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| h ATTACHMENT6Page5of7DIifrXR1(e~i)o-ekijl)i)kAlltermshavethesamemeaningasinthepreviousequation,except:R<~semi-infiniteclou9dosconversionfactor[6:1109-21Jf~4~35E9se"(Xe)Theatmospherictritiumconcentrationiscalculatedasfollows:C~PcX~C~tritiumconcentrationinair(uCi/m3)Fboil-offrateofpoolwater~4,377ml/secc~tritiumconcentrationinpoolwater.077uCi/ml3.RESULTS3.1DoseCommitmentatExclusionbreaBoundary(EAB)Nu"lideAdultabsorbeddosecommitmentatEAB(rem)131I132I133'5KrTotalTnyroid0.1172.50K-30.119Skin1.51E-51.15K-61.62E-5WholeBody1.458-51~38"-81.458-53.1.1TritiumconcentrationstEABDuringthefirsttwohoursfollowingtheaccident,themaximustritiumcon"entrationsttheExclusionAreaBoundary(EAB)iscalculatedtobe2.98-8uCi/ml(2.9E-2uCi/m3)inair.Thisvalueiswellbelowthemaximumpermissibleconcentration(MPC)fortritium,whichis2E-7uCi/ml.TheMPCisthelimitingconcentrationforachronicexposure.SinceanindividualattheEABispostulatedtobeexposedforamaximumoftwohours,thecontributionoftritiumtohistotaldoseisinsignificant.3.2DoseCommitmenatLPZThefollowingcalculationswereperformedforthemaximumexposedindividualattheLPZouterboundaryduringthe30-dayperiodoftheaccident. | | h ATTACHMENT6Page5of7DIifrXR1(e~i)o-ekijl)i)kAlltermshavethesamemeaningasinthepreviousequation,except:R<~semi-infiniteclou9dosconversionfactor[6:1109-21Jf~4~35E9se"(Xe)Theatmospherictritiumconcentrationiscalculatedasfollows:C~PcX~C~tritiumconcentrationinair(uCi/m3)Fboil-offrateofpoolwater~4,377ml/secc~tritiumconcentrationinpoolwater.077uCi/ml3.RESULTS3.1DoseCommitmentatExclusionbreaBoundary(EAB)Nu"lideAdultabsorbeddosecommitmentatEAB(rem)131I132I133'5KrTotalTnyroid0.1172.50K-30.119Skin1.51E-51.15K-61.62E-5WholeBody1.458-51~38"-81.458-53.1.1TritiumconcentrationstEABDuringthefirsttwohoursfollowingtheaccident,themaximustritiumcon"entrationsttheExclusionAreaBoundary(EAB)iscalculatedtobe2.98-8uCi/ml(2.9E-2uCi/m3)inair.Thisvalueiswellbelowthemaximumpermissibleconcentration(MPC)fortritium,whichis2E-7uCi/ml.TheMPCisthelimitingconcentrationforachronicexposure.SinceanindividualattheEABispostulatedtobeexposedforamaximumoftwohours,thecontributionoftritiumtohistotaldoseisinsignificant.3.2DoseCommitmenatLPZThefollowingcalculationswereperformedforthemaximumexposedindividualattheLPZouterboundaryduringthe30-dayperiodoftheaccident. |
| ATTACHMENT6Page6of7Nu"liheA]ultahsorbe4dosecoz~itmntatLPZ(re~)1311132I133~e~85KzTotalTnyroid4.1211.92E-30.123Skin1~89'52'9-62'8E"5lAoleBody1.82E-53.488-81.82E-53.2.1TritiumconcentrationatLPZDuringthefirsteighthoursfollowingthea=cident,themaximustime-averageitritiumcon"entrationattheLPZboundaryiscalculatedtobe2.7E-9uCi/mlinair.ThisvalueissellbelowtheMPCfortritium.Sincetheatmosphericdilutionfactor(Xi/Q)usedinthiscalculationisapplicabletothefirsttvohoursoftheaccidentonly,andsinceinanycastheaccidentispostulate9tolastonly30days,thecontributionoftritiumtohtotaldoseisinsignificant.4~CON"LUSZONSThemaximuscalculatedthyroi0dosismuch'lessthan1Xofthe10CFR100limitof303