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| {{#Wiki_filter:0 December 3, 2014FPL. L-2014-35910 CFR 50.46U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, D. C. 20555-0001Re: Turkey Point Units 3 and 4Docket Nos. 50-250 and 50-25110 CFR 50.46, "Acceptance Criteria forEmergency Core Cooling Systems in Light WaterNuclear Power Reactors" -30 Day Special Report | | {{#Wiki_filter:0 December 3, 2014FPL. L-2014-359 10 CFR 50.46U.S. Nuclear Regulatory Commission Attn: Document Control DeskWashington, D. C. 20555-0001 Re: Turkey Point Units 3 and 4Docket Nos. 50-250 and 50-25110 CFR 50.46, "Acceptance Criteria forEmergency Core Cooling Systems in Light WaterNuclear Power Reactors" |
| | -30 Day Special Report |
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| |
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| ==References:== | | ==References:== |
| : 1. Florida Power & Light Company (FPL) letter, M. Kiley to U. S. Nuclear RegulatoryCommission, "Turkey Point Unit 3, Docket No. 50-250, 10 CFR 50.46, 'Acceptance Criteria forEmergency Core Cooling Systems in Light Water Nuclear Power Reactors' -30 Day SpecialReport," L-2014-077, March 24, 2014.2. Florida Power & Light Company (FPL) letter, M. Kiley to U. S. Nuclear RegulatoryCommission, "Turkey Point Unit 4, Docket No. 50-251, 10 CFR 50.46, 'Acceptance Criteria forEmergency Core Cooling Systems in Light Water Nuclear Power Reactors' -30 Day SpecialReport," L-2014-302, October 15, 2014.10 CFR 50.46(a)(3)(ii) requires that changes to the Large Break Loss of Coolant Accident(LBLOCA) Evaluation Model (EM) and Small Break LOCA (SBLOCA) EM peak clad temperature(PCT) exceeding 50°F have to be reported to the NRC within 30 days. This letter meets thisrequirement.FPL letters L-2014-077 (Reference 1) and L-2014-302 (Reference 2) submitted the 30 DaySpecial Reports for Turkey Point Units 3 and 4, respectively. The 30 Day Special Reportsdocumented a LBLOCA PCT of 2121OF with a cumulative change of 770F. The LBLOCA PCTreported in the 30 day special reports removed the 120F mixed core penalty no longer applicablefor Unit 3 Cycle 27 and Unit 4 Cycle 28 and future cycles with only 15x1 5 Upgraded fuelassemblies.By letter dated November 19, 2014, Westinghouse identified an error in the LBLOCA EM in thecalculation of decay heat in the WCOBRA/TRAC code. Correction of the errors impacts theapplication of the sampled decay heat uncertainty, which may result in small changes to thedecay heat power. These issues have been evaluated to estimate the impact on AutomatedStatistical Treatment of Uncertainty Method (ASTRUM) Best-Estimate (BE) LBLOCA analysisresults. The correction of these errors resulted in an estimated impact of +3 OF on LBLOCA PCTfor Turkey Point Units 3 and 4. Table 1 below provides a summary of the new LBLOCA PCT forTurkey Point Units 3 and 4. The revised LBLOCA PCT for Units 3 and 4 is 2124 OF with acumulative change of 80°F due to the LBLOCA EM errors. The SBLOCA EM is not affected bythe identified errors.Florida Power & Light Company9760 SW 344 St Homestead, FL 33035 L-2014-359Page 2 of 2Table ITurkey Point Units 3 and 4 LBLOCA Evaluation Model ErrorPeak Cladding CumulativeTemperature ChangeLBLOCA10 CFR 50.46 30-day Special Reports (Refs.1 & 2) 2121 OF 77 OF2014 ECCS Model Assessments 3 OF 3 OFDecay Group Uncertainty Factors ErrorsDecember 2014 30 Day Special Report 2124 OF 80 OF10 CFR 50.46(a)(3)(ii) also requires that a schedule for reanalysis be provided or compliance withthe requirements of the regulation be shown if the error is significant. For the Turkey Point Unitscontinued compliance with 10 CFR 50.46 requirements is demonstrated by the new estimatedLBLOCA PCT