-EplantswhichutilizedtheJune1985evaluationmodel.Table3presentstheresultsofthelimitingbreakreanalyzedwithaconservativesetofradiationenclosuredata.Table4presentsalistofthesignificantparametersdisplayedgraphicallyforthebreak.Theresultsoftheevaluationconfirmthat13.0kw/ftisanacceptablevalueforthePLHGRinthepresentanalysis.ThepeakcladtemperatureandmaximumlocalandcorewidecladoxidationvaluesasshowninTable3,arewellbelowthe10CFR50.46acceptancelimitsof2200F,17%and1%respectively.
The0.6OEG/PDproducedthehighestcladtemperatureof2107Fandapeaklocaloxidationof7.62%comparedtotheacceptancecriteriaof2200Fand17%0respectively.The0.6OEG/PDalsoresultedinthehighestcorewideoxidationoflessthan0.7%whichiswellbelowthe1%acceptancecriteria.Areviewofthetheeffectsofinitialoperatingconditionsontheseresultswasperformed.ItwasdeterminedthatovertherangesofoperatingconditionsallowedbytheTechnicalSpecification,aPLHGRof13.0kw/ftisanacceptablelimit.ConclusionsTheresultsoftheECCSperformanceevaluationforthepresentanalysisforSt.LucieUnit2demonstratedapeakcladtemperatureof2107F,apeaklocalcladoxidationpercentageof7.62%,andapeakcorewideoxidationpercentageoflessthan0.7%comparedtotheacceptancecriteriaof2200F,17%and1%~espectively.Therefore,operationofSt.LucieUnit2atacorepowerlevelof2754Neth(102%of2700Nwth)andaPLHGRof13.0kw/ftisinconformancewith10CFR50.46.
Table1St.Lucie-Unit2SinificantParametersandInitialConditionsForBreakSectrumStud(1)ParametersReference~CclePresent~AnalaiaCorePowerat102%ofNominal(MMt)CoreAverageLinearHeatRateat102%ofNominal(kw/ft)~PeakLinearHeatGenerationRate(PLHGR)HotAssembly,HotChannel(kw/ft)PLHGRHotAssembly,AverageChannel(kw/ft)CoreInletTemperature(OF)CoreOutletTemperature('F)VesselFlow(10ibm/hr)CoreFlow((10ibm/hr)GapconductanceatPLHGR'Btu/hr-ft'-'F)(2)FuelCenterlineTemperatureatPLHGR(F)FuelAverageTemperatureatPLHGR(4F)HotRodGasPressure(psia)HotRodBurnup(NMO/MTU)NumberofTubesPluggedperSteamGeneratorAugmentationFactorSafetyInjectionTank(SIT)gaspressure(psig)InitialContainmentTemperature(F)27544.9013.011.45552603.8136.1131.11416322820781118103812501.015706027544.9013.011.57552603.8136.1131.11460329621021118103814301.0020090Hotrodradiationenclosure,andcoreandvesselflowratesweienotchangedforthebreakspectrumstudy.Theirimpactissubsequentlyevaluatedbasedonthelimitingbreaksizedeterminedbythisstudy.STRIKIN-IIvaluesathotrodburnupwhichyieldshighestpeakcladtemperature.
Table2St.Lucie-Unit2BreakSpectrum-ResultsBreakSizeTAO()Time,SecondsFuelAverageTemperatureatTAOFPeakCladTemperatureOF0.8OEG/PO0.8OEG/PO0.4OEG/PO0.8OES/PO0.6OES/PO0.4OES/PO20.022.627.618.020.225.4107711231074991992984206120652034(b)(b)(b)(a)Timeofannulusdownflow-endofblowdown.(b)Slotbreakswerejudgedtobenon-limitingbasedontheirsignificantlylowerfuelave~agetemperatureatTAO.andbecausetherefloodheattransferapplicabletotheslotbreaksisnoworsethan'heconservativeheattransferappliedtotheguillotinebreaks.Oouble-EndedGuillotineatPumpOischarge.Oouble-EndedSlotatPumpOischarge.
Table3St.Lucie-Unit2tnitialConditionsandResultsforLimitinBreakSize0.6OEG/POReference~CnlePtesent~AnalsisInitialConditionsPeakLinearHeatGenerationRate(kw/ft)RadiationEnclosurex-factorPeakLinearHeatGenerationRate(PLHGR)HotAssembly,AverageChannel(kw/ft)13.02.1911.4513.02.0011.80ResultsPeakCladTemperature('F)TimeofPeakCladTemperature(Seconds)TimeofCladRupture(Seconds)PeakLocalCladOxidation(%)TotalCore-WideCladOxidation(%)210625955.8516.12~0.70210726644.747.62+0.70'Lowerx-factorindicatesflatterpowerdistributioninthevicinityofthehotrod.
