Text

Submittal of Fifth Ten-Year Inservice Inspection Interval ISI Program Plan, Revision 0
	ML18122A213
Person / Time
Site:	Saint Lucie
Issue date:	05/02/2018
From:	Snyder M; Florida Power & Light Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-2018-110
	Download: ML18122A213 (74)
	v • d • e

MAY 0 2 ztJ18 L-2018-110 10 CFR 50.4 10CFR SO.SSa U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit 1 Docket No. 50-335 Fifth Ten-Year Inservice Inspection Interval lSI Progratn Plan - Revision 0 The fifth 10-year inservice inspection (lSI) interval for St. Lucie Unit 1 began on February 11, 2018, and ends on February 10, 2028. The attached outlines the lSI Program Plan for St. Lucie Unit 1. The lSI Program Plan is based on the requirements of the 2007 Edition of ASME Section XI with Addenda through 2008 as modified *by 10 CFR SO.SSa.

Attached is one copy of the Fifth Interval lSI Program Plan.

Please contact Michael Snyder, Licensing J\!Ianager at (772) 467-7036 if there are any questions about this subtnittal.

Very truly yours,

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Michael J. Snyder Licensing Manager St. Lucie Nuclear Plant MJS/I<WF th Interval-ISI-PSL-1-Progratn Plan Rev. 0- 73 pages cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957

NextEra Energy Nuclear Engineering Qepartment Fleet Programs Engineering Group Inspection Section 15430 Endeavor Drive Jupiter, Florida 33478 Fifth I nservice Inspection Interval Program Plan For St. Lucie Nuclear Power Plant Unit 1 St. Lucie Nuclear Power Plant 6501 South Highway A 1A Jensen Beachl Florida 34957 Commercial Service Date: December 21 , 19 76 NRC Docket Number: 50-335 Document Number: 5th lntervai-ISI-PSL-1-Program Plan, Rev. 0 Prepared by:

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Record of Revision Affected Revision Description of Changes Pages/Sections 0 All Initial issue (EC 290622)

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Table of Contents Cover Page .......................................................................................................................................1 Record of Revision ........................................................................................................................... 2 Table of Contents............................................................................................................................. 3 Abbreviations ................................................................................................................................... 6 Abstract 7 1.0 Introduction .......................................................................................................................... 8 1.1 ISI Program Development ......................................................................................... 8 1.2 Other ISI Programs ................................................................................................... 8 1.2.1 Other ISI Programs ....................................................................................... 8 1.2.2 Steam Generator (SG) Eddy Current (ET) Program ...................................... 8 1.2.3 Snubber Program .......................................................................................... 8 1.2.4 Pressure Testing Program ............................................................................. 8 1.2.5 Repair and Replacement Program ................................................................ 8 1.2.6 IWE Containment Inservice Inspection Program (IWE).................................. 8 1.3 Construction Permit .................................................................................................. 9 1.4 Commercial Service Date ......................................................................................... 9 1.5 Background............................................................................................................... 9 1.5.1 Preservice Examination ................................................................................. 9 1.5.2 First Inspection Interval ................................................................................. 9 1.5.3 Second Inservice Inspection Interval ............................................................. 9 1.5.4 Third Inservice Inspection Interval ................................................................. 9 1.5.5 Fourth Inservice Inspection Interval ............................................................. 10 1.5.5 FifthInservice Inspection Interval ................................................................. 10 1.6 Applicable Editions and Addenda to Section XI ....................................................... 10 1.6.1 Code of Federal Regulations Conditions .................................................... 10 1.7 System Classification .............................................................................................. 13 1.7.1 Systems Classifications ............................................................................... 13 1.7.2 Optional Construction .................................................................................. 13 1.7.3 Containment Penetrations ........................................................................... 13 1.7.4 Class MC Components................................................................................ 13 1.8 Inspection Program ................................................................................................. 14 1.9 Regulatory Guide .................................................................................................... 14 1.10 Postulated Rupture Locations In Fluid Systems Piping Inside and Outside Containment ........................................................................................................... 14 1.11 Plant Life Extension ................................................................................................ 15 1.13 Successive Examinations ....................................................................................... 15 1.14 NDE Examination and Personnel Qualification/Certification .................................... 15 1.14.1 Alternative Examination ............................................................................... 16 1.14.2 System Leakage Tests ................................................................................ 16 1.14.3 Surface Examination ................................................................................... 16 1.14.4 Certification and Recertification (IWA-2314) ................................................ 16 1.14.5 Appendix VIII Requirements ........................................................................ 16 2.0 Risk Informed (RI) ISI Requirements .................................................................................. 16 3.0 Development of the Class 1 Examination Plan ................................................................... 19 3.1 Class 1 Code Exemptions ....................................................................................... 19 3.2 Component Examination Basis ............................................................................... 19 3.3 Category B-A .......................................................................................................... 20 3.4 Category B-B .......................................................................................................... 21 3.5 Category B-D .......................................................................................................... 22 3.6 Category B-F .......................................................................................................... 23 3.7 Category B-G-1....................................................................................................... 23 3.8 Category B-G-2....................................................................................................... 24 Page 3 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 3.9 Category B-J ........................................................................................................... 25 3.10 Category B-K .......................................................................................................... 25 3.11 Category B-L-2 ....................................................................................................... 26 3.12 Category B-M-2 ...................................................................................................... 27 3.13 Category B-N-1, B-N-2 & B-N-3 .............................................................................. 28 3.14 Category B-O .......................................................................................................... 29 3.15 Category B-P .......................................................................................................... 30 3.16 Category B-Q .......................................................................................................... 31 4.0 Development of Class 2 Examination Plan ......................................................................... 32 4.1 Class 2 Code Exemptions ....................................................................................... 32 4.1.1 IWC-1221 .................................................................................................... 32 4.1.2 IWC-1222 .................................................................................................... 33 4.1.3 IWC-1223 .................................................................................................... 33 4.2. Component Examination Basis ............................................................................... 34 4.3 Category C-A .......................................................................................................... 34 4.4 Category C-B .......................................................................................................... 35 4.5 Category C-C .......................................................................................................... 36 4.6 Category C-D .......................................................................................................... 37 4.7 Category C-F-1 ....................................................................................................... 37 4.8 Category C-F-2 ....................................................................................................... 37 4.9 Category C- H ......................................................................................................... 37 5.0 Development of the Class 3 Examination Plan ................................................................... 38 5.1 Class 3 Code Exemptions and Exclusions .............................................................. 38 5.1.1 IWD-1220 .................................................................................................... 38 5.1.2 IWD-1220 .................................................................................................... 38 5.1.3 IWD-5240 .................................................................................................... 39 5.2 Component Exemption Basis .................................................................................. 39 5.3 Category D-A .......................................................................................................... 40 5.4 Category D-B .......................................................................................................... 41 6.0 IWE Metal Containment Requirements ............................................................................... 41 7.0 Development of Component Supports Examination Plan ................................................... 41 7.1 Code Exemptions for Supports ............................................................................... 41 7.2 Support Examination Basis ..................................................................................... 42 7.2.1 Category F-A ............................................................................................... 42 7.2.2 Item Numbers .............................................................................................. 43 7.3 Snubbers ................................................................................................................ 45 8.0 IWL Concrete Containment Requirements ......................................................................... 45 9.0 Augmented and Other Programs ........................................................................................ 46 9.1 Class 1.................................................................................................................... 46 9.1.1 Reactor Coolant Pump Flywheel ................................................................. 46 9.1.2 MRP-139 ..................................................................................................... 46 9.1.3 MRP-146 ..................................................................................................... 46 9.1.4 MRP-227 ..................................................................................................... 47 9.1.5 N-729-4 ....................................................................................................... 47 9.1.6 N-722-1 ....................................................................................................... 48 9.1.7 N-770-2 ....................................................................................................... 48 9.1.8 Material Surveillance Capsules ................................................................... 48 9.1.9 NRC Bulletin 88-08 ...................................................................................... 48 9.1.10 NRC Bulletin 88-11 ...................................................................................... 49 9.2 Class 2.................................................................................................................... 49 9.2.1 SRP 6.6 ....................................................................................................... 49 9.2.2 NRC Bulletin 79-13 ...................................................................................... 49 9.2.3 MRP-192 ..................................................................................................... 50 10.0 Evaluation/Acceptance Criteria ........................................................................................... 50 Page 4 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 10.1 Supplemental Examinations .................................................................................... 50 10.2 Additional Examinations .......................................................................................... 50 10.3 Successive Examinations for Components ............................................................. 50 10.3.1 IWB-2420 .................................................................................................... 50 10.3.2 IWC-2420 .................................................................................................... 51 10.3.3 IWC-2420 .................................................................................................... 51 11.0 Repair/Replacement Activities ............................................................................................ 51 12.0 Relief Requests .................................................................................................................. 51 13.0 Addition of Components ..................................................................................................... 51 14.0 Records .............................................................................................................................. 51 14.1 General ................................................................................................................... 51 14.2 Nondestructive Examination ................................................................................... 51 14.3 Final Reports .......................................................................................................... 52 14.4 Inservice Inspection Summary Report..................................................................... 52 14.5 NIS-2 or NIS-2A Reports......................................................................................... 52 14.6 NIS BB Form........................................................................................................... 52 15.0 References ......................................................................................................................... 53 Appendix - A P&ID Drawings ........................................................................................................ 55 Appendix B - Calibration Block Listing ............................................................................................ 56 Appendix C - Relief Requests ........................................................................................................ 58 Appendix D - ASME Section XI Code Cases.................................................................................. 59 Appendix E - Augmented Examinations ......................................................................................... 66 Appendix F - St Lucie Unit 1 ISI Isometric Drawings ...................................................................... 69 Appendix G - Class 1 Acceptance Critiera ..................................................................................... 73 Appendix H - Class 2 Acceptance Criteria...................................................................................... 73 Appendix I - Class 3 Acceptance Criteria ....................................................................................... 73 Appendix J - Component Support Acceptance Standard................................................................ 73 Page 5 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Abbreviations ANII Authorized Nuclear Inservice Inspector MT Magnetic Particle Testing (Examination)

ANSI American Nuclear Standard Institute N/A Not Applicable AOV Air Operated Valve NDE Nondestructive Testing ASME American Society of Mechanical NPS Nominal Pipe Size Engineers B&PV Boiler and Pressure Vessel Code OD Outside Diameter BC Branch Connection PDS Program Boundary Drawings BMV Bare Metal Visual P&ID Piping and Instrumentation Diagram CCW Component Cooling Water PSI Preservice Inspection CRDM Control Rod Drive Mechanism PSL-1 St. Lucie Unit 1 CFR Code of Federal Regulations PT Liquid Penetrant Testing CH Charging System PWR Pressurized Water Reactor CHR Containment Heat Removal QA Quality Assurance CPS Code Programs Section QC Quality Control CRS Code Required Surface QP Quality Procedure CSI Component Support and Inspections PZR Pressurizer CS Containment Spray RCS Reactor Coolant system CV Control Valve RCP Reactor Coolant Pump CVCS Chemical and Volume Control System RHR Residual Heat Removal ECCS Emergency Core Cooling System RI-ISI Risk-Informed Inservice Inspection ECT Eddy Current Testing RPV Reactor Pressure Vessel FPL Florida Power & Light Company SD Structural Discontinuity FPS Fuel Pool System SDC Shutdown Cooling FSAR Final Safety Analysis Report SDCHX Shutdown Cooling Heat Exchanger FW Feedwater System SG Steam Generator HPSI High Pressure Safety Injection SRP Standard Review Plan HS High Stress SIS Safety Injection System HX Heat Exchanger t Thickness of Component, Pipe, etc ID Identification TE Terminal End IE Inspection and Enforcement UFSAR Updated Final Safety Analysis Report ISI Inservice Inspection USNRC United States Nuclear Regulatory Commission IST Inservice Testing UT Ultrasonic Testing (Examination)

JPN Juno Nuclear Engineering VT Visual Testing (Examination)

LER License Event Report LPSI Low Pressure Safety Injection LS Longitudinal Seam Weld MOV Motor Operated Valve MSIV Main Steam Isolation Valve MS Main Steam System Page 6 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Abstract This document describes the Class 1, 2, and 3 Inservice Inspection (ISI) Program Plan Fifth 10-Year Inservice Inspection Interval for St. Lucie Nuclear Power Plant, Unit No. 1.

The program plan was developed and prepared to meet the requirements of the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code,Section XI, 2007 Edition with 2008 Addenda, and 10CFR50.55a for Class 1, 2, and 3 systems. This program plan is subject to the limitations and modifications of 10CFR50.55a(b)(2), except design and access provisions and preservice examination requirements. This program plan identifies those components and/or systems and their supports that are subject to examination and testing.

Where applicable, ASME Code Cases are incorporated. The Code Cases used are either approved through publication in 10CFR50.55a, NRC Regulatory Guide 1.147, or are included in a Relief Request.

Other alternatives to the Code requirements have been included as relief requests, or they reference specific NRC regulations. Areas where Code compliance is not possible are also included as relief requests, along with proposed alternatives.

This document implements a Risk-Informed selection criterion for Examination Category B-F, B-J, C-F-1 and C-F-2 piping welds. This alternative to the requirements of Section XI was submitted to the NRC during the Fifth 10-year interval as Relief Request RR-01.

The ISI Programs for Containment, Inservice Pressure Tests, and Snubber Examinations are covered under separate plant documents. General requirements for these programs are included for completeness.

Additional requirements for augmented examinations are addressed. The ISI Program Plan does not require these examinations, but rather are included and administered at the request of the plant.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 1.0 Introduction St. Lucie Unit 1 is a two-loop Combustion Engineering Pressurized Water Nuclear Power Plant.

Florida Power and Light Company (FPL) is the Owner of Record.

1.1 ISI Program Development This document details the Inservice Inspection Program Plan of Class 1, 2, and 3 components for the Fifth 10-Year Inservice Inspection Interval for St. Lucie Nuclear Power Plant, Unit No. 1.

th The schedule of examinations is located in document 5 -Interval-ISI-PSL1-Schedule.

The isometrics used for locations of welds during examinations are located in ISI-PSL Sketches. The schedule and isometrics are separate controlled documents.

1.2 Other ISI Programs This document does not address every aspect of Inservice Inspection. The following details the examination and testing requirements of those parts covered by other documents.

1.2.1 Inservice Testing Program (IST)

The program for Inservice Testing of Class 1, Class 2, and Class 3 Pumps and Valves is covered by the St. Lucie Inservice Testing (IST) Program, which is submitted and approved separately.

1.2.2 Steam Generator (SG) Eddy Current (ET) Program The Steam Generator (SG) Eddy Current Testing (ET) Program is governed by the requirements of St. Lucie Plant Technical Specifications and is administered separately.

1.2.3 Snubber Program The program for the examination and testing of safety-related snubbers is addressed by St. Lucie Plant procedures.

1.2.4 Pressure Test Program The program for Inservice System Pressure Testing of ASME Code Class 1, Class 2, and Class 3 components and systems is addressed by St. Lucie Plant procedures.

1.2.5 Repair and Replacement Program The Repair and Replacement Program for ASME Code Class 1, 2, and 3 component and systems is addressed by St. Lucie Plant procedures.

1.2.6 Metal Containment Inservice Inspection Program (IWE) nd The Metal Containment Inservice Inspection Program, 2 Interval IWE-PSL-1/2-Program Plan, controls the examination of Containment Building under Subsection IWE and is administered separately.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 1.3 Construction Permit The Construction permit for St. Lucie Nuclear Power Plant Unit 1 was issued during July 1970. Florida Power and Light Company (FPL) is the Owner of Record.

1.4 Commercial Service Date The Operating License for St. Lucie Nuclear Power Plant Unit 1 was issued during March 1976.

The Commercial Service Date for St. Lucie Nuclear Power Plant Unit 1 is December 21, 1976.

1.5 Background St. Lucie Unit 1 has been examined to the requirements of different Editions and Addenda of Section XI. The applicable Edition of Section XI was mandated by changes to 10 CFR 50.55a at 10-year intervals or earlier.

1.5.1 Preservice Examinations The Preservice Inspection was conducted in accordance with the 1970 Edition with Addenda through Winter 1970 of the ASME B&PV Code,Section XI.

1.5.2 First Inservice Inspection Interval During the first Inservice Inspection Interval, the first inservice inspection period was conducted in accordance with the 1970 Edition with Addenda through Winter 1970 Addenda of the ASME Boiler and Pressure Vessel (B&PV) Code,Section XI. The second and third periods were conducted in accordance with the 1974 Edition with Addenda through Summer 1975 of ASME B&PV Code,Section XI.

The Reactor Pressure Vessel (RPV) examinations were conducted in accordance with the 1977 Edition with Addenda through Summer 1978.

System Pressure tests were conducted in accordance with the 1980 Edition with Addenda through Winter 1981.

The first interval for St. Lucie Unit 1 began on February 11, 1978 and ended on February 10, 1988.

1.5.3 Second Inservice Inspection Interval The Second Ten Year Inservice Inspection Interval was conducted in accordance with the 1983 Edition with Addenda through Summer 1983 of Section XI. The second interval ran from February 11, 1988 to February 10, 1998.

1.5.4 Third Inservice Inspection Interval The Third Ten Year Inservice Inspection Interval was conducted in accordance with the 1989 Edition with No Addenda of Section XI. The third interval ran from February 11, 1998 to February 10, 2008.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 1.5.5 Fourth Inservice Inspection Interval The Fourth Interval was conducted in accordance with the 2001 Edition of ASME Section XI with Addenda through 2003 as modified by 10CFR50.55a. The Fourth Interval ran from February 11, 2008 to February 10, 2018.