of 2124°F remaining below the limit of 22000F.Should there be any questions, please contact Robert Tomonto, Licensing Manager, at305-246-7327.Very truly yours,Michael KileyVice PresidentTurkey Point Nuclear Plantcc: Regional Administrator, Region II, USNRCSenior Resident Inspector, USNRC, Turkey Point Plant}} | | : 1. Florida Power & Light Company (FPL) letter, M. Kiley to U. S. Nuclear Regulatory Commission, "Turkey Point Unit 3, Docket No. 50-250, 10 CFR 50.46, 'Acceptance Criteria forEmergency Core Cooling Systems in Light Water Nuclear Power Reactors' |
| | -30 Day SpecialReport," |
| | L-2014-077, March 24, 2014.2. Florida Power & Light Company (FPL) letter, M. Kiley to U. S. Nuclear Regulatory Commission, "Turkey Point Unit 4, Docket No. 50-251, 10 CFR 50.46, 'Acceptance Criteria forEmergency Core Cooling Systems in Light Water Nuclear Power Reactors' |
| | -30 Day SpecialReport," |
| | L-2014-302, October 15, 2014.10 CFR 50.46(a)(3)(ii) requires that changes to the Large Break Loss of Coolant Accident(LBLOCA) |
| | Evaluation Model (EM) and Small Break LOCA (SBLOCA) |
| | EM peak clad temperature (PCT) exceeding 50°F have to be reported to the NRC within 30 days. This letter meets thisrequirement. |
| | FPL letters L-2014-077 (Reference |
| | : 1) and L-2014-302 (Reference |
| | : 2) submitted the 30 DaySpecial Reports for Turkey Point Units 3 and 4, respectively. |
| | The 30 Day Special Reportsdocumented a LBLOCA PCT of 2121OF with a cumulative change of 770F. The LBLOCA PCTreported in the 30 day special reports removed the 120F mixed core penalty no longer applicable for Unit 3 Cycle 27 and Unit 4 Cycle 28 and future cycles with only 15x1 5 Upgraded fuelassemblies. |
| | By letter dated November 19, 2014, Westinghouse identified an error in the LBLOCA EM in thecalculation of decay heat in the WCOBRA/TRAC code. Correction of the errors impacts theapplication of the sampled decay heat uncertainty, which may result in small changes to thedecay heat power. These issues have been evaluated to estimate the impact on Automated Statistical Treatment of Uncertainty Method (ASTRUM) |
| | Best-Estimate (BE) LBLOCA analysisresults. |
| | The correction of these errors resulted in an estimated impact of +3 OF on LBLOCA PCTfor Turkey Point Units 3 and 4. Table 1 below provides a summary of the new LBLOCA PCT forTurkey Point Units 3 and 4. The revised LBLOCA PCT for Units 3 and 4 is 2124 OF with acumulative change of 80°F due to the LBLOCA EM errors. The SBLOCA EM is not affected bythe identified errors.Florida Power & Light Company9760 SW 344 St Homestead, FL 33035 L-2014-359 Page 2 of 2Table ITurkey Point Units 3 and 4 LBLOCA Evaluation Model ErrorPeak Cladding Cumulative Temperature ChangeLBLOCA10 CFR 50.46 30-day Special Reports (Refs.1 & 2) 2121 OF 77 OF2014 ECCS Model Assessments 3 OF 3 OFDecay Group Uncertainty Factors ErrorsDecember 2014 30 Day Special Report 2124 OF 80 OF10 CFR 50.46(a)(3)(ii) also requires that a schedule for reanalysis be provided or compliance withthe requirements of the regulation be shown if the error is significant. |
| | For the Turkey Point Unitscontinued compliance with 10 CFR 50.46 requirements is demonstrated by the new estimated LBLOCA PCT of 2124°F remaining below the limit of 22000F.Should there be any questions, please contact Robert Tomonto, Licensing |
| | : Manager, at305-246-7327. |
| | Very truly yours,Michael KileyVice President Turkey Point Nuclear Plantcc: Regional Administrator, Region II, USNRCSenior Resident Inspector, USNRC, Turkey Point Plant}} |
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Category:Letter
