ML16015A181

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Official Exhibit - NRC-046-00-BD01 - Florida Power and Light, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 4; Licensing Report (December 14, 2010)(ADAMS Accession No. ML103560177)
ML16015A181
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 11/10/2015
From:
NRC/OGC
To:
Atomic Safety and Licensing Board Panel
SECY RAS
References
50-250-LA, 50-251-LA, ASLBP 15-935-02-LA-BD01, RAS 28502
Download: ML16015A181 (30)


Text

NRC-046 Submitted Nov. 10, 2015 Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: FLORIDA POWER & LIGHT COMPANY (Turkey Point Nuclear Generating, Units 3 and 4)

ASLBP #: 15-935-02-LA-BD01 Docket #: 05000250 & 05000251 Exhibit #: NRC-046-00-BD01 Identified: 1/4/2016 Admitted: 1/4/2016 Withdrawn:

Rejected: Stricken:

Other:

Turkey Point Units 3 and 4 LICENSE AMENDMENT REQUEST FOR EXTENDED POWER UPRATE ATTACHMENT 4 Licensing Report This coversheet plus 1502 pages Turkey Point Units 3 and 4 EPU LAR Att. 4-1 Licensing Report

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 1.0 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-1 1.0.1 General Overview of the Turkey Point 3 and 4 Extended Power Uprate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-1 1.0.2 Plant Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-2 1.0.3 Schedule . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-2 1.0.4 Plant Modifications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-2 1.0.4.1 Reactor System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-3 1.0.4.2 Emergency Core Cooling System . . . . . . . . . . . . . . . . . . 1.0-4 1.0.4.3 Steam and Power Conversion . . . . . . . . . . . . . . . . . . . . . 1.0-4 1.0.4.4 Auxiliary Feedwater (AFW) . . . . . . . . . . . . . . . . . . . . . . . 1.0-6 1.0.4.5 Spent Fuel Pool (SFP) . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-6 1.0.4.6 Onsite AC . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-7 1.0.4.7 Offsite AC . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-7 1.0.5 Current Licensing Basis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-8 1.0.6 Risk Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-8 1.0.7 Treatment of Issues Related to the Renewed Operating License . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-9 1.0.8 Additional Review Areas . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-10 1.0.9 Use of Industry Operating Experience . . . . . . . . . . . . . . . . . . . . . . 1.0-11 1.0.10 EPU Relation to Other Concurrent Licensing Activities . . . . . . . . . 1.0-11 1.0.11 Regulatory Commitments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-11 1.0.12 Treatment of Proprietary Information . . . . . . . . . . . . . . . . . . . . . . . 1.0-12 1.1 Nuclear Steam Supply System Parameters . . . . . . . . . . . . . . . . . . . . . . . . 1.1-1 1.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.1-1 1.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.1-1 1.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.1-1 1.1.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.1-1 1.1.2.3 Description of Analyses and Evaluation . . . . . . . . . . . . . . 1.1-2 1.1.2.4 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.1-2 1.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.1-3 2.0 Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.1-1 2.1 Materials and Chemical Engineering . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.1-1 2.1.1 Reactor Vessel Materials Surveillance Program . . . . . . . . . . . . . . 2.1.1-1 2.1.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.1-1 2.1.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.1-3 2.1.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.1-3 Turkey Point Units 3 and 4 EPU Licensing Report i

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.1.1.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.1-4 2.1.1.2.3 Description of Analyses and Evaluations . . . 2.1.1-5 2.1.1.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.1-6 2.1.1.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.1-6 2.1.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.1-7 2.1.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.1-7 2.1.2 Pressure-Temperature Limits and Upper-Shelf Energy . . . . . . . . . 2.1.2-1 2.1.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.2-1 2.1.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.2-3 2.1.2.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.2-3 2.1.2.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.2-3 2.1.2.2.3 Description of Analyses and Evaluations . . . 2.1.2-5 2.1.2.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.2-5 2.1.2.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.2-5 2.1.2.3 Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.2-6 2.1.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.2-7 2.1.3 Pressurized Thermal Shock . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.3-1 2.1.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.3-1 2.1.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.3-3 2.1.3.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.3-3 2.1.3.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.3-3 2.1.3.2.3 Description of Analyses and Evaluations . . . 2.1.3-4 2.1.3.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.3-7 2.1.3.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.3-7 2.1.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.3-7 2.1.3.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.3-8 2.1.4 Reactor Internal and Core Support Materials . . . . . . . . . . . . . . . . . 2.1.4-1 2.1.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.4-1 2.1.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.4-3 2.1.4.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.4-3 2.1.4.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.4-4 2.1.4.2.3 Description of Analyses and Evaluations . . . 2.1.4-5 2.1.4.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.4-9 2.1.4.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.4-9 Turkey Point Units 3 and 4 EPU Licensing Report ii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.1.4.3 Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.4-9 2.1.4.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.4-10 2.1.5 Reactor Coolant Pressure Boundary Materials . . . . . . . . . . . . . . . 2.1.5-1 2.1.5.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.5-1 2.1.5.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.5-5 2.1.5.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.5-5 2.1.5.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.5-5 2.1.5.2.3 Description of Analyses and Evaluations . . . 2.1.5-6 2.1.5.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.5-10 2.1.5.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.5-11 2.1.5.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.5-12 2.1.5.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.5-12 2.1.6 Leak-Before-Break . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.6-1 2.1.6.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.6-1 2.1.6.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.6-3 2.1.6.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.6-3 2.1.6.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.6-4 2.1.6.2.3 Description of Analyses and Evaluations . . . 2.1.6-5 2.1.6.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.6-5 2.1.6.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.6-5 2.1.6.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.6-6 2.1.6.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.6-6 2.1.7 Protective Coating Systems - Organic Materials . . . . . . . . . . . . . . 2.1.7-1 2.1.7.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.7-1 2.1.7.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.7-3 2.1.7.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.7-3 2.1.7.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.7-3 2.1.7.2.3 Discussion of Analyses and Evaluations . . . . 2.1.7-4 2.1.7.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.7-4 2.1.7.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.7-4 2.1.7.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.7-4 2.1.7.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.7-4 2.1.8 Flow-Accelerated Corrosion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.8-1 2.1.8.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.8-1 2.1.8.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.8-2 Turkey Point Units 3 and 4 EPU Licensing Report iii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.1.8.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.8-2 2.1.8.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.8-4 2.1.8.2.3 Description of Analyses and Evaluations . . . 2.1.8-4 2.1.8.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.8-6 2.1.8.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.8-7 2.1.8.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.8-7 2.1.8.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.8-7 2.1.9 Steam Generator Tube Inservice Inspection . . . . . . . . . . . . . . . . . 2.1.9-1 2.1.9.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.9-1 2.1.9.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.9-2 2.1.9.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.9-2 2.1.9.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.9-3 2.1.9.2.3 Description of Analyses and Evaluations . . . 2.1.9-3 2.1.9.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.9-3 2.1.9.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.9-4 2.1.9.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.9-4 2.1.9.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.9-4 2.1.10 Steam Generator Blowdown System . . . . . . . . . . . . . . . . . . . . . . . 2.1.10-1 2.1.10.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.10-1 2.1.10.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.10-2 2.1.10.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.10-2 2.1.10.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.10-3 2.1.10.2.3 Description of Analyses and Evaluations . . . 2.1.10-3 2.1.10.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.10-3 2.1.10.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.10-4 2.1.10.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.10-4 2.1.11 Chemical and Volume Control System . . . . . . . . . . . . . . . . . . . . . . 2.1.11-1 2.1.11.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.11-1 2.1.11.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.11-4 2.1.11.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.11-4 2.1.11.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.11-5 2.1.11.2.3 Description of Analysis and Evaluations . . . . 2.1.11-6 2.1.11.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.11-9 2.1.11.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.11-9 Turkey Point Units 3 and 4 EPU Licensing Report iv

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.1.11.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.11-10 2.2 Mechanical and Civil Engineering . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.1-1 2.2.1 Pipe Rupture Locations and Associated Dynamic Effects . . . . . . . 2.2.1-1 2.2.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.1-1 2.2.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.1-3 2.2.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.1-3 2.2.1.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.2.1-4 2.2.1.2.3 Description of Analyses and Evaluations . . . 2.2.1-4 2.2.1.2.4 License Renewal Impact Evaluation . . . . . . . 2.2.1-5 2.2.1.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.1-6 2.2.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.1-6 2.2.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.1-6 2.2.2 Pressure-Retaining Components and Component Supports . . . . . 2.2.2-1 2.2.2.1 NSSS Piping, Components and Supports . . . . . . . . . . . . 2.2.2-6 2.2.2.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.2.2-6 2.2.2.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.2.2-7 2.2.2.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-11 2.2.2.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-12 2.2.2.2 Balance of Plant Piping, Components, and Supports . . . 2.2.2-14 2.2.2.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.2.2-14 2.2.2.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.2.2-15 2.2.2.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-19 2.2.2.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-20 2.2.2.3 Reactor Vessel and Supports . . . . . . . . . . . . . . . . . . . . . 2.2.2-30 2.2.2.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.2.2-30 2.2.2.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.2.2-31 2.2.2.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-36 2.2.2.3.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-36 2.2.2.4 Control Rod Drive Mechanism . . . . . . . . . . . . . . . . . . . . . 2.2.2-45 2.2.2.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.2.2-45 2.2.2.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.2.2-46 2.2.2.4.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-47 2.2.2.5 Steam Generators and Supports . . . . . . . . . . . . . . . . . . . 2.2.2-49 2.2.2.5.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.2.2-49 2.2.2.5.2 Technical Evaluation - Steam Generator Structural Integrity . . . . . . . . . . . . 2.2.2-49 Turkey Point Units 3 and 4 EPU Licensing Report v

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.2.2.5.3 Technical Evaluation - Primary-to-Secondary Pressure Differential . . . . . . . . . . . . . . . . . . . 2.2.2-52 2.2.2.5.4 Technical Evaluation - Steam Generator Thermal-Hydraulic Analysis . . . . . 2.2.2-53 2.2.2.5.5 Technical Evaluation - Steam Generator Tube Wear . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-56 2.2.2.5.6 Technical Evaluation - Steam Generator Loose Parts . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-58 2.2.2.5.7 Technical Evaluation - Steam Generator Hardware . . . . . . . . . . . . . . . . . . . 2.2.2-60 2.2.2.5.8 Technical Evaluation - Steam Drum Component . . . . . . . . . . . . . . . . . . . . . 2.2.2-65 2.2.2.5.9 Technical Evaluation - Steam Generator Chemistry . . . . . . . . . . . . . . . . . . . 2.2.2-70 2.2.2.5.10 Technical Evaluation - Regulatory Guide 1.20 Evaluation - Vibration Assessment Program for Reactor Internals . . . . . . . . . . . . . . . . . . . 2.2.2-72 2.2.2.5.11 Technical Evaluation - Structural Evaluation of Increased Primary-to-Secondary Pressure Differential . . . . . . . . . . . . . . . . . . . 2.2.2-75 2.2.2.5.12 Technical Evaluation - Steam Generator Tube Integrity . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-78 2.2.2.5.13 Evaluation - LOCA Rarefaction Wave Analysis . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-82 2.2.2.5.14 Technical Evaluation - Steam Generator Supports . . . . . . . . . . . . . . . . . . . . 2.2.2-84 2.2.2.5.15 Steam Generator - Overall Results . . . . . . . 2.2.2-85 2.2.2.5.16 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-85 2.2.2.5.17 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-86 2.2.2.6 Reactor Coolant Pumps and Supports . . . . . . . . . . . . . . . 2.2.2-98 2.2.2.6.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.2.2-98 2.2.2.6.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.2.2-98 2.2.2.6.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-104 2.2.2.7 Pressurizer and Supports . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-108 2.2.2.7.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.2.2-108 2.2.2.7.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.2.2-109 2.2.2.7.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-113 2.2.2.7.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-113 Turkey Point Units 3 and 4 EPU Licensing Report vi

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.2.3 Reactor Pressure Vessel Internals and Core Supports . . . . . . . . . 2.2.3-1 2.2.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.3-1 2.2.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.3-4 2.2.3.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.3-4 2.2.3.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.2.3-7 2.2.3.2.3 Description of Analyses and Evaluations . . . 2.2.3-7 2.2.3.2.4 License Renewal Impact Evaluation . . . . . . . 2.2.3-12 2.2.3.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.3-12 2.2.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.3-12 2.2.4 Safety-Related Valves and Pumps . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.4-1 2.2.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.4-1 2.2.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.4-6 2.2.4.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.4-6 2.2.4.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.2.4-9 2.2.4.2.3 Description of Analyses and Evaluations . . . 2.2.4-9 2.2.4.2.4 License Renewal Impact Evaluation . . . . . . . 2.2.4-10 2.2.4.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.4-10 2.2.4.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.4-17 2.2.4.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.4-17 2.2.5 Seismic and Dynamic Qualification of Mechanical and Electrical Equipment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.5-1 2.2.5.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.5-1 2.2.5.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.5-6 2.2.5.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.5-6 2.2.5.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.2.5-7 2.2.5.2.3 Description of Analyses and Evaluations . . . 2.2.5-7 2.2.5.2.4 License Renewal Impact Evaluation . . . . . . . 2.2.5-7 2.2.5.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.5-8 2.2.5.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.5-8 2.2.6 NSSS Design Transients . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.6-1 2.2.6.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.6-1 2.2.6.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.6-4 2.2.6.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.6-4 2.2.6.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.2.6-5 Turkey Point Units 3 and 4 EPU Licensing Report vii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.2.6.2.3 Description of Analyses and Evaluations . . . 2.2.6-5 2.2.6.2.4 License Renewal Impact Evaluation . . . . . . . 2.2.6-5 2.2.6.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.6-5 2.2.6.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.6-6 2.2.6.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.6-6 2.2.7 Bottom-Mounted Instrumentation Guide Tubes and Flux Thimble . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.7-1 2.2.7.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.7-1 2.2.7.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.7-5 2.2.7.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.7-5 2.2.7.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.2.7-5 2.2.7.2.3 Description of Analyses and Evaluations . . . 2.2.7-6 2.2.7.2.4 License Renewal Impact Evaluation . . . . . . . 2.2.7-7 2.2.7.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.7-7 2.2.7.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.7-8 2.2.7.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.7-8 2.3 Electrical Engineering . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.1-1 2.3.1 Environmental Qualification of Electrical Equipment . . . . . . . . . . . 2.3.1-1 2.3.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.1-1 2.3.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.1-2 2.3.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.1-2 2.3.1.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.3.1-3 2.3.1.2.3 Description of Analyses and Evaluations . . . 2.3.1-3 2.3.1.2.4 License Renewal Impact Evaluation . . . . . . . 2.3.1-9 2.3.1.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.1-10 2.3.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.1-10 2.3.2 Offsite Power System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.2-1 2.3.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.2-1 2.3.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.2-2 2.3.2.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.2-2 2.3.2.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.3.2-3 2.3.2.2.3 Description of Analyses and Evaluations . . . 2.3.2-3 2.3.2.2.4 License Renewal Impact Evaluation . . . . . . . 2.3.2-4 2.3.2.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.2-4 2.3.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.2-6 Turkey Point Units 3 and 4 EPU Licensing Report viii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.3.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.2-6 2.3.3 AC Onsite Power System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.3-1 2.3.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.3-1 2.3.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.3-3 2.3.3.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.3-3 2.3.3.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.3.3-4 2.3.3.2.3 Description of Analysis and Evaluations . . . . 2.3.3-4 2.3.3.2.4 License Renewal Impact Evaluation . . . . . . . 2.3.3-12 2.3.3.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.3-12 2.3.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.3-12 2.3.3.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.3-13 2.3.4 DC Onsite Power System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.4-1 2.3.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.4-1 2.3.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.4-2 2.3.4.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.4-2 2.3.4.2.2 Description of Analysis and Evaluations . . . . 2.3.4-2 2.3.4.2.3 License Renewal Impact Evaluation . . . . . . . 2.3.4-3 2.3.4.2.4 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.4-3 2.3.4.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.4-3 2.3.4.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.4-3 2.3.5 Station Blackout . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.5-1 2.3.5.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.5-1 2.3.5.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.5-3 2.3.5.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.5-3 2.3.5.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.3.5-4 2.3.5.2.3 Description of Analysis and Evaluation . . . . . 2.3.5-4 2.3.5.2.4 License Renewal Impact Evaluation . . . . . . . 2.3.5-7 2.3.5.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.5-7 2.3.5.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.5-8 2.4 Instrumentation and Controls . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.1-1 2.4.1 Reactor Protection, Safety Features Actuation, and Control Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.1-1 2.4.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.1-1 2.4.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.1-7 2.4.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.1-7 Turkey Point Units 3 and 4 EPU Licensing Report ix