1.5.6 Fifth Inservice Inspection Interval The Fifth Interval is being conducted in accordance with the 2007 Edition of ASME Section XI with Addenda through 2008 as modified by 10CFR50.55a The Fifth 10-Year Inservice Inspection Interval is divided into three successive Inspection periods as determined by calendar years of plant service within the interval Table 1 Fifth Inservice Inspection Interval Period Start End th 5 Interval 2/11/2018 2/10/2028 st 1 Period 2/11/2018 2/10/2021 nd 2 Period 2/11/2021 2/10/2025 rd 3 Period 2/11/2025 2/10/2028 1.6 Applicable Editions and Addenda to Section XI th In accordance with 10CFR50.55a(b)(2), in effect one year prior to the start of the 5 ISI Interval dated 2-11-2018, the Inservice Inspection Requirements for the Fifth Inservice Inspection interval applicable to Class 1, 2, and 3 components at St. Lucie Unit 1 are based on the 2007 Edition with Addenda through 2008 of ASME Section XI.

Portions of the ISI Program are based on other Editions and Addenda of Section XI, Relief Requests, the Code of Federal Regulations, Regulatory Guides, and Plant Technical Specifications and commitments. Where this has occurred, it is documented within this Program.

1.6.1 Code of Federal Regulations Conditions The following mandatory and optional Code of Federal Regulations Conditions are included in 10CFR50.55a as of August 17, 2017. Only those 10CFR50.55a Limitations and Modifications applicable to the 2007 Edition with 2008 Addenda of Section XI nondestructive examination requirements for Class 1, 2, and 3 components and component supports are listed. These Limitations and Modifications were reviewed for inclusion in the ISI Program Plan and dispositioned as follows:

1.6.1.1 St. Lucie 1 will not utilize the option in 10CFR50.55a(b)(2)(ii), to examine Class 1 piping per ASME Section XI, 1974 Edition with the Summer 1975 Addenda. St. Lucie 1 has a RI-ISI application for Class 1 and 2 piping, therefore, this modification is not applicable.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 1.6.1.2 The St. Lucie 1 design does not include a concrete containment subject to ASME Section XI, Subsection IWL requirements, therefore the mandatory modification in 10CFR50.55a(b)(2)(viii) does not apply to St. Lucie 1.

1.6.1.3 The St. Lucie 1 design includes a metal containment subject to ASME Section XI, Subsection IWE requirements, therefore the mandatory modification in 10CFR50.55a(b)(2)(ix) applies to St. Lucie 1. These Subsection IWE requirements and 10CFR50.55a requirements are nd addressed under Containment ISI Program Plan 2 Interval-IWE-PSL-1/2-Program Plan.

1.6.1.4 As required by 10CFR50.55a(b)(2)(x), St. Lucie 1 will apply the station 10CFR50 Appendix B Quality Assurance Program of NQA-1 to Section XI activities.

1.6.1.5 As required by 10CFR50.55a(b)(2)(xii), St. Lucie 1 will not apply the provisions of IWA-4660, Underwater Welding, as this section is not approved for use on irradiated materials.

1.6.1.6 As allowed by 10CFR50.55a(b)(2)(xiv), for Appendix VIII Qualified Personnel, St. Lucie 1 will use the annual practice requirements in VII-4240 of Section XI Appendix VII in place of the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of annual hands-on training (when deemed appropriate) as discussed in 10CFR50.55a(b)(2)(xiv). When utilizing this option, the annual practice requirements will be performed on material or welds that contain cracks, or by analyzing prerecorded data from material or welds that contain cracks. All training will be completed no earlier than 6 months prior to performing ultrasonic examinations.

1.6.1.7 As required by 10CFR50.55a(b)(2)(xviii)(A), Level I and II nondestructive examination personnel at St. Lucie 1 will be recertified on a 3-year interval in lieu of the 5-year interval specified in IWA-2314(a) and IWA-2314(b) of the 2007 Edition with 2008 Addenda.

1.6.1.8 As required by 10CFR50.55a(b)(2)(xix), The provisions in IWA-4520(b)(2) and IWA-4521 of the 2008 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1)(ii) of this section, allowing the substitution of ultrasonic examination for radiographic examination specified in the Construction Code, are not approved for use. Note that the conditions prohibiting the use of IWA-2240 and IWA-4520(c) are not applicable to licensees implementing the 2007 Edition with the 2008 Addenda of ASME Section XI.

1.6.1.9 As required by 10CFR50.55a(b)(2)(xx)(B), St. Lucie 1 will apply the NDE provisions in IWA-4520(a)(2) of the 2002 Addenda of Section XI when performing system leakage tests after repair and replacement activities performed by welding or brazing on a pressure retaining boundary.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 1.6.1.10 As required by 10CFR50.55a(b)(2)(xxi)(A), the provisions of Table IWB-2500-1, Examination Category B-D, Full Penetration Welded Nozzles in Vessels, Items Nos. B3.120 and B3.140 of Inspection Program B in the 1998 Edition will be applied by St. Lucie 1. As allowed by 10CFR50.55a(b)(2)(xxi)(A), a visual examination with enhanced magnification that has a resolution sensitivity to resolve 0.044 inch (1.1 mm) lower case characters without ascender or decender (e.g., a,e,n,v), utilizing the allowable flaw length criteria in Table IWB-3512-1, 2007 Edition with the 2008 Addenda, with a limiting assumption on the flaw aspect ratio, may be performed instead of an ultrasonic examination.

1.6.1.11 St. Lucie 1 will not implement the provision in IWA-2220, Surface Examination that allows the use of an ultrasonic examination method. The use of this provision is prohibited by 10CFR50.55a(b)(2)(xxii). Based on the RI-ISI application on Class 1 and 2 piping welds, St. Lucie 1 does not need to perform surface examinations on this piping.

1.6.1.12 10CFR50.55a(b)(2)(xxiii) prohibits the use of provisions for eliminating mechanical processing of thermally cut surfaces in IWA-4461.4.2 of the 2007 Edition with the 2008 Addenda of Section XI.

1.6.1.13 10CFR50.55a(b)(2)(xxv) prohibits the use of provisions in IWA-4340, Mitigation of Defects by Modification, in the 2007 Edition with 2008 Addenda of Section XI.

1.6.1.14 10CFR50.55a(b)(2)(xxvi) requires that repair and replacement activity provisions in IWA-4540(c) of the 1998 Edition of Section XI for pressure testing Class 1, 2, and 3 mechanical joints must be applied.

1.6.1.15 10CFR50.55a(b)(2)(xxvii) When performing visual examination in accordance with IWA-5242 of Section XI of the ASME BPV Code, 2003 Addenda through the 2006 Addenda, or IWA-5241 of the 2007 Edition through the latest edition and addenda incorporated by reference in paragraph (a)(1)(ii) of this section, insulation must be removed from 17-4 PH or 410 stainless steel studs or bolts aged at a temperature below 1100 °F or having a Rockwell Method C hardness value above 30, and from A-286 stainless steel studs or bolts preloaded to 100,000 pounds per square inch or higher.

These requirements will be implemented in accordance with the FPL Bolted Joint Program.

1.6.1.16 10CFR50.55a(b)(2)(xxix) requires prior NRC authorization to implement Nonmandatory Appendix R, Risk-Informed Inspection Requirements for Piping. St. Lucie 1 intends to submit a Relief Request to implement Appendix R.

1.6.1.14 St. Lucie 1 will utilize the option in 10CFR50.55a(b)(3)(v). Article IWF-5000, Inservice Inspection Requirements for Snubbers," of the ASME BPV Code,Section XI, must be used when performing inservice inspection examinations and tests of snubbers at nuclear power plants, as conditioned in paragraph (B) of this section.

1.6.1.15 10CFR50.55a(g)(6)(ii)(D)(1) requires that St Lucie augment the inservice inspection program by implementing ASME Code Case N-729-4 subject to the conditions specified in paragraphs 10CFR50.55a(g)(6)(ii)(D)(2) through (D)(4). See Appendix D of this program plan for implementation of this requirement.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 1.6.1.16 10CFR50.55a(g)(6)(ii)(E)(1) requires that St Lucie augment the inservice inspection program by implementing ASME Code Case N-722-1 subject to the conditions specified in paragraphs (g)(6)(ii)(E)(2) through (4). The inspection requirements of ASME Code Case N-722-1 do not apply to components with pressure retaining welds fabricated with Alloy 600/82/182 materials that have been mitigated by weld overlay or stress improvement. See Appendix D of this program plan for implementation of this requirement.

1.6.1.17 10CFR50.55a(g)(6)(ii)(F)(1) requires that St Lucie implement the requirements of ASME Code Case N-770-2 subject to the conditions specified in paragraphs (g)(6)(ii)(F)(2) through (13) effective date August 17, 2017. See Appendix D of this program plan for implementation of this requirement.

1.7 System Classification System safety classifications, design and fabrication requirements meet the intent of 10 CFR 50.2 and Regulatory Guide 1.26, as identified within the St. Lucie Unit 1 Updated Final Safety Analysis Report (UFSAR).

Water, steam and radioactive containing components (other than turbines and condensers) are designated Quality Group A, B, C, or D in accordance with their importance to safety.

1.7.1 System Classifications Class 1 system boundaries are developed based on 10 CFR 50.2(v), and the St.

Lucie Unit 1 UFSAR. Class 2 and 3 system boundaries are developed based on Regulatory Guide 1.26 and the St. Lucie Unit 1 UFSAR.

System Quality Group classification interfaces between components of different quality groups are designated on various system piping and instrument diagrams (P&ID's) (see Appendix A).

Vessels, piping, pumps and valves were built and installed according to the rules of ASME Section III and USA Standard B31.7 for those systems classified as Class 1, 2, and 3.

1.7.2 Optional Construction Optional construction of a component within a system boundary to a classification higher than the minimum class established in the component design specification does not affect the overall system classification by which the applicable rules of Section XI are determined.

1.7.3 Containment Penetrations Portions of piping penetrating the containment vessel which are required to be constructed to Class 1 or 2 rules for piping and which may differ from the classification of the balance of the piping system, may not affect the overall system classification that determines the applicable rules of Section XI.

1.7.4 Class MC Components 10 CFR 50.55a was amended, effective November 22, 1999, to address the requirements of ISI of metal containment buildings. The program for IWE examinations specifically defines the classification of those areas examined.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 1.8 Inspection Program Examinations for Class 1, 2, and 3 components are scheduled in accordance with ASME Section XI IWB-2411 and Table IWB-2411-1). Examinations are scheduled based upon previous 10-Year intervals, to the extent practical and within the limits established in IWB-2420. Class 1 and 2 piping weld examinations are based on the Risk-Informed selection criteria, see Relief Request No. RR-01.

In order to be consistent in determining percentages, FPL chose to multiply the number of examination areas by the minimum or maximum percentages of Program B and rounding to the nearest whole number. This will be the number FPL uses for determining how many welds/components will be examined each period.

The Inservice Inspection Schedule Tables for inservice examinations of the components th th of St. Lucie 1 are located in the 5 -Interval-ISI-PSL1-Schedule. The 5 -Interval-ISI-PSL1-Schedule includes tables that have brief descriptions of each component subject to examination, the required Code references, and any other pertinent information that is useful for determining examination requirements. The information and summary tables th located in 5 -Interval-ISI-PSL1-Schedule satisfy the requirements of IWA-2420(b)(1) through (6) respectively.

1.9 Regulatory Guides The Regulatory Guides determined to be applicable to PSL-1 for purposes of this ISI Program are listed below:

Table 2 USNRC Regulatory Guides 1.14 Revision 1 Reactor Coolant Pump Flywheel Integrity 1.26 Quality Group Classifications Materials and Inspections for Reactor Vessel Closure 1.65 Studs Inservice Inspection of Pressurized Water Reactor Steam 1.83 Generator Tubes, Revision 1, July 1985 1.147 Section XI Code Case Acceptability (Latest Revision) 1.10 Postulated Rupture Locations In Fluid Systems Piping Inside and Outside Containment Branch Technical Position MEB 3-1 required FPL to determine where piping failure in fluid systems outside of the containment would have an adverse effect on other components and equipment. FPL completed a detailed engineering analysis of the Residual Heat Removal, Chemical Volume Control, Main Steam, Main Feedwater, Auxiliary Feedwater, and Steam Generator Blowdown systems.

Generic letter 87-11 revised Branch Technical Position MEB 3-1, "Postulated Rupture Locations in Fluid System Piping Inside and Outside Containment," as contained in the Standard Review Plan (SRP), Section 3.6.2, "Determination of Rupture Locations and Dynamic Effects Associated with the Postulated Rupture of Piping," UFSAR Reference 3.6.28. All modifications to Class 2 and 3 piping systems may invoke this new criteria (see UFSAR Appendix 3.J) in lieu of the original criteria provided that the requirements stipulated in UFSAR Appendix 3J are fully complied with. The new criteria is based on portions of the revised Branch Technical Position MEB 3-1 applicable to St. Lucie Unit 1.

Additional detail is provided in Design Basis Document DBD-SLI-PBK-, Select Licensing Issues - Pipe Break Criteria.

Page 14 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 The engineering analysis determined that portions of the Main Steam and Feedwater systems needed to be included in the ISI examination schedule. These included those supports and welds to the first support beyond the Class 2 boundary. Appropriate welds and supports will be examined under SRP 6.6 in Appendix E.

FPL will examine the applicable welds in the Main Steam and Feedwater systems in accordance with the requirements of USNRC Standard Review Plan 6.6,Section I.6, Augmented Inservice Inspection of Class 2 Welds. The scope of these examinations is identified under Augmented Section, Appendix E.

1.11 Plant Life Extension The ISI Program will implement the FPL commitment to manage the effects of aging for systems/structures/components within the scope of license renewal. The Section XI Program is credited as an aging management program for license renewal. As such, changes to the Section XI Program shall consider License Renewal requirements described in the "Operating License Renewal" section of the St. Lucie Unit 1 Design Basis Document, DBD-SLI-OLR-1, Volume 20-10, "Operating License Renewal".

1.12.1 Engineering Evaluation PSL-ENG-LRAM-01-026, Evaluation of Environmental Effects of Fatigue - License Renewal Basis Document.

1.12.2 Engineering Evaluation PSL-ENG-LRAM-00-056, Reactor Vessel Internals Inspection Program - License Renewal Basis Document 1.12.3 Engineering Evaluation PSL-ENG-LRAM-00-097, ASME Section XI, Subsections IWB, IWC and IWD Inservice Inspection Program - License Renewal Program Basis Document.

1.12.4 Engineering Evaluation PSL-ENG-LRAM-00-119, ASME Section XI, Subsection IWF Inservice Inspection Program -License Renewal Program Basis Document.

1.12.5 Engineering Evaluation PSL-ENG-LRAM-00-120, Reactor Vessel Integrity Program - License Renewal Basis Document.

1.12 Successive Examinations The sequence of component examinations may be modified in accordance with the requirements of IWB-2420. This allows FPL to alter the sequence of examinations to allow the examination of several components in an area during one outage instead of over several outages. This will reduce costs and radiation exposure. The percentage requirements of IWB-2411, IWC-2411, IWD-2411, and IWF-2410 will be satisfied. Due to the implementation of the Risk-Informed ISI Program (see Relief Request No. RR-01),

the scheduling of piping weld examinations will not follow Code requirements, as the selection criteria are different. However, the percentage requirements of IWB-2411 and IWC-2411 for those components selected will be maintained. The modified examination schedule is designed to optimize the performance of work within the plant to reduce radiation dose, eliminate interference with other work, and reduce costs.

1.13 NDE Examination and Personnel Qualification/Certification All NDE will be performed in accordance with the requirements of the 2007 Edition to 2008 Addenda with the following modifications as required by 10CFR50.55a.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 1.13.1 Alternative Examinations (IWA-2240)

The provisions in IWA-4520(b)(2) and IWA-4521 of the 2008 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1)(ii) of this section, allowing the substitution of ultrasonic examination for radiographic examination specified in the Construction Code, are not approved for use.

[Reference 10CFR50.55a(b)(2)(xix)].

1.13.2 System Leakage Tests The NDE provision in IWA-4520(a)(2) requires use of the 2002 Addenda of Section XI when performing system leakage tests after repair and replacement activities performed by welding or brazing on a pressure retaining boundary,

[Reference 10CFR50.55a(b)(2)(xx)(B)].

1.13.3 Surface Examinations The provision in IWA-2220, Surface Examination allows the use of an ultrasonic examination method. The use of this provision is prohibited, [Reference 10CFR50.55a(b)(2)(xxii)].

1.13.4 Certification and Recertification (IWA-2314)

Level I and II nondestructive examination personnel, and personnel qualified under the American Society for Nondestructive Testing Central Certification Program and ANSI/ASNT CP-189 shall be recertified on a 3-year interval in lieu of the 5-year interval specified in IWA-2314(a) and IWA-2314(b), [Reference 10 CFR 50.55a(b)(2)(xviii)(A)].

1.13.5 Appendix VIII Requirements 1.13.5.1 10CFR50.55a(b)(2)(xiv) requires that all personnel qualified for performing ultrasonic (UT) examinations in accordance with Appendix VIII shall receive additional annual hands-on training. This requirement consists of at least eight hours of hands on training on samples containing cracks no earlier than six months prior to performing examinations at a licensees facility. St. Lucie will comply with these additional training requirements for personnel performing Section XI Appendix VIII, UT examinations.

1.13.5.2 FPL will implement the requirements of ASME Section XI, Appendix VII

& VIII, as modified by 10CFR50.55a.

2.0 Risk-Informed (RI) ISI Requirements 2.1 PSL-1 is continuing to implement an alternative Risk-Informed Inservice Inspection (RI-ISI) Program for Class 1 piping welds.

rd During the 3 Inspection Interval, the alternative Risk-Informed Inservice Inspection Program was submitted by letter dated July 30, 2003 (L-2003-187) and supplemented by letters dated December 4, 2003 (L-2003-300) and January 28, 2004 (L-2004-016) and approved by the USNRC, SER dated March 25, 2004, St. Lucie Nuclear Plant, Unit No.

