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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
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ACCELERATED DI UTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR: 9112040019 DOC. DATE: 91/11/26 NOTARIZED: NO DOCKET FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power & Light Co. 05000335 50-389 St. Lucie Plant, Unit 2, Florida Power & Light Co. 05000389 AUTH. NAME AUTHOR AFFILIATION SAGER,D.A. Florida Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards responses to NRC 910912 ltr transmitting safety evaluation on station blackout rule (10CFR50.63(a)).
Commitment for required blackout duration revised to target D reliability level of equal to or greater than 0.975.
DISTRIBUTION CODE: A050D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: Station Blackout (USI A-44) 10CFR50.63, MPA A-22 NOTES:
RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 PD 1 1 NORRIS,J 1 1 D INTERNAL: ACRS 1 1 AEOD/DS P/TPAB 1 1 NRR PD2-4PM TAM 1 1 NRR/DET/ESGB 8D 2 2 NRR/DST/SELB NRR/DST/SRXB8E 3
1 3
1 N /. - PLB8Dl 01 3 3 G 1 1 EXTERNAL: NRC PDR 1 1 NSIC D
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL 17
4 P.O. Box c, Ft. Pierce, FL 34954-0120 L-91-311 November 26, 1991 10 CFR 50.63 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Safet Evaluation on Station Blackout Rule By letter dated September 12, 1991 (J. A. Norris to J. H.
Goldberg), the NRC forwarded to Florida Power & Light Company (FPL) a Safety Evaluation (SE) on the Station Blackout (SBO) rule for St.
Lucie Units 1 and 2. By letter L-91-282, dated October 17, 1991, as required by 10 CFR 50.63(c)(4), FPL provided its commitment schedule for implementing equipment and associated procedure modifications necessary to meet the requirements of 10 CFR
- 50. 63 (a) .
In its letter of October 17, 1991, FPL committed to provide responses to the "Requests" of, as well as comments on, the NRC's SBO SE. Enclosed are FPL's Request responses and comments on the subject SBO SE. Additionally, as discussed in the enclosure, FPL has revised its commitment, for the required SBO duration. FPL will maintain the St. Lucie Unit 1 EDGs at a targeted reliability level equal to or greater that 0.975. As a result, FPL considers the required coping duration for St." Lucie Unit 1 as four hours.
FPL requests written NRC acknowledgement of the acceptability of FPL's responses to the NRC Requests of the SBO SE as .well as the positions delineated in the FPL Comments section of the enclosure.
If you have any additional questions on the enclosed, please contact us.
Very truly yours, D. A. ger Vice esident St. L ie Plant Enclosure DAS/PSL N570-91 cc: Stewart D. Ebneter, Regional Administrator, Region Senior Resident Inspector, USNRC, St. Lucie Plant II, USNRC 9ii20400i9 9ilI,26 05000335 PDR ADOCK P PDR an FPL Group company
't 1 t
E II'
Enclosure St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Safet Evaluation on Station Blackout Rule Requests Safet Evaluation Section 2.3e4
~Re uest: The licensee should complete the ventilation studies and include the studies and the results in the documentation supporting the SBO submittal that is maintained by the licensee. The licensee should implement any procedure changes and modifications that are required to assure adequate ventilation is maintained, in the areas containing SBO equipment, for the required coping duration.
FPL Res onse: FPL will complete SBO ventilation studies on a schedule sufficient to support the implementation of any procedure changes and modifications that may be required to a'ssure adequate ventilation is maintained in the areas containing safe shutdown equipment for the required coping duration.
The St. Lucie Unit 1 ventilation, studies will include the following:
- 1) Control Room FPL will calculate the peak Control Room temperature assuming that, a single train of heating, ventilation, and air conditioning (HVAC) is available and powered by the Alternate AC (AAC) source. The single HVAC train consists of an air handler and its respective compressor (i.e., HVA-3A with ACC-3A, HVA-3B with ACC-3B, or HVA-3C with ACC-3C) The peak temperature will be calculated and confirmed acceptable with respect to the availability of safe shutdown equipment and Control Room habitability during the SBO event.
- 2) Reactor Containment Buildin The peak containment temperature will be calculated assuming:
a) A Reactor Coolant System (RCS) leak rate consistent with the RCS inventory analysis performed to address the Request of Safety Evaluation Section 2.3.6, Reactor coolant inventor b) No containment heat removal systems are operating throughout the SBO event.
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Vt ~
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St. hucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Safet Evaluation on Station Blackout Rule(cont) c) Normal containment heat removal system is restored (i.e., the containment fan coolers) following termination of the SBO event.
The calculated peak containment temperature will be used to confirm the availability of SBO safe shutdown equipment during the SBO event.
- 3) Reactor Auxiliar Buildin Char in Pum Room FPL will calculate the peak temperature in the charging pump room assuming only one Reactor Auxiliary Building (RAB) main supply fan (i.e.,
HVS-4A or HVS-4B) and no RAB main exhaust fan operating.