rem.TheAaole-boiyandskindosesarecompletelyinsignificant.REFERENCES1.Florid'aPover8LightCompany:"St-LuciePlant-UnitNo.1,SpentFuelStorageFacilityModificationSafetyAnalysisReport,DocketNo.5'3-335.2.Eickelpas"h,N.,andR.Hock:"FissionProductReleaseafterReactorStutdeun",LhEA-SS-17S/i9,inErperiencefree~OperetinendFuellingNu=learPoverPlants,Vienna,19743.ExxonNuclearCompany,Inc.:"St~Lu"ieUnit1RadiologicalAssessmentofPostulatedAccidents".XN-NF-84-85(P),Rv.l.4.V.S.AtomicEnergyCommission,RegulatoryGuide1.4:AssumptionsUsedforEvaluatingthePotentialRadiologicalConsequencesofaLossofCoolantAccidentforPressurizedWaterReactors".Rev.2,1974.5'.S.Nu"learRadulatoryCommission,RegulatoryGuide1.25:"AssunptionsusdforEvaluatingthePotentialRadiologicalConsequencesofaFuel ATTACHMENT6Page7of7HandlingA"cidentinthFuelHandlingandStorageFacilityforBoilingandPressurize)M~terRa"tors"~6J.S.NuclearRegulatoryCo~mission,RegulatoryGuide1.109:"CalculationsofAnnualDosestoNonfro~RoutineRleasesofRactorEffluentsforthePurposeofEvaluatingCompliancewitn10CFRPart50,AppendixI"~Rev.1,1977~7.Lederer,C.M.,andV.S.Shirley,eds:TableofZsotops,7thEd~,19788.FloridaPowr5LightCompany:"St~Lu"iePlant-UnitNo~1,UpdatedFinalSafetyAnalysisReport",AmendmentNo.6. | | ATTACHMENT6Page6of7Nu"liheA]ultahsorbe4dosecoz~itmntatLPZ(re~)1311132I133~e~85KzTotalTnyroid4.1211.92E-30.123Skin1~89'52'9-62'8E"5lAoleBody1.82E-53.488-81.82E-53.2.1TritiumconcentrationatLPZDuringthefirsteighthoursfollowingthea=cident,themaximustime-averageitritiumcon"entrationattheLPZboundaryiscalculatedtobe2.7E-9uCi/mlinair.ThisvalueissellbelowtheMPCfortritium.Sincetheatmosphericdilutionfactor(Xi/Q)usedinthiscalculationisapplicabletothefirsttvohoursoftheaccidentonly,andsinceinanycastheaccidentispostulate9tolastonly30days,thecontributionoftritiumtohtotaldoseisinsignificant.4~CON"LUSZONSThemaximuscalculatedthyroi0dosismuch'lessthan1Xofthe10CFR100limitof303rem.TheAaole-boiyandskindosesarecompletelyinsignificant.REFERENCES1.Florid'aPover8LightCompany:"St-LuciePlant-UnitNo.1,SpentFuelStorageFacilityModificationSafetyAnalysisReport,DocketNo.5'3-335.2.Eickelpas"h,N.,andR.Hock:"FissionProductReleaseafterReactorStutdeun",LhEA-SS-17S/i9,inErperiencefree~OperetinendFuellingNu=learPoverPlants,Vienna,19743.ExxonNuclearCompany,Inc.:"St~Lu"ieUnit1RadiologicalAssessmentofPostulatedAccidents".XN-NF-84-85(P),Rv.l.4.V.S.AtomicEnergyCommission,RegulatoryGuide1.4:AssumptionsUsedforEvaluatingthePotentialRadiologicalConsequencesofaLossofCoolantAccidentforPressurizedWaterReactors".Rev.2,1974.5'.S.Nu"learRadulatoryCommission,RegulatoryGuide1.25:"AssunptionsusdforEvaluatingthePotentialRadiologicalConsequencesofaFuel ATTACHMENT6Page7of7HandlingA"cidentinthFuelHandlingandStorageFacilityforBoilingandPressurize)M~terRa"tors"~6J.S.NuclearRegulatoryCo~mission,RegulatoryGuide1.109:"CalculationsofAnnualDosestoNonfro~RoutineRleasesofRactorEffluentsforthePurposeofEvaluatingCompliancewitn10CFRPart50,AppendixI"~Rev.1,1977~7.Lederer,C.M.,andV.S.Shirley,eds:TableofZsotops,7thEd~,19788.FloridaPowr5LightCompany:"St~Lu"iePlant-UnitNo~1,UpdatedFinalSafetyAnalysisReport",AmendmentNo.6. |