1- Relief Request 19 Regarding Risk-Informed Inservice Inspection Program (TAC No.

MC0244).

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 This alternative to the requirements of Section XI was re-submitted to the NRC for review and approval for the fourth 10-year interval as Relief Request No. 1 (L-2007-195 & L-th 2008-189). The 4 Interval RI-ISI Program has been approved by SER dated November 2, 2008 (TAC NO. MD7739).

This alternative to the requirements of Section XI is being re-submitted to the NRC for review and approval for the fifth 10-year interval as Relief Request No. RR-01, which includes the Class 1 and Class 2 Risk-Informed application.

The RI-ISI program is a living program requiring feedback of new, relevant information to ensure the appropriate identification of high safety significance piping locations. The originally submitted RI-ISI program was evaluated and submitted in accordance with NEI-04-05, Living Program Guidance To Maintain Risk-Informed Inservice Inspection Programs for Nuclear Plant Piping Systems, published April 2004.

2.2 Inservice Inspection of Class 1 and Class 2 piping welds will be performed in accordance with the RI-ISI methodology of EPRI TR-112657 Revised Risk-Informed Inservice Inspection Evaluation Procedure Revision B-A, Code Case N-578-1 and Relief Request

RR-01. The RI-ISI program was developed and will be maintained in accordance with this EPRI TR and the associated guidance documents. The RI-ISI program supersedes the ASME XI exam selection requirements of Examination Categories B-F, B-J, C-F-1 and C-F-2. The applicable aspects of the ASME XI Code not affected by the RI-ISI program will be retained.

2.3 Class 1 and Class 2 systems will continue to receive system pressure testing and VT-2 examinations.

2.4 The RI-ISI program is a living program. Relevant indications from examinations at St.

Lucie and throughout the industry will be evaluated to ensure the appropriate piping locations are distinguished as a High Safety Significant. The risk ranking of piping segments will be reviewed and adjusted after every period, prior to the next periods first outage, in accordance with the FPLs approved relief request, ENG-CSI 2.4, and industry guidance developed by the Nuclear Energy Institute (NEI) RI-ISI Living Program (NEI 04-05). Significant changes (Regulatory actions, industry experience, etc.) may require more frequent adjustments. Resubmittal of the RI-ISI program to the regulatory authority will be in accordance with the NEI 04-05 RI-ISI Living Program. RI periodic evaluations are included in Appendix B.

2.5 Additional and Successive Examinations 2.5.1 If piping structural elements are accepted for continued service by analytical evaluation in accordance with ASME Section XI, Paragraph IWB-3600, the areas containing the flaws or relevant conditions shall be reexamined during the next three inspection periods.

2.5.2 If reexaminations reveal that the flaws or relevant conditions remain essentially unchanged for three successive inspection periods for Class 1 and unchanged in the next inspection period for Class 2, the piping examination schedule may revert to the original schedule for successive inspections.

2.5.3 The evaluation will include whether other elements on the segment or segments are subject to the same root cause and degradation mechanism. Additional examinations will be performed on these elements up to a number equivalent to the number of elements required to be examined on the segment or segments initially.

Page 17 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 2.5.4 If unacceptable flaws or relevant conditions are again found similar to the initial problem, the remaining elements identified as susceptible will be examined. No additional examinations will be performed if there are no additional elements identified as being susceptible to the same service related root cause conditions or degradation mechanism.

2.5.5 The successive examination requirements of IWB-2420 (Class 1) and IWC-2420 (Class 2) must be fully met for any existing element that has been accepted for continued service based on an analytical evaluation per IWB/IWC-3600, regardless of whether the subject element is an RI-ISI selection.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 3.0 Development of the Class 1 Examination Plan Plant controlled isometric, P&IDs, component drawings, and plant walkdowns were used to develop the ISI drawings and the scope of examinations. During examinations, drawings will be used to locate and identify each component. Other plant controlled drawings or documents will be used when additional information is required.

th Refer to the 5 -Interval-ISI-PSL-1-Schedule for a complete listing of components subject to examination and the proposed examination schedule.

3.1 Class 1 Code Exemptions IWB-1220 -Components Exempt from Examination 1

The following components or parts of components are exempted from the volumetric and surface examination requirements of IWB-2500:

(a) components that are connected to the reactor coolant system and part of the reactor coolant pressure boundary, and that are of such a size and shape so that upon postulated rupture the resulting flow of coolant from the reactor coolant system under normal plant operating conditions is within the capacity of makeup systems which are operable from on-site emergency power. The emergency core cooling systems are excluded from the calculation of makeup capacity; (b) (1) components and piping segments NPS 1 and smaller, except steam generator tubing; (2) components and their piping segments which have one inlet and one outlet, both of which are NPS 1 and smaller; 2

(3) Components and piping segments which have multiple inlets or multiple outlets whose cumulative pipe cross-sectional area does not exceed the cross-sectional area defined by the OD of NPS 1 pipe.

(c) reactor vessel head connections and associated piping, NPS 2 and smaller, made inaccessible by control rod drive penetrations.

(d) welds or portions of welds that are inaccessible due to being encased in concrete, buried underground, located inside a penetration, or encapsulated by guard pipe.

1 The exemptions from examination in IWC-1220 may be applied to those components permitted to be Class 2 in lieu of Class 1 by the regulatory authority having jurisdiction at the plant site.

2 For heat exchangers, the shell side and tube side may be considered separate components.

3.2 Component Examination Basis This section describes each Examination Category. The required percentage of examinations and any limitations for each Examination Category is described. All other requirements are found in the 2007 Edition with the 2008 Addenda of Section XI. The th Summary Tables located in 5 Interval ISI-PSL-1-Schedule satisfy the requirements of IWA-2420(b)(1) through (6) respectively.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 3.3 Category B-A, Pressure Retaining Welds in Reactor Vessel Table B-A provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-A, Pressure Retaining Welds in Reactor Vessel. Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively.

The percentage of scheduled examinations for this Examination Category was developed in accordance with IWB-2411, Inspection Program, subparagraphs (a)(2) and (a)(3),

which allows examinations to be partially deferred or deferred, respectively, to the end of an inspection interval.

UNIT 1 Table B-A Item Number of Number Scheduled by Period Parts Examined Numbers Welds 1 2 3 B1.11 Circumferential 2 0 0 2 B1.12 Longitudinal 9 0 0 9 B1.21 Circumferential 2 0 0 2 B1.22 Meridional 6 0 0 6 B1.30 Shell-to-Flange Welds 1 0 0 1 Totals 20 0 0 20 There are no item numbers B1.20, B1.21, B1.22, B1.40, B1.50 or B1.51 applicable at St Lucie Unit 1.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 3.4 Category B-B, Pressure Retaining Welds in Vessels Other Than Reactor Vessels.

Table B-B provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-B, Pressure Retaining Welds in Vessels Other Than Reactor Vessels. Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively.

UNIT 1 Table B-B Number Scheduled by Item Number of Parts Examined Period Numbers Welds 1 2 3 B2.11 Circumferential 2 0 2 0 B2.31 Circumferential 2 0 0 1 B2.40 Tubesheet to Head 4 1 0 1 Welds Totals 12 1 2 2 There are no item numbers B2.12 B2.20, B2.21, B2.22, B2.32, B2.50, B2.51, B2.52, B2.60, B2.70 & B2.80 applicable at St Lucie Unit 1.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 3.5 Category B-D, Full Penetration Welded Nozzles in Vessels Table B-D provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-D, Full Penetration Welded Nozzles in Vessels. Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively.

The percentage of scheduled examinations for this Examination Category was developed in accordance with IWB-2411, Inspection Program, subparagraph (a)(2), which allows examinations to be partially deferred to the end of an inspection interval.

UNIT 1 Table B-D Item Number of Number Scheduled by Period Parts Examined Numbers Welds 1 2 3 Nozzle-to-Vessel B3.90 6 0 0 6 Welds Nozzle Inside Radius B3.100 6 0 0 6 Section 1 Nozzle Inside Radius B3.120 6 0 6 0 Section Nozzle to Vessel B3.130 6 3 0 3 Welds 1 Nozzle Inside Radius B3.140 6 3 0 3 Section Totals 30 6 6 18 There are no item numbers B3.110, B3.150 & B3.160 applicable at St Lucie Unit 1.

1 As stated in 10CFR50.55a examination of inner radius is mandated by 50.55a(b)(2)(xxi)(A). The provisions of Table IWB 2500-1, Examination Category B-D, Full Penetration Welded Nozzles in Vessels, Items B3.40 and B3.60 (Inspection Program A) and Items B3.120 and B3.140 (Inspection Program B) of the 1998 Edition must be applied when using the 1999 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1)(ii) of this section. A visual examination with magnification that has a resolution sensitivity to resolve 0.044 inch (1.1 mm) lower case characters without an ascender or descender (e.g., a, e, n, v), utilizing the allowable flaw length criteria in Table IWB-3512-1, 1997 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1)(ii) of this section, with a limiting assumption on the flaw aspect ratio (i.e., a/l = 0.5), may be performed instead of an ultrasonic examination.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 3.6 Category B-F, Pressure Retaining Dissimilar Metal Welds These components will be examined under the RI-ISI Program (Reference Section 2.0) and Relief Request No. RR-01.

3.7 Category B-G Pressure Retaining Bolting, Greater Than 2 in. in Diameter Table B-G-1 provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-G-1, Pressure Retaining Bolting, Greater Than 2 inches in Diameter. Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively.

The percentage of scheduled examinations for this Examination Category was developed in accordance with IWB-2411, Inspection Program, subparagraph (a)(4), which allows examinations to be deferred until disassembly of a component for maintenance, repair/replacement activity, or volumetric examination.

UNIT 1 Table B-G-1*

Number of Number Scheduled by Item Period Parts Examined Bolting Numbers Groups 1 2 3 B6.10 Closure Head Nuts 1 0 1 0 B6.20 Closure Studs, in place 1 0 1 0 B6.40 Threads in Flange 1 0 0 1 B6.50 Closure Washers, Bushings 1 0 1 0 B6.180 Bolts and Studs 4 0 1 0 1 Flange Surface, when B6.190 1 4 0 0 1 connection disassembled Nuts, Bushings, and B6.200 8 0 1 0 Washers Total 20 0 5 2 There are no item numbers B6.60, B6.70, B6.80, B6.90, B6.110, B6.120, B6.130, B6.140, B6.150, B6.160, B6.170, B6.210, B6.220 & B6.230 applicable to St Lucie Unit 1.

IWB-2500-1, B-G-1, Note (3) Volumetric examination of bolting for heat exchangers, pumps, or valves may be conducted on one heat exchanger, one pump, or one valve among a group of heat exchangers, pumps, or valves that are similar in design, type, and function. In addition, when the component to be examined contains a group of bolted connections of similar design and size, such as flanged connections, the examination may be conducted on one bolted connection among the group.

1 Required if disassembled Page 23 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 3.8 Category B-G-2, Pressure Retaining Bolting, 2 in. and Less in Diameter Table B-G-2 provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-G-2, Pressure Retaining Bolting, 2 Inches and Less in Diameter. Examination is only required when the flange/valve is disassembled or bolting is removed. Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively.

The percentage of scheduled examinations for this Examination Category was developed in accordance with IWB-2411, Inspection Program, subparagraph (a)(4), which allows examinations to be deferred until disassembly of a component for maintenance, repair/replacement activity, or volumetric examination.

UNIT 1 1,2 Table B-G-2 Number Scheduled by Item Number of Bolting Parts Examined Period Numbers Assemblies 1 2 3 B7.20 Bolts, Studs, and Nuts 1 * *

B7.30 Bolts, Studs, and Nuts 4 * *

B7.50 Bolts, Studs, and Nuts 13 * *

B7.70 Bolts, Studs, and Nuts 16 * *

Totals 24 * *

There are no item number B7.10, B7.40, or B7.60 applicable at St Lucie Unit 1.

Examinations are performed when bolted connections are disassembled.

1 IWB-2500-1, B-G-2, Note (2) For components other than piping, examination of bolting is required only when the component is examined under Examination Category B-B, B-L-2, or B-M-2. Examination of bolted connection is required only once during the interval.

2 IWB-2500-1, B-G-2, Note (3) The examination of flange bolting in piping systems may be limited to one bolted connection among a group of bolted connections that are similar in design, size, function, and service. Examination is required only when a flange is disassembled. Examination of a bolted connection is required only once during the interval.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 3.9 Category B-J, Pressure Retaining Welds in Piping These components will be examined under the RI ISI Program (Reference Section 2.0) and Relief Request No. RR-01.

3.10 Category B-K, Welded Attachments for Vessels, Piping, Pumps, and Valves Table B-K provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-K, Welded Attachments for Vessels, Piping, Pumps, and Valves.

Welded attachments for piping inspected under Item Number B10.20 are scheduled in accordance with Notes (4) and (5) of Table IWB-2500-1, Examination Category B-K, as found within the ASME B&PV Code,Section XI, 2007 Edition with the 2008 Addenda.

Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively.

UNIT 1 Table B-K Number of Number Scheduled by Item Parts Examined Welded Period Numbers Attachments 1 2 3 B10.10 Welded Attachments 5 0 0 2 B10.20 Welded Attachments 5 1 0 0 B10.30 Welded Attachments 16 0 2 0 Totals 26 1 2 2 There are no Item Number B10.40 components at St Lucie Unit 1.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 3.11 Category B-L-2, Pump Casing Table B-L-2 provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-L-2, Pump Casing Unit 1 Table B-L-2 Number of Number Scheduled by Item Period Parts Examined Welds or Numbers Components 1 2 3 B12.20 Pump Casing (B-L-2) 4 * *

Totals 4 0 0 0 B-L Examine the internal surfaces of one of the four Reactor Coolant Pumps when disassembled for maintenance. *Pump to be identified when pump is disassembled.

Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 3.12 Category B-M-2, Valve Bodies Table B-M-2 provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-M-2, Valve Bodies. The percentage of scheduled examinations for Examination Category B-M-2 was developed in accordance with IWB-2411, Inspection Program, subparagraph (a)(4), which allows examinations to be deferred until disassembly of a component for maintenance, repair/replacement activity, or volumetric examination. Examination of at least one valve in each group of valves is required once per interval when disassembled for maintenance, repair, or volumetric examination. Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively. Valve interior inspections are required under Examination Category B-M-2, Item No. B12.50, have been grouped based on size, constructional design, manufacturing method, and function in accordance with Note (3) of Table IWB-2500-1, Examination Category B-M-2. These valve groupings are as follows:

Listing of Class 1 Valves by Group Group Number Zone Valve Number Type Size 1-021 CV-3227 1-022 CV-3217 1 Check 12" 1-023 CV-3237 1-024 CV-3247 1-021 V-3624 1-022 V-3614 2 Gate 12" 1-023 V-3634 1-024 V-3644 1-028 V-3652 1-028 V-3651 3 Gate 10" 1-029 V-3480 1-029 V-3481 1-039 CV-3124 1-039 CV-3114 4 Check 6" 1-040 CV-3144 1-040 CV-3134 Page 27 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 3.13 Category B-N-1, B-N-2 & B-N-3 Interior of Reactor Vessel Table B-N-1, B-N-2 & B-N-3 provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-N-1, Interior of Reactor Vessel. The scope of examinations performed under this Examination Category include VT-3 visual examination of accessible areas above and below the reactor core made accessible for examination by removal of components during normal refueling activities (once each inspection period). Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively. The percentage of scheduled examinations for this Examination Category is not applicable in accordance with IWB-2411, Inspection Program, subparagraph (a)(1).

Table B-N-1, B-N-2, B-N-3 also provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-N-2 (PWR), Item Nos. B13.50 and B13.60, Interior Attachments Within Beltline Region, and Interior Attachments Beyond Beltline Region, respectively. The scope of examinations performed under these Item Numbers includes VT-1 visual examination of interior attachments within the beltline region (once per interval), and VT-3 visual examination of interior attachments beyond the beltline region (once per interval). To reduce radiation exposure, 100% of the required examinations will be deferred to the end of the interval in accordance with Table IWB-2500-1, thereby allowing these examinations to be completed during a single, scheduled refueling outage.

Additionally, the required percentage of examinations for these Item Numbers is not applicable for examinations deferred to the end of an inspection interval as delineated within IWB-2411, Inspection Program, subparagraph (a)(3).

UNIT 1 Table B-N-1, B-N-2, B-N-3 Number Item Number of Scheduled by Parts Examined Numbers Areas Period 1 2 3 B13.10 (B-N-1) Vessel Interior 8 8 8 8 (B-N-2) Interior Attachments Within B13.50 22 0 0 22 Beltline Region (B-N-2) Interior Attachments Beyond B13.60 4 0 0 4 Beltline Region B13.70 (B-N-3) Core Support Structure 31 0 0 31 Totals 66 8 8 65 There are no item numbers B13.20, B13.30, or B13.40 applicable to St Lucie Unit 1.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 3.14 Category B-O, Pressure Retaining Welds in Control Rod Drive and Instrument Housings Table B-O provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-O, Pressure Retaining Welds in Control Rod Drive and Instrument Housings. Refer to Appendix C and D for applicable Relief Requests and Code Cases. The required extent of this examination is 10% of the peripheral control rod housings. St Lucie Unit 1 has 32 control rod housings on the periphery with 5 welds per housing and 8 ICI Housings with 1 weld per housing. The required percentage of examinations for this Examination Category is not applicable for examinations deferred to the end of an inspection interval as delineated within IWB-2411, Inspection Program, subparagraph (a)(3).