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.4.1.2.2 Input Parameters, Assumptions and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.4.1-7 2.4.1.2.3 Description of Analyses and Evaluations . . . 2.4.1-7 2.4.1.2.4 License Renewal Impact Evaluation . . . . . . . 2.4.1-24 2.4.1.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.1-24 2.4.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.1-24 2.4.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.1-24 2.4.2 Plant Operability (Margin to Trip) . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.2-1 2.4.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.2-1 2.4.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.2-2 2.4.2.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.2-2 2.4.2.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.4.2-2 2.4.2.2.3 Description of Analyses and Evaluations . . . 2.4.2-3 2.4.2.2.4 License Renewal Impact Evaluation . . . . . . . 2.4.2-4 2.4.2.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.2-4 2.4.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.2-5 2.4.3 Pressurizer Relief Component Sizing . . . . . . . . . . . . . . . . . . . . . . . 2.4.3-1 2.4.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.3-1 2.4.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.3-4 2.4.3.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.3-4 2.4.3.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.4.3-5 2.4.3.2.3 Description of Analyses and Evaluations . . . 2.4.3-9 2.4.3.2.4 License Renewal Impact Evaluation . . . . . . . 2.4.3-9 2.4.3.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.3-9 2.4.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.3-10 2.4.4 Measurement Uncertainty Recapture Power Uprate . . . . . . . . . . . 2.4.4-1 2.4.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.4-1 2.4.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.4-1 2.4.4.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.4-1 2.4.4.2.2 Summary of Measurement Uncertainty Recapture Evaluation . . . . . . . . . 2.4.4-1 2.4.4.3 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.4-12 2.5 Plant Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.1.1.1-1 2.5.1 Internal Hazards . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.1.1.1-1 2.5.1.1 Flooding . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.1.1.1-1 2.5.1.1.1 Flood Protection . . . . . . . . . . . . . . . . . . . . . . 2.5.1.1.1-1 Turkey Point Units 3 and 4 EPU Licensing Report x

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.5.1.1.2 Equipment and Floor Drains . . . . . . . . . . . . . 2.5.1.1.2-1 2.5.1.1.3 Circulating Water System . . . . . . . . . . . . . . . 2.5.1.1.3-1 2.5.1.2 Missile Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.1.2.1-1 2.5.1.2.1 Internally Generated Missiles . . . . . . . . . . . . 2.5.1.2.1-1 2.5.1.2.2 Turbine Generator . . . . . . . . . . . . . . . . . . . . . 2.5.1.2.2-1 2.5.1.3 Pipe Failures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.1.3-1 2.5.1.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.1.3-1 2.5.1.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.1.3-2 2.5.1.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.1.3-6 2.5.1.3.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.1.3-6 2.5.1.4 Fire Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.1.4-1 2.5.1.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.1.4-1 2.5.1.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.1.4-3 2.5.1.4.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.1.4-10 2.5.2 Pressurizer Relief Tank . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.2-1 2.5.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.2-1 2.5.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.2-3 2.5.2.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.2-3 2.5.2.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.5.2-3 2.5.2.2.3 Description of Analyses and Evaluations . . . 2.5.2-4 2.5.2.2.4 License Renewal Impact Evaluation . . . . . . . 2.5.2-5 2.5.2.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.2-6 2.5.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.2-6 2.5.3 Fission Product Control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.3.1-1 2.5.3.1 Fission Product Control Systems and Structures . . . . . . . 2.5.3.1-1 2.5.3.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.3.1-1 2.5.3.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.3.1-2 2.5.3.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.3.1-4 2.5.3.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.3.1-5 2.5.3.2 Main Condenser Evacuation System . . . . . . . . . . . . . . . . 2.5.3.2-1 2.5.3.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.3.2-1 2.5.3.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.3.2-2 2.5.3.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.3.2-4 2.5.3.3 Turbine Gland Sealing Systems . . . . . . . . . . . . . . . . . . . . 2.5.3.3-1 2.5.3.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.3.3-1 2.5.3.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.3.3-3 2.5.3.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.3.3-5 Turkey Point Units 3 and 4 EPU Licensing Report xi

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.5.4 Component Cooling and Decay Heat Removal . . . . . . . . . . . . . . . 2.5.4.1-1 2.5.4.1 Spent Fuel Pool Cooling and Cleanup System . . . . . . . . 2.5.4.1-1 2.5.4.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.4.1-1 2.5.4.1.2 Technical Evaluations . . . . . . . . . . . . . . . . . . 2.5.4.1-3 2.5.4.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.1-11 2.5.4.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.1-11 2.5.4.2 Station Service Water System . . . . . . . . . . . . . . . . . . . . . 2.5.4.2-1 2.5.4.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.4.2-1 2.5.4.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.4.2-3 2.5.4.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.2-6 2.5.4.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.2-6 2.5.4.3 Reactor Auxiliary Cooling Water Systems (Component Cooling Water System) . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.3-1 2.5.4.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.4.3-1 2.5.4.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.4.3-3 2.5.4.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.3-11 2.5.4.3.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.3-11 2.5.4.4 Ultimate Heat Sink . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.4-1 2.5.4.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.4.4-1 2.5.4.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.4.4-3 2.5.4.4.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.4-5 2.5.4.5 Auxiliary Feedwater . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.5-1 2.5.4.5.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.4.5-1 2.5.4.5.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.4.5-5 2.5.4.5.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.5-9 2.5.5 Balance-of-Plant Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.5.1-1 2.5.5.1 Main Steam . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.5.1-1 2.5.5.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.5.1-1 2.5.5.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.5.1-3 2.5.5.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.5.1-8 2.5.5.2 Main Condenser . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.5.2-1 2.5.5.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.5.2-1 2.5.5.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.5.2-2 2.5.5.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.5.2-4 2.5.5.3 Turbine Bypass . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.5.3-1 2.5.5.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.5.3-1 2.5.5.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.5.3-2 2.5.5.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.5.3-4 Turkey Point Units 3 and 4 EPU Licensing Report xii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.5.5.4 Condensate and Feedwater . . . . . . . . . . . . . . . . . . . . . . . 2.5.5.4-1 2.5.5.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.5.4-1 2.5.5.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.5.4-3 2.5.5.4.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.5.4-7 2.5.6 Waste Management Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.6.1-1 2.5.6.1 Gaseous Waste Management Systems . . . . . . . . . . . . . . 2.5.6.1-1 2.5.6.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.6.1-1 2.5.6.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.6.1-4 2.5.6.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.6.1-7 2.5.6.2 Liquid Waste Management Systems . . . . . . . . . . . . . . . . 2.5.6.2-1 2.5.6.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.6.2-1 2.5.6.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.6.2-3 2.5.6.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.6.2-7 2.5.6.3 Solid Waste Management Systems . . . . . . . . . . . . . . . . . 2.5.6.3-1 2.5.6.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.6.3-1 2.5.6.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.6.3-4 2.5.6.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.6.3-7 2.5.7 Additional Considerations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.7.1-1 2.5.7.1 Emergency Diesel Engine Fuel Oil Storage and Transfer System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.7.1-1 2.5.7.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.7.1-1 2.5.7.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.7.1-3 2.5.7.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.7.1-7 2.5.7.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.7.1-7 2.5.7.2 Light Load Handling System (Related to Refueling) . . . . 2.5.7.2-1 2.5.7.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.7.2-1 2.5.7.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.7.2-3 2.5.7.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.7.2-5 2.5.8 Additional Review Areas (Plant Systems) . . . . . . . . . . . . . . . . . . . 2.5.8.1-1 2.5.8.1 Circulating Water System . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.8.1-1 2.5.8.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.8.1-1 2.5.8.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.8.1-1 2.5.8.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.8.1-3 2.5.8.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.8.1-3 2.6 Containment Review Considerations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.1-1 2.6.1 Primary Containment Functional Design . . . . . . . . . . . . . . . . . . . . 2.6.1-1 2.6.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.1-1 2.6.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.1-3 Turkey Point Units 3 and 4 EPU Licensing Report xiii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.6.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.1-3 2.6.1.2.2 Containment Response to Loss-of-Coolant Accident . . . . . . . . . . . . . . . 2.6.1-7 2.6.1.2.3 Containment Response to Main Steam Line Break . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.1-11 2.6.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.1-13 2.6.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.1-13 2.6.2 Subcompartment Analyses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.2-1 2.6.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.2-1 2.6.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.2-3 2.6.2.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.2-3 2.6.2.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.6.2-3 2.6.2.2.3 Description of Analyses and Evaluations . . . 2.6.2-4 2.6.2.2.4 License Renewal Impact Evaluation . . . . . . . 2.6.2-5 2.6.2.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.2-5 2.6.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.2-5 2.6.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.2-5 2.6.3 Mass and Energy Release . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.3.1-1 2.6.3.1 Mass and Energy Release Analysis for Postulated Loss-of-Coolant Accident . . . . . . . . . . . . . . . . 2.6.3.1-1 2.6.3.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.6.3.1-1 2.6.3.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.6.3.1-2 2.6.3.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.3.1-11 2.6.3.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.3.1-12 2.6.3.2 Mass and Energy Release Analysis for Secondary System Pipe Ruptures . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.3.2-1 2.6.3.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.6.3.2-1 2.6.3.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.6.3.2-2 2.6.3.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.3.2-8 2.6.3.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.3.2-8 2.6.4 Combustible Gas Control in Containment . . . . . . . . . . . . . . . . . . . 2.6.4-1 2.6.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.4-1 2.6.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.4-3 2.6.4.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.4-3 2.6.4.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.6.4-3 2.6.4.2.3 Description of Analyses and Evaluations . . . 2.6.4-3 Turkey Point Units 3 and 4 EPU Licensing Report xiv

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.6.4.2.4 License Renewal Impact Evaluation . . . . . . . 2.6.4-3 2.6.4.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.4-3 2.6.4.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.4-4 2.6.4.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.4-4 2.6.5 Containment Heat Removal . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.5-1 2.6.5.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.5-1 2.6.5.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.5-2 2.6.5.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.5-2 2.6.5.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.6.5-3 2.6.5.2.3 Description of Analyses and Evaluations . . . 2.6.5-4 2.6.5.2.4 License Renewal Impact Evaluation . . . . . . . 2.6.5-4 2.6.5.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.5-5 2.6.5.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.5-5 2.6.6 Pressure Analysis for ECCS Performance Capability . . . . . . . . . . 2.6.6-1 2.6.6.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.6-1 2.6.6.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.6-1 2.6.6.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.6-2 2.6.6.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.6.6-2 2.6.6.2.3 Description of Analyses and Evaluations . . . 2.6.6-2 2.6.6.2.4 License Renewal Impact Evaluation . . . . . . . 2.6.6-2 2.6.6.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.6-3 2.6.6.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.6-3 2.6.6.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.6-3 2.7 Habitability, Filtration, and Ventilation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.1-1 2.7.1 Control Room Habitability System . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.1-1 2.7.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.1-1 2.7.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.1-6 2.7.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.1-6 2.7.1.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.7.1-7 2.7.1.2.3 Description of Analyses and Evaluations . . . 2.7.1-7 2.7.1.2.4 License Renewal Impact Evaluation . . . . . . . 2.7.1-9 2.7.1.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.1-9 2.7.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.1-9 2.7.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.1-10 Turkey Point Units 3 and 4 EPU Licensing Report xv

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.7.2 Engineered Safety Feature Atmosphere Cleanup . . . . . . . . . . . . . 2.7.2-1 2.7.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.2-1 2.7.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.2-4 2.7.2.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.2-4 2.7.2.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.7.2-5 2.7.2.2.3 Description of Analyses and Evaluations . . . 2.7.2-5 2.7.2.2.4 License Renewal Impact Evaluation . . . . . . . 2.7.2-6 2.7.2.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.2-7 2.7.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.2-7 2.7.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.2-7 2.7.3 Control Room Area Ventilation System . . . . . . . . . . . . . . . . . . . . . 2.7.3-1 2.7.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.3-1 2.7.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.3-5 2.7.3.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.3-5 2.7.3.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.7.3-5 2.7.3.2.3 Description of Analyses and Evaluations . . . 2.7.3-5 2.7.3.2.4 License Renewal Impact Evaluation . . . . . . . 2.7.3-5 2.7.3.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.3-5 2.7.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.3-5 2.7.3.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.3-6 2.7.4 Spent Fuel Pool Area Ventilation System . . . . . . . . . . . . . . . . . . . . 2.7.4-1 2.7.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.4-1 2.7.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.4-3 2.7.4.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.4-3 2.7.4.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.7.4-3 2.7.4.2.3 Description of Analyses and Evaluations . . . 2.7.4-3 2.7.4.2.4 License Renewal Impact Evaluation . . . . . . . 2.7.4-5 2.7.4.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.4-5 2.7.4.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.4-5 2.7.5 Auxiliary and Radwaste Area and Turbine Areas Ventilation Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.5-1 2.7.5.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.5-1 2.7.5.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.5-3 2.7.5.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.5-3 Turkey Point Units 3 and 4 EPU Licensing Report xvi