MONTHYEARL-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24262A2272024-09-18018 September 2024 Transmittal of Additional Errata Pages for WCAP-18830-P (Proprietary) and WCAP-18830-NP (Non-Proprietary), Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles IR 05000250/20243012024-09-18018 September 2024 NRC Examination Results Summary - Examination Reports: 05000250/2024301 and 05000251/2024301 ML24158A0052024-09-17017 September 2024 Completion of Subsequent License Renewal Site Specific Environmental Review and Modification to Subsequent Renewed Facility Operating Licenses L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24207A0342024-09-13013 September 2024 – Exemption from Certain Requirements of 10 CFR 50.46 for Use of Axiom Fuel Rod Cladding – Letter ML24256A1132024-09-13013 September 2024 Regulatory Audit Summary Related to the Review of Regarding the Updated Spent Fuel Pool Criticality Safety Analysis License Amendment Request IR 05000250/20240052024-08-23023 August 2024 Updated Inspection Plan for Turkey Point Units 3 & 4 - Report 05000250/2024005 and 05000251/2024005 ML24234A0062024-08-22022 August 2024 Project Manager Assignment L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report IR 05000250/20240112024-08-0606 August 2024 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000250/2024011 and 05000251/2024011 ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-112, Condition Prohibited by Technical Specifications2024-07-10010 July 2024 Condition Prohibited by Technical Specifications ML24173A1902024-06-28028 June 2024 Withdrawal of an Amendment Request ML24159A2652024-06-26026 June 2024 Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter IR 05000250/20244012024-06-0505 June 2024 – Security Baseline Inspection Report 05000250-2024401, 05000251-2024401 and 07200062-2024401 L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000250/20240012024-05-10010 May 2024 Integrated Inspection Report 05000250/2024001 and 05000251/2024001 L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report ML24127A1862024-05-0909 May 2024 Request for Withholding Information from Public Disclosure ML24135A0942024-05-0909 May 2024 Periodic Update to the Updated Final Safety Analysis Report ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report IR 05000250/20240102024-05-0101 May 2024 Design Basis Assurance Inspection Programs Inspection Report 05000250/2024010 and 05000251/2024010 and Notice of Violation L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024 Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024 Radiological Emergency Plan Revision 76 L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024 Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02 L-2024-057, 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications2024-04-11011 April 2024 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications ML24087A1992024-04-0505 April 2024 Achp Section 106 Letter Re Notice of Availability of the Final Environmental Impact Statement for Turkey Point Units 3 & 4 Subsequent License Renewal Application ML24096A2162024-04-0505 April 2024 Ltr. to Marcellus Osceola, Chairman, Seminole Tribe of Florida, Re., Section 106 Letters for Turkey Point ML24087A1982024-04-0505 April 2024 Notice of Availability of the Final Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML24096A2182024-04-0505 April 2024 Ltr. to Stephanie Bryan, Tribal Chair, Poarch Band of Creek Indians, Re., Section 106 Letters for Turkey Point ML24096A2152024-04-0505 April 2024 Ltr. to Lewis Johnson, Principal Chief, Seminole Nation of Oklahoma, Re., Section 106 Letters for Turkey Point ML24087A2012024-04-0505 April 2024 Letter to Talbert Cypress, Miccosukee Tribe of Indians of Florida; Re., Section 106 Letters for Turkey Point ML24087A2002024-04-0505 April 2024 Letter to Miami-Dade County Office of Historic Preservation Re Section 106 on Turkey Point Units 3 & 4 EIS ML24096A2142024-04-0505 April 2024 Ltr. to David Hill, Principal Chief, the Muscogee (Creek) Nation, Re., Section 106 Letters for Turkey Point ML24072A2832024-04-0101 April 2024 Ltr to Dianne Strand-Notice of Avail.