UNIT 1 Table B-O Number Scheduled by Item Number of Parts Examined Period Numbers Welds 1 2 3 Welds in Control Rod Drive (CRD)

B14.20 32 0 0 8*

Housings (10% of Periphery)

Welds in In-Core Instrumentation B14.21 Nozzle (ICI) Housings >NPS 2 8 0 0 1 (DN50) (10% ICI Housings)

Totals 40 0 0 9

Per Relief Request (future submittal)

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 3.15 Category B-P, All Pressure Retaining Components The system leakage test shall be conducted prior to plant startup following each refueling outage.

On systems borated for the purpose of controlling reactivity, insulation shall be removed from pressure retaining bolted connections for VT-2 visual examination. Insulation removal and VT-2 visual examination of insulated bolted connections may be deferred until the system is depressurized. When corrosion-resistant bolting material with a chromium content of at least 10%, such as SA-564 Grade 630 H1100, SA-453 Grade 660, SB-637 Type 718 or SB-637 Type 750 is used, it is permissible to perform the VT-2 examination without insulation removal. (IWA-5241). Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively.

UNIT 1 Table B-P Number Scheduled by Item Period Description Test Procedure Number 1 2 3 1

B15.10 Class 1 1-ISP-01.01 * *

1 1-ISP-01.01 Reactor Coolant System ASME Leakage Test is performed at the conclusion of each refueling outage.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 3.16 Category B-Q, Steam Generator Tubing Table B-Q provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-Q, Steam Generator Tubing The extent and frequency of steam generator tubing surveillance requirements (B16.20) are contained in plant Technical Specification 6.8.4.I. Procedure ENG-CSI-2.3, Steam Generator Integrity Program Administration, contains the requirements for the steam generator examinations. Administrative requirements associated with ASME Section XI are addressed by this document. Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively.

UNIT 1 Table B-Q Number Scheduled by Item Number of Period Description Number components 1 2 3 Steam Generator 1

B16.20 Tubing in U-Tube S/G Program * *

Design Extent and Frequency of examination shall be by the Plant Technical specifications.

There are no B16.10 items at St Lucie Unit 1.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 4.0 Development of the Class 2 Examination Plan Plant controlled isometric, P&IDs, component drawings, and plant walkdowns were used to develop the ISI drawings and the scope of examinations. During examinations, drawings will be used to locate and identify each component. Other plant controlled drawings or documents will be used when additional information is required.

th Refer to the 5 -Interval-ISI-PSL-1-Schedule for a complete listing of components subject to examination and the proposed examination schedule.

4.1 Class 2 Code Exemptions The following Class 2 exemption criteria are applicable. Paragraph IWC-1220 of ASME Section XI, 2007 Edition with Addenda through 2008 lists those piping and components exempt from examination.

IWC-1220 - Components Exempt from Examination The following components or parts of components are exempted from the volumetric and surface examination requirements of IWC-2500; 4.1.1 IWC-1221, Components within RHR, ECC, and CHR Systems or Portions of 1

Systems .

(a) For systems, except high pressure safety injection systems in pressurized water reactor plants:

(1) components and piping segments NPS 4 (DN100) and smaller.

(2) components and piping segments which have one inlet and one outlet, both of which are NPS 4 (DW 100) and smaller.

2 (3) components and piping segments which have multiple inlets or outlets, whose cumulative cross-sectional area does not exceed the cross-sectional area defined by the OD of NPS 4 (DN 100) pipe.

(b) For high pressure safety injection systems in pressurized water reactor plants:

(1) components and piping segments NPS 1 1/2 (DN 40) and smaller.

(2) components and piping segments which have one inlet and one outlet, both of which are NPS 1 1/2 (DN 40) and smaller.

2 (3) components and piping segments which have multiple inlets or outlets, whose cumulative cross-sectional area does not exceed the cross-sectional area defined by the OD of NPS 4 (DN 40) pipe.

(c) Vessels, piping, pumps, valves, other components, and component connections of any size in statically pressurized, passive (i.e., no pumps) 3 safety injection systems of pressurized water reactor plants.

(d) Piping and other components of any size beyond the last shutoff valve in open-ended portions of systems that do not contain water during normal plant operating conditions.

1 RHR, ECC and CHR systems are the Residual Heat Removal, Emergency Core Cooling, and Containment Heat Removal Systems, respectively.

2 For heat exchangers, the shell side and tube side may be considered separate components.

3 Statically pressurized, passive safety injection systems of pressurized water reactor plants are typically called:

(a) accumulator tank and associated system (b) safety injection tank and associated system (c) core flooding tank and associated system Page 32 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 4.1.2 IWC-1222, Components within Systems or Portions of Systems Other Than 1

RHR, ECC, and CHR Systems .

(a) For systems, except auxiliary feedwater systems in pressurized water reactor plants:

(1) components and piping segments NPS 4 (DN 100) and smaller.

(2) components and piping segments which have one inlet and one outlet, both of which are NPS 4 (DN 100) and smaller.

2 (3) components and piping segments which have multiple inlets or outlets, whose cumulative cross-sectional area does not exceed the cross-sectional area defined by the OD of NPS 4 (DN 100) pipe.

(b) For auxiliary feedwater systems in pressurized water reactor plants:

(1) components and piping segments NPS 1 1/2 (DN 40) and smaller.

(2) components and piping segments which have one inlet and one outlet, both of which are NPS 1 1/2 (DN 40) and smaller.

2 (3) components and piping segments which have multiple inlets or outlets, whose cumulative cross-sectional area does not exceed the cross-sectional area defined by the OD of NPS 1 1/2 (DN 40) pipe.

(c) Vessels, piping, pumps, valves, other components, and component connections of any size in systems or portions of systems that operate (when the safety function is required) at a pressure equal to or less than 275 psig (1900kPa) and at a temperature equal to or less than 200°F (95°C).

(d) Piping and other components of any size beyond the last shutoff valve in open-ended portions of systems that do not contain water during normal plant operating conditions.

1 RHR, ECC and CHR systems are the Residual Heat Removal, Emergency Core Cooling, and Containment Heat Removal Systems, respectively.

2 For heat exchangers, the shell side and tube side may be considered separate components.

4.1.3 IWC-1223, Inaccessible Welds Welds or portions of welds that are inaccessible due to being encased in concrete, buried underground, located inside a penetration, or encapsulated by guard pipe.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 4.2 Component Examination Basis This section describes each Examination Category. The required percentage of examinations and any limitations for each Examination Category is described. All other requirements are found in Section XI, 2007 Edition with Addenda through 2008. The th Summary Tables located in 5 -Interval-ISI-PSL-1-Schedule satisfy the requirements of IWA-2420(b)(1) through (6) respectively.

A narrative discussion of Class 2 components subject to examination and testing are described in detail below:

4.3 Category C-A, Pressure Retaining Welds in Pressure Vessels Table C-A provides the examination scope and schedule for Table IWC-2500-1, Examination Category C-A, Pressure Retaining Welds in Pressure Vessels. Refer to Appendix C and D for applicable Relief Requests and Code Cases.

UNIT 1 Table C-A Number Scheduled by Item Number of Parts Examined Period Numbers Welds 1 2 3 C1.10 Shell Circumferential Welds 2 0 0 1 C1.20 Head Circumferential Welds 2 1 0 0 C1.30 Tubesheet to Shell Welds 4 0 1 1 Totals 8 1 1 2 Page 34 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 4.4 Category C-B, Pressure Retaining Nozzle Welds in Vessels Table C-B provides the examination scope and schedule for Table IWC-2500-1, Examination Category C-B, Pressure Retaining Nozzle Welds in Vessels. Refer to Appendix C and D for applicable Relief Requests and Code Cases.

UNIT 1 Table C-B Number Scheduled by Item Number of Period Parts Examined Numbers Welds 1 2 3 1

C2.21 Nozzle-to-Shell (or Head) Weld 6 2 2 2 1

C2.22 Nozzle Inside Radius Section 2 1 0 0 Totals 8 3 2 2 There are no item numbers C2.10, C2.31 or C2.32 applicable at St Lucie Unit 1.

1 Examinations are scheduled in accordance with Note (4) of Table IWC-2500-1, Examination Category C-B, for multiple vessels of similar design, size, and service.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 4.5 Category C-C, Welded Attachments for Vessels, Piping, Pumps, and Valves Table C-C provides the examination scope and schedule for Table IWC-2500-1, Examination Category C-C, Welded Attachments for Vessels, Piping, Pumps, and Valves. Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively.

Examinations are scheduled in accordance with Table IWC-2500-1, Examination Category C-C, Note (5), regarding Class 2 supports with integral attachments.

UNIT 1 Table C-C Number of Number Scheduled by Item Period Parts Examined Welded Numbers Attachments 1 2 3 C3.10 Welded Attachments 12 0 0 1 C3.20 Welded Attachments 40 1 2 1 Totals 52 1 2 2 There are no item numbers C3.30 or C3.40 applicable at St Lucie Unit 1.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 4.6 Category C-D - Pressure Retaining Bolting > 2" in Diameter St Lucie Unit 1 has no Category C-D bolting.

4.7 Category C-F-1, Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping.

These components will be examined under the RI ISI Program (Reference Section 2.0) and Relief Request No. RR-01.

4.8 Category C-F-2, Pressure Retaining Welds in Carbon or Low Alloy Steel Piping These components will be examined under the RI ISI Program (Reference Section 2.0) and Relief Request No. RR-01.

4.9 Category C-H, All Pressure Retaining Components The pressure retaining components within the class 2 system boundaries are subjected to system leakage tests in accordance with IWC-5220 and visually examined per IWA-5240.

System leakage tests will be performed in accordance with the rules of Section XI as modified by IWA-5110(c), which exempts piping that penetrates a containment vessel from periodic pressure testing when the piping and isolation valves perform a containment function and the balance of the piping system is outside the scope of Section XI, Division 1 (non-classed).

UNIT 1 Table C-H Number Scheduled by Item Period Parts Examined Numbers 1 2 3 C7.10 Pressure Retaining Parts * *

Pressure testing is performed once each examination period.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 5.0 Development of the Class 3 Examination Plan Plant controlled isometric, P&IDs, component drawings, and plant walkdowns were used to develop the ISI drawings and the scope of examinations. During examinations, drawings will be used to locate and identify each component. Other plant controlled drawings or documents will be used when additional information is required.

th Refer to the 5 -Interval-ISI-PSL-1-Schedule for a complete listing of components subject to examination and the proposed examination schedule.

The Class 3 system boundaries subject to examination and testing were developed based upon the requirements of Regulatory Guide 1.26, and ASME Section XI, Table IWD-2500-1.

5.1 Class 3 Code Exemptions and Exclusions The following Class 3 exemption criteria are applicable. Paragraph IWD-1220 of Section XI, 2007 Edition with Addenda through 2008 lists those piping and components exempt from examination.

5.1.1 IWD-1210 - Examination Requirements The examination requirements of this Subsection shall apply to pressure retaining components and their welded attachments on Class 3 systems in support of the following functions:

(a) reactor shutdown (b) emergency core cooling (c) containment heat removal (d) atmosphere cleanup (e) reactor residual heat removal (f) residual heat removal from spent fuel storage pool 5.1.2 IWD-1220 - Components Exempt from Examination The following components or parts of components are exempted from the VT-1 visual examination requirements of IWD-2500:

(a) components and piping segments NPS 4 (DN100) and smaller (b) components and piping segments which have one inlet and one outlet, both of which are NPS 4 (DN 100) and smaller (c) components1 and piping segments which have multiple inlets or multiple outlets whose cumulative pipe cross-sectional area does not exceed the cross-sectional area defined by the OD of NPS 4 (DN 100) pipe.

(d) components that operate at a pressure of 275 psig (1,900 kPa) or less and at a temperature of 200°F (95°C) or less in systems (or portions of systems) whose function is not required in support of reactor residual heat removal, containment heat removal, and emergency core cooling; (e) welds or portions of welds that are inaccessible due to being encased in concrete, buried underground, located inside a penetration, or encapsulated by guard pipe.

1 For heat exchangers, the shell side and tube side may be considered separate components.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 5.1.3 IWD-5222 Boundaries (a) The pressure-retaining boundary for closed systems includes only those portions of the system required to operate or support the safety-related function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required.

(b) The pressure-retaining boundary for nonclosed systems (e.g., service water systems) includes only those portions of the system required to operate or support the safety function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required. Open-ended discharge piping is included in the pressure-retaining boundary, provided it is periodically pressurized to conditions described in IWD-5221.

(c) The following portions of systems are excluded from examination requirements:

(1) Items outside the boundaries of IWD-5222(a).

(2) Items outside the boundaries of IWD-5222(b).

(3) Open-ended discharge piping that is not periodically pressurized to conditions described in IWD-5221.

(4) Portions of systems that are associated with a spray header or are normally submerged in its process fluid such that the external surfaces of the pressure-retaining boundary are normally wetted during its pressurized conditions.

5.2 Component Examination Basis This section describes each Examination Category. The required percentage of examinations and any limitations for each Examination Category is described. All other requirements are found in Section XI, 2007 Edition with Addenda through 2008. The th Summary Tables located in the 5 -Interval- ISI-PSL-1-Schedule satisfy the requirements of IWA-2420(b)(1) through (6) respectively.

The Class 3 system boundaries are identified on the site P&ID drawings. Specific examinations are in accordance with the ASME B&PV Code,Section XI, Table IWD-2500-1, as further described below.

The following components or parts of components are exempted from the VT-1 visual examination requirements of IWD-2500, Examination and Inspection, in accordance with IWD-1220, Components Exempt from Examination:

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 5.3 Category D-A, Welded Attachments for Vessels, Piping, Pumps, and Valves Table D-A provides the examination scope and schedule for Table IWD-2500-1, Examination Category D-A, Welded Attachments for Vessels, Piping, Pumps, and Valves.

Examinations will include each vessel welded attachment most subject to corrosion, and each vessel welded attachment most subject to corrosion of one vessel for each multiple-vessel group associated with component supports.

Examinations will also include 10% of the piping and pump welded attachments most subject to corrosion that are associated with component supports. Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively. The piping and pump welded attachment sample will be proportional to the total number of non-exempt welded attachments connected to the piping and pumps in each system.

UNIT 1 Table D-A No. of Minimum No. Minimum Number Item Parts Required by Period Welded of Exams Numbers Examined Attachments Required 1 2 3 Welded D1.10 16 10 4 2 4 Attachments Welded D1.20 36 4 1 1 2 Attachments Welded D1.30 6 2 0 2 0 Attachments Totals 60 16 5 5 6 T

There is no item number D1.40 applicable to St. Lucie Unit 1.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 5.4 Category D-B, All Pressure Retaining Components Table D-B identifies the system leakage and hydrostatic tests conducted in accordance with Table IWD-2500-1, Examination Category D-B, All Pressure Retaining Components. Refer to Appendices C and D for applicable Relief Requests and Code Cases, respectively.

UNIT 1 Table D-B Number Scheduled by Item Period Parts Examined Numbers 1 2 3 D2.10 Pressure Retaining Parts * *

A system leakage test (IWD-5220) shall be performed during each inspection period.

6.0 IWE Metal Containment Requirements The requirements for Code Class MC (Metal Containment) are found in the St. Lucie Nuclear Power Plant Unit 1 and 2 Second IWE Inspection Interval Program Plan, which is administered separately. This document establishes the administrative, managerial, and implementation control for the IWE Containment Inspection Program Plan for the Third 10-year Inservice Inspection interval.

7.0 Development of Component Supports Examination Plan Plant controlled isometric, P&IDs, component drawings, and plant walkdowns were used to develop the ISI drawings and the scope of examinations. During examinations, drawings will be used to locate and identify each component. Other plant controlled drawings or documents will be used when additional information is required.

th Refer to the 5 -Interval-ISI-PSL-1-Schedule for a complete listing of components subject to examination and the proposed examination schedule.

The Class 1, 2, and 3 system boundaries subject to examination and testing were developed based upon the requirements of Regulatory Guide 1.26, and ASME Section XI, Table IWF-2500-1.

7.1 Code Exemptions for Supports Under IWF-1230, component supports exempt from the examination requirements of IWF-2000 are those connected to piping and other items exempted from volumetric, surface, or VT-1 or VT-3 visual examination by IWB-1220, IWC-1220, IWD-1220, and IWE-1220. In addition, portions of supports that are inaccessible by being encased in concrete, buried underground, or encapsulated by guard pipe are also exempt from the examination requirements of IWF-2000.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 7.2 Support Examination Basis This section describes Examination Category F-A. The required percentage of examinations and any limitations is described. All other requirements are found in th Section XI, 2007 Edition with Addenda through 2008. The Summary Tables located in 5 Interval ISI-PSL-1-Schedule satisfy the requirements of IWA-2420(b)(1) through (6) respectively.

A narrative discussion of F-A supports subject to examination and testing is described in detail below:

7.2.1 Category F-A, Supports The Class 1, 2, 3, and MC component support boundaries are based on the requirements described in ASME B&PV Code,Section XI, Table IWF-2500-1, as indicated below. The term "component support" includes supports for such items as vessels and pumps, and supports for piping that are treated separately for selection purposes.

Exemptions from support examination requirements are in accordance with Article IWF-1000, Scope and Responsibility, subsection IWF-1230, Supports Exempt from Examination, with the exception of IWE examinations which are discussed within Section 6.0. Component supports exempt from the requirements of Article IWF-2000, Examination and Inspection, are those connected to piping and other items exempt from volumetric, surface, VT-1, or VT-3 visual examination under the following:

IWB-1220, IWC-1220 and IWD-1220 Components Exempt from Examination In addition, portions of supports that are inaccessible due to being encased in concrete, buried underground, or encapsulated by guard pipe, is also exempt from the requirements of Article IWF-2000, in accordance with IWF-1230, Supports Exempt from Examination.