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.7.5.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.7.5-4 2.7.5.2.3 Description of Analyses and Evaluations . . . 2.7.5-4 2.7.5.2.4 License Renewal Impact Evaluation . . . . . . . 2.7.5-5 2.7.5.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.5-5 2.7.5.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.5-5 2.7.6 Engineered Safety Feature Ventilation System . . . . . . . . . . . . . . . 2.7.6-1 2.7.6.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.6-1 2.7.6.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.6-6 2.7.6.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.6-6 2.7.6.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.7.6-6 2.7.6.2.3 Description of Analyses and Evaluations . . . 2.7.6-6 2.7.6.2.4 License Renewal Impact Evaluation . . . . . . . 2.7.6-8 2.7.6.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.6-8 2.7.6.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.6-8 2.7.7 Other Ventilation Systems (Containment) . . . . . . . . . . . . . . . . . . . 2.7.7-1 2.7.7.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.7-1 2.7.7.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.7-4 2.7.7.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.7-4 2.7.7.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.7.7-5 2.7.7.2.3 Description of Analyses and Evaluations . . . 2.7.7-5 2.7.7.2.4 License Renewal Impact Evaluation . . . . . . . 2.7.7-6 2.7.7.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.7-7 2.7.7.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.7-7 2.7.7.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.7-7 2.8 Reactor Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.1-1 2.8.1 Fuel System Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.1-1 2.8.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.1-1 2.8.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.1-4 2.8.1.2.1 Fuel System Design Features . . . . . . . . . . . . 2.8.1-4 2.8.1.2.2 Mechanical Compatibility and Performance . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.1-4 2.8.1.2.3 Seismic/LOCA . . . . . . . . . . . . . . . . . . . . . . . . 2.8.1-6 2.8.1.2.4 Fuel Rod Performance . . . . . . . . . . . . . . . . . 2.8.1-9 2.8.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.1-16 2.8.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.1-16 Turkey Point Units 3 and 4 EPU Licensing Report xvii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.8.2 Nuclear Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.2-1 2.8.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.2-1 2.8.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.2-5 2.8.2.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.2-5 2.8.2.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.8.2-5 2.8.2.2.3 Description of Analyses and Evaluations . . . 2.8.2-6 2.8.2.2.4 License Renewal Impact Evaluation . . . . . . . 2.8.2-7 2.8.2.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.2-7 2.8.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.2-7 2.8.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.2-8 2.8.3 Thermal and Hydraulic Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.3-1 2.8.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.3-1 2.8.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.3-3 2.8.3.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.3-3 2.8.3.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.8.3-3 2.8.3.2.3 Description of Analyses and Evaluations . . . 2.8.3-5 2.8.3.2.4 License Renewal Impact Evaluation . . . . . . . 2.8.3-8 2.8.3.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.3-8 2.8.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.3-8 2.8.3.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.3-9 2.8.4 Emergency Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.4.1-1 2.8.4.1 Functional Design of Control Rod Drive System . . . . . . . 2.8.4.1-1 2.8.4.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.4.1-1 2.8.4.1.2 Technical Evaluation - Control Rod Drive System . . . . . . . . . . . . . . . . . . . . . 2.8.4.1-5 2.8.4.1.3 Technical Evaluation - CRDM Cooling System . . . . . . . . . . . . . . . . . . . . . . . 2.8.4.1-6 2.8.4.1.4 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.4.1-9 2.8.4.2 Overpressure Protection During Power Operation . . . . . . 2.8.4.2-1 2.8.4.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.4.2-1 2.8.4.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.8.4.2-3 2.8.4.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.4.2-5 2.8.4.3 Overpressure Protection During Low Temperature Operation . . . . . . . . . . . . . . . . . . . . . . . 2.8.4.3-1 2.8.4.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.4.3-1 2.8.4.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.8.4.3-3 Turkey Point Units 3 and 4 EPU Licensing Report xviii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.8.4.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.4.3-6 2.8.4.3.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.4.3-6 2.8.4.4 Residual Heat Removal System . . . . . . . . . . . . . . . . . . . 2.8.4.4-1 2.8.4.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.4.4-1 2.8.4.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.8.4.4-3 2.8.4.4.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.4.4-7 2.8.5 Accident and Transient Analyses . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.5.0-1 2.8.5.0 Non-LOCA Analyses Introduction . . . . . . . . . . . . . . . . . . 2.8.5.0-1 2.8.5.0.1 Fuel Design Mechanical Features . . . . . . . . . 2.8.5.0-1 2.8.5.0.2 Peaking Factors, Kinetics Parameters . . . . . 2.8.5.0-1 2.8.5.0.3 EPU Program Features . . . . . . . . . . . . . . . . . 2.8.5.0-2 2.8.5.0.4 Other Major Analysis Inputs . . . . . . . . . . . . . 2.8.5.0-3 2.8.5.0.5 Overtemperature and Overpower T Reactor Trip Setpoints . . . . . . . . . . . . . . . . . 2.8.5.0-4 2.8.5.0.6 RPS and ESFAS Functions Assumed in Analyses . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.5.0-4 2.8.5.0.7 RCCA Insertion Characteristics . . . . . . . . . . . 2.8.5.0-5 2.8.5.0.8 Reactivity Coefficients . . . . . . . . . . . . . . . . . . 2.8.5.0-5 2.8.5.0.9 Computer Codes Used . . . . . . . . . . . . . . . . . 2.8.5.0-5 2.8.5.0.10 Classification of Events . . . . . . . . . . . . . . . . . 2.8.5.0-8 2.8.5.0.11 Events Evaluated or Analyzed . . . . . . . . . . . 2.8.5.0-9 2.8.5.0.12 Analysis Methodology . . . . . . . . . . . . . . . . . . 2.8.5.0-9 2.8.5.0.13 Operator Actions . . . . . . . . . . . . . . . . . . . . . . 2.8.5.0-12 2.8.5.0.14 Notable Safety Analysis Input Changes . . . . 2.8.5.0-12 2.8.5.0.15 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.5.0-12 2.8.5.1 Increase in Heat Removal by the Secondary System . . . 2.8.5.1.1-1 2.8.5.1.1 Reduction In Feedwater Enthalpy, Increase In Feedwater Flow, Increase in Steam Flow, and Inadvertent Opening of a Steam Generator Relief or Safety Valve . . . . 2.8.5.1.1-1 2.8.5.1.2 Steam System Piping Failures Inside and Outside Containment . . . . . . . . . . . . . . . 2.8.5.1.2-1 2.8.5.2 Decrease in Heat Removal By the Secondary System . . 2.8.5.2.1-1 2.8.5.2.1 Loss of External Load, Turbine Trip, Loss of Condenser Vacuum, and Steam Pressure Regulator Failure . . . . . . . . . . . . . . 2.8.5.2.1-1 2.8.5.2.2 Loss of Non-Emergency AC Power to the Station Auxiliaries . . . . . . . . . . . . . . . . . . 2.8.5.2.2-1 2.8.5.2.3 Loss of Normal Feedwater Flow . . . . . . . . . . 2.8.5.2.3-1 Turkey Point Units 3 and 4 EPU Licensing Report xix

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.8.5.2.4 Feedwater System Pipe Breaks Inside and Outside Containment . . . . . . . . . . . . . . . 2.8.5.2.4-1 2.8.5.3 Decrease in Reactor Coolant System Flow . . . . . . . . . . . 2.8.5.3.1-1 2.8.5.3.1 Loss of Forced Reactor Coolant Flow . . . . . . 2.8.5.3.1-1 2.8.5.3.2 Reactor Coolant Pump Rotor Seizure and Reactor Coolant Pump Shaft Break . . . . . . . 2.8.5.3.2-1 2.8.5.4 Reactivity and Power Distribution Anomalies . . . . . . . . . . 2.8.5.4.1-1 2.8.5.4.1 Uncontrolled Rod Cluster Control Assembly Withdrawal from a Subcritical or Low-Power Startup Condition . . . . . . . . . . . . 2.8.5.4.1-1 2.8.5.4.2 Uncontrolled Rod Cluster Control Assembly Withdrawal at Power . . . . . . . . . . . . . . . . . . . 2.8.5.4.2-1 2.8.5.4.3 Control Rod Misoperation . . . . . . . . . . . . . . . 2.8.5.4.3-1 2.8.5.4.4 Startup of an Inactive Loop at an Incorrect Temperature . . . . . . . . . . . . . . . . . . 2.8.5.4.4-1 2.8.5.4.5 Chemical and Volume Control System Malfunction . . . . . . . . . . . . . . . . . . . . 2.8.5.4.5-1 2.8.5.4.6 Spectrum of Rod Ejection Accidents . . . . . . . 2.8.5.4.6-1 2.8.5.5 Inadvertent Operation of Emergency Core Cooling System and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory . . . 2.8.5.5-1 2.8.5.5.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.5.5-1 2.8.5.5.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.8.5.5-3 2.8.5.5.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.5.5-6 2.8.5.6 Decrease in Reactor Coolant Inventory . . . . . . . . . . . . . . 2.8.5.6.1-1 2.8.5.6.1 Inadvertent Opening of Pressurizer Pressure Relief Valve . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.5.6.1-1 2.8.5.6.2 Steam Generator Tube Rupture . . . . . . . . . . 2.8.5.6.2-1 2.8.5.6.3 Emergency Core Cooling System and Loss-of-Coolant Accidents . . . . . . . . . . . 2.8.5.6.3-1 2.8.5.7 Anticipated Transients Without Scram . . . . . . . . . . . . . . . 2.8.5.7-1 2.8.5.7.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.5.7-1 2.8.5.7.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.8.5.7-3 2.8.5.7.3 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.5.7-5 2.8.5.7.4 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.5.7-5 2.8.5.7.5 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.5.7-5 2.8.6 Fuel Storage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.6.1-1 2.8.6.1 New Fuel Storage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.6.1-1 2.8.6.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.6.1-1 Turkey Point Units 3 and 4 EPU Licensing Report xx

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.8.6.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.8.6.1-2 2.8.6.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.6.1-3 2.8.6.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.6.1-3 2.8.6.2 Spent Fuel Storage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.6.2-1 2.8.6.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.6.2-1 2.8.6.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.8.6.2-4 2.8.6.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.6.2-11 2.8.6.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.6.2-11 2.8.7 Additional Reactor Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.7.2-1 2.8.7.1 Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.7.2-1 2.8.7.2 Natural Circulation Cooldown . . . . . . . . . . . . . . . . . . . . . . 2.8.7.2-1 2.8.7.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.7.2-1 2.8.7.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.8.7.2-3 2.8.7.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.7.2-5 2.8.7.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.7.2-6 2.8.7.3 Loss of Residual Heat Removal at Reduced Inventory . . 2.8.7.3-1 2.8.7.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.7.3-1 2.8.7.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.8.7.3-2 2.8.7.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.7.3-4 2.8.7.3.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.7.3-4 2.9 Source Terms and Radiological Consequences Analyses . . . . . . . . . . . . . 2.9.1-1 2.9.1 Source Terms for Radwaste Systems Analyses . . . . . . . . . . . . . . . 2.9.1-1 2.9.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.1-1 2.9.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.1-3 2.9.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.1-3 2.9.1.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.9.1-3 2.9.1.2.3 Description of Analyses and Evaluations . . . 2.9.1-4 2.9.1.2.4 License Renewal Impact Evaluation . . . . . . . 2.9.1-5 2.9.1.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.1-5 2.9.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.1-5 2.9.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.1-6 2.9.2 Radiological Consequences Analyses Using Alternative Source Terms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.2-1 2.9.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.2-1 2.9.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.2-4 2.9.2.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.2-4 Turkey Point Units 3 and 4 EPU Licensing Report xxi

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.9.2.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.9.2-5 2.9.2.2.3 Description of Analyses and Evaluations . . . 2.9.2-5 2.9.2.2.4 License Renewal Impact Evaluation . . . . . . . 2.9.2-5 2.9.2.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.2-5 2.9.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.2-5 2.9.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.2-5 2.10 Health Physics . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.10.1-1 2.10.1 Occupational and Public Radiation Doses . . . . . . . . . . . . . . . . . . . 2.10.1-1 2.10.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.10.1-1 2.10.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.10.1-4 2.10.1.2.1 Normal Operation Radiation Levels and Shielding Adequacy . . . . . . . . . . . . . . . . 2.10.1-4 2.10.1.2.2 Radiation Monitoring Setpoints . . . . . . . . . . . 2.10.1-11 2.10.1.2.3 Post Accident Vital Area Accessibility . . . . . . 2.10.1-13 2.10.1.2.4 Normal Operation Radwaste Effluents and Annual Dose to the Public . . . . . . . . . . . 2.10.1-15 2.10.1.2.5 Ensuring Occupational and Public Radiation Exposures Are ALARA . . . . . . . . . 2.10.1-20 2.10.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.10.1-21 2.10.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.10.1-22 2.11 Human Performance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.11.1-1 2.11.1 Human Factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.11.1-1 2.11.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.11.1-1 2.11.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.11.1-3 2.11.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.11.1-3 2.11.1.2.2 Description of Analysis and Evaluations . . . . 2.11.1-3 2.11.1.2.3 License Renewal Impact Evaluation . . . . . . . 2.11.1-8 2.11.1.2.4 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.11.1-8 2.11.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.11.1-9 2.12 Power Ascension and Testing Plan . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.12-1 2.12.1 Approach to EPU Power Level and Test Plan . . . . . . . . . . . . . . . . 2.12-1 2.12.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.12-1 2.12.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.12-2 2.12.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.12-2 2.12.1.2.2 Background . . . . . . . . . . . . . . . . . . . . . . . . . . 2.12-2 2.12.1.2.3 Power Ascension Test Plan . . . . . . . . . . . . . 2.12-4 Turkey Point Units 3 and 4 EPU Licensing Report xxii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.12.1.2.4 Comparison of EPU Test Program to the Initial Plant Test Program . . . . . . . . . . . . . . . . . . . . 2.12-9 2.12.1.2.5 Post Modification Testing Requirements . . . . 2.12-9 2.12.1.2.6 Description of Analyses and Evaluations . . . 2.12-9 2.12.1.2.7 License Renewal Impact Evaluation . . . . . . . 2.12-16 2.12.1.2.8 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.12-16 2.12.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.12-16 2.12.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.12-17 2.13 Risk Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-1 2.13.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-1 2.13.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-2 2.13.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-2 2.13.2.2 Risk Perspective on the Design of Turkey Point Units 3 and 4 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-3 2.13.2.3 Turkey Point Units 3 and 4 PRA Model . . . . . . . . . . . . . . 2.13-4 2.13.2.3.1 Internal Events . . . . . . . . . . . . . . . . . . . . . . . 2.13-6 2.13.2.3.2 Steam Generator Tube Rupture (SGTR) . . . 2.13-8 2.13.2.3.3 Interfacing System LOCA (ISLOCA) . . . . . . . 2.13-8 2.13.2.3.4 Transients . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-8 2.13.2.3.5 Internal Flooding . . . . . . . . . . . . . . . . . . . . . . 2.13-10 2.13.2.3.6 Turbine Missile Generation . . . . . . . . . . . . . . 2.13-11 2.13.2.4 External Events and Shutdown Risk . . . . . . . . . . . . . . . . 2.13-11 2.13.2.4.1 Seismic Events . . . . . . . . . . . . . . . . . . . . . . . 2.13-11 2.13.2.4.2 Fire . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-13 2.13.2.4.3 High Winds, Floods, and Other External Events . . . . . . . . . . . . . . . . . . 2.13-13 2.13.2.4.4 Other Miscellaneous Challenges . . . . . . . . . 2.13-15 2.13.2.5 Shutdown Operations Risk . . . . . . . . . . . . . . . . . . . . . . . . 2.13-15 2.13.2.6 PRA Model Attributes . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-16 2.13.2.6.1 Function/System Level Success Criteria . . . . 2.13-16 2.13.2.6.2 Operator Actions . . . . . . . . . . . . . . . . . . . . . . 2.13-20 2.13.2.6.3 Component and System Reliability . . . . . . . . 2.13-21 2.13.2.7 Level 2 Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-22 2.13.2.8 IPE/IPEEE Vulnerabilities . . . . . . . . . . . . . . . . . . . . . . . . 2.13-22 2.13.2.9 EPU Risk Analysis and Sensitivity Studies . . . . . . . . . . . 2.13-22 2.13.2.9.1 Comparison of Current and EPU Plant Risks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-22 2.13.2.9.2 Sensitivity Studies . . . . . . . . . . . . . . . . . . . . . 2.13-24 Turkey Point Units 3 and 4 EPU Licensing Report xxiii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.13.2.9.3 Technical Summary . . . . . . . . . . . . . . . . . . . 2.13-28 2.13.2.10 Quality of PRA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-29 2.13.2.10.1 Model Peer Review . . . . . . . . . . . . . . . . . . . . 2.13-29 2.13.2.10.2 Review Against NEI A and B Findings . . . . . 2.13-29 2.13.2.10.3 PRA Maintenance and Update . . . . . . . . . . . 2.13-41 2.13.2.10.4 Other Relevant Open Items . . . . . . . . . . . . . 2.13-42 2.13.2.11 Software . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-42 2.13.2.11.1 Thermal Hydraulic Software . . . . . . . . . . . . . 2.13-42 2.13.2.11.2 CAFTA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-42 2.13.2.11.3 HRA Calculator . . . . . . . . . . . . . . . . . . . . . . . 2.13-42 2.13.2.12 Technical Evaluation Conclusion . . . . . . . . . . . . . . . . . . . 2.13-43 2.13.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-43 2.13.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-44 Turkey Point Units 3 and 4 EPU Licensing Report xxiv