-Final Site-Specific Supp. 5a, 2nd Renewal to the GEIS for License Renewal L-2024-013, Submittal of Periodic Reports2024-03-28028 March 2024 Submittal of Periodic Reports L-2024-040, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-03-28028 March 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections 2024-09-25
[Table view] Category:Licensee 30-Day Written Event Report
MONTHYEARL-2019-058, CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2019-03-25025 March 2019 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2018-063, CFR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications2018-03-26026 March 2018 CFR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications L-2017-102, Submittal of 10 CFR 50.46 - Emergency Core Cooling 30-Day Report2017-06-0202 June 2017 Submittal of 10 CFR 50.46 - Emergency Core Cooling 30-Day Report L-2017-069, Special Report - Containment Tendon Corrosion Protection Medium Volume Reduction2017-04-17017 April 2017 Special Report - Containment Tendon Corrosion Protection Medium Volume Reduction L-2016-124, 10 CFR 50.46 30-Day Report for Turkey Point, Seabrook, and Point Beach2016-06-17017 June 2016 10 CFR 50.46 30-Day Report for Turkey Point, Seabrook, and Point Beach L-2016-065, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors, - 30 Day Special Report2016-04-0505 April 2016 Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors, - 30 Day Special Report L-2014-359, 10 CFR 50.46 Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors, 30 Day Special Report2014-12-0303 December 2014 10 CFR 50.46 Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors, 30 Day Special Report L-2014-077, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 30 Day Special Report2014-03-24024 March 2014 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 30 Day Special Report L-2014-065, Special Report - Accident Monitoring Instrumentation2014-02-25025 February 2014 Special Report - Accident Monitoring Instrumentation L-2014-037, Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 30 Day Special Report2014-02-18018 February 2014 Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 30 Day Special Report L-2013-184, Special Report - Accident Monitoring Instrumentation2013-05-30030 May 2013 Special Report - Accident Monitoring Instrumentation L-2013-117, Special Report - Accident Monitoring Instrumentation2013-03-29029 March 2013 Special Report - Accident Monitoring Instrumentation L-2010-235, LER, Turkey Point, Units 3 and 4, Special Report - Accident Monitoring Instrumentation Inoperable2010-10-13013 October 2010 LER, Turkey Point, Units 3 and 4, Special Report - Accident Monitoring Instrumentation Inoperable L-2010-114, Special Report Re Inoperable Main Steam Lines High Range-Noble Gas Effluent Monitor Greater than 7 Days2010-06-14014 June 2010 Special Report Re Inoperable Main Steam Lines High Range-Noble Gas Effluent Monitor Greater than 7 Days L-2010-100, Accident Monitoring Instrumentation Special Report2010-05-14014 May 2010 Accident Monitoring Instrumentation Special Report L-2005-096, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - Annual Report and 30-Day Report2005-04-27027 April 2005 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - Annual Report and 30-Day Report ML18227A5071977-07-29029 July 1977 Transmittal of Licensee Event Report 251-77-4, Steam Generator Tube Plugs ML18227A5081977-05-13013 May 1977 Transmittal of Licensee Event Report 251-77-2 Boric Acid Transfer Pumps 2019-03-25
