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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
ACCESSION NBR:FACIL:50-33550-389AUTH.NAI'IEWOODY~C.O.RECIP.NAI'IEREGULATORY'ORI"IATION DISTRIBUTION BYR~EI'I(RIDS)8702180096 DQC..DATE.'7/02/09 NOT*RID:NOSt.LuciePlantiUnitiiFloridaPowerCcLightCo.St.LuciePlantiUnit2>FloridaPower5LightCo.AUTHORAFFILIATION FloridaPowerSrLightCo.RECIPIENT AFFILIATION DocumentControlBranch(Document-'ontrol Desk)DOCKET0500033505000389
SUBJECT:
Forwardsaddiinfofor860702applicati onforamendtoLicenseNPF-16respentfuelstorage>per861210request.ShippingcaskI'IodelsNAC-15NLI-1/2onlycasksthatmeet25tonTechSpeclimitforUnit1caskcrane.DISTRIBUTION CODE:A001DCOPIEBRECEIVED:
LTRiENCLIBIZE:TITLE:QRSubmittal:
GeneralDistribution NOTES:RECIPIENT IDCODE/NAI'IE PWR-BEBPWR-BFOBPWR-BPD8PD04PIJR-BPEICSBINTERNAL:ADI'I/LFI'IB NHFT/TSCBREQFI01COPIESLTTRENCL115510111RECIPIENT IDCODE/NANE PWR-BPElCSBPWR-BPD8LATOURIGNY>EPWR-BRSBELD/HDS2NRR/ORASCOPIESLTTRENCL2201111010EXTERNAL:
EGMBRUSKEiSNRCPDR02111LPDRNSIC0305,1111TOTALNUj'IBEROFCOPIESREQUIRED:
LTTR22ENCL18 lit1vls8hliriP'llt1,,1'tt~t)rtt*~~ttjgitttgtft'tettltt".3f'".":)
9$g4l~tttttttt"IttiII*l?it~t P.o.B000,JUNOBEACH,FL33408.0420
~ygllhy~FEBRUARY91987L-87-48U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Gentlemen:Re:St.LucieUnitsIand2DocketNos.50-335and50-389SentFuelTransferByletterL-86-250, datedJuly2,l986,FloridaPower&LightCompany(FPL)proposedtoamendtheSt.LucieUnit2operating licenseNPF-l6toestablish theoptionofstoringspentfuelfromSt.LucieUnitIintheSt.LucieUnit2spentfuelpool.TheUnitIspentfuelpoolwilllosefullcorereservecapacityasaresultofthel987refueling outage,andtheplannedUnitIspentfuelpoolrerackcannotbeaccomplished priortol988.If,intheinterim,fullcoreoff-loadofUnitIshouldbenecessary, UnitIspentfuelcouldbestoredintheUnit2spentfuelpool.ByletterdatedDecemberIO,I986(E.G.TourignytoC.O.Woody)theNRCStaffrequested additional information requiredtocontinuetheirreviewofthisproposedlicenseamendment.
AttachedisFPL'sresponsetothisrequest.lfadditional information isrequiredonthistopic,pleasecontactus.Very,truly yours,C.O.WGroup'President NuclearEnergyCOW/EJW/gpAttachment cc:Dr.J.NelsonGrace,RegionII,USNRCUSNRCResidentInspector, St.LuciePlant8702i80096 870209PDRADOCK05000335pPDR.UMoolEJW4/00I/IanFPLGroupcompany I~Mh&rrr~".~Ill',~~Ii>>i.;,~~MI'--hII4-~0<<dil<<44-'IcIriII',<<~4->>rf>>II'Ii'>>m4'Iill,,4J>>r~~",<<I~rII>><<>><<'<<~llmk.
