Text

Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan
	ML22004A307
Person / Time
Site:	Seabrook
Issue date:	01/04/2022
From:	Booth B; NextEra Energy Seabrook
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	SBK-L-21126
	Download: ML22004A307 (83)
	v • d • e

SBK-L-21126 U.S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 115 5 5 Rockville Pike Rockville, MD 20582 Seabrook Station NEXTeraM ENERGy_Et SEABROOK January 4, 2022 Docket No. 50-443 10 CFR 50.55a(g)

Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan The Fourth 10-Year Inservice Inspection (ISI) Interval for NextEra Energy Seabrook, LLC (NextEra Seabrook) began on August 19, 2020 and ends on August 18, 2030. Pursuant to 10 CFR 50.55a(g)(4)(ii) the ISI Program Plan for NextEra Seabrook is based on the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, Division 1, 2013 Edition.

NextEra Seabrook is hereby submitting the Fourth 10 Year ISI Program Plan. The Program Plan is provided within the Enclosure. The planned Relief Requests for the Fourth 10 Year ISI Interval will be submitted under different correspondence, at a later date.

Should you have any questions concerning this response, please contact Mr. Brian O'Callahan, Programs Engineering Manager, at (603) 773-7046.

Sincerely, NextEra Energy Seabrook, LLC Enclosure NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874

United States Nuclear Regulatory Commission SBK-L-21126/Page 2 cc:

NRC Region I Administrator NRC Project Manager NRC Senior Resident Inspector

ENCLOSURE TO SBK-L-21126 Fourth 10 Year lnservice Inspection (ISi) Program Plan

NextEra Energy Nuclear Engineering Department Fleet Programs Engineering Group Inspection Section 700 Universe Blvd Juno Beach, FL 33408 Fourth lnservice Inspection Interval Program Plan For Seabrook Station Unit 1 P.O. Box 300 Seabrook, New Hampshire 03847 SBK-1 Commercial Service Date:

August 19, 1990 SBK-1 USNRC Docket Number:

Unit 1 443 Document Number: 4th lnterval-ISl-SBK-1-Program Plan Rev. 0

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Fleet Engineering Programs Fleet Engineering Programs

Seabrook Station Unit 1 ISi Program Revision 0 September 30, 2021 Document No. 4th lnterval-ISl-SBK-1-Program Plan Record of Revision Rev Date Affected Reason for Revision No:

Pages Entire Initial Fourth 10-Year Inspection Interval 0

September 30, 2021 Document Program Plan as required by 1 OCFR50.55a(g)(4)

Page 2 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Table of Contents Revision 0 September 30, 2021 Cover Page..................................................................................................................................... 1 Table of Contents.......................................................................................................................... 3 Abbreviations................................................................................................................................. 7 Abstract......................................................................................................................................... 8 1.0 Introduction........................................................................................................................ 9 1.1 ISi Program Development........................................................................................ 9 1.2 Other ISi Programs.................................................................................................. 9 1.3 Construction Permit............................................................................................... 1 O 1.4 Operating License and Commercial Service Dates................................................ 1 O 1.5 Background............................................. ~************************************************************** 1 O 1.5.1 Preservice Examinations............................................................................ 11 1.5.2 First lnservice Inspection Interval............................................................... 11 1.5.3 Second lnservice Inspection Interval.......................................................... 11 1.5.4 Third lnservice Inspection Interval.............................................................. 11 1.5.5 Fourth lnservice Inspection Interval............................................................ 11 1.6 Applicable Editions and Addenda to Section X....................................................... 12 1.6.1 10CFR50.55a Code of Federal Regulations Conditions............................. 12

1. 7 System Classification............................................................................................. 16 1.7.1 ASME Code Class.................,.................................................................... 16

1. 7.2 Optional Construction................................................................................. 17

1. 7.3 Containment Penetrations.......................................................................... 17

1. 7.4 Class MC and Class CC Components........................................................ 17 1.8 Inspection Program Plan........................................................................................ 17