Component supports selected and examined are those supports for components, (i.e., vessels, pumps, etc.), that are required to be examined in accordance with the following:

IWB-2500, IWC-2500 and IWD-2500 Examination and Inspection Requirements Supports examined for piping are selected in accordance with the percentages and sampling requirements of Table IWF-2500-1 from the support population of all piping not exempted under IWB-1220, IWC-1220, and IWD-1220, in accordance with IWF-2510, Supports Selected for Examination.

Examinations will be in accordance with Table IWF-2500-1, Examination Category F-A, and will include 25% of Class 1, 15% of Class 2, and 10% of Class 3 supports on non-exempt piping.

Examinations will also include selection of piping supports other than those selected under Class 1, 2, 3, and MC component supports for components being examined under Code Item No. 1.40 (Supports other than Piping Supports).

The total percentage sample will be comprised of supports from each system where the individual sample sizes are proportional to the total number of non-exempt supports of each type and function within each system.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 For multiple components other than piping, within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.

To the extent practical, the same supports selected for examination during the first inspection interval shall be examined during each successive inspection interval.

7.2.2 Item Numbers Supports have been categorized in the Fifth Ten-Year Interval Inservice Inspection Program Plan and Inservice Inspection Schedule to identify support types by component support function as follows (e.g. F1.10A, F1.10B, etc.,):

A - Deadweight hangers B - Restraints (multi-directional)

C - Thermal Movement (spring hangers)

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 UNIT 1 Table F-A Minimum Minimum #

Number Percent Item No. of Scheduled by Period System of Exams Numbers Supports Supports Required 1 2 3 Required CH 24 9.16% 6 2 2 2 F1.10A RC 21 8.02% 6 3 1 2 SI 77 29.39% 20 9 5 6 CH 13 4.96% 4 1 1 2 F1.10B RC 14 5.34% 4 1 2 1 SI 18 6.87% 5 2 1 2 CH 12 4.58% 3 3 0 0 F1.10C RC 41 15.65% 11 3 5 3 SI 42 16.03% 11 3 4 4 27 21 22 CC 3 0.71% 1 0 0 1 CS 26 6.18% 4 1 2 1 F1.20A FW 10 2.38% 2 1 0 1 MS 4 0.95% 1 1 0 0 SI 144 34.20% 22 7 8 7 CC 7 1.66% 2 0 1 1 CS 22 5.23% 4 3 1 0 F1.20B FW 7 1.66% 2 1 0 1 MS 5 1.19% 1 0 0 1 SI 86 20.43% 13 2 5 6 CC 15 3.56% 3 1 1 1 CS 13 3.09% 2 1 1 0 F1.20C FW 16 3.80% 3 1 1 1 MS 18 4.28% 3 0 1 2 SI 45 10.69% 7 6 2 2 25 23 25 C 15 3.15% 2 0 0 2 CC 151 31.72% 16 8 4 4 CW 60 12.61% 6 2 2 2 F1.30A FW 26 5.46% 3 2 1 0 PW 2 0.42% 1 0 0 1 SF 3 0.63% 1 0 1 0 C 6 1.26% 1 0 1 0 CC 89 18.70% 9 2 4 3 F1.30B CW 41 8.61% 5 1 2 2 FW 49 10.29% 5 1 2 2 SF 3 0.63% 1 0 0 1 C 1 0.21% 1 0 0 1 CC 26 5.46% 3 2 0 1 F1.30C CW 2 0.42% 1 0 0 1 SF 2 0.42% 1 1 0 0 19 17 20 Page 44 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 UNIT 1 Table F-A, F1.40 Total Minimum # Scheduled Number Number of Number by Period of Group Components of Supports in Group Supports 1 2 3 Required in Group Reactor Vessel 1 3 3 0 3 0 Steam Generators 2 2 1 0 0 1 Pressurizer 1 1 1 0 1 0 Reactor Coolant Pumps 4 16 1 0 0 1 Shutdown Cooling heat 2 4 1 0 1 0 Exchanger (SCHE)

Low Pressure Safety 2 4 1 0 0 1 Injection Pumps (LPSI)

Charging Pump Supports 3 3 1 0 1 0 Service Water Strainers 2 2 1 1 0 0 Component Cooling Water 2 8 1 1 0 0 Heat Exchanger Component Cooling Water 3 2 1 1 0 0 Pumps Component Cooling Water 1 2 2 2 0 0 Surge Tank Fuel Pool Cooling Pumps 2 2 1 0 0 1 Fuel Pool Cooling Heat 2 2 1 0 0 1 Exchangers TOTAL 7 6 5 7.3 Snubbers Snubbers are functionally tested under the Snubber Program, which is administered separately. The requirements for the snubber program are included in OSP-73.01. Visual, VT-3, examinations are performed on snubbers as required by Examination Category F-A, when selected. The snubbers as well as the welded attachments associated with snubbers are scheduled and tracked within the ISI Program database.

8.0 IWL Concrete Containment Requirements St. Lucie Unit 1 has a concrete missile shield surrounding the metal containment. This missile shield does not perform any containment functions and is outside the scope of Section XI. No examinations are required.

The bottom of containment has a metal liner, covered with concrete. The concrete serves only as a protective covering and is outside the scope of Section XI. No examinations are required.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 9.0. Augmented and Other Programs This section identifies augmented inspection programs maintained within the ISI Program that are not required by ASME Section XI. However, due to the nature of the augmented requirements, these programs have been included within the ISI Program. These augmented programs satisfy NRC requirements, operating experience, engineering judgment, etc. Augmented program revisions or deviations shall be governed by the referenced documents. The following is the detailed description of the St. Lucie Unit 1 Inservice Inspection Program Plan Basis for Augmented Examination of additional components/systems.

9.1 Class 1 9.1.1 Reactor Coolant Pump Flywheel As required by the UFSAR, Section 5.5.5.3, each Reactor Coolant Pump Flywheel is examined per the requirements of Regulatory Guide 1.14, Position C.4.b. The bore and keyway areas of each Reactor Coolant Pump flywheel are examined ultrasonically approximately every three years. Additionally, the flywheels receive a complete volumetric examination (UT) and a surface examination of all exposed surfaces at or near the end of each Inspection Interval.

Schedule identifier - Category AUG, Item RG 1.14 9.1.2 MRP-139 - Primary System Piping Butt Weld Inspection and Evaluation Guidelines (Historical)

The guideline provides generic inspection and evaluation guidelines for PWR primary system alloy 600/82/182 butt welds. Per the implementation protocol of the NEI 03-08 initiative, these guidelines are mandatory for PWR licensees. On January 4, 2011, MRP letter 2010-046 was issued that provided interim guidance for the rescission of MRP-139, R1 mandatory requirements when 10CFR50.55a was revised to require implementation of ASME Code Case N-770-2.

10CFR50.55a, effective date August 17, 2017, requires that St Lucie implement the requirements of ASME Code Case N-770-2 with conditions.

9.1.3 MRP-146 - Management of Thermal Fatigue in Normally Stagnant Non-Isolable RCS Branch Lines This report provides needed guidelines and other good practice recommendations for evaluating and inspecting regions in normally stagnant PWR reactor coolant system branch lines where there may be potential for thermal fatigue cracking that could lead to leakage and forced plant outages. Per the implementation protocol of the NEI 03-08 initiative, these guidelines are needed actions for PWR licensees.

Exams Required First Outage After January 31, 2009. Item Installed SL1-23 Reference AR#01666237-01, AR#1906729. Reference documents MRP-146 Rev 1 (EPRI TR 1022564): Tables 1-1A/B (Item #3) and Figures 2-1 & 2-2; SIA File No. ROM-10-008 Rev 1; EC 277280; AR 01666237-01.

AR#1906729. Examination required at the sixth (SL1-29) & twelfth (SL1-35) RFO from when the drain lines were replaced in Spring 2010 for Unit 1 (SL1-23).

Examination reverts back to every other outage as identified in MRP-146 Revision 1 after the twelfth RFO (SL1-35). The re-inspection frequency is the new re-inspection frequency in PSL-ENG-SESJ-13-005 "Technical Justification for Deviation from EPRI MRP-146 Inspection Schedule for 2 Inch Drain Lines".

The deviation is located under EC-280047.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 UT examination of Horizontal pipe base material at weld to be performed as required by MRP-146, Figures 2-15 & 2-18. UT examination to be performed on inner 1/3 thickness of base material within a 1/2 inch wide region around the pipe as close as practical to the toe of the socket weld on the horizontal piping. UT of the weld and beneath the weld not required.

Schedule identifier - Category AUG, Item MRP-146 9.1.4 MRP-227 - PRESSURIZED WATER REACTOR (PWR) INTERNALS INSPECTION AND EVALUATION GUIDELINES MRP-227 the technical basis for implementing inspection requirements for PWR RVI components that are subject to any of the applicable degradation mechanisms (e.g., stress corrosion cracking (SCC), intergranular stress corrosion cracking, irradiation-assisted stress corrosion cracking (IASCC), wear, fatigue, thermal and/or neutron embrittlement, void swelling, and irradiation-enhanced stress relaxation) during the LR period. MRP-227 also provides a brief, high-level summary of flaw evaluation guidelines for RVI components that exhibit active degradation mechanisms, and establishes requirements for inspection of additional components if an active degradation mechanism is discovered (i.e., expansion of the scope of RVI component inspections).

Schedule identifier - Category AUG, Item MRP-227 9.1.5 Code Case N-729 Alternative Examination requirements for PWR reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration Welds,Section XI, Division 1 10CFR50.55a(g)(6)(ii)(D)(1) requires that St Lucie augment the inservice inspection program by implementing ASME Code Case N-729-4 subject to the conditions specified in paragraphs 10CFR50.55a(g)(6)(ii)(D)(2) through (4). For the replacement component installed during PSL 1-20, a BMV examination is required every 3rd RFO or 5 years, whichever is less and a Volumetric and/or surface examination is required of all nozzles not to exceed 1 Inspection Interval (nominally 10 calendar years). The first BMV examination was required PSL 23 and the first Volumetric and/or Surface examination is required by 2015.

Reference FPL Engineering Evaluation PTN-ENG-SESJ-01-0058, Rev. 0.

FPL submitted and received NRC approval to defer the volumetric/surface examinations of the replacement RPV head to 2021 via Relief Request #12 th during the previous (4 ) interval.

Schedule identifier - Category AUG, Item B4.30 Schedule identifier - Category AUG, Item B4.40 Page 47 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 9.1.6 Code Case N-722 Additional Examinations for PWR Pressure Retaining Welds in Class 1 components Fabricated With Alloy 600/82/182 Materials,Section XI, Division 1 10CFR50.55a(g)(6)(ii)(E) requires that St Lucie augment the inservice inspection program by implementing ASME Code Case N-722-1 subject to the conditions specified in paragraphs (g)(6)(ii)(E)(2) through (4). The inspection requirements of ASME Code Case N-722-1 do not apply to components with pressure retaining welds fabricated with Alloy 600/82/182 materials that have been mitigated by weld overlay or stress improvement. For inspections to be conducted every refueling outage and inspections conducted every other refueling outage, the initial inspection shall be performed at the next refueling outage after January 1, 2009. For inspections to be conducted once per interval, the inspections shall begin in the interval in effect on January 1, 2009, and shall be prorated over the remaining periods and refueling outages in this interval.

Inspections are required every other outage beginning January 1, 2009.

Schedule identifier - Category AUG, Item B15.205 Schedule identifier - Category AUG, Item B15.215 9.1.7 Code Case N-770 Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation ActivitiesSection XI, Division 1 10CFR50.55a(g)(6)(ii)(F)(1) requires that St Lucie implement the requirements of ASME Code Case N-770-2 subject to the conditions specified in paragraphs (g)(6)(ii)(F)(2) through (13) effective date August 17, 2017.

Schedule identifier - Category AUG, Item B Schedule identifier - Category AUG, Item C-1 Schedule identifier - Category AUG, Item D 9.1.8 Material Surveillance Capsules Material Surveillance capsules are identified via the ISI program for tracking and removal. Direction is provided for scheduling purposes from the Fleet Materials Group.

Schedule identifier - Category AUG, Item APP. H 9.1.9 NRC Bulletin 88-08 Visually inspect suspect locations on an interval basis Schedule identifier - Category AUG, Item 88-08 Page 48 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 9.1.10 NRC Bulletin 88-11 PSL-ENG-LRAM-15-001, Pressurizer Surge Line Welds Inspection Program -

Aging Management Program (AMP) - License Renewal Basis Document. This Aging Management Program was approved by NRC Safety Evaluation Report dated October 13, 2016 (ML16235A158 and CAC NOS. MF7026 and MF7027).

This License Renewal Basis Document is based Structural Integrity Associates, Inc. Report No. 1301103.401, Rev 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L dated May 2015, and Structural Integrity Associates, Inc. Report No. 1301103.301 through 304, Appendix L Flaw Tolerance Evaluation of Surge Line, PSL Units 1 & 2.

th Starting in the fourth interval and continuing into the 5 interval volumetric examination will be implemented on all Surge Line welds scheduled under the rules of ASME Section XI. All relevant indications identified in the pressurizer surge line welds that exceeds the acceptance criteria will be documented in the corrective action program and reported to Site Engineering to assess the impact on the Environmental Assisted Fatigue (EAF) evaluation. These relevant indications may require further evaluation per ASME Code Section XI, Appendix L. In addition, continued operability of the welds will be assessed based on engineering evaluation, repair, replacement, or analytical evaluation in accordance with ASME Code Section XI, Subarticle IWB-3600.

Schedule identifier - Category AUG, Item 88-11 9.2 Class 2 9.2.1 Standard Review Plan 6.6 (a) Welds in those portions of systems addressed in USNRC Branch Technical Position MEB 3-1 and UFSAR Appendix 3J; (b) Welds in those portions of systems addressed in SRP 6.6 paragraph I.6.

In addressing the augmented examination requirements, referenced in (a) and (b) above, pipe-to-pipe welds and longitudinal seams are required to be examined. Additionally, the boundary is extended past the code class boundary (MSIV) to the first restraint providing at least two degrees of restraint to piping thermal expansion. The welds and supports thus affected are specifically identified through Examination Notes in the Main Steam and Feedwater examination Tables.

Schedule identifier - Category AUG, Item SRP-6.6 9.2.2 NRC Bulletin 79-13 Augmented Feedwater Examinations, as a result of a continuation of NRC Bulletin 79-13, and NRC Informational Notice 93-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators.

FPL will perform a continuous enhanced ultrasonic examination starting at the Feedwater Nozzle ramp and extending out to a point of 1 diameter on the elbow.

Examinations will be performed in conjunction with the Code examination th schedule as identified within the 5 -Interval-ISI-PSL-1-Schedule examination Tables.

Schedule identifier - Category AUG, Item 79-13 Page 49 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 9.2.3 MRP-192 - Assessment of RHR Mixing Tee Thermal Fatigue in PWR Plants This report provides needed guidelines and other good practice recommendations for evaluation and inspecting all PWR RHR mixing tee welds within at least four internal pipe diameters downstream from the mixing tee junction point, including the mixing tee downstream weld where there may be potential for thermal fatigue cracking that could lead to leakage and forced plant outages. Per the implementation protocol of the NEI 03-08 initiative, these guidelines are needed actions for PWR licensees.

Schedule identifier - Category AUG, Item MRP-192 10.0 Evaluation/Acceptance Criteria Florida Power and Light will perform non-destructive examinations using visual, surface (Penetrant and Magnetic Particle), and volumetric (Ultrasonic, Radiography, and Eddy Current) techniques. Other NDE techniques may be utilized when required.

During inservice inspections, NDE indications are evaluated against the acceptance standards of ASME Section XI. Components with indications that do not exceed the acceptance criteria will be considered acceptable for continued service. Additional examinations are not required.

Examinations that reveal indications shall be evaluated in accordance with article IWA-3000, IWB-3000, IWC-3000, IWD-3000, and IWF-3000, as applicable. Additional guidance for conditions identified during component support examinations, including minimum thread engagement acceptability, is located in engineering discipline standard STD-C-011.

10.1 Supplemental Examinations Examinations that detect flaws/conditions that require evaluation in accordance with the requirements of IWB-3100, IWC-3100, or IWF-3100, may be supplemented by other examination methods and techniques within the limits specified by IWB-3200, IWC-3200, or IWF-3200.

10.2 Additional Examinations Examinations that reveal flaws or relevant conditions that exceed the referenced acceptance standard, shall be extended to include additional examinations during the current outage. The additional examination requirements of IWB-2430, IWC-2430, IWD-2430, or IWF-2430, (as applicable) shall be performed as determined by Nuclear Engineering. When applicable, the criteria of Code Case N-586-1 may be applied to establish alternative examination requirements.

10.3 Successive Examination for Components Where components are accepted for continued service by analytical evaluation, IWB-2420(b), IWC-2420(b), or IWF-2420(b), the area containing the flaws or component support shall be subsequently reexamined in accordance with the following; 10.3.1 Class 1 Components (IWB-2420)

If a component is accepted for continued service by analytical evaluation, the areas containing flaws or relevant conditions shall be reexamined during the next three inspection periods listed in the schedule of the Inspection Program of IWB-2400. If the flaws or relevant conditions remain essentially unchanged for three successive inspection periods, the component examination schedule will revert to the original schedule of successive inspections.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 10.3.2 Class 2 Components (IWC-2420)

If a component is accepted for continued service by analytical evaluation, the areas containing flaws or relevant conditions shall be reexamined during the next inspection period listed in the schedule of the Inspection Program of IWC-2400. If the flaws or relevant conditions remain essentially unchanged for the next inspection period, the inspection schedule will revert to the original schedule of successive inspections.

10.3.3 Component Supports (IWF-2420)

If a component support is accepted for continued service by analytical evaluation, the component support shall be reexamined during the next inspection period listed in the schedule of the Inspection Program of IWF-2410. If the examinations do not require additional corrective measures during the next inspection period, the inspection schedule will revert to the original schedule of successive inspections.