~<<.I<<4~>>i>>44'-'I"~4li.-'>>~4->>'4l~44~M=I'4*)(42~.-y<<I~I~I"'Ir~<<h'Irrr4>>,ff<<,I,<<4h>>,4hr<<II4'.MI>>IIhl4-ii.444~",I,M,'..4ilt~>>>>'rit.i-filiIitfi4,~~'IPI.<<4<44.'Mg"II'Mr444IU4fii>>,',F44~I.*<<f(IifI>><<lt4'ilI>>=4.>>Ii'I~I"IIIf1iik<<.IM4\"'hii~',IIll>><<III.lhI'1"'I".i,4<<,',,"<<ilkii'~'.4l",frl>>r,hl>>ri<<h<<<<
.~ll4I'Ill4~$<<hri,i44>>+w>>4<<IM)QV4~Mh<<r'4~IM-~ll<<r3IPrh'Ofi4I>>'l4I.>>rlll~r~i'IrI',IrI~<<v<<rIl ATTACHMENT REQUESTFORADDITIONAL INFORMATION FLORIDAPOWER8LIGHTCOMPANYST.LUCIEUNITSIAND2SPENTFUELTRANSFERBETWEENUNITSPLANT,ELECTRICAL, INSTRUMENTATION ANDCONTROLSYSTEMSBRANCHInyoursubmittal datedJuly2,l986,youproposedalicensing amendment toestablish theoptionoftransferring andstoringspentfuelassemblies (SFAs)fromtheSt.LucieUnitIspentfuelpool(SFP)totheSt.LucieUnit2SFPinordertopermitfullcoreoff-loadcapability atUnitI,shoulditberequired, duetolossofUnitIfullcorereservestoragecapacityfollowing thel987refueling outage.Providethefollowing additional information withrespecttothisproposal:
I.Providefurtherdetailsregarding theUnitISFAstobestoredintheUnit2SFP.Thedetailsshouldincludenumber,typeandageofexistingSFAstobetransferred toUnit2andtheSFAlocations intheUnit2storagerackstobeutilized.
Alsoprovideanynecessary drawingstoclarifyyourresponse.
~ResonseTheSt.LucieUnitIspentfuelassemblies whichwouldbeconsidered initially forstorageintheSt.LucieUnit2spentfuelpoolwouldbethosethathavehadthelongestdecaytimeintheUnitIspentfuelpool,i.e.BatchA,Combustion Engineering assemblies whichwereoffloadedfromtheUnitIcoreduringUnitIsfirstrefueling outageinApril-May l978,andhaveremainedinthespentfuelpoolsincethatoffload.RefertoSt.LucieUnitIUpdatedFinalSafetyAnalysisReport(FSAR)Table4.2-landFigure4.2-3.Althoughtheproposedamendment wouldnotlimitthenumberofSFAsthatcouldbetransferred totheUnit2SFP,itisexpectedthatonlyl5to25SFAswouldbesubjecttotransfer, shouldthisoptionbecomenescessary.
FigureI-IshowstheUnitIspentfuelpoolwiththeBatchAassemblies indicated.
FigureI-2showstheUnit2spentfuelpool.TheUnitIassemblies wouldbeputintotheindicated rackpositions closesttothecasklaydownarea,shouldthetransferbenecessary.
Thiswouldbeconsistent withtherequirements ofSt.LucieUnit2Technical Specification 5.6.l.2.ConfirmthatyouwillhandlenomorethanoneSFAatagiventimeinashippingcask,andthatonlyonetypeofshippingcaskwillbeused.~ResonseAtthistime,shippingcaskModelNos.NAC-IandNLI-I/2aretheonlycasksthatmeetthe25tonTechnical Specification 3.9.I3limitfor.theUnitIcaskcrane.BoththeNAC-IandNLI-I/2casksarecapableofholdingonlyonePWRfuelassembly.
Therefore, handlingmorethanoneSFAinacaskisprevented bythedesignofthesecasks.EJW4/00I/2 fiI~lvtvfit-v'00k40rtl(kl~0'4"II*v&vII-ltVI.Il,.vvltiv"l44040itf,ll4'vI,I,4I0'Ifl4',f,0I,00~400'ttthfl0'I00~..40ii4*4~',vl,I4~44Iv-"44'Itf4~~ill"I0viVvtII~~~4I0'0llllflWV,r"S-'4~v00ft004flIIr4.~4If00ItIVV'l000~I~4104040f44000IIlOI4It(tIIIfvI00tlI'III~Iv04fv..l44IV~j'll~gfttt4slI 3eProvideasummaryoftheevaluation performed concerning theshippingcaskloadpathbetweentheunits.Thissummaryshouldincludeadiscussion ofthemeansutilizedtoconfirmthatsafetyrelatedequipment including piping,components, andelectricconduitsthatarelocatedneartheloadpathandthosethatareburiedundertheloadpathwillnotbeadversely affectedwithregardtotheircapability toperformtheirintendedsafetyfunctions duringnormalspentfueltransferfromUnitItoUnit2andintheeventofanaccidentsuchascaskdrop.Also,provideanynecessary drawingstoclarifyyourresponse.