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 2.5.4.4 Ultimate Heat Sink 2.5.4.4.1 Regulatory Evaluation The ultimate heat sink (UHS) is the source of cooling water provided to dissipate reactor decay heat and essential cooling system heat loads after a normal reactor shutdown or a shutdown following an accident. FPLs review focused on the impact that the proposed EPU has on the decay heat removal capability of the UHS. Additionally, FPLs review included evaluation of the design-basis UHS temperature limit determination to confirm that post-licensing data trends (e.g.,

air and water temperatures, humidity, wind speed, water volume) do not establish more severe conditions than previously assumed.

The NRCs acceptance criteria for the UHS are based on:

  • GDC-5, insofar as it requires that SSCs important to safety not be shared among nuclear power units unless it can be shown that sharing will not significantly impair their ability to perform their safety functions; and
  • GDC-44, insofar as it requires that a system with the capability to transfer heat loads from safety-related SSCs to a heat sink under both normal operating and accident conditions be provided.

Specific review criteria are contained in SRP Section 9.2.5 and other guidance provided in Matrix 5 of RS-001.

Current Licensing Basis As noted in PTN Updated Final Safety Analysis Report (UFSAR), Section 1.3, the General Design Criteria (GDC) used during licensing of the Turkey Point Nuclear Plant predate those provided today in 10 CFR 50, Appendix A. The PTN GDCs were developed based on the 1967 Atomic Energy Commission Proposed General Design Criteria and are addressed in various sections of the UFSAR.

The PTN GDC applicable to the UHS and within the scope of the stated regulatory evaluation is as follows:

PTN GDC-4, Sharing of Systems: Reactor facilities may share systems or components if it can be shown that such sharing will not result in undue risk to the health and safety of the public.

(GDC-5)

The PTN systems provided to transfer heat from safety-related components to the UHS, i.e.,

closed cooling water canals, are the Component Cooling Water (CCW) System and the Intake Cooling Water (ICW) System. The site occupies an area approximately 2 miles wide by 5 miles long and includes 168 miles of earthen canals covering approximately 6100 acres (4370 acres of water surface). The average canal depth is 2.8 feet. The total water volume in the cooling canals is approximately 12,300 acre-feet (4 billion gallons). The canals receive heated condenser water at one end and supply cooled water at the other end for reuse. The discharge canal receives heated effluent from the plant and distributes the flow into 32 feeder canals. Water in the feeder canals flows south and discharges to a single collecting canal that distributes water to six return canals. Water in the return canals flows north to the plant intake. The entire water circuit, plant Turkey Point Units 3 and 4 EPU Licensing Report 2.5.4.4-1 Ultimate Heat Sink

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 discharge back to plant intake, is 13.2 miles and takes approximately 44 hours1.833 days <br />0.262 weeks <br />0.0603 months <br />. The temperature rise across the plant, from intake to discharge, averages 15-30°F depending upon the unit, unit load, and various other factors. The average intake temperature is 2.5°F above the average ambient air temperature. The closed cooling water canal system is a shared heat sink that services Turkey Point Units 1, 2, 3 & 4.

The CCW System is the heat sink for the Residual Heat Removal (RHR) System, the Chemical and Volume Control System (CVCS), the Spent Fuel Pit Cooling System and various Reactor Coolant System (RCS) components. A separate CCW System is provided for each nuclear unit.

However, the CCW System provides cross-tie connections for CCW-supplied components that could serve both Turkey Point Units 3 and 4. These components include the safety injection pumps. These cross-tie connections are subject to design criteria involving minimum capacity requirements, unit intermix prohibitions, single active failure tolerance and passive failure isolation capability.

The ICW System provides the cooling water to the safety-related CCW Heat Exchangers as well as to the non-safety-related Turbine Plant Cooling Water (TPCW) Heat Exchangers. A separate ICW System is provided for each nuclear unit.

Although there is no specific PTN GDC analogous to GDC-44 on Cooling Water, the GDC requirements are addressed in the plant design. The Auxiliary Feedwater (AFW) System supplies cooling water to the steam generators at times when the normal feedwater systems are not available. The CCW and ICW Systems are discussed above. These cooling water systems transfer heat from safety-related SSCs to either the ultimate heat sink (cooling canals) in the cases of CCW and ICW Systems or to the atmosphere in the case of the AFW System The CCW system is designed with sufficient redundancy such that a single active failure will not prevent the system from accomplishing its support function of cooling safety related equipment.

The intake cooling water system provides sufficient redundancy so that at least one intake cooling water pump will continue to operate to handle heat loads from design basis accidents following a postulated single active failure. The AFW System is designed with sufficient mechanical and electrical redundancy such that the single failure of an active component, either in the AFW System or in a supporting system, can be accommodated without loss of the overall AFW System safety-related functions.

PTNs UHS and associated structures were evaluated for plant license renewal. System and system components, materials of construction, operating histories and programs used to manage aging effects are documented in NUREG-1759, Safety Evaluation Report (SER) Related to the License Renewal of the Turkey Point Nuclear Plant, Units 3 and 4, dated April 2002 and supplemented in May 2002. See SER Sections 2.4.2.4, 2.4.2.6, and 2.4.2.11. Although the earthen canals were identified as within the scope of license renewal, no aging management program was required while the associated intake and discharge structures cited the Systems and Structures Monitoring Program as appropriate to manage their identified aging effects.

Turkey Point Units 3 and 4 EPU Licensing Report 2.5.4.4-2 Ultimate Heat Sink

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 2.5.4.4.2 Technical Evaluation 2.5.4.4.2.1 Introduction The UHS at PTN is a closed-loop cooling canal system that accepts the rejected heat loads from the plants at one end (discharge) and returns cooled water at the opposite (intake) end. The closed-loop cooling water canal system is a shared heat sink that services Turkey Point Fossil Units 1 & 2, and Nuclear Units 3 & 4. The total volume of water in the cooling canals is approximately 12,300 acre-feet (4 billion gallons).

The ultimate heat sink provides water to the Intake Cooling Water (ICW) System via the Intake Structure. The Intake Structure is Seismic Class I to the extent that water is always available to the ICW System. The Intake Cooling Water System provides cooling water for heat removal from safety-related heat exchangers, including the Component Cooling Water heat exchangers which cool the Residual Heat Removal System. Refer to LR Section 2.5.4.2, Station Service Water System, for a description of the cooled components and the water users supplied by the Intake Cooling Water System.

The maximum cooling canal water temperature was assumed to vary seasonally throughout the year for cooldown analyses. Temperatures were adjusted from 92°F (spring/fall) to 97°F (summer) based on the season. See LR Section 2.8.4.4, Residual Heat Removal System which describes the cooldown scenarios using the Ultimate Heat Sink for heat rejection.

A maximum cooling water temperature of 100°F is used for the safety analyses which rely on the ultimate heat sink for heat removal. See LR Section 2.6.1, Primary Containment Functional Design which describes the postulated accident scenarios using the ultimate heat sink for heat rejection.

The closed-loop cooling canal is also used by the non-safety related Circulating Water System to provide cooling water for heat removal from the turbine cycle during normal plant power operations. Refer to LR Section 2.5.8.1, Circulating Water System.

2.5.4.4.2.2 Input Parameters, Assumptions, and Acceptance Criteria Assumptions The following Ultimate Heat Sink temperatures were assumed in RHR Cooldown and postulated accident analyses.

Ultimate Heat Sink Temperatures Used in Analyses Temperature (°F) Time Interval Type of Analysis Used In 92° Spring/Fall RHR Cooldown 97° Summer RHR Cooldown 100° Year-Round Accident Turkey Point Units 3 and 4 EPU Licensing Report 2.5.4.4-3 Ultimate Heat Sink

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Acceptance Criteria The ultimate heat sink shall remove the Design Basis Accident heat load with a maximum temperature of 100°F.

2.5.4.4.2.3 Description of Analyses and Evaluations The Ultimate Heat Sink was evaluated to ensure it is capable of performing its intended function of a reliable water supply and heat removal capacity for normal and accident conditions following EPU.

The Ultimate Heat Sink was evaluated for the circulating water discharge temperatures during EPU normal operation and initial normal cooldown. These effects were evaluated against the Florida Department of Environmental Protection National Pollutant Discharge Elimination System (NPDES) permit (FL0001562) limits for PTN in LR Section 2.5.8.1, Circulating Water System.

Additional evaluations related to the Ultimate Heat Sink are addressed in the following Licensing Report Sections:

  • Intake Cooling Water discharge temperatures, heat loads, and flow rates to the cooling canal system - LR Section 2.5.4.2, Station Service Water System.
  • Post-accident heat removal requirements - LR Section 2.6.1, Primary Containment Functional Design.

2.5.4.4.2.4 License Renewal Impact Evaluation Portions of the Ultimate Heat Sink are within the scope of License Renewal. EPU activities do not add any new components nor do they introduce any new functions for existing components that would change the license renewal system evaluation boundaries. The changes associated with the operation of the Ultimate Heat Sink at EPU conditions do not add any new or previously unevaluated materials to the system. System component internal and external environments remain within the parameters previously evaluated. Thus, no new aging effects requiring management are identified.

2.5.4.4.2.5 Results The Ultimate Heat Sink continues to meet its licensing, design, and performance capabilities at EPU conditions as evidenced by the evaluation results below.

General Design Criteria The evaluation of the Ultimate Heat Sink capabilities at EPU conditions demonstrates that PTN will continue to meet the current licensing basis with respect to the requirements of PTN GDC-4.

There will be no increase in the amount of water withdrawn as a result of the EPU project. The Ultimate Heat Sink contains sufficient volume to provide cooling water to both units under all normal, abnormal, and accident conditions. Therefore, the Ultimate Heat Sink continues to meet Turkey Point Units 3 and 4 EPU Licensing Report 2.5.4.4-4 Ultimate Heat Sink

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 the design requirements with respect to sharing of systems and components in accordance with PTN licensing basis and PTN GDC-4.

Water Supply and Heat Removal Requirements The Ultimate Heat Sink will continue to provide the required water supply and heat sink capacity at EPU conditions; the Intake Cooling Water flow requirements for cooling of safety-related heat exchangers either do not change or decrease slightly. The maximum increase in cooled water temperature leaving the cooling canal system to return to the units is approximately 0.9°F, from 91.9°F to 92.8°F. The analysis results discussed in LR Section 2.8.4.4, Residual Heat Removal System and LR Section 2.6.1, Primary Containment Functional Design confirm that the Ultimate Heat Sink will continue to provide sufficient water supply and heat removal for cooldown and to mitigate the postulated accident scenarios.

The intake cooling water returned to the Ultimate Heat Sink from cooled components experiences a small temperature change at normal operating, cooldown, and accident conditions due to the EPU. During normal operation and normal cooldown, the intake cooling water discharge temperatures increase slightly and the time to cooldown the plant is extended. During accident conditions, the intake cooling water discharge temperatures continue to be bound by existing analyses and the system design parameters. The circulating water flow rates remain within the existing design rating of the pumps. The circulating water discharge temperature is expected to increase by approximately 4°F at EPU conditions. The effect of intake cooling water discharge temperature changes during normal operation, normal cooldown, and accident conditions at EPU is minimal due to the mixing of the intake cooling water with circulating water, screen wash, and storm drain flows at the Discharge Structure before the effluent is discharged to the cooling canals. The intake cooling water flow rate is insignificant when compared to the flow rate of the circulating water through the condenser.

The discharge of circulating water is governed by the Florida NPDES permit. As discussed in LR Section 2.5.8.1, Circulating Water System. The higher circulating water temperature during normal plant power generation has no impact on the current NPDES permit which does not limit the maximum discharge temperature, differential temperature across the condenser, or total discharge heat.

2.5.4.4.3 Conclusion FPL has assessed the effects of the proposed EPU on the UHS safety function, including the validation of the design-basis UHS temperature limit based on post-licensing data. Based on this information, FPL concludes that the proposed EPU will not compromise the design-basis safety function of the UHS, and that the UHS will continue to satisfy the requirements of the plants current licensing basis with regard to PTN GDC-4 following implementation of the proposed EPU.

Therefore, FPL finds the proposed EPU acceptable with respect to the UHS.