11.0 Repair/Replacement Activities The requirements of the 2007 Edition with the 2008 Addenda of Section XI and the Repair and Replacement Program for St. Lucie Nuclear Plant shall be met for Class 1, 2, and 3 piping and components and their supports. QI-10-PR/PSL-8, Control of Repairs and Replacements, details specific requirements for the repair, replacement, or modification of ISI components.

12.0 Relief Requests A relief request is required when there are situations where Code requirements cannot be met or where an alternative is desired. Relief Requests shall be prepared using the NEI guidance for the standard format for requests from commercial reactor licenses pursuant to 10CFR50.55a. Relief requests will be reviewed for completeness, technical adequacy, and implementation. Reviewers may be the site ISI Coordinators, the Fleet Program Engineer, NDE personnel, and any other group the relief request may affect. Typical examples where relief requests are submitted are as follows:

12.1 For Class 1 and 2 weld examinations, relief is required if 90% or less of the Code required coverage was achieved (unable to meet Code examination requirements).

12.2 The request for use of an alternative to a requirement listed within ASME Section XI. An example is the use of a Code Case that has not been approved for use by the latest revision of NRC Reg. Guide 1.147.

13.0 Addition of Welds, Components, and Components Supports The rules for selection and scheduling of examinations for new welds shall be in accordance with paragraphs IWB-2411(b), IWC-2411(b), IWD-2411(b), IWF-2410(c).

14.0 Records 14.1 General Records of Inservice Inspection Program Plans, outage schedules, calibration standards, examination and test procedures, results of activities, final reports, certifications, and corrective actions will be developed and maintained in accordance with IWA-6000.

14.2 Nondestructive Examinations Completed NDE examination data packages shall be submitted to the Fleet Program Engineer following completion of the inservice examination activity.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 14.3 Final Reports 14.3.1 Final reports shall be generated for the following activities:

(a) Nondestructive examination activities performed on Class 1, 2, and 3 systems, components and their supports (b) Nondestructive examination activities performed on Class MC system (c) Snubber examinations and tests (d) System pressure tests (e) Eddy current examinations (f) Repairs and replacements 14.3.2 The final reports shall contain, as a minimum, the information required in the NIS-1 or OAR-1 (Code Case N-532-5 as accepted in NRC Reg. Guide 1.147).

14.4 Inservice Inspection Summary Report FPL shall forward a summary report, NIS-1 or OAR-1, of the ISI activity to the Nuclear Regulatory Commission in accordance with IWA-6230 or Code Case N-532-5 (as accepted in NRC Reg. Guide 1.147), as applicable.

14.5 NIS-2 or NIS-2A Reports NIS-2 forms, or if Code Case N-532-5 is followed, an NIS-2A form, will be completed for each repair or replacement.

14.6 NIS-BB Form An NIS-BB form will be completed after each Steam Generator tube examination (If applicable).

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 15.0 References The Inservice Inspection Program for Class 1, 2, and 3 (or Quality Groups A, B, and C respectively) systems and components and supports, was developed after reviewing the following documents and procedures. Limitations of design, geometry, and materials of construction may have an impact on the implementation of some of these documents.

15.1 10 CFR 50.55(a) Code of Federal Regulations.

15.2 Section XI of the American Society of Mechanical Engineers (ASME) Code, 2007 Edition through the 2008 Addenda.

15.3 USNRC Regulatory Guide 1.14 - Reactor Coolant Pump Flywheel Integrity, Revision 1, dated August 1975.

15.4 USNRC Regulatory Guide 1.26 - Quality Group Classifications and standards for Water-,

Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants, Revision 3, dated February 1976.

15.5 USNRC Regulatory Guide 1.147 - Inservice Inspection Code Case Acceptability ASME Section XI.

15.6 USNRC Information Notice 93-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators, dated March 24, 1993.

15.7 USNRC Bulletin 79-13, Cracking in Feedwater System Piping.

15.8 USNRC Bulletin 88-11, Pressurizer Surge Line Thermal Stratification.

15.9 EPRI Document, Guideline for the Implementation of Appendix VIII and 10 CFR 50.55a, Update 2005, EPRI, Palo Alto, CA: 2005 1010007 15.10 USNRC Standard Review Plan 6.6, paragraph I.6, (for Class 2 Augmented Inspections).

15.11 Branch Technical Position MEB 3-1, High Energy Fluid Systems, Protection Against Postulated Piping Failures in Fluid Systems Outside Containment.

15.12 First, Second, Third and Fourth Interval Inservice Inspection Long Term Programs, Plans, and Schedules for St. Lucie Unit 1.

15.13 St. Lucie Unit 1 Updated Final Safety Analysis Report 15.14 St. Lucie Unit 1 Technical Specifications, Docket number 50-335.

15.15 STD-C-011, Acceptance Criteria for As-Built Safety Related Piping and Pipe Supports, and Specification SPEC-M-004, Maintenance Bolting Specification for St. Lucie Units 1 and 2 and Turkey Point Units 3 and 4.

15.16 Generic Aging Lessons Learned (GALL) Report.

15.17 St. Lucie Document - QI-10-PR/PSL-4, Plant Inservice Inspection.

15.18 St. Lucie Document - OSP-73.01, Guidelines for the Implementation of the Snubber Inspection and Test Program.

15.19 St. Lucie Document - QI-10-PR/PSL-8, Control of Repairs and Replacements.

15.20 St. Lucie Document - QI-11-PR/PSL-8, Control of Inservice Pressure Testing.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 15.21 Engineering QI - ENG-QI 5.2, Implementation of ASME Section XI (Inservice Inspection).

15.22 Engineering Evaluation PSL-ENG-LRAM-01-026, Evaluation of Environmental Effects of Fatigue - License Renewal Basis Document.

15.23 Engineering Evaluation PSL-ENG-LRAM-00-056, Reactor Vessel Internals Inspection Program - License Renewal Basis Document.

15.24 Engineering Evaluation PSL-ENG-LRAM-00-097, ASME Section XI, Subsections IWB, IWC and IWD Inservice Inspection Program - License Renewal Program Basis Document.

15.25 Engineering Evaluation PSL-ENG-LRAM-00-119, ASME Section XI, Subsection IWF Inservice Inspection Program -License Renewal Program Basis Document.

15.26 Engineering Evaluation PSL-ENG-LRAM-00-120, Reactor Vessel Integrity Program -

License Renewal Basis Document.

15.27 CSI Procedure- ER-SR-107, Alloy 600 Management Program nd 15.28 St. Lucie Document 2 Interval IWE-PSL-1/2-Program Plan, St. Lucie Nuclear Power Plant Unit 1 and 2 Second IWE Inspection Interval Program Plan.

15.29 MRP-146- Materials Reliability Program: Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines (MRP-146, Revision 1),

EPRI, Palo Alto, CA: 2011. 1022564 15.30 Nuclear Energy Institute NEI 04-05, Living Program Guidance to Maintain Risk-Informed Inservice Inspection Programs for Nuclear Plant Piping Systems, April 2004 15.31 MRP-192 - Materials Reliability Program: Assessment of RHR Mixing Tee Thermal Fatigue in PWR Plants (MRP-192), EPRI, Palo Alto, CA: 2005. 1013305.

15.32 EPRI Document, Nondestructive Evaluation: Guideline for Conducting Ultrasonic Examinations of Dissimilar Metal Welds, Revision 1. EPRI, Palo Alto, CA: 2013.

3002000091 15.33 ER-AA-208, Dissimilar Metal (DM) Weld Examination Process 15.34 ER-AA-119, Snubber Program 15.35 OSP-73.01, Guidelines for the Implementation of the Snubber Inspection and Test Program 15.36 St. Lucie Document 5th-Interval-ISI-PSL-1-Schedule, " Fifth Inservice Inspection Interval Schedule For St. Lucie Unit 1".

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Appendix A P&ID Drawings Drawing Sheet P&ID Title Number Number 8770-G-078 110A/110B Reactor Coolant System 8770-G-078 111A Reactor Coolant Pump 1A1 8770-G-078 111B Reactor Coolant Pump 1A2 8770-G-078 111C Reactor Coolant Pump 1B1 8770-G-078 111D Reactor Coolant Pump 1B2 8770-G-078 120A Chemical and Volume Control System 8770-G-078 120B Chemical and Volume Control System 8770-G-078 121A Chemical and Volume Control System 8770-G-078 121B Chemical and Volume Control System 8770-G-078 130A Safety Injection System 8770-G-078 130B Safety Injection System 8770-G-078 131 Safety Injection System, Sheet 2 8770-G-078 140 Fuel Pool System 8770-G-079 1 Main Steam 8770-G-079 7 Main Steam 8770-G-080 3 Feedwater and Condensate Systems 8770-G-080 4 Feedwater and Condensate Systems 8770-G-082 1 Circulating and Intake Cooling Water System 8770-G-082 2 Intake Cooling Water Lube Water System 8770-G-083 1 Component Cooling System, Sheet 1 8770-G-083 2 Component Cooling System, Sheet 2 8770-G-086 1 Miscellaneous Systems, Sheet 1 8770-G-088 1 Containment Spray and Refueling Water Systems 8770-G-088 2 Containment Spray and Refueling Water Systems 8770-G-096 1A Emergency Diesel Generator System, Diesel Engine 1A1 8770-G-096 1B Emergency Diesel Generator System, Diesel Engine 1A2 8770-G-096 1C Emergency Diesel Generator System, Air Start Package 1A 8770-G-096 2A Emergency Diesel Generator System, Diesel Engine 1B1 8770-G-096 2B Emergency Diesel Generator System, Diesel Engine 1B2 8770-G-096 2C Emergency Diesel Generator System, Air Start Package 1B Page 55 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Appendix B Calibration Block Listing Block ID MATERIAL SIZE APPLICATION UT-1 SA-533 GR.B 11" RPV UPPER SHELL UT-2 SA-533 GR.B 9" RPV UT-3A SA-533 GR.B 7" RPV UT-4 SA-533 GR.B 5" RPV UT-4A SA-533 CL.1, GR.B 5" PZR UT-5 SA-533 CL.1, GR.B 3" 3" RC PIPING SA-516 GR.70 UT-6 3.5" RC PIPING W/304L CLAD SA-516 GR.70 PSL-2 SPRAY NOZZLE UT-7A 3" UNCLAD SE RPV FLANGE UT-8 SA-533 GR.B 7" LIGAMENT UT-9 SA-533 GR.B RPV INLET NOZZLE UT-10 SA-533 GR.B RPV OUTLET NOZZLE SA-351 CF8M 12.75" DIAMETER SAFE UT-16 12.75 x 1.25"T SA-106 GR.B ENDS SA-182,TP316 6" DIAMETER SAFE UT-17 6 x 1.25"T SA-533 CL1 A ENDS SA-182, 316 CHARGING INLET UT-18 5 x 1.25T SA-533, GR B NOZZLE SE SA-182 TP316 4 5/8" DIAMETER SAFE UT-19 4.625 x .625"T SA-533 CL1 A ENDS 12.75" DIAMETER PZR.

UT-23 SA-351 CF8M 12.75 x 1.312"T SURGE NOZZLE SAFE END UT-28A SA-533 GR.B CL1 4" RCS PIPE 18" DIAMETER UT-29 SA-516 GR.70 18 x 1"T FEEDWATER UT-31 SA-516 GR.70 6 x 6 x 1.625"T FLAT BLOCK SA-182 TP316 LETDOWN & DRAIN UT-33 3 7/16 x 7/8"T SA-533 CL1 NOZZLE SAFE END SA-182 TP316 4.5" dia x SPRAY NOZZLE UT-34 SA-533 CL1 .93" T SAFE END SA-376 (SA-312)

UT-35 1.34"T 12" SCH. 160 TP304 UT-37/UT37R SA 312 TP304 1.125"T 10.75" O.D.

UT-38 SA-312 TP304 .719"T 6" SCH. 160 PIPING UT-39 SA-312 TP304 .531" 4" SCH. 160 PIPING UT-40 SA-312 TP316 .531" 20" SCH. 80 PIPING UT-41 A-106 GR.B 1.031" 20" SCH. 80 PIPING UT-42 A-106 GR.B 1.50" 20" SCH. 120 IPING UT-43 A-106 GR.B .938" 18" SCH. 80 PIPING UT-44 A-515 GR 70 2" 35.5" DIAMETER UT-45 A-155/515 GR.65 1.250" 34" DIAMETER UT-46 A-106 GR.B 1.125" 10" SCH. 160 UT-47 A-106 GR.B .594" 10" SCH. 80 UT-48 A-106 GR.B .906" 8" SCH. 160 Page 56 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Block ID MATERIAL SIZE APPLICATION UT-49 A-519 1.5" 6" DIA.

UT-50 A-182 TP304 1.56" 12" SCH. 160 UT-54 A-312 TP304 .562" 6" SCH. 120 A-540-80A GR. B23 UT-54R 4.75 RCP STUD CL4 UT-56 A-516-79B GR.70 1.15" 1" + CLAD FLAT PLATE UT-58R SA-540 GR.B23 4.75 4.75" RCP STUD UT-59 A-351 CF8M CSS/CS RCP SAFE END BLOCK UT-60 SA312 TP304 .280 6 SCH 40 4 SCH 80 (From PTN UT-61 SA-312 TP304 UT-48) 12 SCH 160 PSL-1 UT-65 SA403/WP-S 1.310T Surge Line 7-1.125-8-CS-RPV STUD 52-SLC (UT-52) 3-SS-160-.434-SA-312 TP304 .434 3 SCH 160 (PSL-1 block) 22-SLC 2-SS-160-.342-SA-312 TP304 .342 2 SCH 160 (PSL-1 block) 20-SLC 10-SS-30-.308-SA-312 TP 304 .308 10SCH 30 (PSL-1 block) 36-SLC Z-20787(UT- PSL-1 Mainsteam Valve SA193 GR B16 2.25

62) Bolting PSL-1 S/G Welds 8, 80, 20T-102 SA508 CL3 4 173 PSL-1 S/G Welds 65, 20T-103 SA508 CL3 5.6 160, 169 SA508 CL3 (CS 20T-120 7.25 PSL-1 S/G Weld 3 W/CL) 20T-125 SA533 GR B CL1 4.002 PSL-1 S/G Weld 162 SA508 CL3 (CS 20T-133 8.4 PSL-1 S/G Welds 4, 22 W/CL)

PSL-1 S/G Welds 256, 20T-156 SB-166 1.1 284 20T-158 SA508 CL1A 1.1 PSL-1 S/G Weld 256 20T-167 SA508 CL3 4.972 PSL-1 S/G Welds 5,6,7 20T-173 SA508 CL1 4.305 PSL-1 S/G Weld 16 20T-174 SA508 CL1 3.220 PSL-1 S/G Welds 17, 18 BC/P101SL PSL-1 Pressurizer Shell SA508 GR3 CL2 5.0 (5061573) Welds Page 57 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Appendix C Relief Request Relief Requests Relief Request Description Status Number Risk-Informed ISI Program For Class 1 & 2 RR-01 Pending Submittal Piping Welds RR-02 Not Used N/A Approved January 4, 2018 RR-03 ICW Patch Plate Repairs CAC. NO. MF9288 ML17341A442 RR-04 CEDM Alternative Pending Submittal RR-05 Half Nozzle Repair Pending Submittal RR-06 RWT Tank Repairs Pending Submittal Copies of the relief requests and associated documentation are maintained in the ISI Program Notebook.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Appendix D ASME Section XI Code Cases Regulatory Number Description Guide Revision Repair Welding Using Automatic or Machine Gas Tungsten-Arc Welding (GTAW) Temper Bead Technique,Section XI, N-432-1 18 Division 1 Evaluation Criteria For Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping,Section XI Division 1, N-513-3 The repair or replacement activity temporarily deferred under the provisions of this Code Case shall be performed 18 during the next scheduled outage N-526 Alternative Requirements for Successive Inspections of Class 1 and 2 Vessels,Section XI, Division 1 18 Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report N-532-5 18 Preparation and Submission as Required by IWA-4000 and IWA-6000,Section XI, Division 1 N-537 Location of Ultrasonic Depth-Sizing Flaws,Section XI, Division1 18 Alternative Requirements for Wall Thickness Restoration of Class 2 and High Energy Class 3 Carbon Steel Piping,Section XI, Division 1 (1) Paragraph 5(b): for repairs performed on a wet surface, the overlay is only acceptable until the next refueling outage.

N-561-2 (2) Paragraph 7(c): if the cause of the degradation has not been determined, the repair is only acceptable until the 18 next refueling outage.

(3) The area where the weld overlay is to be applied must be examined using ultrasonic methods to demonstrate that no crack-like defects exist.

(4) Piping with wall thickness less than the diameter of the electrode shall be depressurized before welding.

Alternative Requirements for Wall Thickness Restoration of Class 3 Moderate Energy Carbon Steel Piping,Section XI, Division 1 (1) Paragraph 5(b): for repairs performed on a wet surface, the overlay is only acceptable until the next refueling outage.

N-562-2 (2) Paragraph 7(c): if the cause of the degradation has not been determined, the repair is only acceptable until the 18 next refueling outage.

(3) The area where the weld overlay is to be applied must be examined using ultrasonic methods to demonstrate that no crack-like defects exist.

(4) Piping with wall thickness less than the diameter of the electrode shall be depressurized before welding.

N-586-1 Alternative Examination Requirements for Classes 1, 2, and 3 Piping Component and Supports,Section XI, Division 1 18 N-600 Transfer of Qualifications Between Owners,Section XI, Division 1 18 Page 59 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Appendix D ASME Section XI Code Cases Regulatory Number Description Guide Revision Ultrasonic Examination of Penetration Nozzles in Vessels, Examination Category B-D, Item Nos. B3.10 and B3.90, reactor N-613-2 18 Nozzle-to-Vessel Welds, Figs. IWB-2500-7(a), (b), and (c),Section XI, Division 1 Alternative Calibration Block Material,Section XI, Division 1 N-639 Chemical ranges of the calibration block may vary from the materials specification if (1) it is within the chemical 18 range of the component specification to be inspected, and (2) the phase and grain shape are maintained in the same ranges produced by the thermal process required by the material specification.