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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
REGULATOINFORMATIONDISTRIHUTIQNSTEM(RIDB)ACCESSIONNHR:8712280232DOC.DATE:'7/12/23NOTARIZED:NOFACIL:50-335St.LuciePlantiUnitiiFloridaPower5LightCo.AUTH.NAMEAUTHORAFFILIATIONWOODYiC.O.FloridaPower5LightCo.RECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)
SUBJECT:
ForwardsrevisedresponsestoQuestions2>657rereplacementofspentfuelracks'erNRC870716requestforaddiinfo0subsequentdiscussionsw/util.DISTRIHUTIONCODE:A001DCOPIESRECEIVED:LTRlENCLLSIZE:TITLE:ORSubmittal:GeneralDistributionNOTES:DOCKET005000335RECIPIENTIDCODE/NAMEPD2-2LATOURIGNYiEINTERNAL:ARM/DAF/LFMHNRR/DEST/CEHNRR/DEBT/RSHNRR/S/ILRHREGIL01EXTERNAL:LPDRNSICCOPIESLTTRENCL101101111111111RECIPIENTIDCODE/NAMEPD2-2PDNRR/DEBT/ADSNRR/DEBT/MTHNRR/DOE*/TBHOGC/HDB2RES/DE/EIHNRCPDRCOPIESLTTRENCL551111101111TOTALNUMHEROFCOPIESREQUIRED:LTTR20ENCL17 0PIItII1 P.0X14000,JUNOBEACH,FL33408.0420~ps>lb'~>i~DECENHER8S198~L-87-537U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555Gentlemen:Re:St.LucieUnitIDocketNo.50-335SentFuelRerackByletterL-87-245,datedJunel2,l987,FloridaPower&LightCompany(FPL)submittedaproposedlicenseamendmenttopermitreplacementofthespentfuelpoolracksatSt.LucieUnitItoensurethatsufficientfuturecapacityexistsfor'storageofspentfuel.ByletterdatedJulyl6,l987(E.G.TourignytoC.O.Woody)theNRCStaffrequestedadditionalinformationintheareaofplantsystemsitneededtocontinueitsreviewofthisproposedlicenseamendment.BylettersL-87-374,datedSeptember8,l987,andL-87-4I9,datedOctoberl9,l987,FPLsubmittedresponsestothisrequest.AsaresultofsubsequentdiscussionswiththeNRC,itwasdeterminedthatFPL'sresponsestoquestions2,6,and7wouldneedtoberevised.AttachedareFPL'srevisedresponses.tfadditionalinformationisrequired,pleasecontactus.Verytrulyyours,C.O.WooExecutiveicePresidentCOW/EJW/gpAttachmentscc:Dr.J.NelsonGrace,RegionalAdministrator,RegionII,USNRCSeniorResidentInspector,USNRC,St.LuciePlant8712280232871223PDRADDCZOSOOO335P,PDREJW4/050/IanFPLGroupcompany 4I4414PIIkIVpW~4'~~4k444lkItWPIIJH~41W44hh4 QUESTION82QUESTION:Kesubmittalspecifiesthatthespentfuelpoolcoolingsystemconsists,inpart,oftwospentfuelpoolcoolingsystempumpsandoneheatexchanger.Sinceallheatexchangersrequiremaintenanceatsomepointintime,itisnotclearhowthespentfuelpoolwillbecooledduringthetimethatthesinglespentfuelpoolcoolingsystemheatexchangerisoutofserviceformaintenance.ProvideadiscussionofhowthespentfuelpooliscooledandthetemperatureismaintainedbelowtheTechnicalSpecificationtemperaturelimitforthefollowingconditions:l.'Jheheatexchangerisoutofserviceforpluggingoffailedtubes.2.'Iheheatexchangerisoutofserviceforcleaningofthetubes.3.'Iheheatexchangerisoutofserviceforreplacement.RESPONSE:Duetothelowpressure,lowtemperatureserviceenvironment,andthecarefullycontrolledwaterchemistry,(ofboththeCCWandSFPCS)theSFPheatexchangerwillonlyinfrequentlyrequiremaintenance.Maintenanceoperationsuchascleaningandtubepluggingcannormallybescheduledinadvanceforperiodsoflowpooldecayheatloads(justbeforeanormalrefueling).'Ihespentfuelpoolheatexchangerisdesignedforthelifeoftheplant,thereforeitsreplacementisnotpostulated.However,intheextremelyunlikelyeventthatreplacementisrequired,alternatemeansofprovidingcoolingtotheSFPcouldbeimplementedduringreplacement.IftherewerenocoolingprovidedtotheSFPsuchthatboilingweretooccur,redundantsourcesofmakeupwatertotheSFPareavailable,asdiscussedinStLucieUnit1FSARAmendmentNo6,Section9.1.3.4andinSection3.2.3oftheStLuciePlantUnitNo1SntFuelStoraeFacilitModification,SafetyAnalysisReport,transmittedvialetterL-87-245datedJune12,1987.BoilingofthewaterintheSFPisadddressedinSection9.1.3.4oftheFSARandinSection3.2.2.4oftheSafetyAnalysisReport.('thereisnoTechnicalSpecificationtemperaturelimitfortheSFP.)Attachment6containstheSpentFuelPoolBoilingAnalysis.1heresultsofthisanalysisdemonstratethatthemaximumcalculatedthyroiddoseismuchlessthan1%ofthe10CFR100limitof300remandtheMolebodyandskindoesarqcompletelyinsignificant.1herefore,nooff-sitedoselimitswillbeexceededifboilingoccursinthespentfuelpool.
tJPEWR&7%37Rev4Page10QUESTION86QUESTION:Foreachstepinthereplacementoftheracks','"pr'ovidedrawingswhichshowthelocationofthespentfuelandthemovementofthefuelwhichdemonstratesthatnoheavyloadwillbecarriedoverspentfueloroveranyrackwhichcontainsspentfuel.(Note:Thisinformationcanbeplacedonthesetofdrawingsprovidedinresponsetoquestion5).RESPONSE:2heattacheddrawingsshowthevariouslocationsofthespentfuelduringtherackinstallation.Describedbelowisthesequenceofrackremovalandinstallation.RelocateallthefuelassembliespresentlystoredinexistingRacks1and2.Followingtheremovalplan(seeQuestion85),removeRacks1and2fromthepoolasshowninFigurel.2~Followingtheinstallationplan(seeQuestion45),installnewRacksFl,G2andGlasshowninFigure2.3~RelocateallthefuelassembliesstoredinexistingRacks3,4,5and6tothesouthernmostcellsofnewracksFl,G2andGlasshowninFigure3.4~Followingtheremovalplan(seeQuestion85),removeexistingRacks3,4,5and6asshowninFigure3.5.Followingtheinstallationplan(seeQuestion05),installnewRacksD2,C3andClasshowninFigure4.6.RelocateallthefuelassembliesstoredinexistingRacks7,8,9,10,13and14intonewRacksD2,C3andClasshowninPigure5.7~Followingtheremovalplan(seeQuestion85),removeexistingRacks7,8,9,10,13and14asshowninFigure5.8.Pollowingtheinstallationplan(seeQuestionS5),installnewRacksD3,B2andC4asshowninFigure6.9.RelocateallthefuelassembliesstoredinexistingRacks11and12intonewRackD3asshowninFigure7.10.Followingtheremovalplan(seeQuestionP5),removeexistingRacks11and12asshowninFigure7.Followingtheinstallationplan(seeQuestionf5),installnewracksBl,C2,A2,Al,Dl,Hl,E2andElasshowninFigure8.0093L/0017L 1l1~)
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.JPE-LR-87-037Rev4Page1262GlCASKAREAI7X75X77X70C~7X7~7X7~i7X7rIP.(r147X77X7l2/z7X77X7FIGURE2(REvl)=NEWRACKSi=EXISTlNGRACKSgg=FUELnuctaaruuUtuconauucuonTITLE:SEQUENCEOFRACKREMOVALANDINSTALLATIONENCLOSURE:2OF8