The supply fan will be assumed to be operating once the AAC source is available to the blacked-out unit. The charging pump room peak temperature will be evaluated with respect to the SBO event charging system availability.
RAB Electrical E ui ment and Batter Room FPL will calculate the peak temperature in safety-,related electrical equipment rooms. It will be assumed that one train of the electrical equipment room supply fans (HVS-5A or HVS-5B) and exhaust fans (train "A" fans RV-2, RV-3, RV-4, HVE-11 or train "B" fans RV 1g and HVE-12) will be powered from the AAC source.
Other RAB Areas FPL will evaluate the effects of reduced ventilation capability in the remainder of the RAB with respect to the SBO event safe shutdown equipment availability. Peak temperatures and equipment availability will be analyzed accordingly.
- 4) Auxiliar Feedwater'FW S stem The steam-driven AFW pump and other AFW system components necessary to provide feedwater to the steam generators rely on natural ventilation. As a result, the AFW system operating conditions would not be affected by special SBO event environmental conditions and no ventilation evaluations nor analyses will be performed.
The evaluations and analyses described above will be included in the St. Lucie Unit 1 Updated Final Safety Analysis Report (UFSAR).
Any recpxired procedure changes identified as a result of these evaluations and analyses will be in the procedures developed to deal with a SBO event at St. Lucie Unit 1.
d n
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St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Safet Evaluation on Station Blackout Rule(cont)
Safet Evaluation Section 2.3.6 Receuest: The licensee should evaluate and confirm that there will be adequate reactor coolant system inventory to ensure continued core cooling for the required 8-hour SBO duration and recovery therefrom with an assumed leakage rate of 112 gpm, and include this information in the documentation supporting the SBO submittal that is maintained by the licensee.
FPL Res onse:
As noted below in Station Blackout Duration of FPL Comments, FPL has reconsidered its commitment for the required SBO duration. FPL revises its commitment conservatively and will maintain the St.
Lucie Unit 1 EDGs at a reliability level equal to or greater than 0.975. As a result, FPL will consider the required duration for St. Lucie Unit 1 as four hours. Therefore, the coping FPL evaluation and confirmation of adequate reactor coolant system inventory to ensure continued core cooling will be conducted for a four hour SBO event duration.
In accordance with NRC SE Section 2.3.6, Reactor coolant inventor FPL will evaluate and confirm that adequate RCS inventory will remain at the termination of the SBO event. However, the evaluation will not consider the effects on the non-blacked-out (NBO) unit's EDG load profile of the hypothetical 112 gpm RCS leak rate.
Similarly, the St. Lucie Unit 1 SBO Emergency Operating Procedures (EOPs) will not assume that operator actions are required to mitigate the effects of a small break loss of coolant accident (SBLOCA) (i.e., due to the 112 gpm RCS leak rate) in conjunction with an SBO event. The evaluation will verify that the assumed 112 gpm RCS leak rate, which FPL will assume decreases throughout the course of the event as RCS pressure decreases, will not result in the loss of core coverage, that sufficient core cooling is available for the SBO event duration, and that recovery from the event is analytically achievable.
The St. Lucie Unit 1 RCS inventory evaluation and confirmation will be completed by FPL using RETRAN03 MODOOO and assuming a decay heat load in accordance with ANS 1979 (times a 1.05 uncertainty factor).
The inventory loss evaluation will assume a pressure-dependent leak rate which decreases over the duration of the SBO event; RCS inventory makeup via a charging pump will be assumed at some time following the completion of the AAC intertie. Auxiliary Feedwater (AFW) initiation will be assumed in accordance with system design and safety injection will be assumed to be unavailable for the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SBO event.
"St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Safet Evaluation on Station Blackout Rule(cont)
The evaluation and confirmation will be completed by September 12, 1993, and the results of the evaluation will be included in the St.
Lucie Unit 1 Updated Final Safety Analysis Report (UFSAR).
Safet Evaluation Section 2.5 Receuest: The licensee should provide a full description, including the nature and objectives, of the required procedure changes identified in 2.4 and 2.5 above in the documentation supporting the SBO submittals that is to be maintained by the licensee.
i FPL Res onse: FPL will complete the SBO procedure changes by September 12, 1993. These procedures will give detailed instructions on the method for cross-tying the St. Lucie Unit 2 EDGs to Unit 1 as well as the Unit 1 EDGs to Unit 2. The revised procedures will not consider multiple event scenarios such as a small break loss of coolant accident (SBLOCA) resulting from Reactor Coolant Pump (RCP) seal 'failure(s). Existing EOPs would be used for multiple event accident management.
The full description, including the nature and objectives, of the required procedure changes identified in Sections 2.4 and 2.5 of the SE, will be included in the St. Lucie Unit 1 Updated Final Safety Analysis Report (UFSAR).
Safet Evaluation Section 2.7 Receuest: The licensee should confirm that an EDG reliability program which meets the guidance of RG 1.155, Section 1.2, will be implemented. Confirmation that such a program is in place or will be implemented should be included in the documentation supporting the SBO submittals that is to be maintained by the licensee.