Turkey Point Units 3 and 4 EPU Licensing Report 2.5.4.4-5 Ultimate Heat Sink

NRC-046 Submitted Nov. 10, 2015 Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: FLORIDA POWER & LIGHT COMPANY (Turkey Point Nuclear Generating, Units 3 and 4)

ASLBP #: 15-935-02-LA-BD01 Docket #: 05000250 & 05000251 Exhibit #: NRC-046-00-BD01 Identified: 1/4/2016 Admitted: 1/4/2016 Withdrawn:

Rejected: Stricken:

Other:

Turkey Point Units 3 and 4 LICENSE AMENDMENT REQUEST FOR EXTENDED POWER UPRATE ATTACHMENT 4 Licensing Report This coversheet plus 1502 pages Turkey Point Units 3 and 4 EPU LAR Att. 4-1 Licensing Report

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 1.0 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-1 1.0.1 General Overview of the Turkey Point 3 and 4 Extended Power Uprate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-1 1.0.2 Plant Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-2 1.0.3 Schedule . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-2 1.0.4 Plant Modifications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-2 1.0.4.1 Reactor System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-3 1.0.4.2 Emergency Core Cooling System . . . . . . . . . . . . . . . . . . 1.0-4 1.0.4.3 Steam and Power Conversion . . . . . . . . . . . . . . . . . . . . . 1.0-4 1.0.4.4 Auxiliary Feedwater (AFW) . . . . . . . . . . . . . . . . . . . . . . . 1.0-6 1.0.4.5 Spent Fuel Pool (SFP) . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-6 1.0.4.6 Onsite AC . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-7 1.0.4.7 Offsite AC . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-7 1.0.5 Current Licensing Basis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-8 1.0.6 Risk Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-8 1.0.7 Treatment of Issues Related to the Renewed Operating License . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-9 1.0.8 Additional Review Areas . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-10 1.0.9 Use of Industry Operating Experience . . . . . . . . . . . . . . . . . . . . . . 1.0-11 1.0.10 EPU Relation to Other Concurrent Licensing Activities . . . . . . . . . 1.0-11 1.0.11 Regulatory Commitments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-11 1.0.12 Treatment of Proprietary Information . . . . . . . . . . . . . . . . . . . . . . . 1.0-12 1.1 Nuclear Steam Supply System Parameters . . . . . . . . . . . . . . . . . . . . . . . . 1.1-1 1.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.1-1 1.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.1-1 1.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.1-1 1.1.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.1-1 1.1.2.3 Description of Analyses and Evaluation . . . . . . . . . . . . . . 1.1-2 1.1.2.4 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.1-2 1.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.1-3 2.0 Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.1-1 2.1 Materials and Chemical Engineering . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.1-1 2.1.1 Reactor Vessel Materials Surveillance Program . . . . . . . . . . . . . . 2.1.1-1 2.1.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.1-1 2.1.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.1-3 2.1.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.1-3 Turkey Point Units 3 and 4 EPU Licensing Report i

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.1.1.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.1-4 2.1.1.2.3 Description of Analyses and Evaluations . . . 2.1.1-5 2.1.1.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.1-6 2.1.1.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.1-6 2.1.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.1-7 2.1.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.1-7 2.1.2 Pressure-Temperature Limits and Upper-Shelf Energy . . . . . . . . . 2.1.2-1 2.1.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.2-1 2.1.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.2-3 2.1.2.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.2-3 2.1.2.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.2-3 2.1.2.2.3 Description of Analyses and Evaluations . . . 2.1.2-5 2.1.2.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.2-5 2.1.2.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.2-5 2.1.2.3 Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.2-6 2.1.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.2-7 2.1.3 Pressurized Thermal Shock . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.3-1 2.1.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.3-1 2.1.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.3-3 2.1.3.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.3-3 2.1.3.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.3-3 2.1.3.2.3 Description of Analyses and Evaluations . . . 2.1.3-4 2.1.3.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.3-7 2.1.3.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.3-7 2.1.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.3-7 2.1.3.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.3-8 2.1.4 Reactor Internal and Core Support Materials . . . . . . . . . . . . . . . . . 2.1.4-1 2.1.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.4-1 2.1.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.4-3 2.1.4.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.4-3 2.1.4.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.4-4 2.1.4.2.3 Description of Analyses and Evaluations . . . 2.1.4-5 2.1.4.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.4-9 2.1.4.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.4-9 Turkey Point Units 3 and 4 EPU Licensing Report ii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.1.4.3 Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.4-9 2.1.4.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.4-10 2.1.5 Reactor Coolant Pressure Boundary Materials . . . . . . . . . . . . . . . 2.1.5-1 2.1.5.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.5-1 2.1.5.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.5-5 2.1.5.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.5-5 2.1.5.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.5-5 2.1.5.2.3 Description of Analyses and Evaluations . . . 2.1.5-6 2.1.5.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.5-10 2.1.5.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.5-11 2.1.5.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.5-12 2.1.5.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.5-12 2.1.6 Leak-Before-Break . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.6-1 2.1.6.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.6-1 2.1.6.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.6-3 2.1.6.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.6-3 2.1.6.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.6-4 2.1.6.2.3 Description of Analyses and Evaluations . . . 2.1.6-5 2.1.6.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.6-5 2.1.6.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.6-5 2.1.6.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.6-6 2.1.6.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.6-6 2.1.7 Protective Coating Systems - Organic Materials . . . . . . . . . . . . . . 2.1.7-1 2.1.7.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.7-1 2.1.7.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.7-3 2.1.7.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.7-3 2.1.7.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.7-3 2.1.7.2.3 Discussion of Analyses and Evaluations . . . . 2.1.7-4 2.1.7.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.7-4 2.1.7.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.7-4 2.1.7.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.7-4 2.1.7.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.7-4 2.1.8 Flow-Accelerated Corrosion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.8-1 2.1.8.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.8-1 2.1.8.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.8-2 Turkey Point Units 3 and 4 EPU Licensing Report iii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.1.8.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.8-2 2.1.8.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.8-4 2.1.8.2.3 Description of Analyses and Evaluations . . . 2.1.8-4 2.1.8.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.8-6 2.1.8.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.8-7 2.1.8.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.8-7 2.1.8.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.8-7 2.1.9 Steam Generator Tube Inservice Inspection . . . . . . . . . . . . . . . . . 2.1.9-1 2.1.9.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.9-1 2.1.9.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.9-2 2.1.9.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.9-2 2.1.9.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.9-3 2.1.9.2.3 Description of Analyses and Evaluations . . . 2.1.9-3 2.1.9.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.9-3 2.1.9.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.9-4 2.1.9.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.9-4 2.1.9.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.9-4 2.1.10 Steam Generator Blowdown System . . . . . . . . . . . . . . . . . . . . . . . 2.1.10-1 2.1.10.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.10-1 2.1.10.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.10-2 2.1.10.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.10-2 2.1.10.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.10-3 2.1.10.2.3 Description of Analyses and Evaluations . . . 2.1.10-3 2.1.10.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.10-3 2.1.10.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.10-4 2.1.10.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.10-4 2.1.11 Chemical and Volume Control System . . . . . . . . . . . . . . . . . . . . . . 2.1.11-1 2.1.11.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.11-1 2.1.11.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.11-4 2.1.11.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.11-4 2.1.11.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.1.11-5 2.1.11.2.3 Description of Analysis and Evaluations . . . . 2.1.11-6 2.1.11.2.4 License Renewal Impact Evaluation . . . . . . . 2.1.11-9 2.1.11.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.11-9 Turkey Point Units 3 and 4 EPU Licensing Report iv

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.1.11.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.11-10 2.2 Mechanical and Civil Engineering . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.1-1 2.2.1 Pipe Rupture Locations and Associated Dynamic Effects . . . . . . . 2.2.1-1 2.2.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.1-1 2.2.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.1-3 2.2.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.1-3 2.2.1.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.2.1-4 2.2.1.2.3 Description of Analyses and Evaluations . . . 2.2.1-4 2.2.1.2.4 License Renewal Impact Evaluation . . . . . . . 2.2.1-5 2.2.1.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.1-6 2.2.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.1-6 2.2.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.1-6 2.2.2 Pressure-Retaining Components and Component Supports . . . . . 2.2.2-1 2.2.2.1 NSSS Piping, Components and Supports . . . . . . . . . . . . 2.2.2-6 2.2.2.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.2.2-6 2.2.2.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.2.2-7 2.2.2.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-11 2.2.2.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-12 2.2.2.2 Balance of Plant Piping, Components, and Supports . . . 2.2.2-14 2.2.2.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.2.2-14 2.2.2.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.2.2-15 2.2.2.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-19 2.2.2.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-20 2.2.2.3 Reactor Vessel and Supports . . . . . . . . . . . . . . . . . . . . . 2.2.2-30 2.2.2.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.2.2-30 2.2.2.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.2.2-31 2.2.2.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-36 2.2.2.3.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-36 2.2.2.4 Control Rod Drive Mechanism . . . . . . . . . . . . . . . . . . . . . 2.2.2-45 2.2.2.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.2.2-45 2.2.2.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.2.2-46 2.2.2.4.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-47 2.2.2.5 Steam Generators and Supports . . . . . . . . . . . . . . . . . . . 2.2.2-49 2.2.2.5.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.2.2-49 2.2.2.5.2 Technical Evaluation - Steam Generator Structural Integrity . . . . . . . . . . . . 2.2.2-49 Turkey Point Units 3 and 4 EPU Licensing Report v

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.2.2.5.3 Technical Evaluation - Primary-to-Secondary Pressure Differential . . . . . . . . . . . . . . . . . . . 2.2.2-52 2.2.2.5.4 Technical Evaluation - Steam Generator Thermal-Hydraulic Analysis . . . . . 2.2.2-53 2.2.2.5.5 Technical Evaluation - Steam Generator Tube Wear . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-56 2.2.2.5.6 Technical Evaluation - Steam Generator Loose Parts . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-58 2.2.2.5.7 Technical Evaluation - Steam Generator Hardware . . . . . . . . . . . . . . . . . . . 2.2.2-60 2.2.2.5.8 Technical Evaluation - Steam Drum Component . . . . . . . . . . . . . . . . . . . . . 2.2.2-65 2.2.2.5.9 Technical Evaluation - Steam Generator Chemistry . . . . . . . . . . . . . . . . . . . 2.2.2-70 2.2.2.5.10 Technical Evaluation - Regulatory Guide 1.20 Evaluation - Vibration Assessment Program for Reactor Internals . . . . . . . . . . . . . . . . . . . 2.2.2-72 2.2.2.5.11 Technical Evaluation - Structural Evaluation of Increased Primary-to-Secondary Pressure Differential . . . . . . . . . . . . . . . . . . . 2.2.2-75 2.2.2.5.12 Technical Evaluation - Steam Generator Tube Integrity . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-78 2.2.2.5.13 Evaluation - LOCA Rarefaction Wave Analysis . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-82 2.2.2.5.14 Technical Evaluation - Steam Generator Supports . . . . . . . . . . . . . . . . . . . . 2.2.2-84 2.2.2.5.15 Steam Generator - Overall Results . . . . . . . 2.2.2-85 2.2.2.5.16 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-85 2.2.2.5.17 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-86 2.2.2.6 Reactor Coolant Pumps and Supports . . . . . . . . . . . . . . . 2.2.2-98 2.2.2.6.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.2.2-98 2.2.2.6.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.2.2-98 2.2.2.6.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-104 2.2.2.7 Pressurizer and Supports . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-108 2.2.2.7.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.2.2-108 2.2.2.7.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.2.2-109 2.2.2.7.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-113 2.2.2.7.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.2-113 Turkey Point Units 3 and 4 EPU Licensing Report vi

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.2.3 Reactor Pressure Vessel Internals and Core Supports . . . . . . . . . 2.2.3-1 2.2.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.3-1 2.2.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.3-4 2.2.3.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.3-4 2.2.3.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.2.3-7 2.2.3.2.3 Description of Analyses and Evaluations . . . 2.2.3-7 2.2.3.2.4 License Renewal Impact Evaluation . . . . . . . 2.2.3-12 2.2.3.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.3-12 2.2.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.3-12 2.2.4 Safety-Related Valves and Pumps . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.4-1 2.2.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.4-1 2.2.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.4-6 2.2.4.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.4-6 2.2.4.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.2.4-9 2.2.4.2.3 Description of Analyses and Evaluations . . . 2.2.4-9 2.2.4.2.4 License Renewal Impact Evaluation . . . . . . . 2.2.4-10 2.2.4.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.4-10 2.2.4.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.4-17 2.2.4.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.4-17 2.2.5 Seismic and Dynamic Qualification of Mechanical and Electrical Equipment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.5-1 2.2.5.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.5-1 2.2.5.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.5-6 2.2.5.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.5-6 2.2.5.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.2.5-7 2.2.5.2.3 Description of Analyses and Evaluations . . . 2.2.5-7 2.2.5.2.4 License Renewal Impact Evaluation . . . . . . . 2.2.5-7 2.2.5.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.5-8 2.2.5.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.5-8 2.2.6 NSSS Design Transients . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.6-1 2.2.6.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.6-1 2.2.6.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.6-4 2.2.6.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.6-4 2.2.6.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.2.6-5 Turkey Point Units 3 and 4 EPU Licensing Report vii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.2.6.2.3 Description of Analyses and Evaluations . . . 2.2.6-5 2.2.6.2.4 License Renewal Impact Evaluation . . . . . . . 2.2.6-5 2.2.6.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.6-5 2.2.6.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.6-6 2.2.6.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.6-6 2.2.7 Bottom-Mounted Instrumentation Guide Tubes and Flux Thimble . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.7-1 2.2.7.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.7-1 2.2.7.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.7-5 2.2.7.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.7-5 2.2.7.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.2.7-5 2.2.7.2.3 Description of Analyses and Evaluations . . . 2.2.7-6 2.2.7.2.4 License Renewal Impact Evaluation . . . . . . . 2.2.7-7 2.2.7.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.7-7 2.2.7.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.7-8 2.2.7.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2.7-8 2.3 Electrical Engineering . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.1-1 2.3.1 Environmental Qualification of Electrical Equipment . . . . . . . . . . . 2.3.1-1 2.3.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.1-1 2.3.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.1-2 2.3.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.1-2 2.3.1.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.3.1-3 2.3.1.2.3 Description of Analyses and Evaluations . . . 2.3.1-3 2.3.1.2.4 License Renewal Impact Evaluation . . . . . . . 2.3.1-9 2.3.1.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.1-10 2.3.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.1-10 2.3.2 Offsite Power System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.2-1 2.3.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.2-1 2.3.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.2-2 2.3.2.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.2-2 2.3.2.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.3.2-3 2.3.2.2.3 Description of Analyses and Evaluations . . . 2.3.2-3 2.3.2.2.4 License Renewal Impact Evaluation . . . . . . . 2.3.2-4 2.3.2.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.2-4 2.3.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.2-6 Turkey Point Units 3 and 4 EPU Licensing Report viii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.3.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.2-6 2.3.3 AC Onsite Power System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.3-1 2.3.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.3-1 2.3.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.3-3 2.3.3.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.3-3 2.3.3.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.3.3-4 2.3.3.2.3 Description of Analysis and Evaluations . . . . 2.3.3-4 2.3.3.2.4 License Renewal Impact Evaluation . . . . . . . 2.3.3-12 2.3.3.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.3-12 2.3.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.3-12 2.3.3.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.3-13 2.3.4 DC Onsite Power System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.4-1 2.3.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.4-1 2.3.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.4-2 2.3.4.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.4-2 2.3.4.2.2 Description of Analysis and Evaluations . . . . 2.3.4-2 2.3.4.2.3 License Renewal Impact Evaluation . . . . . . . 2.3.4-3 2.3.4.2.4 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.4-3 2.3.4.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.4-3 2.3.4.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.4-3 2.3.5 Station Blackout . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.5-1 2.3.5.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.5-1 2.3.5.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.5-3 2.3.5.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.5-3 2.3.5.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.3.5-4 2.3.5.2.3 Description of Analysis and Evaluation . . . . . 2.3.5-4 2.3.5.2.4 License Renewal Impact Evaluation . . . . . . . 2.3.5-7 2.3.5.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.5-7 2.3.5.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3.5-8 2.4 Instrumentation and Controls . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.1-1 2.4.1 Reactor Protection, Safety Features Actuation, and Control Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.1-1 2.4.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.1-1 2.4.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.1-7 2.4.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.1-7 Turkey Point Units 3 and 4 EPU Licensing Report ix