JPE-LR-87W37RELOCATEDFUE.LASSEMBLIESrage13FROMRACKS5THRU6G2'ASKAREAROV'SREViOVEe7X7I7X7I7ZVi7X7IIrlo7X7ir147X79r7X77X7r8z7X7.r127X7y7iXIIs7)l7FIGLJRFa(,,)=NEWRACKS:"":=EXISTINGRACKSQ=FVELflUCJRBlUQlltL4COflSCfLICQOllI~TITLE:SEQUENCEOFRACKREMOVALANDINSTALLATIONENCLOSURE:3OF8 I
I~P~~II~JPE-LR-87-037Rev4Page14FI62Gl.CASKAREAD2CI7X7~'+7X7X76g7(X7:7X7li.'plI7X77X7=NEVRACKS":=FXISTINGRACKSFIGURF4(,,)NnuclearuautucunecrucaanTITS:SEQUENCEOFRACKRE)iOVALANDXNSTALLATZPNENCLOSURE:4OF8I
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JPE-LR-87-037Rev4Page16G2GICASKAREAD2CI.D3827X7=NEWRACKS;=EXISTINGRACKSFIGURE6,,nuaaaruut>cuccnsaucaon'TITLE:SEQUENCEOFRACKREMOVALANDINSTALLATIONENCLOSURE:6OF8
~~~~0~~0j'r~i~.rp~~0i5lgr'g~~~~/"~i00tgo 0~0'l'4t JPE-LR-87-037Rev4Page18GlCASKAREAgD2C3CIE2ElD3C2DIB2BlA2Al=NORWRACKS=FUELFIGURE8nuuaaruaueuconmrucuanI-TITLE:SEQUENCEOFRACKREMOVALANDINSTALLATIONIENCLOSURE:8OF8l QUESTION47Provideadditionaldiscussiononthetemporarycranethatwillbeusedtohandlethespentfuelstoragerackswithinthefuelbuilding.Aspartofthediscussion,specify1)whetherthecraneissinglefailureproof;2)whetherthetemporarycranewillbecarriedoverthespentfuelpool;and3)theloadpaththatthefuelbuildingcranewilltaketocarrythetemporarycrane.Providedrawingsofthetemporarycraneandpertinentdetailswhichdemonstratesthecrane'scompliancewiththeguidelinesofNUREG-0612andNUREG&554.Ifthetemporarycraneisnotsinglefailureproof,providetheresultsoftheanalysiswhichdemonstratesthattheappropriatesafetyfactorshavebeenappliedtothecraneandthatloadhandlingbythecranewillbeinaccordancewiththeguidelinesofNUREG-0612.RESPONSE:'Ihetemporarycraneisofdoublegirder,symmetricallymounteddoublehoistconstructiondesignedpertheguidelinesoftheCraneManufacturer'sAssociationofAmerica(StandardCMAA70)~Inaddition,structuralmembersinthecranestructuremeetthestressrequirementsofNUREG0612.Thecranetraversesthepoolinthenorth-southdirectionoverrailswhichrunadjacenttothepooledgesresultinginanapproximately34'-6"cranespan.%herackinstallationprocedurecallsforheavyloadstoberestrictedtotheregionsofthepoolwherethereisnofuelstoredintheracks.1hecraneisnotsinglefailureproof,andisnotqualifiedtohandlefuel.Itmay,however,beusedtoperformdummygagetestingontheinstalledfuelrackstoensurethattheymeettherequiredopeningsize.'Ihetemporarycranewillbeusedasastagingplatformonwhichtosettheoldrackswhiletheliftinghardwareischangedouttoenabletherackstoberemovedfromthefuelhandlingbuilding.'jhespacingbetweenthecenterlinesofthegirdersisaccordinglysetat74.83inchestocoincidewithcenter-to-centerspacingoftheoldracksupportchannels.3hetemporarycranewillalsobeusedtosetthenewrackmodulesattheirdesignatedlocationsinthepoolafterthenewracksarebroughtintothecaskareabythecaskcrane.%hecaskcranewillcarrythetemporarycranethroughthehatchdooropeninginfivepieces;twoendtrucks,twogirdersandonehoist.'Jhe4footareainthenorthendofthepoolwillbeutilizedforinstallingthecrane.Whilethetemporarycranewillbecarriedoverthespentfuelpool,itwillnotbecarriedoverspentfuel.