FPL Res onse: FPL will confirm, by September 12, 1993, that an EDG reliability program has been implemented to attain and maintain the St. Lucie Unit 1 targeted EDG reliability. Confirmation that such a program is in place will be included in the St. Lucie Unit 1 Updated Final Safety Analysis Report (UFSAR).
Safet Evaluation Section 3.0
~Re uest: The licensee is expected to maintain the reliability of the Unit 2 EDGs at 0.974 or greater in accordance with the licensing basis for Unit 2 in regard to the SBO issue. The licensee
St. "Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Safet Evaluation on Station Blackout Rule(cont) is also encouraged to update the SBO coping procedures for Unit 2 to incorporate the enhanced capability provided by the AC intertie between Units 1 and 2.
FPL Res onse: FPL will maintain the reliability of the St. Lucie Unit 2 EDGs at 0.974 or greater in accordance with the licensing basis for Unit 2 in regard to the SBO issue by implementation of an EDG reliability program which attains and maintains the St. Lucie Unit 2 targeted EDG reliability.
As discussed above in the FPL Res onse to the NRC Request related to Safety Evaluation Section 2.5, FPL will complete the SBO procedure changes by September 12, 1993. Consistent with FPL philosophy on the operation of St. Lucie Units 1 and 2, these procedure changes will implement a similar strategy for operationally coping with an SBO at either St Lucie Unit 1 or 2.
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St: ?ucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Safet Evaluation on Station Blackout Rule(cont)
FPL Comments Station Blackout Duration In the St. Lucie units 1 and 2 Safety Evaluation on Station Blackout, the NRC staff, in Section 2.1 Station Blackout Duration, observes:
During the May 21, 1991, meeting with the NRC staff, the licensee agreed to...an 8-hour coping duration.
FPL has reconsidered its commitment for the required SBO duration.
FPL revises its commitment conservatively and will maintain the St.
Lucie Unit 1 EDGs at a targeted reliability level equal to or greater that 0.975. As a result, FPL considers the required coping duration for St. Lucie Unit 1 as four hours.
Pro osed AAC ower source In Section 2.2.2, Pro osed AAC ower source, of the NRC's SE, the NRC states,
...(T)he licensee provided (during the site audit review) the NBO loads (Unit 2) as 1954 kW and SBO loads (Unit 1) as 897 kW...The...(SAIC TER) documents the LOOP loads of the Unit 2 (NBO unit) as 2802.5 kW...and the corrected SBO loads of the Unit 1 (SBO unit) as 1133.5 kW. This tabulation indicates a total load of 3936 kW for the NBO and SBO unit...
FPL notes that the NBO loads of 1954 kW and the SBO loads of 897 kW were identified as conceptual values and provided as informational loadings during the St.Lucie Plant SBO site audit to qualitatively demonstrate that the St. Lucie Units 1 and 2 EDGs have sufficient capacity to qualify as AAC sources. Subsequent to that audit, FPL has conducted detailed task analyses and completed engineering calculations for the SBO event which have concluded that the St.
Lucie Unit 2 EDGs have sufficient capacity to operate equipment which may be required under SBO conditions. These load calculations and task analyses resulted in somewhat different equipment alignments from those of the NRC's SE.
Nonetheless, FPL will analyze plant response to the SBO event assuming that a maximum of 3936 kW is available to both units from the operating St. Lucie Unit 2 EDG. This analysis will be used to
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St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Safet Evaluation on Station Blackout Rule(cont) conclude that acceptable plant response to an SBO event can be confirmed considering the St. Lucie Unit 2 UFSAR LOOP EDG load profile concurrent with the St. Lucie Unit 1 required SBO loads.
The analysis will confirm that these combined loads do not exceed 3936 kW and will include the blacked-out unit's (i.e., Unit 1) components considered in the NRC SE which FPL determines may be required during an SBO event. The ventilation studies described in FPL's response to the NRC Request for SE Section 2.3.4 above will determine which ventilation loads are required. Additionally, FPL will assume calculated running kW loads for each required component during the SBO event in liew of the worst-case design basis accident LOOP/LOCA EDG load values of the NRC's SBO SE.
These loads, and the plant response analyses to support their acceptability, will be included in the St. Lucie Unit 1 Updated Final Safety Analysis Report (UFSAR).
SBO Submittal Documentation In the staff's SE, various Requests state that FPL "...should...
include this information in the documentation supporting the SBO submittal that is maintained by the licensee." FPL intends to meet this aspect of the NRC's SBO SE for St. Lucie Unit 1 by incorporating the SBO evaluations and/or confirmations in the St.
Lucie Unit 1 Updated Final Safety Analysis Report (UFSAR).
As FPL has committed to meeting 10 CFR 50.63 by September 12, 1993, all SBO evaluations and/or confirmations will be included in the first annual UFSAR update subsequent to September 12, 1993 (i.e.,
July 21, '1994).
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