[Table view] |
Text
0 December 3, 2014FPL. L-2014-359 10 CFR 50.46U.S. Nuclear Regulatory Commission Attn: Document Control DeskWashington, D. C. 20555-0001 Re: Turkey Point Units 3 and 4Docket Nos. 50-250 and 50-25110 CFR 50.46, "Acceptance Criteria forEmergency Core Cooling Systems in Light WaterNuclear Power Reactors"
-30 Day Special Report
References:
- 1. Florida Power & Light Company (FPL) letter, M. Kiley to U. S. Nuclear Regulatory Commission, "Turkey Point Unit 3, Docket No. 50-250, 10 CFR 50.46, 'Acceptance Criteria forEmergency Core Cooling Systems in Light Water Nuclear Power Reactors'
-30 Day SpecialReport,"
L-2014-077, March 24, 2014.2. Florida Power & Light Company (FPL) letter, M. Kiley to U. S. Nuclear Regulatory Commission, "Turkey Point Unit 4, Docket No. 50-251, 10 CFR 50.46, 'Acceptance Criteria forEmergency Core Cooling Systems in Light Water Nuclear Power Reactors'
-30 Day SpecialReport,"
L-2014-302, October 15, 2014.10 CFR 50.46(a)(3)(ii) requires that changes to the Large Break Loss of Coolant Accident(LBLOCA)
Evaluation Model (EM) and Small Break LOCA (SBLOCA)
EM peak clad temperature (PCT) exceeding 50°F have to be reported to the NRC within 30 days. This letter meets thisrequirement.
FPL letters L-2014-077 (Reference
- 1) and L-2014-302 (Reference
- 2) submitted the 30 DaySpecial Reports for Turkey Point Units 3 and 4, respectively.
The 30 Day Special Reportsdocumented a LBLOCA PCT of 2121OF with a cumulative change of 770F. The LBLOCA PCTreported in the 30 day special reports removed the 120F mixed core penalty no longer applicable for Unit 3 Cycle 27 and Unit 4 Cycle 28 and future cycles with only 15x1 5 Upgraded fuelassemblies.
By letter dated November 19, 2014, Westinghouse identified an error in the LBLOCA EM in thecalculation of decay heat in the WCOBRA/TRAC code. Correction of the errors impacts theapplication of the sampled decay heat uncertainty, which may result in small changes to thedecay heat power. These issues have been evaluated to estimate the impact on Automated Statistical Treatment of Uncertainty Method (ASTRUM)
Best-Estimate (BE) LBLOCA analysisresults.
The correction of these errors resulted in an estimated impact of +3 OF on LBLOCA PCTfor Turkey Point Units 3 and 4. Table 1 below provides a summary of the new LBLOCA PCT forTurkey Point Units 3 and 4. The revised LBLOCA PCT for Units 3 and 4 is 2124 OF with acumulative change of 80°F due to the LBLOCA EM errors. The SBLOCA EM is not affected bythe identified errors.Florida Power & Light Company9760 SW 344 St Homestead, FL 33035 L-2014-359 Page 2 of 2Table ITurkey Point Units 3 and 4 LBLOCA Evaluation Model ErrorPeak Cladding Cumulative Temperature ChangeLBLOCA10 CFR 50.46 30-day Special Reports (Refs.1 & 2) 2121 OF 77 OF2014 ECCS Model Assessments 3 OF 3 OFDecay Group Uncertainty Factors ErrorsDecember 2014 30 Day Special Report 2124 OF 80 OF10 CFR 50.46(a)(3)(ii) also requires that a schedule for reanalysis be provided or compliance withthe requirements of the regulation be shown if the error is significant.
For the Turkey Point Unitscontinued compliance with 10 CFR 50.46 requirements is demonstrated by the new estimated LBLOCA PCT of 2124°F remaining below the limit of 22000F.Should there be any questions, please contact Robert Tomonto, Licensing
- Manager, at305-246-7327.
Very truly yours,Michael KileyVice President Turkey Point Nuclear Plantcc: Regional Administrator, Region II, USNRCSenior Resident Inspector, USNRC, Turkey Point Plant