ik ATTACHMENT6Page1of7RADIOLOICALCONSEQUNCESOFASPENTFUELPOOLLOSSOFCO'COLIN"ACCIDENf1~INMODU"TIOVInthecourseofreviewingtheproposeBmoiificationofthespentfuelstoragefacilityatthSt.LuciePlantUnit1,theNRChasrequesteBFP6Ltoprovidetneresultsofananalysistoshowthatnooff-siteBoselimitswillbeexceedeBwerealossofthespentfuelpoolcoolingsystemtoresultinthspentfuelpoolboiling.2.METHODOLOGY2.1AssumptionsTneanalysisoftheradiologicalconsequencesofalossofthspentfu1poolcoolingsystemisboundeBbythefollowingassumptions:1.thereactorhasbeenshutdownforsvendayspriortothestartofthoaccident(thisisconsistentwith[1:3-28]*)2.onefullcorehasbeenBischargeBintothespentfuelpool3.thedyna~icsofthepoolboilingarecharacterizedbythedatainref.[1:3-37]4~theleakratecofficientforiodineleakingfromdefe"tivefu1rodsisthesameasforrodsintherea"torsevendaysaftershutdown[2:391](althoughthisisdataforaBWR,itistheonlyactuallymeasuredleakratedataavailableandshouldberepresentativeoflight-waterreactors)5.the'radionuclidecoreinventoryi.stakenfro~ref.[3:Table3.3]+5.thepoolwaterclean-upsystemwillbecomeinoprativewhenthepoolcoolingsystemfails7~nocreditistakenfortheemergencyfiltrationsysteminthefu1haaBlingbuildingHVACsystem8.thetritiwaconcentrationinthepoolwateristakenfromref.[1:5-14]*Numbersinsquarebracketsarereferencenumbers,followBbypageortablenumberCnangeoffuelvendoranduseofhigherburnupdictatestheuseofanupdatedraBionuclidecoreinventory.
ATTACHMENT6Page2of79.theleakratecoefficientfornoblegasesisfivetiesthatforlodinesf2:399]10.onepercentofthefuelrodsintheassembliesinthepoolaredefective11.theatmosphericdilutionfactors(Xi/Q)atthnwrestsiteboundarydistanceandattheouterboundaryofthelowpopulationzone(LPZ)aretakenfromref.[8:2.3-24J12.theleakageofhalogensandnoblegasesfromspentfu1frompreviousrefuelingsisnegligible13.theconcentrationsofhalogensandnoblegasesinthespntfu1poolatthestartoftheaccidentarenegligible'4.a11halogens*andnoblegasesleakingfromthefuelrodsvt.llevolvedirectlyintotheatmospherefollowingpoolboiling15.theeaterlevelinsidethefuelpool~l.llb23feetabovethetopofthefuelatthestartofthea=cident16.sufficientmake-upeatervillbeprovide9tokeepthefu1coveredvltheateratalltimes17.thea"cidentispresumedtolast30days+*Bee"Discussion",below.Tnisassumptionisconsistentwithanalysesofotherdesignbasisaccidentsinvolvingprolongedreleases,suhasareactorloss-of-coolantaccident(LO"-A)~2.1.1Di,sussionTheassumptionthatallhalogensleakingfromthefuelrodsarereleaseddirectlytotheatmosphereishighlyconservative.Itissupportedbythgeneralprinciplethatdissolvedgasesbecomelesssolublewithin"reasingtemperatures,~1ththesolubilitybecomingessntiallyserosttheboilingpointofthosolvent.Furthermore,sincethecleanupsystemisassumedtohavefailed,thereisnomechanismforremovingthebuild-upofradioidinesexceptevaporationsTheconcentrationintheestervillthusincrease@biletheaccumulationintheairut.llberemovedbytheventilationsystem.Eventually,aquasi-staticequtlibriumvillbeachieved-theconcentrationintheeater~111reachamaximumvalueandtherateofvolatilizationfromthepoolvillbeequaltotherateofreleasefromthefuel.