~ResenseTheevaluation considered aspentfueltrans-shipment pathstartingattheUnitIcaskloadingareaandtraveling totheUnit2caskloadingareaasindicated inFigure3-l.Thispath,initsentirety, coincides withaportionoftheintermodal casktransporter pathpreviously evaluated foreffectsuponunderground structures andutilities.
Thespentfueltrans-shipment pathroadsurfaceispavedwithPortlandcementconcreteorasphaltic concrete.
Thefuelelementstobetransported willutilizeaoneelementshippingcaskhavingamaximumweightof25tonswhenloadedwiththespentfuelassembly.
Twotransport vehicleswereconsidered intheevaluation.
WheelloadsforthetwovehiclesareshowninFigures3-Iand3-2.Thereactions ofthetwotransport vehicleswerecomparedtothemaximumreactions oftheintermodal casktransporter thatwaspreviously evaluated.
Sincethereactions oftheintermodal casktransporter aregreaterthanthereactionforeitherofthetwotransport
- vehicles, theintermodal casktransporter evaluation isconsidered tobeanenveloping evaluation.
Theeffectoftheintermodal casktransporter wheelloads(andthusthespentfueltransporter wheelloads)ontheroadway,missileprotection slabsandunderground facilities (i.e.,pipes,electrical conduit,manholesandcatchbasins)hasbeenanalyzed.
Thepunchingshearoftheconcreteroadwayisacceptable forsurfaceareasofbothsingleanddualtirewheels.Eachsurfaceareawasalsoevaluated formaximumsoilbearingcapacityandfoundtobeacceptable.
Themaximumstressesanddeflections ofthemissileprotection slabs,underground pipesandconduitarewithintheallowable range.Theultimatestrengthdesignofthemanholesandcatchbasinsusingtheappropriate loadcriteriawasreviewedandfoundtobeacceptable.
Theroadwaywillbeinspected forgeneraldeterioration sothatitcanberepaired, ifnecessary, priortothetransport ofspentfuel.Theshippingcaskwillbeadequately securedtothetransport vehicle.Thepossibility ofacaskdrophasbeengreatlyminimized bythefollowing:
a.conservative designmarginsintheliftingcomponents b.redundant brakingsystemsforhoistsystemsc.periodictestsandinspections ofthecranesEJW4/001/3 4h,t4I4If4Ut4~~III~4I'Ut444IUII4IhI~~I,"4II,4llN~N~*ttt4III~4IUll,f,tII4I4I4III444II4, d.useofqualified craneoperators andriggerse.theuseofapprovedoperating andadministrative procedures RefertoFPLresponsetoQuestionNo.8foradiscussion ofacaskdropaccidentinthecasklaydownareaofeitherunit.4.Providethedetailsofthespentfuelshippingcaskandverifythatitmeetstherequirements of10CFRPart71.~ResonseForanytransferoffuelbetweenSt.LucieUnitsIand2priortocompletion ofthererackoftheUnitIfuelstoragepool,thespecificcasktypewillbeeithertheModelNo.NAC-IortheModelNLI-I/2series.Pursuantto10CFR71.12,FPLwillregistertheNAC-IcaskwiththeNRCpriortoitsuse.TheNRChasissuedCertificate ofCompliance No.9183,RevisionNo.3datedNovember14,1984forthiscaskwhichstatesthattheNAC-Iisapprovedforuseunderthegenerallicenseprovisions of10CFRPart71.12.TheNLI-I/2caskiscurrently registered forusebyFPL.TheNRChasissuedCertificate ofCompliance No.9010,RevisionNo.16,datedJanuary16,1986forthiscaskwhichstatesthattheNLI-I/2isapprovedforuseunderthegenerallicenseprovisions of10CFRPart71.12.5.According tothetechnical specification forSt.LucieUnitI,thespentfuelstoragecaskcanbemovedintothespentfuelstoragepoolareawhenthespentfuelinthepoolhasagedmorethan1190or1490hours,depending ontheamountofspentfuelinthepool.Thetechnical specifications alsoallownewspentfueltobemovedintothespentfuelstorageareaafterthereactorhasbeenshutdownfor72hours.However,thereisnobasisprovidedfortheminimumshutdowntimethatwouldberequiredifnewspentfuelweretransferred byashippingcasktotheSt.LucieUnit2SFP.Therefore, provideananalysisfortheminimumshutdowntimethatwouldberequiredforapostulated designbasiscaskdropaccidentoccurring outdoorsbetweenUnitsIand2andconfirmthattheresulting off-sitedosesarelessthan10%ofthe10CFRPart100guideline dosevalues.~ResonseSection9.1.4.3.e oftheUnitIFSARprovidesananalysisofthepotential offsitedoseresulting fromthedroppingofacaskcontaining tenspentfuelassemblies outsidethefuelhandlingbuildingunderadversemeteorological dilutionconditions.