1. 9 Regulatory Guide................................................................................................... 18 1.1 O ASME Section XI Code Cases............................................................................... 18 1.11 Plant Life Extension............................................................................................... 22 1.12 Successive Examinations...................................................................................... 22 1.13 NOE and Personnel Qualification/Certification....................................................... 22 1.13.1 Alternative Examinations............................................................................ 23 1.13.2 System Leakage Tests for Repair Replacement Activities.......................... 23 1.13.3 Surface Examinations................................................................................. 23 1.13.4 Certification and Recertification.................................................................. 23 1.13.5 Appendix VI 11 Requirements....................................................................... 23 2.0 Risk Informed (RI) ISi Requirements................................................................................ 24 3.0 Development of the Class 1 Examination Plan................................................................. 27 3.1 Class 1 Code Exemptions...................................................................................... 27 3.2 Component Examination Basis.............................................................................. 28 3.3 Category B-A......................................................................................................... 28 3.4 Category B-B......................................................................................................... 29 3.5 Category B-D......................................................................................................... 30 3.6 Category B-F......................................................................................................... 31 Page 3 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021

3. 7 Category B-G-1...................................................................................................... 32 3.8 Category B-G-2...................................................................................................... 33 3.9 Category B-J.......................................................................................................... 34 3.1 O Category B-K......................................................................................................... 34 3.11 Category B-L-2...................................................................................................... 35 3.12 Category B-M-2..................................................................................................... 35 3.13 Category B-N-1, B-N-2 & B-N-3............................................................................. 37 3.14 Category B-0......................................................................................................... 38 3.15 Category B-P......................................................................................................... 39 3.16 Category B-Q......................................................................................................... 39 3.17 Category R-A......................................................................................................... 40 4.0 Development of Class 2 Examination Plan.......................................................................43 4.1 Class 2 Code Exemptions...................................................................................... 43 4.1.1 IWC-1221................................................................................................... 43 4.1.2 IWC-1222................................................................................................... 44 4.1.3 IWC-1223................................................................................................... 45 4.2.

Component Examination Basis.............................................................................. 45 4.3 Category C-A......................................................................................................... 46 4.4 Category C-B......................................................................................................... 46 4.5 Category C-C......................................................................................................... 46 4.6 Category C-D......................................................................................................... 47 4.7 Category C-F-1...................................................................................................... 47 4.8 Category C-F-2...................................................................................................... 47 4.9 Category C-H......................................................................................................... 47 5.0 Development of the Class 3 Examination Plan.................................................................48 5.1 Examination Requirements.................................................................................... 48 5.2 Class 3 Code Exemptions and Exclusions............................................................. 48 5.3 Component Exemption Basis................................................................................. 50 5.4 Category D-A......................................................................................................... 50 5.5 Category D-B......................................................................................................... 51 6.0 IWE Metal Containment Requirements............................................................................ 51 7.0 Development of Component Supports Examination Plan................................................. 51 7.1 Code Exemptions for Supports.............................................................................. 52 7.1.1 IWF-1230 Supports Exempt from Examination1.......................................... 52 7.2 Support Examination Basis.................................................................................... 52 7.2.1 Category F-A.............................................................................................. 52 7.2.2 Item Numbers............................................................................................. 53 7.3 Snubbers............................................................................................................... 54 8.0 IWL Concrete Containment Requirements....................................................................... 54 9.0 Augmented and Other Programs............... :..................................................................... 54 9.1 Class 1................................................................................................................... 55 9.1.1 Reactor Coolant Pump Flywheel................................................................ 55 9.1.2 Code Case N-722-1................................................................................... 55 9.1.3 Code Case N-729-6................................................................................... 55 Page 4 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 9.1.4 Code Case N-770-5................................................................................... 56 9.1.5 TB-07-02.................................................................................................... 56 9.1.6 MRP-146.................................................................................................... 59 9.1.7 WCAP-16913-P.......................................................................................... 59 9.2.