TableaSt.LucieUnit2VariablesPlottedasaFunctionotTimefortheLimitinLareBreakl/ariaaieFiaureNumberCorePowerPressureinCenterHotAssemblyNodeLeakFlowHotAssemblyFlow(belowhotspot)HotAssemblyFlow{abovehotspot)HotAssemblygualityContainmentPressureMassAddedtoCoreDuringRefloodPeakClaaTemperatureHotSpotGapConductancePeakLocalCladOxidationTemperatureofFuelCenterline,FuelAverage,CladandCoolantatHottestNodeHotSpotHeatTransferCoefficientHotRodinternalGasPressure1234567891011121314
Reference:
l.AcceptanceCrfterfaforEmergencyCoreCoolingSystemsforLightMaterCooledNuclearPowerReactors,FederalRegister,Vol.39,No.3,January4,1974.2.Letter,D.N.Crutchfield(NRC)toA.E.Scherer(C-E),"SafetyEval-uationofCombustionEngineerfngECCSLargeBreakEvaluationModelandAcceptanceforReferencfngofRelatedLicensingTopicalReports",July31,1986.3.LetterC.O.Woody(FPL)toF.J.Miraglia(NRC),"St.LucieUnitNo.2DocketNo.50-389CELargeBreakLOCAAnalysis",January3,1986,L-86-37.4.Letter,A.E.Scherer(C-E)toJ.R.Miller(NRC),'LD-81-095,Enclosure1-P,"C-EECCSEva1uatfonNodelFlowSlockageAnalysis".(Proprietary),December15,1981.5.Letter,A.E.Scherer(C-E)toC.0.Thomas(NRC),LO-86-027,"Responses-toquestionsonC-E'sRevfsedEvaluationModelforLargeBreakLOCAAnalysis",(Proprietary),June17,1986.6.Letter,A.E.Scherer(C-E)toC.0.Thomas(NRC),L0-85-032,"RevisiontoC-EModelforLargeBreakLOCAAnalysis",July3,1985.7.CENPO-133,Supplement5-P,"CEFLASH-4A.AFORTRAN77OfgftalComputerProgramforReactorSlowdownAnalysis",June1985.8.CENPD134,Supplement2-P,"CONPERC-ll,AProgramforEmergencyReffll-RefloodoftheCore",June1985.9.CENPO-132-P.Supplement3-P,"CalculativeNethodsfortheC-ELargeBreakLOCAEvaluationModelfortheAnalysisofC-EandMDesignedNSSS",June1985.
1O.Letter,A.E.Scherer(C-E)toC.O.Thomas(NRC),L0-85-050,Enclosure,"SupplementalMaterialforInclusioninCENPO-132.Supplement3-P",(Proprietary),November5,1985.11.CENP0-135,Supplement2-P,"STRIKIN-II,ACylindricalGeometryFuelRodHeatTransferProgram(Modifications)",February1975.CENP0-135-P,Supplement4-P,"STRIKIN-II.ACylindricalGeometryFuelRodHeatTransferProgram",August1976.CENP0-135-P,Supplement5-P,"STRIKIN-II,ACylindricalGeometryFuelRodHeatTransferProgram",April1977.12.CENP0-138-P,andSupplement1-P."PARCH,AFORTRANIVOigitalProgramtoEvaluatePoolBoiling,AxialRodandCoolantHeatup",February1975.CENPO-138Supplement2-P,"PARCH-AFORTRAN-IVQigitalProgramtoEvaluatePoolBoiling,AxialRodandCoolantHeatup",January1977.13.CENP0-139-P-A,"C-EFuelEvaluationModelTopicalReport",July1974.14.CEN-161(B)-P,"ImprovementstoFuelEvaluationModelTopicalReport",July1981.15.LetterfromR.A.Clark(NRC)toA.E.Lundvall,Jr.(BGSE),datedMarch31,1983.16.Letter,J.L.Perryman(FPSL)toE.L.Trapp(C-E),FRN-86-404,"St.Lucie2LargeBreakLOCAReevaluation",November10,1986.3183-43-4-87 FIgura1ST.LUCIEUNIT2O.BxDOUBLEENDEDGUILLOTINEBREAKINPUMPDISCHARGELEGCOREPOSER120011000080QQ6000I~O400020GO000qaaaaaaaaaaC4aaaaP)aaaaaaaiQTlNKINSEC Figllf82ST.LUCIEUNIT20.8xOOUBLEENDEDGUILLOTINEBREAKINPUMPOISCHARGELEGPRESSUREINCENTERHOTASSEMBLYNOOE240002000016GO0g1200.G8GGG4GG.GCDCDCDCDCDCDCQCDCDCDCDODCDCDCUCDCDCDCDTIl1ElNSEC Figure3~ST.LUCIEUNIT2O.BxDOUBLEENDEDGUILLOTINEBREAKINPUMPDISCHARGELEGLEAKFLONiZGOQO.-PUMPSIDE---REACTORVESSELSIDE1000008GQQO.CQGOGGO.4GOGG2GOGOC)C)CDOCDCQC)CDC)CDC)CQC)OOCVCDC)CDTIf1EI'!4SEC FIgUre4ST.LUCIEUNIT20.8xOOUBLEENOEDGUILLOTINEBREAKINPUMPOISCHARGELEGHOTASSEMBLYFLOW,BELOWHOTSPOT3000020000iO.GGGCOKlGGG-IGGGGCD-20GGG-30GGOCDCDCDC)CD(0C)CDCDCUC)CDC)CaCDCDCDCUCDCICDCD
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