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.4.1.2.2 Input Parameters, Assumptions and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.4.1-7 2.4.1.2.3 Description of Analyses and Evaluations . . . 2.4.1-7 2.4.1.2.4 License Renewal Impact Evaluation . . . . . . . 2.4.1-24 2.4.1.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.1-24 2.4.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.1-24 2.4.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.1-24 2.4.2 Plant Operability (Margin to Trip) . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.2-1 2.4.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.2-1 2.4.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.2-2 2.4.2.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.2-2 2.4.2.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.4.2-2 2.4.2.2.3 Description of Analyses and Evaluations . . . 2.4.2-3 2.4.2.2.4 License Renewal Impact Evaluation . . . . . . . 2.4.2-4 2.4.2.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.2-4 2.4.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.2-5 2.4.3 Pressurizer Relief Component Sizing . . . . . . . . . . . . . . . . . . . . . . . 2.4.3-1 2.4.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.3-1 2.4.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.3-4 2.4.3.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.3-4 2.4.3.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.4.3-5 2.4.3.2.3 Description of Analyses and Evaluations . . . 2.4.3-9 2.4.3.2.4 License Renewal Impact Evaluation . . . . . . . 2.4.3-9 2.4.3.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.3-9 2.4.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.3-10 2.4.4 Measurement Uncertainty Recapture Power Uprate . . . . . . . . . . . 2.4.4-1 2.4.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.4-1 2.4.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.4-1 2.4.4.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.4-1 2.4.4.2.2 Summary of Measurement Uncertainty Recapture Evaluation . . . . . . . . . 2.4.4-1 2.4.4.3 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.4-12 2.5 Plant Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.1.1.1-1 2.5.1 Internal Hazards . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.1.1.1-1 2.5.1.1 Flooding . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.1.1.1-1 2.5.1.1.1 Flood Protection . . . . . . . . . . . . . . . . . . . . . . 2.5.1.1.1-1 Turkey Point Units 3 and 4 EPU Licensing Report x

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.5.1.1.2 Equipment and Floor Drains . . . . . . . . . . . . . 2.5.1.1.2-1 2.5.1.1.3 Circulating Water System . . . . . . . . . . . . . . . 2.5.1.1.3-1 2.5.1.2 Missile Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.1.2.1-1 2.5.1.2.1 Internally Generated Missiles . . . . . . . . . . . . 2.5.1.2.1-1 2.5.1.2.2 Turbine Generator . . . . . . . . . . . . . . . . . . . . . 2.5.1.2.2-1 2.5.1.3 Pipe Failures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.1.3-1 2.5.1.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.1.3-1 2.5.1.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.1.3-2 2.5.1.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.1.3-6 2.5.1.3.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.1.3-6 2.5.1.4 Fire Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.1.4-1 2.5.1.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.1.4-1 2.5.1.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.1.4-3 2.5.1.4.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.1.4-10 2.5.2 Pressurizer Relief Tank . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.2-1 2.5.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.2-1 2.5.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.2-3 2.5.2.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.2-3 2.5.2.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.5.2-3 2.5.2.2.3 Description of Analyses and Evaluations . . . 2.5.2-4 2.5.2.2.4 License Renewal Impact Evaluation . . . . . . . 2.5.2-5 2.5.2.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.2-6 2.5.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.2-6 2.5.3 Fission Product Control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.3.1-1 2.5.3.1 Fission Product Control Systems and Structures . . . . . . . 2.5.3.1-1 2.5.3.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.3.1-1 2.5.3.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.3.1-2 2.5.3.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.3.1-4 2.5.3.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.3.1-5 2.5.3.2 Main Condenser Evacuation System . . . . . . . . . . . . . . . . 2.5.3.2-1 2.5.3.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.3.2-1 2.5.3.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.3.2-2 2.5.3.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.3.2-4 2.5.3.3 Turbine Gland Sealing Systems . . . . . . . . . . . . . . . . . . . . 2.5.3.3-1 2.5.3.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.3.3-1 2.5.3.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.3.3-3 2.5.3.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.3.3-5 Turkey Point Units 3 and 4 EPU Licensing Report xi

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.5.4 Component Cooling and Decay Heat Removal . . . . . . . . . . . . . . . 2.5.4.1-1 2.5.4.1 Spent Fuel Pool Cooling and Cleanup System . . . . . . . . 2.5.4.1-1 2.5.4.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.4.1-1 2.5.4.1.2 Technical Evaluations . . . . . . . . . . . . . . . . . . 2.5.4.1-3 2.5.4.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.1-11 2.5.4.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.1-11 2.5.4.2 Station Service Water System . . . . . . . . . . . . . . . . . . . . . 2.5.4.2-1 2.5.4.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.4.2-1 2.5.4.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.4.2-3 2.5.4.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.2-6 2.5.4.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.2-6 2.5.4.3 Reactor Auxiliary Cooling Water Systems (Component Cooling Water System) . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.3-1 2.5.4.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.4.3-1 2.5.4.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.4.3-3 2.5.4.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.3-11 2.5.4.3.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.3-11 2.5.4.4 Ultimate Heat Sink . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.4-1 2.5.4.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.4.4-1 2.5.4.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.4.4-3 2.5.4.4.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.4-5 2.5.4.5 Auxiliary Feedwater . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.5-1 2.5.4.5.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.4.5-1 2.5.4.5.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.4.5-5 2.5.4.5.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.4.5-9 2.5.5 Balance-of-Plant Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.5.1-1 2.5.5.1 Main Steam . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.5.1-1 2.5.5.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.5.1-1 2.5.5.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.5.1-3 2.5.5.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.5.1-8 2.5.5.2 Main Condenser . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.5.2-1 2.5.5.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.5.2-1 2.5.5.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.5.2-2 2.5.5.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.5.2-4 2.5.5.3 Turbine Bypass . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.5.3-1 2.5.5.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.5.3-1 2.5.5.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.5.3-2 2.5.5.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.5.3-4 Turkey Point Units 3 and 4 EPU Licensing Report xii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.5.5.4 Condensate and Feedwater . . . . . . . . . . . . . . . . . . . . . . . 2.5.5.4-1 2.5.5.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.5.4-1 2.5.5.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.5.4-3 2.5.5.4.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.5.4-7 2.5.6 Waste Management Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.6.1-1 2.5.6.1 Gaseous Waste Management Systems . . . . . . . . . . . . . . 2.5.6.1-1 2.5.6.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.6.1-1 2.5.6.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.6.1-4 2.5.6.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.6.1-7 2.5.6.2 Liquid Waste Management Systems . . . . . . . . . . . . . . . . 2.5.6.2-1 2.5.6.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.6.2-1 2.5.6.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.6.2-3 2.5.6.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.6.2-7 2.5.6.3 Solid Waste Management Systems . . . . . . . . . . . . . . . . . 2.5.6.3-1 2.5.6.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.6.3-1 2.5.6.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.6.3-4 2.5.6.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.6.3-7 2.5.7 Additional Considerations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.7.1-1 2.5.7.1 Emergency Diesel Engine Fuel Oil Storage and Transfer System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.7.1-1 2.5.7.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.7.1-1 2.5.7.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.7.1-3 2.5.7.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.7.1-7 2.5.7.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.7.1-7 2.5.7.2 Light Load Handling System (Related to Refueling) . . . . 2.5.7.2-1 2.5.7.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.7.2-1 2.5.7.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.7.2-3 2.5.7.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.7.2-5 2.5.8 Additional Review Areas (Plant Systems) . . . . . . . . . . . . . . . . . . . 2.5.8.1-1 2.5.8.1 Circulating Water System . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.8.1-1 2.5.8.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.5.8.1-1 2.5.8.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.5.8.1-1 2.5.8.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.8.1-3 2.5.8.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5.8.1-3 2.6 Containment Review Considerations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.1-1 2.6.1 Primary Containment Functional Design . . . . . . . . . . . . . . . . . . . . 2.6.1-1 2.6.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.1-1 2.6.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.1-3 Turkey Point Units 3 and 4 EPU Licensing Report xiii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.6.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.1-3 2.6.1.2.2 Containment Response to Loss-of-Coolant Accident . . . . . . . . . . . . . . . 2.6.1-7 2.6.1.2.3 Containment Response to Main Steam Line Break . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.1-11 2.6.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.1-13 2.6.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.1-13 2.6.2 Subcompartment Analyses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.2-1 2.6.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.2-1 2.6.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.2-3 2.6.2.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.2-3 2.6.2.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.6.2-3 2.6.2.2.3 Description of Analyses and Evaluations . . . 2.6.2-4 2.6.2.2.4 License Renewal Impact Evaluation . . . . . . . 2.6.2-5 2.6.2.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.2-5 2.6.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.2-5 2.6.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.2-5 2.6.3 Mass and Energy Release . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.3.1-1 2.6.3.1 Mass and Energy Release Analysis for Postulated Loss-of-Coolant Accident . . . . . . . . . . . . . . . . 2.6.3.1-1 2.6.3.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.6.3.1-1 2.6.3.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.6.3.1-2 2.6.3.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.3.1-11 2.6.3.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.3.1-12 2.6.3.2 Mass and Energy Release Analysis for Secondary System Pipe Ruptures . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.3.2-1 2.6.3.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.6.3.2-1 2.6.3.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.6.3.2-2 2.6.3.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.3.2-8 2.6.3.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.3.2-8 2.6.4 Combustible Gas Control in Containment . . . . . . . . . . . . . . . . . . . 2.6.4-1 2.6.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.4-1 2.6.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.4-3 2.6.4.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.4-3 2.6.4.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.6.4-3 2.6.4.2.3 Description of Analyses and Evaluations . . . 2.6.4-3 Turkey Point Units 3 and 4 EPU Licensing Report xiv

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.6.4.2.4 License Renewal Impact Evaluation . . . . . . . 2.6.4-3 2.6.4.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.4-3 2.6.4.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.4-4 2.6.4.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.4-4 2.6.5 Containment Heat Removal . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.5-1 2.6.5.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.5-1 2.6.5.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.5-2 2.6.5.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.5-2 2.6.5.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.6.5-3 2.6.5.2.3 Description of Analyses and Evaluations . . . 2.6.5-4 2.6.5.2.4 License Renewal Impact Evaluation . . . . . . . 2.6.5-4 2.6.5.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.5-5 2.6.5.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.5-5 2.6.6 Pressure Analysis for ECCS Performance Capability . . . . . . . . . . 2.6.6-1 2.6.6.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.6-1 2.6.6.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.6-1 2.6.6.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.6-2 2.6.6.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.6.6-2 2.6.6.2.3 Description of Analyses and Evaluations . . . 2.6.6-2 2.6.6.2.4 License Renewal Impact Evaluation . . . . . . . 2.6.6-2 2.6.6.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.6-3 2.6.6.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.6-3 2.6.6.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6.6-3 2.7 Habitability, Filtration, and Ventilation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.1-1 2.7.1 Control Room Habitability System . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.1-1 2.7.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.1-1 2.7.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.1-6 2.7.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.1-6 2.7.1.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.7.1-7 2.7.1.2.3 Description of Analyses and Evaluations . . . 2.7.1-7 2.7.1.2.4 License Renewal Impact Evaluation . . . . . . . 2.7.1-9 2.7.1.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.1-9 2.7.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.1-9 2.7.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.1-10 Turkey Point Units 3 and 4 EPU Licensing Report xv

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.7.2 Engineered Safety Feature Atmosphere Cleanup . . . . . . . . . . . . . 2.7.2-1 2.7.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.2-1 2.7.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.2-4 2.7.2.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.2-4 2.7.2.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.7.2-5 2.7.2.2.3 Description of Analyses and Evaluations . . . 2.7.2-5 2.7.2.2.4 License Renewal Impact Evaluation . . . . . . . 2.7.2-6 2.7.2.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.2-7 2.7.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.2-7 2.7.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.2-7 2.7.3 Control Room Area Ventilation System . . . . . . . . . . . . . . . . . . . . . 2.7.3-1 2.7.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.3-1 2.7.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.3-5 2.7.3.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.3-5 2.7.3.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.7.3-5 2.7.3.2.3 Description of Analyses and Evaluations . . . 2.7.3-5 2.7.3.2.4 License Renewal Impact Evaluation . . . . . . . 2.7.3-5 2.7.3.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.3-5 2.7.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.3-5 2.7.3.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.3-6 2.7.4 Spent Fuel Pool Area Ventilation System . . . . . . . . . . . . . . . . . . . . 2.7.4-1 2.7.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.4-1 2.7.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.4-3 2.7.4.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.4-3 2.7.4.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.7.4-3 2.7.4.2.3 Description of Analyses and Evaluations . . . 2.7.4-3 2.7.4.2.4 License Renewal Impact Evaluation . . . . . . . 2.7.4-5 2.7.4.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.4-5 2.7.4.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.4-5 2.7.5 Auxiliary and Radwaste Area and Turbine Areas Ventilation Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.5-1 2.7.5.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.5-1 2.7.5.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.5-3 2.7.5.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.5-3 Turkey Point Units 3 and 4 EPU Licensing Report xvi