Alternative Requirements for Inner Radius Examination of Class 1 Reactor Vessel Nozzles,Section XI, Division 1 N-648-1 In lieu of a UT examination, licensees may perform a VT-1 examination in accordance with the code of record for 18 the Inservice Inspection Program utilizing the allowable flaw length criteria of Table IWB-3512-1 with limiting assumptions on the flaw aspect ratio.

Ferritic and Dissimilar Metal Welding Using SMAW Temper Bead Technique Without Removing the Weld Bead Crown for N-651 18 the First Layer,Section XI, Division 1 Alternative Wall Thickness Restoration For Class 2 and 3 Carbon Steel Raw Water Service,Section XI Division 1 (1) Paragraph 4(b): for repairs performed on a wet surface, the overlay is only acceptable until the next refueling outage.

N-661-2 (2) Paragraph 7(c): if the cause of the degradation has not been determined, the repair is only acceptable until the 18 next refueling outage.

(3) The area where the weld overlay is to be applied must be examined using ultrasonic methods to demonstrate that no crack-like defects exist.

(4) Piping with wall thickness less than the diameter of the electrode shall be depressurized before welding.

Evaluation Criteria for Temporary Acceptance of Degradation in Moderate Energy Class 2 or 3 Vessels and Tanks, N-705 18 Section XI, Division 1 Alternative Examination Requirements of Table IWB-2500-1 and Table IWC-2500-1 for PWR Stainless Steel Residual and N-706-1 18 Regenerative Heat Exchangers,Section XI, Diviision 1 Page 60 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Appendix D ASME Section XI Code Cases Code Regulatory Case Description Guide Number Revision Additional Examinations of PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials,Section XI, Division 1 (As required by 10CFR50.55a(g)(6)(ii)(E), effective date 8/17/2017, with modifications per 10CFR50.55a(g)(6)(ii)(E)(1) through (E)(4)).

(E)(1) All licensees of pressurized water reactors must augment their inservice inspection program by implementing ASME Code Case N-722-1, subject to the conditions specified in paragraphs (g)(6)(ii)(E)(2) through (4) of this section.

The inspection requirements of ASME Code Case N-722-1 do not apply to components with pressure retaining welds fabricated with Alloy 600/82/182 materials that have been mitigated by weld overlay or stress improvement.

(E)(2) If a visual examination determines that leakage is occurring from a specific item listed in Table 1 of ASME Code Case N-722-1 that is not exempted by the ASME Code,Section XI, IWB-1220(b)(1), additional actions must be performed to characterize the location, orientation, and length of a crack or cracks in Alloy 600 nozzle wrought material Per N-722-1 and location, orientation, and length of a crack or cracks in Alloy 82/182 butt welds. Alternatively, licensees may replace 10CFR50.55a the Alloy 600/82/182 materials in all the components under the item number of the leaking component.

(E)(3) If the actions in paragraph (g)(6)(ii)(E)(2) of this section determine that a flaw is circumferentially oriented and potentially a result of primary water stress corrosion cracking, licensees must perform non-visual NDE inspections of components that fall under that ASME Code Case N-722-1 item number. The number of components inspected must equal or exceed the number of components found to be leaking under that item number. If circumferential cracking is identified in the sample, non-visual NDE must be performed in the remaining components under that item number.

(E)(4) If ultrasonic examinations of butt welds are used to meet the NDE requirements in paragraphs (g)(6)(ii)(E)(2) or (3) of this section, they must be performed using the appropriate supplement of Section XI, Appendix VIII, of the ASME BPV Code.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Appendix D ASME Section XI Code Cases Code Regulatory Case Description Guide Number Revision Alternative Examination Requirements for PWR Reactor Vessel Upper Heads with Nozzles Having Pressure-Retaining Partial-Penetration Welds,Section XI, Division 1 (As required by 10CFR50.55a(g)(6)(ii)(D), effective date 8/17/2017, with modifications per 10CFR50.55a(g)(6)(ii)(D)(1) through (D)(4)).

(D)(1) Implementation. Holders of operating licenses or combined licenses for pressurized-water reactors as of or after August 17, 2017 shall implement the requirements of ASME BPV Code Case N-729-4 instead of ASME BPV Code Case N-729-1, subject to the conditions specified in paragraphs (g)(6)(ii)(D)(2) through (4) of this section, by the first refueling outage starting after August 17, 2017.

(D)(2) Appendix I use. Appendix I of ASME BPV Code Case N-729-4 shall not be implemented without prior NRC approval.

(D)(3) Bare metal visual frequency. Instead of Note 4 of ASME BPV Code Case N-729-4, the following shall be implemented. If effective degradation years (EDY) < 8 and if no flaws are found that are attributed to primary water stress Per N-729-4 corrosion cracking: 10CFR50.55a (D)(3)(i) A bare metal visual examination is not required during refueling outages when a volumetric or surface examination is performed; and (D)(3)(ii) If a wetted surface examination has been performed of all of the partial penetration welds during the previous non-visual examination, the reexamination frequency may be extended to every third refueling outage or 5 calendar years, whichever is less, provided an IWA-2212 VT-2 visual examination of the head is performed under the insulation through multiple access points in outages that the VE is not completed. This IWA-2212 VT-2 visual examination may be performed with the reactor vessel depressurized.

(D)(4)Surface exam acceptance criteria. In addition to the requirements of Paragraph -3132.1(b) of ASME BPV Code Case N-729-4, a component whose surface examination detects rounded indications greater than allowed in Paragraph NB-5352 in size on the partial-penetration or associated fillet weld shall be classified as having an unacceptable indication and corrected in accordance with the provisions of paragraph-3132.2 of ASME BPV Code Case N-729-4.

N-731 Alternative Class 1 System Leakage Test Pressure Requirements,Section XI, Division 1 18 N-735 Successive Inspection of Class 1 and 2 Piping Welds,Section XI, Division 1 18 N-765 Alternative to Inspection Interval Scheduling Requirements of IWA-2430,Section XI, Division 1 18 Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Per N-770-2 ActivitiesSection XI, Division 1 (As required by 10CFR50.55a(g)(6)(ii)(F), effective date 8/17/2017, with modifications per 10CFR50.55a 10CFR50.55a(g)(6)(ii)(F)(1) through (F)(13))

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Appendix D ASME Section XI Code Cases Code Regulatory Case Description Guide Number Revision (F)(1) Implementation. Holders of operating licenses or combined licenses for pressurized-water reactors as of or after August 17, 2017, shall implement the requirements of ASME BPV Code Case N-770-2 instead of ASME BPV Code Case N-770-1, subject to the conditions specified in paragraphs (g)(6)(ii)(F)(2) through (13) of this section, by the first refueling outage starting after August 17, 2017.

(F)(2) Categorization. Full structural weld overlays, authorized by the NRC staff in accordance with the alternatives approval process of this section, may be categorized as Inspection Items C-1 or F-1, as appropriate. Welds that have been mitigated by the Mechanical Stress Improvement Process (MSIPTM) may be categorized as Inspection Items D or E, as appropriate, provided the criteria in Appendix I of the code case have been met. For the purpose of determining ISI frequencies, all other butt welds that rely on Alloy 82/182 for structural integrity shall be categorized as Inspection Items A-1, A-2, or B until the NRC staff has reviewed the mitigation and authorized an alternative code case Inspection Item for the mitigated weld, or an alternative code case Inspection Item is used based on conformance with an ASME mitigation code case endorsed in NRC Regulatory Guide 1.147 with any applying conditions specified in NRC Regulatory Guide 1.147, as incorporated by reference in paragraph (a)(3)(ii) of this section. Paragraph -1100(e) of ASME BPV Code N-770-2 Case N-770-2 shall not be used to exempt welds that rely on Alloy 82/182 for structural integrity from any requirement of paragraph (g)(6)(ii)(F) of this section.

(Contd)

(F)(3) Baseline examinations. Baseline examinations for welds in Table 1 of ASME BPV Code Case N-770-2, Inspection Items A-1, A-2, and B, if not previously performed or currently scheduled to be performed in an ongoing refueling outage as of August 17, 2017, in accordance with paragraph (g)(6)(ii)(F) of this section, shall be completed by the end of the next refueling outage. Previous examinations of these welds can be credited for baseline examinations only if they were performed within the re-inspection period for the weld item in Table 1 of ASME BPV Code Case N-770-2 and the examination of each weld meets the examination requirements of paragraphs -2500(a) or -2500(b) of ASME BPV Code Case N-770-2 as conditioned in this section. Other previous examinations that do not meet these requirements can be used to meet the baseline examination requirement, provided NRC approval in accordance with paragraph (z)(1) or (2) of this section, is granted prior to the end of the next refueling outage.

Examination coverage. When implementing Paragraph -2500(a) of ASME BPV Code Case N-770-2, essentially 100 percent of the required volumetric examination coverage shall be obtained, including greater than 90 percent of the volumetric examination coverage for circumferential flaws. Licensees are prohibited from using Paragraphs -2500(c) and

-2500(d) of ASME BPV Code Case N-770-2 to meet examination requirements.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Appendix D ASME Section XI Code Cases Code Regulatory Case Description Guide Number Revision (F)(4) Examination coverage. When implementing Paragraph -2500(a) of ASME BPV Code Case N-770-2, essentially 100 percent of the required volumetric examination coverage shall be obtained, including greater than 90 percent of the volumetric examination coverage for circumferential flaws. Licensees are prohibited from using Paragraphs -2500(c) and

-2500(d) of ASME BPV Code Case N-770-2 to meet examination requirements.

(F)(5) Inlay/onlay inspection frequency. All hot-leg operating temperature welds in Inspection Items G, H, J, and K shall be inspected each inspection interval. A 25 percent sample of Inspection Items G, H, J, and K cold-leg operating temperature welds shall be inspected whenever the core barrel is removed (unless it has already been inspected within the past 10 years) or within 20 years, whichever is less.

(F)(6) Reporting requirements. For any mitigated weld whose volumetric examination detects growth of existing flaws in the required examination volume that exceed the previous IWB-3600 flaw evaluations or new flaws, a report summarizing the evaluation, along with inputs, methodologies, assumptions, and causes of the new flaw or flaw growth is to be provided to the NRC prior to the weld being placed in service other than modes 5 or 6.

(F)(7)Defining "t". For Inspection Items G, H, J, and K, when applying the acceptance standards of ASME BPV Code,Section XI, IWB-3514, for planar flaws contained within the inlay or onlay, the thickness "t" in IWB-3514 is the thickness of the inlay or onlay. For planar flaws in the balance of the dissimilar metal weld examination volume, the thickness "t" in IWB-3514 is the combined thickness of the inlay or onlay and the dissimilar metal weld.

N-770-2 (F)(8) Optimized weld overlay examination. Initial inservice examination of Inspection Item C-2 welds shall be performed Per (Contd) between the third refueling outage and no later than 10 years after application of the overlay. 10CFR50.55a (F)(9) Deferral. Note (11)(b)(1) in ASME BPV Code Case N-770-2 shall not be used to defer the initial inservice examination of optimized weld overlays (i.e., Inspection Item C-2 of ASME BPV Code Case N-770-2).

(F)(10) Examination technique. Note 14(b) of Table 1 and Note (b) of Figure 5(a) of ASME BPV Code Case N-770-2 may only be implemented if the requirements of Note 14(a) of Table 1 of ASME BPV Code Case N-770-2 cannot be met.

(F)(11) Cast stainless steel. Examination of ASME BPV Code Class 1 piping and vessel nozzle butt welds involving cast stainless steel materials, shall be performed with Appendix VIII, Supplement 9 qualifications, or qualifications similar to Appendix VIII, Supplement 2 or 10 using cast stainless steel mockups no later than the next scheduled weld examination after January 1, 2022, in accordance with the requirements of Paragraph -2500(a).

(F)(12) Stress improvement inspection coverage. Under Paragraph I.5.1, for cast stainless steel items, the required examination volume shall be examined by Appendix VIII procedures to the maximum extent practical including 100 percent of the susceptible material volume.

(F)(13) Encoded ultrasonic examination. Ultrasonic examinations of nonmitigated or cracked mitigated dissimilar metal butt welds in the reactor coolant pressure boundary must be performed in accordance with the requirements of Table 1 for Inspection Item A-1, A-2, B, E, F-2, J, and K for 100 percent of the required inspection volume using an encoded method.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Appendix D ASME Section XI Code Cases Code Regulatory Case Description Guide Number Revision N-798 Alternative Pressure Testing Requirements for Class 1 Piping Between the First and Second Vent, Drain, and Test 18 Isolation Devices,Section XI, Division 1 N-800 Alternative Pressure Testing Requirements for Class 1 Piping Between the First and Second Injection Valves,Section XI, 18 Division 1 Page 65 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Appendix E - Augmented Examinations Item Source Description Number Item As required by the UFSAR, Section 5.5.5.3, each Reactor Coolant Pump Flywheel is examined per the requirements of Regulatory Regulatory Guide 1.14, Position C.4.b. The bore and keyway areas of each Reactor Coolant Pump flywheel are examined RG 1.14 Guide 1.14 ultrasonically approximately every three years. Additionally, the flywheels receive a complete volumetric examination (UT) and a surface examination of all exposed surfaces at or near the end of each Inspection Interval.

NRC THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEMS - emphasizes the need for enhanced 88-08 Bulletin ultrasonic testing (UT) and for experienced examination personnel to detect cracks in stainless steel piping.

88-08 NRC Pressurizer Surge Line Thermal Stratification - General Visual (VT-3) examination once per period for issues originally 88-11 Bulletin identified via the bulletin. FPL Continues to monitor the surge line with the VT-3 visual examination.

88-11 Augmented Feedwater Examinations, as a result of a continuation of NRC Bulletin 79-13, and NRC Informational Notice 93-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators.

NRC 79-13 Bulletin FPL will perform a continuous enhanced ultrasonic examination starting at the Feedwater Nozzle ramp and extending out 79-13 to a point of 1 diameter on the elbow. Examinations will be performed in conjunction with the Code examination schedule as identified within the 5th-Interval-ISI-PSL-1-Schedule examination Tables, once per interval.

(a) Welds in those portions of systems addressed in USNRC Branch Technical Position APCSB 3.1 paragraph B.2.4(c);

(b) Welds in those portions of systems addressed in SRP 6.6 paragraph I.6.

In addressing the augmented examination requirements, referenced in (a) and (b) above, pipe-to-pipe welds and SRP-6.6/ longitudinal seams are required to be examined. Additionally, the Code Category (C F-2) boundary is extended past the SRP-6.6 APCSB 3.1 code class boundary (MSIV) to the first restraint providing at least two degrees of restraint to piping thermal expansion.

The welds and supports thus affected are specifically identified through Examination Notes in the Main Steam and Boiler Feedwater examination Tables.

FPL will examine the applicable welds in the Main Steam and Feedwater systems in accordance with the requirements of USNRC Standard Review Plan 6.6,Section I.6, Augmented Inservice Inspection of Class 2 Welds, once per interval.

External visual examination of the material surveillance capsules located at 83°, 97°, 104°, 263°, 277° & 284° in conjunction APP. H APP. H with the 10 year reactor vessel internals examination. Examination frequency is once per interval for the material surveillance holder.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Appendix E - Augmented Examinations Item Source Description Number Item 10CFR50.55a(g)(6)(ii)(D) requires that St Lucie implement the requirements of ASME Code Case N-770-2 subject to the conditions specified in paragraphs (g)(6)(ii)(D)(1) through (D)(4) as modified with conditions delineated in 10CFR dated August 17, 2017. Conditions are identified under ASME Code Case N-729-4 in Appendix D For the replacement component installed during PSL 1-20, a BMV examination is required every 3rd RFO or 5 years, whichever is less and a Volumetric and/or surface examination is required of all nozzles not to exceed 1 Inspection Interval N-729-4 N-729-4 (nominally 10 calendar years). The first BMV examination was required PSL-1-23 (2010) and the first volumetric/surface examination is required by 2015. Reference FPL Engineering Evaluation PTN-ENG-SESJ-01-0058, Rev. 0. FPL submitted and received NRC approval to defer the volumetric/surface examinations of the replacement RPV head for 2 cycles (Relief Request #8) and a subsequent deferral submitted and approved under (Relief Request 12) in the Fourth Interval Code Case Item Number Frequency Method B4.30 Every Third Refueling or 5 Years Visual B4.40 Once per interval Volumetric 10CFR50.55a(g)(6)(ii)(E) requires that St Lucie implement the requirements of ASME Code Case N-722-1 subject to the conditions specified in paragraphs (g)(6)(ii)(E)(1) through (E)(4) as modified with conditions delineated in 10CFR dated August 17, 2017. Conditions are identified under ASME Code Case N-722-1 in Appendix D 10CFR50.55a(g)(6)(ii)(E) requires that St Lucie augment the inservice inspection program by implementing ASME Code Case N-722-1 N-722-1 N-722-1 subject to the conditions specified in paragraphs (g)(6)(ii)(E)(2) through (4). The inspection requirements of ASME Code Case N-722-1 do not apply to components with pressure retaining welds fabricated with Alloy 600/82/182 materials that have been mitigated by weld overlay or stress improvement.

Code Case Item Number Frequency Method B15.205 Once per Interval Visual B15.215 Once per Interval Visual 10CFR50.55a(g)(6)(ii)(F) requires that St Lucie implement the requirements of ASME Code Case N-770-2 subject to the conditions specified in paragraphs (g)(6)(ii)(F)(2) through (13) as modified with conditions delineated in 10CFR dated August 17, 2017. Conditions are identified under ASME Code Case N-770-2 in Appendix D.