Thisanalysisassumesnotonlytenassemblies, butalsoaminimumdecayof90days.BecausetheBatchAassemblies havedecayedinexcessofeightyearsandonlyoneSFAwillbetransferred atatimeasdiscussed intheresponsetoQuestion2,theabovereferenced analysisisbounding.
Therefore, noadditional analysisisnecessary.
EJW4/001/4
.~4<<lliv<<A(4UI4'U'itttiIl.4'>>4~4I(.I',I'II4~AU"~>>'>>Ill'IJ.IIrf/liv)4,/44,'k.'U>lc'4.)Qf.f<<Ur~4/.Pt>I'UAh'tIA-llIUt/i4kil>>~44ll'I/',,/llr'/tfv/<<~>>.:,(Ill/Vk~lt'I/I4>>i<<+Ititk4A4I'UgrU>>J,,;I~,'4'>>Ilt>>itIil/>>g~A,4>>->>&4I4ilitl~>>I4I4A"I~IIIi~4i>>U-UC/i>>IU-II'II4Ii4foil'I~4~It4>>vIilA~.4.4>>.~It~toll>>>>4"I'>>k>>~>>lv--"Lf('IU'I~<<~U>>rWilhII.UC~UI4.'k)UU'lCI'C""t4U~~'.lii~rr~.,ilLI~itAkr',.C>>ti.I<<LUVt/rll4li>>UVD<<~ILIlllri'v<<vk~IAlilIIItlAIl-r/I'Ufl".kt4I4,ll>>v4/<<>>U~44L,Ll>>I<<VI>>r4c.4vi/t'>>444I'.ii444IL1~'I44ilIUCUCU~Ir.14UII~I>ltIvIIil4~I>>.li>>Ik4I~~~:>>II4UUI>>I4~UV<<>>I'W>>~*U/C'4~>>>>~.~,~444Arv4IICQC/~k'\>>k4~4'UU.VillIIC~Ik~At~k4t(4p4I,'Ilk..'If'"AC~4'I4*~4CktCI~"4AilA4A-I<<V~44UI'I~II>>.'iI/~VvvCI'I'4I~4k~<<4~tlI~;,/",,Uit',II,,I'>>>>>./>>VIt4~C>>4,/'II~I~,'Iv>>
6.Provideadescription ofthedoserateatthesurfaceofthepoolwaterforbothUnitsIand2fromthefuelassemblies, controlrods,burnablepoisonrodsoranymiscellaneous materials storedinthepool.Also,providethedoseratefromindividual fuelassemblies astheyarebeingtransferred tothecask,andspecifythedepthofwatershielding thefuelassemblies astheyarebeingtransferred.
Ifthedepthofwatershielding overafuelassemblyduringtransferislessthanIOfeet,orthedoserate3feetabovetheSFPwaterisgreaterthan5mR/hraboveambientradiation levels,thenproposeatechnical specification specifying theminimumdepthofwatershielding tobemaintained overthefuelassemblyasitisbeingtransferred inorder'tomaintainALARAlimits,andidentifythemeasurestakentoassurethatthisminimumdepthwillbemaintained.
~ResonseTravelstopsinthefuelhandlingequipment forbothunitslimitthetraveltorestrictwithdrawal ofthespentfuelassemblies.
Thislimitation, togetherwithwaterlevelcontrol,resultsinthemaintenance ofaminimumwatercoverof9ft.overtheactiveportionofthefuelassembly, resulting inaradiation levelof2.5mR/hrorlessatthesurfaceofthewater(seeSt.LucieUnitIFSARSection9.I.4.3andSt.LucieUnit2FSARSection9.I.4.3.3).
Notethatifthetravelstopsshouldfailandtherewerenooperatoraction,thefuelhandlingmachinecannotraisetheassemblyabovea9ft.water-to-active-fuel-length heightbecauseofthespentfuelmachinedesigngeometry.