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.7.5.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.7.5-4 2.7.5.2.3 Description of Analyses and Evaluations . . . 2.7.5-4 2.7.5.2.4 License Renewal Impact Evaluation . . . . . . . 2.7.5-5 2.7.5.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.5-5 2.7.5.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.5-5 2.7.6 Engineered Safety Feature Ventilation System . . . . . . . . . . . . . . . 2.7.6-1 2.7.6.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.6-1 2.7.6.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.6-6 2.7.6.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.6-6 2.7.6.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.7.6-6 2.7.6.2.3 Description of Analyses and Evaluations . . . 2.7.6-6 2.7.6.2.4 License Renewal Impact Evaluation . . . . . . . 2.7.6-8 2.7.6.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.6-8 2.7.6.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.6-8 2.7.7 Other Ventilation Systems (Containment) . . . . . . . . . . . . . . . . . . . 2.7.7-1 2.7.7.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.7-1 2.7.7.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.7-4 2.7.7.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.7-4 2.7.7.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.7.7-5 2.7.7.2.3 Description of Analyses and Evaluations . . . 2.7.7-5 2.7.7.2.4 License Renewal Impact Evaluation . . . . . . . 2.7.7-6 2.7.7.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.7-7 2.7.7.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.7-7 2.7.7.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7.7-7 2.8 Reactor Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.1-1 2.8.1 Fuel System Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.1-1 2.8.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.1-1 2.8.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.1-4 2.8.1.2.1 Fuel System Design Features . . . . . . . . . . . . 2.8.1-4 2.8.1.2.2 Mechanical Compatibility and Performance . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.1-4 2.8.1.2.3 Seismic/LOCA . . . . . . . . . . . . . . . . . . . . . . . . 2.8.1-6 2.8.1.2.4 Fuel Rod Performance . . . . . . . . . . . . . . . . . 2.8.1-9 2.8.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.1-16 2.8.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.1-16 Turkey Point Units 3 and 4 EPU Licensing Report xvii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.8.2 Nuclear Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.2-1 2.8.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.2-1 2.8.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.2-5 2.8.2.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.2-5 2.8.2.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.8.2-5 2.8.2.2.3 Description of Analyses and Evaluations . . . 2.8.2-6 2.8.2.2.4 License Renewal Impact Evaluation . . . . . . . 2.8.2-7 2.8.2.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.2-7 2.8.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.2-7 2.8.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.2-8 2.8.3 Thermal and Hydraulic Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.3-1 2.8.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.3-1 2.8.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.3-3 2.8.3.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.3-3 2.8.3.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.8.3-3 2.8.3.2.3 Description of Analyses and Evaluations . . . 2.8.3-5 2.8.3.2.4 License Renewal Impact Evaluation . . . . . . . 2.8.3-8 2.8.3.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.3-8 2.8.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.3-8 2.8.3.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.3-9 2.8.4 Emergency Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.4.1-1 2.8.4.1 Functional Design of Control Rod Drive System . . . . . . . 2.8.4.1-1 2.8.4.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.4.1-1 2.8.4.1.2 Technical Evaluation - Control Rod Drive System . . . . . . . . . . . . . . . . . . . . . 2.8.4.1-5 2.8.4.1.3 Technical Evaluation - CRDM Cooling System . . . . . . . . . . . . . . . . . . . . . . . 2.8.4.1-6 2.8.4.1.4 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.4.1-9 2.8.4.2 Overpressure Protection During Power Operation . . . . . . 2.8.4.2-1 2.8.4.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.4.2-1 2.8.4.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.8.4.2-3 2.8.4.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.4.2-5 2.8.4.3 Overpressure Protection During Low Temperature Operation . . . . . . . . . . . . . . . . . . . . . . . 2.8.4.3-1 2.8.4.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.4.3-1 2.8.4.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.8.4.3-3 Turkey Point Units 3 and 4 EPU Licensing Report xviii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.8.4.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.4.3-6 2.8.4.3.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.4.3-6 2.8.4.4 Residual Heat Removal System . . . . . . . . . . . . . . . . . . . 2.8.4.4-1 2.8.4.4.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.4.4-1 2.8.4.4.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.8.4.4-3 2.8.4.4.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.4.4-7 2.8.5 Accident and Transient Analyses . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.5.0-1 2.8.5.0 Non-LOCA Analyses Introduction . . . . . . . . . . . . . . . . . . 2.8.5.0-1 2.8.5.0.1 Fuel Design Mechanical Features . . . . . . . . . 2.8.5.0-1 2.8.5.0.2 Peaking Factors, Kinetics Parameters . . . . . 2.8.5.0-1 2.8.5.0.3 EPU Program Features . . . . . . . . . . . . . . . . . 2.8.5.0-2 2.8.5.0.4 Other Major Analysis Inputs . . . . . . . . . . . . . 2.8.5.0-3 2.8.5.0.5 Overtemperature and Overpower T Reactor Trip Setpoints . . . . . . . . . . . . . . . . . 2.8.5.0-4 2.8.5.0.6 RPS and ESFAS Functions Assumed in Analyses . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.5.0-4 2.8.5.0.7 RCCA Insertion Characteristics . . . . . . . . . . . 2.8.5.0-5 2.8.5.0.8 Reactivity Coefficients . . . . . . . . . . . . . . . . . . 2.8.5.0-5 2.8.5.0.9 Computer Codes Used . . . . . . . . . . . . . . . . . 2.8.5.0-5 2.8.5.0.10 Classification of Events . . . . . . . . . . . . . . . . . 2.8.5.0-8 2.8.5.0.11 Events Evaluated or Analyzed . . . . . . . . . . . 2.8.5.0-9 2.8.5.0.12 Analysis Methodology . . . . . . . . . . . . . . . . . . 2.8.5.0-9 2.8.5.0.13 Operator Actions . . . . . . . . . . . . . . . . . . . . . . 2.8.5.0-12 2.8.5.0.14 Notable Safety Analysis Input Changes . . . . 2.8.5.0-12 2.8.5.0.15 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.5.0-12 2.8.5.1 Increase in Heat Removal by the Secondary System . . . 2.8.5.1.1-1 2.8.5.1.1 Reduction In Feedwater Enthalpy, Increase In Feedwater Flow, Increase in Steam Flow, and Inadvertent Opening of a Steam Generator Relief or Safety Valve . . . . 2.8.5.1.1-1 2.8.5.1.2 Steam System Piping Failures Inside and Outside Containment . . . . . . . . . . . . . . . 2.8.5.1.2-1 2.8.5.2 Decrease in Heat Removal By the Secondary System . . 2.8.5.2.1-1 2.8.5.2.1 Loss of External Load, Turbine Trip, Loss of Condenser Vacuum, and Steam Pressure Regulator Failure . . . . . . . . . . . . . . 2.8.5.2.1-1 2.8.5.2.2 Loss of Non-Emergency AC Power to the Station Auxiliaries . . . . . . . . . . . . . . . . . . 2.8.5.2.2-1 2.8.5.2.3 Loss of Normal Feedwater Flow . . . . . . . . . . 2.8.5.2.3-1 Turkey Point Units 3 and 4 EPU Licensing Report xix

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.8.5.2.4 Feedwater System Pipe Breaks Inside and Outside Containment . . . . . . . . . . . . . . . 2.8.5.2.4-1 2.8.5.3 Decrease in Reactor Coolant System Flow . . . . . . . . . . . 2.8.5.3.1-1 2.8.5.3.1 Loss of Forced Reactor Coolant Flow . . . . . . 2.8.5.3.1-1 2.8.5.3.2 Reactor Coolant Pump Rotor Seizure and Reactor Coolant Pump Shaft Break . . . . . . . 2.8.5.3.2-1 2.8.5.4 Reactivity and Power Distribution Anomalies . . . . . . . . . . 2.8.5.4.1-1 2.8.5.4.1 Uncontrolled Rod Cluster Control Assembly Withdrawal from a Subcritical or Low-Power Startup Condition . . . . . . . . . . . . 2.8.5.4.1-1 2.8.5.4.2 Uncontrolled Rod Cluster Control Assembly Withdrawal at Power . . . . . . . . . . . . . . . . . . . 2.8.5.4.2-1 2.8.5.4.3 Control Rod Misoperation . . . . . . . . . . . . . . . 2.8.5.4.3-1 2.8.5.4.4 Startup of an Inactive Loop at an Incorrect Temperature . . . . . . . . . . . . . . . . . . 2.8.5.4.4-1 2.8.5.4.5 Chemical and Volume Control System Malfunction . . . . . . . . . . . . . . . . . . . . 2.8.5.4.5-1 2.8.5.4.6 Spectrum of Rod Ejection Accidents . . . . . . . 2.8.5.4.6-1 2.8.5.5 Inadvertent Operation of Emergency Core Cooling System and Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory . . . 2.8.5.5-1 2.8.5.5.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.5.5-1 2.8.5.5.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.8.5.5-3 2.8.5.5.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.5.5-6 2.8.5.6 Decrease in Reactor Coolant Inventory . . . . . . . . . . . . . . 2.8.5.6.1-1 2.8.5.6.1 Inadvertent Opening of Pressurizer Pressure Relief Valve . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.5.6.1-1 2.8.5.6.2 Steam Generator Tube Rupture . . . . . . . . . . 2.8.5.6.2-1 2.8.5.6.3 Emergency Core Cooling System and Loss-of-Coolant Accidents . . . . . . . . . . . 2.8.5.6.3-1 2.8.5.7 Anticipated Transients Without Scram . . . . . . . . . . . . . . . 2.8.5.7-1 2.8.5.7.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.5.7-1 2.8.5.7.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.8.5.7-3 2.8.5.7.3 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.5.7-5 2.8.5.7.4 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.5.7-5 2.8.5.7.5 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.5.7-5 2.8.6 Fuel Storage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.6.1-1 2.8.6.1 New Fuel Storage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.6.1-1 2.8.6.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.6.1-1 Turkey Point Units 3 and 4 EPU Licensing Report xx

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.8.6.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.8.6.1-2 2.8.6.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.6.1-3 2.8.6.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.6.1-3 2.8.6.2 Spent Fuel Storage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.6.2-1 2.8.6.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.6.2-1 2.8.6.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.8.6.2-4 2.8.6.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.6.2-11 2.8.6.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.6.2-11 2.8.7 Additional Reactor Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.7.2-1 2.8.7.1 Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.7.2-1 2.8.7.2 Natural Circulation Cooldown . . . . . . . . . . . . . . . . . . . . . . 2.8.7.2-1 2.8.7.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.7.2-1 2.8.7.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.8.7.2-3 2.8.7.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.7.2-5 2.8.7.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.7.2-6 2.8.7.3 Loss of Residual Heat Removal at Reduced Inventory . . 2.8.7.3-1 2.8.7.3.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . 2.8.7.3-1 2.8.7.3.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . 2.8.7.3-2 2.8.7.3.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.7.3-4 2.8.7.3.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8.7.3-4 2.9 Source Terms and Radiological Consequences Analyses . . . . . . . . . . . . . 2.9.1-1 2.9.1 Source Terms for Radwaste Systems Analyses . . . . . . . . . . . . . . . 2.9.1-1 2.9.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.1-1 2.9.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.1-3 2.9.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.1-3 2.9.1.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.9.1-3 2.9.1.2.3 Description of Analyses and Evaluations . . . 2.9.1-4 2.9.1.2.4 License Renewal Impact Evaluation . . . . . . . 2.9.1-5 2.9.1.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.1-5 2.9.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.1-5 2.9.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.1-6 2.9.2 Radiological Consequences Analyses Using Alternative Source Terms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.2-1 2.9.2.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.2-1 2.9.2.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.2-4 2.9.2.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.2-4 Turkey Point Units 3 and 4 EPU Licensing Report xxi

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.9.2.2.2 Input Parameters, Assumptions, and Acceptance Criteria . . . . . . . . . . . . . . . . . . . . 2.9.2-5 2.9.2.2.3 Description of Analyses and Evaluations . . . 2.9.2-5 2.9.2.2.4 License Renewal Impact Evaluation . . . . . . . 2.9.2-5 2.9.2.2.5 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.2-5 2.9.2.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.2-5 2.9.2.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9.2-5 2.10 Health Physics . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.10.1-1 2.10.1 Occupational and Public Radiation Doses . . . . . . . . . . . . . . . . . . . 2.10.1-1 2.10.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.10.1-1 2.10.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.10.1-4 2.10.1.2.1 Normal Operation Radiation Levels and Shielding Adequacy . . . . . . . . . . . . . . . . 2.10.1-4 2.10.1.2.2 Radiation Monitoring Setpoints . . . . . . . . . . . 2.10.1-11 2.10.1.2.3 Post Accident Vital Area Accessibility . . . . . . 2.10.1-13 2.10.1.2.4 Normal Operation Radwaste Effluents and Annual Dose to the Public . . . . . . . . . . . 2.10.1-15 2.10.1.2.5 Ensuring Occupational and Public Radiation Exposures Are ALARA . . . . . . . . . 2.10.1-20 2.10.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.10.1-21 2.10.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.10.1-22 2.11 Human Performance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.11.1-1 2.11.1 Human Factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.11.1-1 2.11.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.11.1-1 2.11.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.11.1-3 2.11.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.11.1-3 2.11.1.2.2 Description of Analysis and Evaluations . . . . 2.11.1-3 2.11.1.2.3 License Renewal Impact Evaluation . . . . . . . 2.11.1-8 2.11.1.2.4 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.11.1-8 2.11.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.11.1-9 2.12 Power Ascension and Testing Plan . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.12-1 2.12.1 Approach to EPU Power Level and Test Plan . . . . . . . . . . . . . . . . 2.12-1 2.12.1.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.12-1 2.12.1.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.12-2 2.12.1.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . 2.12-2 2.12.1.2.2 Background . . . . . . . . . . . . . . . . . . . . . . . . . . 2.12-2 2.12.1.2.3 Power Ascension Test Plan . . . . . . . . . . . . . 2.12-4 Turkey Point Units 3 and 4 EPU Licensing Report xxii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.12.1.2.4 Comparison of EPU Test Program to the Initial Plant Test Program . . . . . . . . . . . . . . . . . . . . 2.12-9 2.12.1.2.5 Post Modification Testing Requirements . . . . 2.12-9 2.12.1.2.6 Description of Analyses and Evaluations . . . 2.12-9 2.12.1.2.7 License Renewal Impact Evaluation . . . . . . . 2.12-16 2.12.1.2.8 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.12-16 2.12.1.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.12-16 2.12.1.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.12-17 2.13 Risk Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-1 2.13.1 Regulatory Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-1 2.13.2 Technical Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-2 2.13.2.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-2 2.13.2.2 Risk Perspective on the Design of Turkey Point Units 3 and 4 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-3 2.13.2.3 Turkey Point Units 3 and 4 PRA Model . . . . . . . . . . . . . . 2.13-4 2.13.2.3.1 Internal Events . . . . . . . . . . . . . . . . . . . . . . . 2.13-6 2.13.2.3.2 Steam Generator Tube Rupture (SGTR) . . . 2.13-8 2.13.2.3.3 Interfacing System LOCA (ISLOCA) . . . . . . . 2.13-8 2.13.2.3.4 Transients . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-8 2.13.2.3.5 Internal Flooding . . . . . . . . . . . . . . . . . . . . . . 2.13-10 2.13.2.3.6 Turbine Missile Generation . . . . . . . . . . . . . . 2.13-11 2.13.2.4 External Events and Shutdown Risk . . . . . . . . . . . . . . . . 2.13-11 2.13.2.4.1 Seismic Events . . . . . . . . . . . . . . . . . . . . . . . 2.13-11 2.13.2.4.2 Fire . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-13 2.13.2.4.3 High Winds, Floods, and Other External Events . . . . . . . . . . . . . . . . . . 2.13-13 2.13.2.4.4 Other Miscellaneous Challenges . . . . . . . . . 2.13-15 2.13.2.5 Shutdown Operations Risk . . . . . . . . . . . . . . . . . . . . . . . . 2.13-15 2.13.2.6 PRA Model Attributes . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-16 2.13.2.6.1 Function/System Level Success Criteria . . . . 2.13-16 2.13.2.6.2 Operator Actions . . . . . . . . . . . . . . . . . . . . . . 2.13-20 2.13.2.6.3 Component and System Reliability . . . . . . . . 2.13-21 2.13.2.7 Level 2 Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-22 2.13.2.8 IPE/IPEEE Vulnerabilities . . . . . . . . . . . . . . . . . . . . . . . . 2.13-22 2.13.2.9 EPU Risk Analysis and Sensitivity Studies . . . . . . . . . . . 2.13-22 2.13.2.9.1 Comparison of Current and EPU Plant Risks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-22 2.13.2.9.2 Sensitivity Studies . . . . . . . . . . . . . . . . . . . . . 2.13-24 Turkey Point Units 3 and 4 EPU Licensing Report xxiii