Class 2 Components.............................................................................................. 60 9.2.1 NRC Bulletin 79-13..................................................................................... 60 9.2.2 MRP-192.................................................................................................... 60 9.2.3 BER Piping (RI-BER).................................................................................. 60 10.0 Evaluation/Acceptance Criteria........................................................................................ 61 10.1 Supplemental Examinations................................................................................... 61 10.2 Additional Examinations......................................................................................... 61 10.3 Successive Examination for Components.............................................................. 61 10.3.1 Class 1 Components (IWB-2420)............................................................... 61 10.3.2 Class 2 Components (IWC-2420)............................................................... 62 10.3.3 Class 3 Components (IWD-2420)............................................................... 62 10.3.4 Component Supports (IWF-2420)............................................................... 62 11.0 Repair/Replacement Activities......................................................................................... 62 12.0 Relief Requests................................................................................................................ 63 13.0 Boundary Classifications.................................................................................................. 63 14.0 Weld/Support Location Maps........................................................................................... 63 15.0 Addition of Welds, Components and Supports................................................................. 63 16.0 Ultrasonic Calibration Blocks............................................................................................ 63 17.0 Records........................................................................................................................... 64 17.1 General.................................................................................................................. 64 17.2 Nondestructive Examination.................................................................................. 64 17.3 Final Reports......................................................................................................... 64 17.4 lnservice Inspection Summary Report.................................................................... 64 17.5 NIS-2 or NIS-2A Reports........................................................................................ 64 18 References...................................................................................................................... 65 Page 5 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Tables Revision O September 30, 2021 Table 1 - Fourth I nservice Inspection Interval............................................................................. 12 Table 2 - USNRC Regulatory Guides.......................................................................................... 18 Table 3 - Applicable Code Cases................................................................................................ 18 Table 4 - Class 1 Valve Grouping............................................................................................... 36 Table 5 - Class 2 Exempt Components....................................................................................... 44 Table 6 - Class 3 Exempt Components....................................................................................... 49 Appendices Appendix A - Relief Request....................................................................................................... A 1 Appendix B - Risk Informed Periodic Update.............................................................................. B1 Appendix C - Boundary Classification Drawings........................................................................ C1 Appendix D - Isometric and Component Drawings..................................................................... D1 Appendix E - Ultrasonic Calibration Blocks................................................................................. E1 Page 6 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Abbreviations ANll Authorized Nuclear lnservice Inspector N/A ANSI American Nuclear Standard Institute NOE AOV Air Operated Valve NPS ASME American Society of Mechanical OD EnQineers B&PV Boiler and Pressure Vessel Code PDS BC Branch Connection POI BMV Bare Metal Visual P&ID CROM Control Rod Drive Mechanism PSI CFR Code of Federal Regulations PT cs Charging System PWR CHR Containment Heat Removal PZR CPS Code Programs Section QA CRV Code Required Volume QC CBS Containment Spray System QP CV Control Valve RC cs Chemical and Volume Control System RCP ECCS Emergency Core Cooling System RH ECT Eddy Current Testing RIS_B ENG Engineering RGX FPE Fleet Program Engineering RPV FPL Florida Power & Light Company SB FPS Fuel Pool System SBK FSAR Final Safety Analysis Report SD FW Feedwater System SFHX HPSI High Pressure Safety Injection SG HS High Stress SGBD HX Heat Exchanger SRP ID Identification SI IE Inspection and Enforcement t

ISi lnservice Inspection TE IST lnservice Testing UFSAR LER License Event Report USN RC LS Longitudinal Seam Weld UT MOV Motor Operated Valve VT MRP Material Reliability Program PWR MSIV Main Steam Isolation Valve PZR MS Main Steam System QA MT Magnetic Particle Testing QC (Examination)

Page 7 of 66 Not Applicable Revision O September 30, 2021 Nondestructive Testing Nominal Pipe Size Outside Diameter Program Boundary Drawings Performance Demonstration Initiative Piping and Instrumentation Diagram Preservice Inspection Liquid Penetrant Testing (Examination)

Pressurized Water Reactor Pressurizer Quality Assurance Quality Control Quality Procedure Reactor Coolant System Reactor Coolant Pump Residual Heat Removal Risk-Informed/Safety-Based Regenerative Heat Exchanger Reactor Pressure Vessel SG Slowdown System Seabrook Station Unit 1 Structural Discontinuity Spent Fuel Heat Exchanger Steam Generator Steam Generator Slowdown Standard Review Plan Safety Injection System Thickness of Component, Pipe, etc.

Terminal End Updated Final Safety Analysis Report United States Nuclear Regulatory Commission Ultrasonic Testing (Examination)

Visual Testing (Examination)

Pressurized Water Reactor Pressurizer Quality Assurance Quality Control

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Abstract Revision 0 September 30, 2021 This document describes the Class 1, 2, and 3 lnservice Inspection (ISi) Program Plan Fourth 10-Year lnservice Inspection Interval for Seabrook Station Unit 1, (Seabrook Station).