RefertoFPLresponsetoQuestion7foradiscussion onmaintaining ALARAlimitsduringfuelassemblytransfer.
FPL'sALARAprogram,coupledwithdesigngeometry, interlocks andlimitswitchesobviatetheneedforadditional fueltransferTechnical Specifications.
7.a.Describethemannerinwhichoccupational exposurewillbekeptALARAduringthetransfer, including theneedforandthemannerinwhichcleaningofthecrudonSFPwallswillbeperformed toreduceexposures ratesintheSFParea.Also,describethemeanstobeutilizedtoensurethatdosestodiversaremaintained ALARA.b.Describethemannerinwhichoccupational exposurewillbekeptALARAduringcleanupoperations aftercompletion ofthespentfueltransfer.
~Resonsea.Duringthepostulated fueltransfer, occupational exposures willbelimitedbyALARAprocedures andguidelines whichcurrently existatSt.Lucie.Additionally, experience gainedfrompreviousfuelmovementoperations andthethermalshieldremovalfromUnitIwillbeusedinkeepingexposures ALARA.FPLletterL-86-458, datedNovemberl4,I986describes FPL'sALARAprogramandpersonnel exposureexperiences.
CrudontheSFPwallsforeitherunitpresentsaninsignificant contribution toexposureatSt.Lucie.Diverswouldnotbeusedintransferring spentfuelbetweentheunits.EJW4/00I/5 U14II,tt~ItIll~1wdttNI'lI~14F~IIIIItf4I4it"4Ill4I4ItttAif4i'dtttt~t'N,<<Utfd14Ud1It4I4~I;144ll4*~~44'1It,>.I,II,NII):filIlIUI4"'1~I'W)I~IUdIIII,/UtII/I441'I~IOUI4tlt~IiitiAldkII44IllitlmttI4Uk.If~t,~ItAIlkttOIIAI~Utkid,I44IUt,.1,tfIO4ttILW,AIW-U4ltItI'.'i'INt14ttt,ItWttUlttt4It'4UIt>>tttI4ttltII4IUO44AI4I1<<IIItUUIt~II.OftUU\1 b.Asdiscussed initema.,above,occupational exposurefromcleanupoperations whichwouldresultfromthepostulated fueltransferwillbelimitedtoALARAbyprocedures andguidelines whichcurrently existatSt.Lucie.8.DiscusstheextentofdamagethattheSFPmayincurfromadroppedspentfuelshippingcask,andconfirmthatsufficient boratedmake-upwaterisavailable'o maintaintheminimumSFPwaterlevelforanyresulting leakage.~ResonseSection9.I.4.3oftheUnitIFSARpostulates twocaskdropaccidents fortheUnitISFP,averticalandatippedcaskdrop.Theverticalcaskdropintothecaskstorageareahasbeenanalyzedtodetermine iftheleaktight barrierofthepoolcanbebreached.
Theresultsoftheanalysisindicatethattheleaktight integrity ismaintained fora25toncaskdrop.Technical Specification 3/4.9.I3,"SpentFuelCaskCrane,"providesassurance thattheUnitIfuelcaskcranedoesnothandleloadsinexcessof25tons.Atippedcaskdrophasalsobeenconsidered andtheanalysisresultsfoundtobeacceptable.
IntheUnit2spentfuelpoolaconcretewalltothetopoftheSFPseparates thecaskstorageareafromthespentfuelstoragearea.Thewallpreventsawaterlevelreduction overthespentfuelassemblies evenifadroppedfuelcaskcausesdamagetothepoolorpoollinerinthecaskstoragearea.Forbothunits,thecaskisphysically prevented andadministratively prohibited fromtraveling overtheSFPoutsidethecaskstoragearea.9.Provideanevaluation ofthetotaldosetomembersofthepublicresulting fromtheproposedtransferconsidering thefollowing:
a.timerequiredtomoveeachfuelassemblyfromtheUnitISFPtotheUnit2SFP;b.releasesofradioiodines andotherradionuclides duringthistime;c.directradiation; d.transferandcleanupoperations; ande.othersourcesofexposureatthesite.~ResonseTheonlydosetomembersofthepublicthatcouldpotentially occurwouldbeasaresultofafuelhandlingorcaskdropaccident.