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Contents 2.13.2.9.3 Technical Summary . . . . . . . . . . . . . . . . . . . 2.13-28 2.13.2.10 Quality of PRA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-29 2.13.2.10.1 Model Peer Review . . . . . . . . . . . . . . . . . . . . 2.13-29 2.13.2.10.2 Review Against NEI A and B Findings . . . . . 2.13-29 2.13.2.10.3 PRA Maintenance and Update . . . . . . . . . . . 2.13-41 2.13.2.10.4 Other Relevant Open Items . . . . . . . . . . . . . 2.13-42 2.13.2.11 Software . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-42 2.13.2.11.1 Thermal Hydraulic Software . . . . . . . . . . . . . 2.13-42 2.13.2.11.2 CAFTA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-42 2.13.2.11.3 HRA Calculator . . . . . . . . . . . . . . . . . . . . . . . 2.13-42 2.13.2.12 Technical Evaluation Conclusion . . . . . . . . . . . . . . . . . . . 2.13-43 2.13.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-43 2.13.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.13-44 Turkey Point Units 3 and 4 EPU Licensing Report xxiv

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 2.5.4.4 Ultimate Heat Sink 2.5.4.4.1 Regulatory Evaluation The ultimate heat sink (UHS) is the source of cooling water provided to dissipate reactor decay heat and essential cooling system heat loads after a normal reactor shutdown or a shutdown following an accident. FPLs review focused on the impact that the proposed EPU has on the decay heat removal capability of the UHS. Additionally, FPLs review included evaluation of the design-basis UHS temperature limit determination to confirm that post-licensing data trends (e.g.,

air and water temperatures, humidity, wind speed, water volume) do not establish more severe conditions than previously assumed.

The NRCs acceptance criteria for the UHS are based on:

  • GDC-5, insofar as it requires that SSCs important to safety not be shared among nuclear power units unless it can be shown that sharing will not significantly impair their ability to perform their safety functions; and
  • GDC-44, insofar as it requires that a system with the capability to transfer heat loads from safety-related SSCs to a heat sink under both normal operating and accident conditions be provided.

Specific review criteria are contained in SRP Section 9.2.5 and other guidance provided in Matrix 5 of RS-001.

Current Licensing Basis As noted in PTN Updated Final Safety Analysis Report (UFSAR), Section 1.3, the General Design Criteria (GDC) used during licensing of the Turkey Point Nuclear Plant predate those provided today in 10 CFR 50, Appendix A. The PTN GDCs were developed based on the 1967 Atomic Energy Commission Proposed General Design Criteria and are addressed in various sections of the UFSAR.

The PTN GDC applicable to the UHS and within the scope of the stated regulatory evaluation is as follows:

PTN GDC-4, Sharing of Systems: Reactor facilities may share systems or components if it can be shown that such sharing will not result in undue risk to the health and safety of the public.

(GDC-5)

The PTN systems provided to transfer heat from safety-related components to the UHS, i.e.,

closed cooling water canals, are the Component Cooling Water (CCW) System and the Intake Cooling Water (ICW) System. The site occupies an area approximately 2 miles wide by 5 miles long and includes 168 miles of earthen canals covering approximately 6100 acres (4370 acres of water surface). The average canal depth is 2.8 feet. The total water volume in the cooling canals is approximately 12,300 acre-feet (4 billion gallons). The canals receive heated condenser water at one end and supply cooled water at the other end for reuse. The discharge canal receives heated effluent from the plant and distributes the flow into 32 feeder canals. Water in the feeder canals flows south and discharges to a single collecting canal that distributes water to six return canals. Water in the return canals flows north to the plant intake. The entire water circuit, plant Turkey Point Units 3 and 4 EPU Licensing Report 2.5.4.4-1 Ultimate Heat Sink

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 discharge back to plant intake, is 13.2 miles and takes approximately 44 hours1.833 days <br />0.262 weeks <br />0.0603 months <br />. The temperature rise across the plant, from intake to discharge, averages 15-30°F depending upon the unit, unit load, and various other factors. The average intake temperature is 2.5°F above the average ambient air temperature. The closed cooling water canal system is a shared heat sink that services Turkey Point Units 1, 2, 3 & 4.

The CCW System is the heat sink for the Residual Heat Removal (RHR) System, the Chemical and Volume Control System (CVCS), the Spent Fuel Pit Cooling System and various Reactor Coolant System (RCS) components. A separate CCW System is provided for each nuclear unit.

However, the CCW System provides cross-tie connections for CCW-supplied components that could serve both Turkey Point Units 3 and 4. These components include the safety injection pumps. These cross-tie connections are subject to design criteria involving minimum capacity requirements, unit intermix prohibitions, single active failure tolerance and passive failure isolation capability.

The ICW System provides the cooling water to the safety-related CCW Heat Exchangers as well as to the non-safety-related Turbine Plant Cooling Water (TPCW) Heat Exchangers. A separate ICW System is provided for each nuclear unit.

Although there is no specific PTN GDC analogous to GDC-44 on Cooling Water, the GDC requirements are addressed in the plant design. The Auxiliary Feedwater (AFW) System supplies cooling water to the steam generators at times when the normal feedwater systems are not available. The CCW and ICW Systems are discussed above. These cooling water systems transfer heat from safety-related SSCs to either the ultimate heat sink (cooling canals) in the cases of CCW and ICW Systems or to the atmosphere in the case of the AFW System The CCW system is designed with sufficient redundancy such that a single active failure will not prevent the system from accomplishing its support function of cooling safety related equipment.

The intake cooling water system provides sufficient redundancy so that at least one intake cooling water pump will continue to operate to handle heat loads from design basis accidents following a postulated single active failure. The AFW System is designed with sufficient mechanical and electrical redundancy such that the single failure of an active component, either in the AFW System or in a supporting system, can be accommodated without loss of the overall AFW System safety-related functions.

PTNs UHS and associated structures were evaluated for plant license renewal. System and system components, materials of construction, operating histories and programs used to manage aging effects are documented in NUREG-1759, Safety Evaluation Report (SER) Related to the License Renewal of the Turkey Point Nuclear Plant, Units 3 and 4, dated April 2002 and supplemented in May 2002. See SER Sections 2.4.2.4, 2.4.2.6, and 2.4.2.11. Although the earthen canals were identified as within the scope of license renewal, no aging management program was required while the associated intake and discharge structures cited the Systems and Structures Monitoring Program as appropriate to manage their identified aging effects.

Turkey Point Units 3 and 4 EPU Licensing Report 2.5.4.4-2 Ultimate Heat Sink

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 2.5.4.4.2 Technical Evaluation 2.5.4.4.2.1 Introduction The UHS at PTN is a closed-loop cooling canal system that accepts the rejected heat loads from the plants at one end (discharge) and returns cooled water at the opposite (intake) end. The closed-loop cooling water canal system is a shared heat sink that services Turkey Point Fossil Units 1 & 2, and Nuclear Units 3 & 4. The total volume of water in the cooling canals is approximately 12,300 acre-feet (4 billion gallons).

The ultimate heat sink provides water to the Intake Cooling Water (ICW) System via the Intake Structure. The Intake Structure is Seismic Class I to the extent that water is always available to the ICW System. The Intake Cooling Water System provides cooling water for heat removal from safety-related heat exchangers, including the Component Cooling Water heat exchangers which cool the Residual Heat Removal System. Refer to LR Section 2.5.4.2, Station Service Water System, for a description of the cooled components and the water users supplied by the Intake Cooling Water System.

The maximum cooling canal water temperature was assumed to vary seasonally throughout the year for cooldown analyses. Temperatures were adjusted from 92°F (spring/fall) to 97°F (summer) based on the season. See LR Section 2.8.4.4, Residual Heat Removal System which describes the cooldown scenarios using the Ultimate Heat Sink for heat rejection.

A maximum cooling water temperature of 100°F is used for the safety analyses which rely on the ultimate heat sink for heat removal. See LR Section 2.6.1, Primary Containment Functional Design which describes the postulated accident scenarios using the ultimate heat sink for heat rejection.

The closed-loop cooling canal is also used by the non-safety related Circulating Water System to provide cooling water for heat removal from the turbine cycle during normal plant power operations. Refer to LR Section 2.5.8.1, Circulating Water System.

2.5.4.4.2.2 Input Parameters, Assumptions, and Acceptance Criteria Assumptions The following Ultimate Heat Sink temperatures were assumed in RHR Cooldown and postulated accident analyses.

Ultimate Heat Sink Temperatures Used in Analyses Temperature (°F) Time Interval Type of Analysis Used In 92° Spring/Fall RHR Cooldown 97° Summer RHR Cooldown 100° Year-Round Accident Turkey Point Units 3 and 4 EPU Licensing Report 2.5.4.4-3 Ultimate Heat Sink

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 Acceptance Criteria The ultimate heat sink shall remove the Design Basis Accident heat load with a maximum temperature of 100°F.

2.5.4.4.2.3 Description of Analyses and Evaluations The Ultimate Heat Sink was evaluated to ensure it is capable of performing its intended function of a reliable water supply and heat removal capacity for normal and accident conditions following EPU.

The Ultimate Heat Sink was evaluated for the circulating water discharge temperatures during EPU normal operation and initial normal cooldown. These effects were evaluated against the Florida Department of Environmental Protection National Pollutant Discharge Elimination System (NPDES) permit (FL0001562) limits for PTN in LR Section 2.5.8.1, Circulating Water System.

Additional evaluations related to the Ultimate Heat Sink are addressed in the following Licensing Report Sections:

  • Intake Cooling Water discharge temperatures, heat loads, and flow rates to the cooling canal system - LR Section 2.5.4.2, Station Service Water System.
  • Post-accident heat removal requirements - LR Section 2.6.1, Primary Containment Functional Design.

2.5.4.4.2.4 License Renewal Impact Evaluation Portions of the Ultimate Heat Sink are within the scope of License Renewal. EPU activities do not add any new components nor do they introduce any new functions for existing components that would change the license renewal system evaluation boundaries. The changes associated with the operation of the Ultimate Heat Sink at EPU conditions do not add any new or previously unevaluated materials to the system. System component internal and external environments remain within the parameters previously evaluated. Thus, no new aging effects requiring management are identified.

2.5.4.4.2.5 Results The Ultimate Heat Sink continues to meet its licensing, design, and performance capabilities at EPU conditions as evidenced by the evaluation results below.

General Design Criteria The evaluation of the Ultimate Heat Sink capabilities at EPU conditions demonstrates that PTN will continue to meet the current licensing basis with respect to the requirements of PTN GDC-4.

There will be no increase in the amount of water withdrawn as a result of the EPU project. The Ultimate Heat Sink contains sufficient volume to provide cooling water to both units under all normal, abnormal, and accident conditions. Therefore, the Ultimate Heat Sink continues to meet Turkey Point Units 3 and 4 EPU Licensing Report 2.5.4.4-4 Ultimate Heat Sink

Turkey Point Units 3 and 4 L-2010-113 Docket Nos. 50-250 and 50-251 Attachment 4 the design requirements with respect to sharing of systems and components in accordance with PTN licensing basis and PTN GDC-4.

Water Supply and Heat Removal Requirements The Ultimate Heat Sink will continue to provide the required water supply and heat sink capacity at EPU conditions; the Intake Cooling Water flow requirements for cooling of safety-related heat exchangers either do not change or decrease slightly. The maximum increase in cooled water temperature leaving the cooling canal system to return to the units is approximately 0.9°F, from 91.9°F to 92.8°F. The analysis results discussed in LR Section 2.8.4.4, Residual Heat Removal System and LR Section 2.6.1, Primary Containment Functional Design confirm that the Ultimate Heat Sink will continue to provide sufficient water supply and heat removal for cooldown and to mitigate the postulated accident scenarios.

The intake cooling water returned to the Ultimate Heat Sink from cooled components experiences a small temperature change at normal operating, cooldown, and accident conditions due to the EPU. During normal operation and normal cooldown, the intake cooling water discharge temperatures increase slightly and the time to cooldown the plant is extended. During accident conditions, the intake cooling water discharge temperatures continue to be bound by existing analyses and the system design parameters. The circulating water flow rates remain within the existing design rating of the pumps. The circulating water discharge temperature is expected to increase by approximately 4°F at EPU conditions. The effect of intake cooling water discharge temperature changes during normal operation, normal cooldown, and accident conditions at EPU is minimal due to the mixing of the intake cooling water with circulating water, screen wash, and storm drain flows at the Discharge Structure before the effluent is discharged to the cooling canals. The intake cooling water flow rate is insignificant when compared to the flow rate of the circulating water through the condenser.

The discharge of circulating water is governed by the Florida NPDES permit. As discussed in LR Section 2.5.8.1, Circulating Water System. The higher circulating water temperature during normal plant power generation has no impact on the current NPDES permit which does not limit the maximum discharge temperature, differential temperature across the condenser, or total discharge heat.

2.5.4.4.3 Conclusion FPL has assessed the effects of the proposed EPU on the UHS safety function, including the validation of the design-basis UHS temperature limit based on post-licensing data. Based on this information, FPL concludes that the proposed EPU will not compromise the design-basis safety function of the UHS, and that the UHS will continue to satisfy the requirements of the plants current licensing basis with regard to PTN GDC-4 following implementation of the proposed EPU.

Therefore, FPL finds the proposed EPU acceptable with respect to the UHS.

Turkey Point Units 3 and 4 EPU Licensing Report 2.5.4.4-5 Ultimate Heat Sink