The Program Plan was prepared to meet the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Division 1, 2013 Edition and 10CFR50.55a for Class 1, 2, and 3 components and component supports. This Program Plan is subject to the conditions listed in 10CFR50.55a (b) (2).

The 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. Code Cases implemented 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 and Examination Categories C-A and C-B for Class 2 vessel welds in accordance with ASME Code Case N-716-1. Note that although Code Case N-716-1 also addresses Examination Category C-D bolting, Seabrook does not have any components in this Examination Category.

The ISi Programs for Class MC Metal Containment, lnservice Pressure Tests, Class CC Concrete Containment, and Snubber Examinations are covered under separate plant programs. General requirements for these programs are included for completeness.

This document also includes inservice augmented examinations required by Seabrook regulatory commitments, 1 OCFR50.55a (g) (6) (ii), industry initiatives and plant original equipment Manufacturers (OEM) such as Westinghouse Technical Publications. The augmented inservice Examinations applicable to Seabrook Station Unit 1 are identified in Section 9.0.

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Seabrook Station Unit 1 ISi Program Revision 0 September 30, 2021 Document No. 4th lnterval-ISl-SBK-1-Program Plan 1.0 Introduction Seabrook Station Unit 1 (SBK-1) is a four loop Pressurized Water Nuclear Power Plant.

NextEra Energy Seabrook, LLC (NextEra Energy) is the Owner of Record.

1.1 ISi Program Development This document details the lnservice Inspection Program Plan of Class 1, 2, and 3 components and component supports for the Fourth 10-Year lnservice Inspection Interval for Seabrook Station Unit 1.

The ISi Schedule Tables for examinations of the major components of Seabrook Station Unit 1 are located in the Seabrook Station Unit 1 ISi data management system (IDDEAL). The ISi database management system includes tables that have brief descriptions of each component subject to examination, the required code references, calibration blocks, NOE procedures, weld/support location maps (isometric drawings) and any other pertinent information that is useful for determining examination requirements.

lnservice examination of component and system pressure tests conducted during successive 120-month inspection intervals must comply with the requirements of the latest edition and addenda of the Code incorporated by reference in 1 OCFR50.55a 12 months prior to the start of the 120-month inspection interval. These requirements are subject to the limitations and modifications listed within 1 OCFR50.55a.

This Program Plan reflects the lnservice Inspection requirements of ASME Section XI, Division 1, 2013 Edition as modified by 10CFR50.55a.

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

1.2.1 lnservice Testing Program (IST}

The program for lnservice Testing of Class 1, Class 2, and Class 3 Pumps and Valves is covered by the Seabrook Station Unit 1 lnservice 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 Seabrook Station Technical Specifications and is administered separately.

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Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan 1.2.3 Snubber Program Revision O September 30, 2021 The program for the examination and testing of safety-related snubbers is addressed by Seabrook Station Unit 1 plant procedures.

1.2.4 System Pressure Test Program The program for lnservice System Pressure Testing of ASME Code Class 1, Class 2, and Class 3 components and systems is addressed by Seabrook Station Unit 1 plant procedures.

1.2.5 Repair and Replacement Program The Repair and Replacement Program for ASME Code Class 1, 2, 3 components, component supports and ASME Code Class MC and CC components is addressed by Seabrook Administrative Procedure MA 6.2.

1.2.6 Metal Containment lnservice Inspection Program (IWE)

The Metal Containment lnservice Inspection Program, 3rd lnterval-IWE-SBK-1-Program Plan, controls the examination of Code Class MC components in accordance with ASME Section XI, Subsection IWE and is administered separately.

1.2.7 Concrete Containment lnservice Inspection Program (IWL)

The Concrete Containment lnservice Inspection Program, 3rd lnterval-IWL-SEA-Prog Plan controls the examination of Code Class CC components in accordance with ASME Section XI, Subsection IWL and is administered separately.

1.3 Construction Permit The Construction permit for Seabrook Station Unit 1 was issued on July 7, 1976.

1.4 Operating License and Commercial Service Dates The Operating License for Seabrook Station Unit 1 was issued on March 15, 1990.