Theseaccidents havebeenanalyzedintheUnitIFSARSections9.I.4.3andl5.4.3.2andintheUnit2FSARSectionsl5.7.4.I.2andI5.7.4.I.3.
EJW4/00I/6 4III'..4.414hICIt>>II:IP>>.:"4,4)IIlli>>4Ih"Ill4IL4/44l!r4rttt444-1t~,I>>r4>>4~84"I'l~C[tlI~IIhr~~~14f4ItI2~~4IIIItI'>>'->>4~14,4JlhrlPttI~ttrit~r4gltrt1444I441lt4I'I444>>4'I~ll44444~I4;,tr>>~ffII'.P4'irI'(1l,".l4>>44.
I.tt',I444it144I~>>>>p>>4~~4",rI4'II1,I'-II41~t>>tt'.I>>4iKIf'4>>~I1llIDhti4~~ll4lt,4~IfoII't14>>t411~I~lr44"','lII14(llIII4~.~IIrI'.lhrrh',llrI>>lit,4lt4thl,t4>>rt~~4,Il4Il,I'ith>>-'4~~tlhrt4'9ttI44'4A~I4I~II4>>L4I4'.<'>>I~ill>>I*hit444444M44'll'l41>>-44)l4
~4l'.4>>P>>4tlI444lt4>>~44*tllt4ilII>>II,4IIltt*tII.h-13'=4'tt>>44'4~~~~rt-444tl,lI~44"-~1~4>>~I~lt~-I>>~ltlt~~I~'~11tt4444'l4I4~4lt~1>>,r~lt4~tt14)Ittllil-ilhit IO.Describetheprovisions formonitoring releasesofradioactive materials, environmental radiological monitoring, andcalculating andreporting effluents andoffsitedosesfromtheproposedtransferoperations andsubsequent clean-upoperations, orjustifynotproviding suchmonitoring, calculating, andreporting.
~ResonseSt.LucieUnitIandUnit2Technical Specifications Section3/4.II,"Radioactive Effluents,"
and3/4.I2,"Radiological Environmental Monitoring",
providerequirements onthemonitoring ofradioactive
- releases, environmental monitoring andsubsequent reporting requirements.
Anypotential fueltransferwouldbesubjecttotheserequirements.
II.Yourrequestindicates thatspentfuelwillbetransferred onlyfromUnitItoUnit2.Confirmthatthisisthecase.Ifyourrequestalsoinvolvesthecapability totransferspentfuelfromUnit2toUnitI,provideinformation comparable tothatindicated previously forthiscase,orconfirmthattheconditions ofthetransferwillbeidentical tothatforUnitItoUnit2.~Resonselfafullcoreoff-loadisrequiredpriortoreracking theUnitISFP,onlyfueldischarged fromUnitIwillbetransferred toUnit2.Nofueldischarged fromUnit2willbetransferred toUnitI.However,afterreracking theUnitISFP,anyspentfuelfromUnitIwhichmayhavebeentransferred totheUnit2SFPcouldbereturnedtotheUnitISFPundertheconditions described above.EJW4/00I/7 flI4'1tIIIIbHIIIvIIIIII>>4'5 ggjttXIXOP7lfI1N8BatchAFuelAssemblies WithLongestContinuous DecayTimeKio1C1iS5JpAAAh88CCbbEEFFGGHHC,CLL2827262524232221201918171615141312II1098765432IlLFigure1-1SpentFuelStorageSt.LucieUnit1 4ltly't ST.LUCIE UNIT2OPERATLGPR'OCEDURE NO>>2-1600022, REVI~ON2UNITNO.2REPUELTNG OPERATION FIGURE6SPENTPUELSTORAGEFOLL(MING REFUELING ORERATION 1))Illan1III~'0I>>II+~p~4r~~57V~d~kuwX~SECTIONBSECTIONAIVIIVIIrIIrIIIIIIYlIIYlIIrlIIYIVYlIIIYlIIIIIkiIIrIlIIVIIIIIIIIIIIVlIIYlIIVYIIYIIIYlIIVIIIIIIIIVVIIVIIIIirIIIrIlIvIIIriIVVIIYVIYlIIIIIIIPIIi'PiIt'lIIVVlIIIIVlIYIVIVIIIIIIVIIIVIIIIIVIIIrtrIIIPIIIllIIIVIIiFigure1-2 Figure3~8H]P'GALGA9'KTICA~ORT~
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