Code Case Item Number Frequency Method N-770-2 N-770-2 B ALL - Once Per Interval Visual B ALL - Every Second Period NOT to Exceed 7 years Volumetric C-1 25% Each Interval Volumetric D 25% Each Interval Volumetric Page 67 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Appendix E - Augmented Examinations Item Source Description Number Item This report provides needed guidelines and other good practice recommendations for evaluating and inspecting regions in normally stagnant PWR reactor coolant system branch lines where there may be potential for thermal fatigue cracking that MRP-146 MRP-146 could lead to leakage and forced plant outages. Per the implementation protocol of the NEI 03-08 initiative, these guidelines are needed actions for PWR licensees.

This report provides needed guidelines and other good practice recommendations for evaluation and inspecting all PWR RHR mixing tee welds within at least four internal pipe diameters downstream from the mixing tee junction point, including the mixing tee downstream weld where there may be potential for thermal fatigue cracking that could lead to leakage and MRP-192 MRP-192 forced plant outages. Per the implementation protocol of the NEI 03-08 initiative, these guidelines are needed actions for PWR licensees.

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St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Appendix F - St Lucie Unit 1 ISI Isometric Drawings Drawing Zone Description 01-001-A Reactor Pressure Vessel General Arrangement 01-001-B Reactor Pressure Vessel Upper Shell Section and Bottom Head Assembly 01-001-C Reactor Pressure Vessel Flange Seal Surface and Shell Segments 01-001-D Plug and Patch Locations 01-001-E RPV - Core Stop Lug and Stabilizing Lug Locations 01-001-F Reactor Pressure Vessel - Vessel Roll-out 01-001-G Reactor Pressure Vessel Upper and Lower Internal Assembly 01-002-A Reactor Pressure Vessel Closure Head 01-002-B Reactor Vessel Closure Head 0-002-C Steam Generator 1A Primary Side Replacement Unit 01-003 Steam Generator 1B Primary Side Replacement Unit 01-004 Pressurizer 01-005-A Pressurizer 01-005-B Pressurizer 01-005-C Reactor Pressure Vessel Upper and Lower Internal Assembly 01-006 Reactor Coolant System - Loop A Hot Leg, From RPV to SG-1A 01-007 Reactor Coolant Piping - Loop B Hot Leg, From RPV to SG-1B 01-008 Reactor Coolant Piping - Loop A Intermediate Leg, From SG-1A to RCP-1A2 01-009 Reactor Coolant Piping - Loop A Cold Leg, From RCP-1A2 to RPV 01-010 Reactor Coolant Piping - Loop B Intermediate Leg, From SG-1B to RCP-1B1 01-011 Reactor Coolant Piping - Loop B Cold Leg, From RCP 1B1 to RPV 01-012 Reactor Coolant Piping - Loop A Intermediate Leg, From SG-1A to RCP-1A1 01-013 Reactor Coolant Piping - Loop A Cold Leg, From RCP-1A1 to RPV 01-014 Reactor Coolant Piping - Loop B Intermediate Leg, From SG-1B to RCP-1B2 01-015 Reactor Coolant Piping - Loop B Cold Leg, From RCP-1B2 to RPV 01-016 Reactor Coolant System-Pressurizer Surge Line 01-017 Reactor Coolant Pump 1A1 01-018 Reactor Coolant Pump 1A2 01-019 Reactor Coolant Pump 1B1 01-020 Reactor Coolant Pump 1B2 01-021-A Loop 1A1 Safety Injection Piping Inside Containment 01-021-B Loop 1A1 Safety Injection Piping Inside Containment 01-022-A Loop 1A2 Safety Injection Piping Inside Containment 01-022-B Loop 1A2 Safety Injection Piping Inside Containment 01-023 Loop 1B1 Safety Injection Piping Inside Containment 01-024-A Loop 1B2 Safety Injection Piping Inside Containment 01-024-B Loop 1B2 Safety Injection Piping Inside Containment 01-025 Combined Pressurizer Spray, Reactor Coolant System 01-026-A Loop 1B1 Spray Line, Reactor Coolant System 01-026-B Loop 1B1 Spray Line, Reactor Coolant System 01-027 Loop 1B2 Spray Line, Reactor Coolant System 01-028 Loop 1B Shutdown Cooling Line 01-029 Loop 1A Shutdown Cooling Line, Safety Injection 01-030-A Pressurizer Auxiliary Spray, Chemical Volume Control System 01-031 Pressurizer Auxiliary Spray, Chemical Volume Control System 01-032-A Charging Line to Loop 1B1, Chemical Volume Control System 01-032-B Chemical Volume Control System, Charging Line to RC Loop 1A2 01-032-C Charging Line to RC Loop 1A2, Chemical Volume Control System 01-033 Charging Line to Loop 1A2, Chemical Volume Control System Page 69 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Appendix F - St Lucie Unit 1 ISI Isometric Drawings Drawing Zone Description 01-034 Loop 1A2 Primary Drain, Reactor Coolant System 01-035 Loop 1B2 Primary Drain, Reactor Coolant System 01-036 Loop 1B1 Primary Drain, Reactor Coolant System 01-037-A Letdown Line from Loop 1B1 01-037-B Letdown Line from Loop 1B1 01-038 Reactor Coolant System, Pressurizer Relief Line 01-039-A Combined SI Piping Loops 1A1 and 1A2 Outside Containment 01-039-B Combined SI Piping Loops 1A1 and 1A2 Outside Containment 01-040-A Combined SI Piping Loops 1B1 and 1B2 Outside Containment 01-040-B Combined SI Piping Loops 1B1 and 1B2 Outside Containment 01-040-C Combined SI Piping Loops 1B1 and 1B2 Outside Containment 01-041 Steam Generator 1A Secondary Side, Replacement Unit 01-042 Steam Generator 1B Secondary Side, Replacement Unit 01-043-A LPSI Pump 1A and 1B Discharge Header Piping 01-043-B LPSI Pump 1A and 1B Discharge Header Piping 01-043-C LPSI Pump 1A and 1B Discharge Header Piping 01-043-D LPSI Pump 1A and 1B Discharge Header Piping 01-044-A LPSI Pump Discharge Header Piping to Loop 1A1 and 1A2 01-044-B LPSI Pump Discharge Header Piping to Loop 1A1 and 1A2 01-044-C LPSI Pump Discharge Header Piping to Loop 1A1 and 1A2 01-044-D LPSI Pump Discharge Header Piping to Loop 1A1 and 1A2 01-046 Letdown Heat Exchanger, Chemical Volume Control System 01-047 A,B, & C Charging Pumps, Chemical Volume Control System 01-049-A Shutdown Cooling Line A Outside Containment 01-049-B Shutdown Cooling Line A Outside Containment 01-050-A Shutdown Cooling Line B Outside Containment 01-050-B Shutdown Cooling Line B Outside Containment 01-050-C Shutdown Cooling Line B Outside Containment 01-051-A Safety Injection - Shutdown Cooling Line A Inside Containment 01-051-B Safety Injection - Shutdown Cooling Line A Inside Containment 01-052-A Shutdown Cooling Line B Inside Containment 01-052-B Shutdown Cooling Line B Inside Containment 01-055 Shutdown Cooling Heat Exchanger 1A 01-056 Shutdown Cooling Heat Exchanger 1B 01-057 Safety Injection Tank 1A1 Piping 01-058 Safety Injection Tank 1A2 Piping 01-059 Safety Injection Tank 1B1 Piping 01-060 Safety Injection Tank 1B2 Piping 01-061-A High Pressure Safety Injection, HPSI Pump 1A to Header 1A 01-061-B High Pressure Safety Injection, HPSI Pump 1A to Header 1A 01-061-C Safety Injection System, HPSI Pump 1A Recirculation System 01-062-A High Pressure Safety Injection, HPSI Pump 1B and 1C to Header B 01-062-B HPSI Pump 1B and 1C to Header B 01-062-C High Pressure Safety Injection, HPSI Pump 1B and 1C to Header B 01-062-D Safety Injection System, HPSI Pump 1B Recirculation System 01-063 Main Steam Line 1A1 Inside Containment 01-064 Main Steam Line 1B1 Inside Containment 01-065 Main Steam Line 1A1 Outside Containment 01-066 Main Steam Line B Outside Containment 01-067 Main Feedwater to Steam Generator 1A Inside Containment Page 70 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Appendix F - St Lucie Unit 1 ISI Isometric Drawings Drawing Zone Description 01-068 Main Feedwater to Steam Generator 1B Inside Containment 01-070-A Combined Inlet Piping to Containment Spray Pumps 1A and 1B from RWST 01-070-B Combined Inlet Piping to Containment Spray Pumps 1A and 1B from RWST 01-070-C Combined Inlet Piping to Containment Spray Pumps 1A and 1B from RWST 01-071 Main Feedwater to Steam Generator 1A Outside Containment 01-072 Main Feedwater to Steam Generator 1B Outside Containment 01-073-A LPSI/HPSI/CS Pumps, Loop 1A Inlet Piping 01-073-B LPSI/HPSI/CS Pumps, Loop 1A Inlet Piping 01-073-C LPSI/HPSI/CS Pumps, Loop 1A Inlet Piping 01-073-D LPSI/HPSI/CS Pumps, Loop 1A Inlet Piping 01-074-A LPSI/HPSI/CS Pumps, Loop 1B Inlet Piping 01-074-B LPSI/HPSI/CS Pumps, Loop 1B Inlet Piping 01-074-C LPSI/HPSI/CS Pumps, Loop 1B Inlet Piping 01-074-D LPSI/HPSI/CS Pumps, Loop 1B Inlet Piping 01-074-E LPSI/HPSI/CS Pumps, Loop 1B Inlet Piping 01-075 Shutdown Cooling Heat Exchanger 1B Discharge Piping 01-076 Shutdown Cooling Heat Exchanger 1A Inlet Piping 01-077 Shutdown Cooling Heat Exchanger 1A Discharge Piping, Safety Injection 01-078 Shutdown Cooling Heat Exchanger 1B Inlet Piping, Safety Injection 01-079-A Shutdown Cooling Heat Exchanger 1B to CS Header 01-079-B Shutdown Cooling Heat Exchanger 1B to CS Header 01-080-A Shutdown Cooling Heat Exchanger 1A to Containment Spray Header 01-080-B Shutdown Cooling Heat Exchanger 1A to Containment Spray Header 01-081 Low Pressure Safety Injection Pump 1A (LPSI)01-082 Low Pressure Safety Injection Pump 1B (LPSI)01-083 Combined HP and Auxiliary HP Headers to Loop 1A1, Safety Injection 01-084 Combined HP and Auxiliary HP Headers to Loop 1A2, Safety Injection 01-085 Combined HP and Auxiliary HP Headers to Loop 1B1, Safety Injection 01-086-A Combined HP and Auxiliary HP Headers loop 1B2 01-086-B Combined HP and Auxiliary HP Headers loop 1B2 01-087-H Charging Pumps Discharge to HPSI Pump Discharge 01-100-A Component Cooling Water HX 1A and 1B Inlet Header 01-100-B Component Cooling Water HX 1A and 1B Inlet Header 01-101-A Component Cooling - Shutdown Cooling HX 1A Inlet 01-101-B Component Cooling - Shutdown Cooling HX 1A Inlet 01-102-A Component Cooling - Shutdown Cooling HX 1A Discharge 01-012-B Component Cooling - Shutdown Cooling HX 1A Discharge 01-102-C Component Cooling - Shutdown Cooling HX 1A Discharge 01-103-A Component Cooling - Shutdown Cooling HX 1B Inlet 01-103-B Component Cooling - Shutdown Cooling HX 1B Inlet 01-104-A Component Cooling - Shutdown Cooling HX 1B Discharge 01-104-B Component Cooling - Shutdown Cooling HX 1B Discharge 01-105-A Component Cooling Water Pumps 1A, 1B, and 1C Inlet 01-105-B Component Cooling Water Pumps 1A, 1B, and 1C Inlet 01-105-C Component Cooling Water Pumps 1A, 1B, and 1C Inlet 01-106 Component Cooling Surge Tank Piping 01-107-A Circulating Water - CCW HX A and B Discharge to Canal 01-107-B Circulating Water - CCW HX A and B Discharge to Canal 01-107-C Circulating Water - CCW HX A and B Discharge to Canal 01-108-A Circulating Water - CCW HX A and B Discharge Piping Page 71 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Appendix F - St Lucie Unit 1 ISI Isometric Drawings Drawing Zone Description 01-108-B Circulating Water - CCW HX A and B Discharge Piping 01-108-C Circulating Water - CCW HX A and B Discharge Piping 01-109-A Circulating Water - Inlet 01-109-B Circulating Water - Inlet 01-109-C Circulating Water - Inlet 01-109-D Circulating Water - Inlet 01-109-E Circulating Water - Intake Cooling Water Pumps Discharge Header 01-110-A Circulating Water - Intake Cooling Water Pumps Discharge Header 01-110-B Circulating Water - Intake Cooling Water Pumps Discharge Header 01-110-C Circulating Water - Intake Cooling Water Pumps Discharge Header 01-110-D Spent Fuel Cooling Pumps 1A and 1B to Fuel Pool Heat Exchanger 01-111-A Spent Fuel Cooling Pumps 1A and 1B from the Spent Fuel Pool 01-111-B Auxiliary Feedwater Pump 1C to Main Feedwater 01-112-A Auxiliary Feedwater Pump 1C to Main Feedwater 01-112-B Auxiliary Feedwater Pumps 1A and 1B to Main Feedwater 01-113-A Auxiliary Feedwater Pumps 1A and 1B to Main Feedwater 01-113-B Auxiliary Feedwater - Condensate Storage Tank from AFW Pump 1C Recirculation Line 01-114 Auxiliary Feedwater to Main Feedwater 01-115 Auxiliary Feedwater to Main Feedwater 01-116 Auxiliary Feedwater to Main Feedwater 01-117 Condensate - Suction to Auxiliary Feedwater Pumps 01-118-A Condensate - Suction to Auxiliary Feedwater Pumps 01-118-B Condensate - Suction to Auxiliary Feedwater Pumps 01-118-C Condensate - Suction to Auxiliary Feedwater Pumps 1A and 1B 01-119-A Condensate - Suction to Auxiliary Feedwater Pumps 1C 01-119-B Condensate - Suction to Auxiliary Feedwater Pumps01-120 Circulating Water - Inlet 01-121-A CCW from Containment Cooling Unit 1A to Penetration 19 01-121-B CCW from Containment Cooling Unit 1A to Penetration 19 01-122-A CCW from Penetration 18 to Containment Cooling Unit 1D 01-122-B CCW from Penetration 18 to Containment Cooling Unit 1D 01-123-A CCW from Penetration 20 to Containment Cooling Unit 1A 01-123-B CCW from Penetration 20 to Containment Cooling Unit 1A 01-124 CCW from Penetration 16 to Containment Cooling Unit 1C 01-125 CCW from Penetration 22 to Containment Cooling Unit 1B 01-126-A CCW from Containment Cooling Unit 1D to Penetration 17 01126-B CCW from Containment Cooling Unit 1D to Penetration 17 01-127 CCW from Containment Cooling Unit 1B to Penetration 21 01-128 Component Cooling Water from Containment Cooling Unit 1C to Penetration 15 Page 72 of 73

St. Lucie Unit 1 ISI Program Plan Revision 0 th Document No. 5 Interval-ISI-PSL-1-Program Plan February 10, 2018 Appendix G - Class 1 Acceptance Criteria Examination Parts Examined Acceptance Category Standard B-A Pressure Retaining Welds in Reactor Vessel IWB-3510 B-B Pressure Retaining Welds in Vessels Other Than Reactor Vessels IWB-3510 B-D Full Penetration Welded Nozzles in Vessels (Inspection Program B) IWB-3512 B-F Pressure Retaining Dissimilar Metal Welds in Vessel Nozzles IWB-3514 B-J Pressure Retaining Welds in Piping IWB-3514 Pressure Retaining Bolting, Greater Than 2 inches in Diameter IWB-3515 &

B-G-1 IWB-3517 B-G-2 Pressure Retaining Bolting, 2 inches and Less in Diameter IWB-3517 B-K Welded Attachments for Vessels, Piping, Pumps, and Valves IWB-3516 B-L-2 Pump Casings IWB-3519 B-M-2 Valve Bodies IWB-3519 B-N-1 Interior of Reactor Vessel IWB-3520.2 Welded Core Support Structures and Interior Attachments to IWB-3520.1 &

B-N-2 Reactor Vessels IWB-3520.2 B-N-3 Removable Core Support Structures IWB-3520.2 B-O Pressure Retaining Welds in Control Rod Housings IWB-3523 B-P All Pressure Retaining Components IWB-3522 Appendix H - Class 2 Acceptance Criteria Examination Parts Examined Acceptance Category Standard C-A Pressure Retaining Welds in Pressure Vessels IWC-3510 C-B Pressure Retaining Nozzle Welds in Vessels IWC-3511 C-C Welded Attachments for Vessels, Piping, Pumps and Valves IWC-3512 C-D Pressure Retaining Bolting Greater than 2 inches in Diameter IWC-3513 Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy C-F-1 IWC-3514 Piping C-F-2 Pressure Retaining Welds in Carbon or Low Alloy Steel Piping IWC-3514 C-H All Pressure Retaining Components IWC-3516 Appendix I - Class 3 Acceptance Criteria Examination Parts Examined Acceptance Category Standard D-A Welded Attachments for Vessels, Piping, Pumps, and Valves IWD-3000 D-B All Pressure Retaining Components IWD-3000 Appendix J - Component Support Acceptance Standards Examination Parts Examined Acceptance Category Standard F-A Class 1, 2, 3 and MC Component Supports IWF-3410 Page 73 of 73