The Commercial Service Date for Seabrook Station Unit 1 is August 19, 1990.

1.5 Background

ASME Class 1 systems and components have been classified for inservice inspection using the guidance specified in 1 O CFR 50.2, Definitions. Classification of Class 2 and 3 systems and components are specified in Regulatory Guide 1.26, Rev. 3 (Quality Group B and C). Specific code classifications and associated boundaries are depicted on the plant Piping and Instrument Drawings (P&IDs) listed in Appendix C.

Typically, systems and components on the P&IDs, which are designated as Safety Class 1, 2, and 3 also correspond to ASME Class 1, 2, and 3, respectively.

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Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 Seabrook Station Unit 1 has implemented the requirements of different Editions and Addenda of Section XI. The applicable Edition of Section XI was mandated by changes to 1 OCFR 50.55a at 10-year intervals or earlier.

1.5.1 Preservice Examinations The Preservice Examination was conducted in accordance with the ASME Boiler and Pressure Vessel (B&PV) Code,Section XI, 1977 Edition through the Summer 1978 Addenda, except for the preservice examinations of ASME Class 2 piping welds, which were performed in accordance with the 197 4 Edition with the Summer 1975 Addenda.

1.5.2 First lnservice Inspection Interval The first 10-Year ISi Interval began on August 19, 1990 and ended on August 18, 2000. The applicable ASME Section XI Code of Record was the 1983 Edition with the Summer 1983 Addenda.

1.5.3 Second lnservice Inspection Interval The second 10-Year ISi Interval began on August 19, 2000 and ended on August 18, 2010. The applicable ASME Section XI Code of Record was the 1995 Edition with the 1996 Addenda.

1.5.4 Third lnservice Inspection Interval The third 10-Year ISi Interval began on August 19, 201 O and ended on August 18, 2020. The applicable ASME Section XI Code of Record was the 2004 Edition.

1.5.5 Fourth lnservice Inspection Interval The Fourth Ten Year lnservice Inspection Interval is being conducted in accordance with ASME Section XI, Division 1, 2013 Edition as modified by 1 OCFR50.55a.

The Fourth Ten Year lnservice Inspection Interval is divided into three successive Inspection periods as determined by calendar years of plant service within the interval. The dates of the fourth 10-year I nservice Inspection Interval and Periods are as follows:

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Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Table 1 Revision 0 September 30, 2021 Fourth lnservice Inspection Interval Period Start End 4th Interval August 19, 2020 August 18, 2030 1st Period August 19, 2020 August 18, 2023 2nd Period August 19, 2023 August 18, 2027 3rd Period August 19, 2027 August 18, 2030 1.6 Applicable Editions and Addenda to Section XI In accordance with 1 OCFR50.55a(g)(4)(ii), the version of Section XI in effect one year prior to the start of the Seabrook Station 4th ISi Interval, August 19, 2019, is the applicable Section XI Code of Record for lnservice Inspection. Accordingly, NextEra Energy Seabrook will implement the requirements for Class 1, 2, and 3 components and component supports at Seabrook Station included in ASME Section XI, Division 1, 2013 Edition.

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

1.6.1 1 OCFR50.55a Code of Federal Regulations Conditions The following mandatory and optional Code of Federal Regulations conditions are included in 1 OCFR50.55a as of the time of this revision. Only those 10CFR50.55a conditions applicable to the ASME Section XI, 2013 Edition for nondestructive examination requirements of Class 1, 2, and 3 components and component supports are listed. The conditions for concrete and metal containment components are listed for completeness only and are not applicable to this Program Plan. These conditions were reviewed for inclusion in the ISi Program Plan and dispositioned as follows:

1.6.1.1 Seabrook Station will not utilize the option in 1 OCFR50.55a(b)(2)(ii) to examine Class 1 piping per ASME Section XI, 1974 Edition with the Summer 1975 Addenda. Seabrook Station will implement a Risk-Informed lnservice Inspection (RI-ISi) application for Class 1 and 2 piping; therefore, this modification is not applicable.

1.6.1.2 The Seabrook Station design includes a concrete containment subject to ASME Section XI, Subsection IWL requirements.