ATTACHMENT6Page3of7Tnissimplifie3modelleadsustoconcludethat,re~ardlessofthea"tualpartitioncofficient,alltheescapingio5inesutileventuallyentertheatmosphere.Amoredetailedcalculationofthisnon-equilibriumsituationr'~ouldresultinsomeinatlo~.rreleaserates,andthereforelourradiolo~icalimpacts~Su"hacalculaionwouldtakecreditfornon-volatilefra"tionsoftheraiioiiineandalsovouldsprea0thereleassoveralongertimeperiod,resultinginlovercon"entrationsduetoraliosctivedecay.Performingsuchscalculation9oesnotappeartobe)ustified,however,sincereliabledataforthebehaviorofradioiodineinboilingpaoleaterisnotreadilyavailable.2.1.2InputdataAtmosphericDilutionFactors(Xi/Q)LocationExclusionareabombaryTimeAfterAccident0-2hrsXX/Q(seclm)8.558-5*Loupopulationzone*8-558-5~3.55x100-8hrs8-24hrs1-4days4-30days7.97E-64.26".-69.53E-73.688-7FissionProductCoreInventory:Nuclidea"Half-lifeCoreInventory(Ci)Duringopration7daysaftershutdovnc131I132I133xe8.02days78.2hoursd5.25days10.7years7.84E71.12Z81.47881.01854.28E72.53"75.8387101E5NuclidessignificanttothepresentanalysisbSeeref.[7]Valuescalculated,basedonequilibriminventoryandradioactivedecayHalf-lifeofparenttellurian-132(132Te)Thehalf-lifeofIis2.3hours-Hovever,itisinsecularcquilibriunvl.thitsparentnuclide,Te.Tnerefore,thedecreaseofitsactivityknthecoresevendaysaftershutdownvt.llbealmostexactlythesameasthedecreaseoftheactivityofitsparent.
ATTACHMENT6Page4of72.2WEI'8333FCALCULATIOVTnedatainreferen"e{2]inlicatethatth>>fra"tionalleakrateofagivennuclidefromthedefectivefuelrodssevendaysaftershutdownwoulddependprimarilyonitschmicalproprtiesan9secon9arilyonitshalf-life.Tnatreportalsoobservesthattheratioofiodinetonoblegasreleasesduringoprationwasapproximately1:5fornuclideswithsimilarhalf-lives~TnepresentanalysisassumesthattheleakratecoefficientofIisthesateasthatgivenforI(thedataindicatesthatitwouldbesomewhatsmaller)~TneratesofXeandKrarecalculatedbasdonthedatainthatreport.Theabsorbe9dosecommitmnttotheadultthyroidforradioiodinesatagivenlocationiscalculatedasfollows:DIirXBRi(eki)o-ei)1)kiD<~adultabsorbeddoseduetonu"lideiduringtiveperiod5~coreinventoryofnu"lideiatcommencementofpoolboilingf~fractionalleakrateofdamagedfuelrod()r~fractionoffailedfuel.01(1X)X~Atmosphericdilutionfa"tor(Xi./Q)duringtimepriod)fromstartofa"cident(sec/m3)B~~adultbreathingrateduringtimeperiodjf4:1.4-2)1.25m3/hr(0-8hrsfromstartofaccident).625m3/hr(8-24hrs).833m3/hr(1-30days)R<Adultdosconversionfactor(rads/curieinhaled)[5:25.5j486for13115.35E4for1321kidecayconstantofnu"lidei(hr)t~o~timefromstartofaccidenttobeginningofperiod5t~l~timefro~startofaccidenttoendofperiod5Tnedosstothewholebodyandtotheskinfromnoblegasesarecalculatedasfollows:
h ATTACHMENT6Page5of7DIifrXR1(e~i)o-ekijl)i)kAlltermshavethesamemeaningasinthepreviousequation,except:R<~semi-infiniteclou9dosconversionfactor[6:1109-21Jf~4~35E9se"(Xe)Theatmospherictritiumconcentrationiscalculatedasfollows:C~PcX~C~tritiumconcentrationinair(uCi/m3)Fboil-offrateofpoolwater~4,377ml/secc~tritiumconcentrationinpoolwater.077uCi/ml3.RESULTS3.1DoseCommitmentatExclusionbreaBoundary(EAB)Nu"lideAdultabsorbeddosecommitmentatEAB(rem)131I132I133'5KrTotalTnyroid0.1172.50K-30.119Skin1.51E-51.15K-61.62E-5WholeBody1.458-51~38"-81.458-53.1.1TritiumconcentrationstEABDuringthefirsttwohoursfollowingtheaccident,themaximustritiumcon"entrationsttheExclusionAreaBoundary(EAB)iscalculatedtobe2.98-8uCi/ml(2.9E-2uCi/m3)inair.Thisvalueiswellbelowthemaximumpermissibleconcentration(MPC)fortritium,whichis2E-7uCi/ml.TheMPCisthelimitingconcentrationforachronicexposure.SinceanindividualattheEABispostulatedtobeexposedforamaximumoftwohours,thecontributionoftritiumtohistotaldoseisinsignificant.3.2DoseCommitmenatLPZThefollowingcalculationswereperformedforthemaximumexposedindividualattheLPZouterboundaryduringthe30-dayperiodoftheaccident.
ATTACHMENT6Page6of7Nu"liheA]ultahsorbe4dosecoz~itmntatLPZ(re~)1311132I133~e~85KzTotalTnyroid4.1211.92E-30.123Skin1~89'52'9-62'8E"5lAoleBody1.82E-53.488-81.82E-53.2.1TritiumconcentrationatLPZDuringthefirsteighthoursfollowingthea=cident,themaximustime-averageitritiumcon"entrationattheLPZboundaryiscalculatedtobe2.7E-9uCi/mlinair.ThisvalueissellbelowtheMPCfortritium.Sincetheatmosphericdilutionfactor(Xi/Q)usedinthiscalculationisapplicabletothefirsttvohoursoftheaccidentonly,andsinceinanycastheaccidentispostulate9tolastonly30days,thecontributionoftritiumtohtotaldoseisinsignificant.4~CON"LUSZONSThemaximuscalculatedthyroi0dosismuch'lessthan1Xofthe10CFR100limitof303rem.TheAaole-boiyandskindosesarecompletelyinsignificant.REFERENCES1.Florid'aPover8LightCompany:"St-LuciePlant-UnitNo.1,SpentFuelStorageFacilityModificationSafetyAnalysisReport,DocketNo.5'3-335.2.Eickelpas"h,N.,andR.Hock:"FissionProductReleaseafterReactorStutdeun",LhEA-SS-17S/i9,inErperiencefree~OperetinendFuellingNu=learPoverPlants,Vienna,19743.ExxonNuclearCompany,Inc.:"St~Lu"ieUnit1RadiologicalAssessmentofPostulatedAccidents".XN-NF-84-85(P),Rv.l.4.V.S.AtomicEnergyCommission,RegulatoryGuide1.4:AssumptionsUsedforEvaluatingthePotentialRadiologicalConsequencesofaLossofCoolantAccidentforPressurizedWaterReactors".Rev.2,1974.5'.S.Nu"learRadulatoryCommission,RegulatoryGuide1.25:"AssunptionsusdforEvaluatingthePotentialRadiologicalConsequencesofaFuel ATTACHMENT6Page7of7HandlingA"cidentinthFuelHandlingandStorageFacilityforBoilingandPressurize)M~terRa"tors"~6J.S.NuclearRegulatoryCo~mission,RegulatoryGuide1.109:"CalculationsofAnnualDosestoNonfro~RoutineRleasesofRactorEffluentsforthePurposeofEvaluatingCompliancewitn10CFRPart50,AppendixI"~Rev.1,1977~7.Lederer,C.M.,andV.S.Shirley,eds:TableofZsotops,7thEd~,19788.FloridaPowr5LightCompany:"St~Lu"iePlant-UnitNo~1,UpdatedFinalSafetyAnalysisReport",AmendmentNo.6.
7('Vr