Therefore., the mandatory conditions in 1 OCFR50.55a (b)(2)(viii)

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Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 apply to Seabrook Station. Examination of concrete containment components is addressed under the Concrete Containment ISi Program, 3rd lnterval-IWL-SEA-Prog Plan.

1.6.1.3 The Seabrook Station design includes a metal shell (or liner) subject to ASME Section XI, Subsection IWE requirements. Therefore, the mandatory conditions in 10CFR50.55a (b)(2)(ix) apply to Seabrook Station. In addition, Seabrook Station will implement the optional conditions for the maximum direct examination distance for remote visual examinations presented in 10CFR50.55a (b)(2)(ix)(B). The examination of metal containment components is addressed under Containment Building Metallic Liner lnservice Inspection Program, 3rd lnterval-IWE-SBK-1-Program Plan.

1.6.1.4 As required by 1 OCFR50.55a (b)(2)(x), Seabrook Station will apply the station 1 OCFR50 Appendix B Quality Assurance Program of NQA-1 to Section XI activities.

1.6.1.5 As required by 1 OCFR50.55a(b)(2)(xii), Seabrook Station may apply the provisions of IWA-4660, Underwater Welding for use on irradiated materials with the conditions set forth in 10CFR50.55a(b)(2)(xii)(A) for welding techniques to be used on ferritic material and 10CFR50.55a(b)(2)(xii)(B) for welding techniques to be used on stainless steel material.

1.6.1.6 As allowed by 1 OCFR50.55a(b)(2)(xiv), for Appendix VIII Qualified Personnel Seabrook Station will use the annual practice requirements in Vll-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 1 OCFR50.55a(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 1 OCFR50.55a(b)(2)(xviii)(A), Level I and II nondestructive examination personnel at Seabrook Station will be recertified, by examination, on a 3-year interval in lieu of the 5-year interval specified in IWA-2314(a) and IWA-2314(b) of the 2013 Edition of Section XI.

1.6.1.8 As required by 1 OCFR50.55a(b)(2)(xviii)(D), Seabrook Station will not implement the requirements in Appendix VII, Table Vll-4110-1 and Appendix VIII, Subarticle Vlll-2200 of the 2013 Edition of Section XI. Alternatively, Seabrook Station will implement the requirements in Appendix VII, Table Vll-4110-1 and Appendix VIII, Subarticle Vlll-2200 in the 2010 Edition of Section XI.

1.6.1.9 As required by 10CFR50.55a(b)(2)(xix), the provisions in IWA-4520(b)(2) and IWA-4521 of the 2013 Edition which allow the Page 13 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 substitution of ultrasonic examination for radiographic examination specified in the Construction Code are not approved for use.

1.6.1.10 As required by 1 OCFR50.55a(b)(2)(xx)(B), Seabrook Station will apply the nondestructive examination method and acceptance criteria of the 1992 Edition or later of Section Ill when performing system leakage tests (in lieu of a hydrostatic test) in accordance with IWA-4520 after repair and replacement activities performed by welding or brazing on a pressure retaining boundary. The nondestructive examination and pressure testing may be performed using procedures and personnel meeting ASME Section XI, 2013 Edition.

1.6.1.11 The use of the provision in IWA-2220, "Surface Examination" that allows the use of an ultrasonic examination method is prohibited by 10CFR50.55a (b)(2)(xxii). Based on the RIS_B application on Class 1 and 2 piping welds, Seabrook Station is not required to perform surface examinations on Class 1 and 2 piping welds.

1.6.1.12 As required by 1 OCFR50.55a(b)(2)(xxv)(B), Seabrook Station will implement the provisions in IWA-4340, Mitigation of Defects by Modification, of the 2013 Edition of Section XI subject to the conditions in 1 OCFR50.55a(b)(2)(xxv)(B)(1) through (3).

1.6.1.13 As required by 1 OCFR50.55a(b)(2)(xxvi), Seabrook Station will pressure test mechanical joints in Class 1, 2, and 3 piping and components greater than NPS 1 which are disassembled and reassembled during the performance of a repair and replacement activity requiring documentation on Form NIS-2. The system pressure test and NOE examiners will meet the requirements of the 2013 Edition of Section XI.

1.6.1.14 As required by 1 OCFR50.55a (b)(2)(xxvii), when performing visual examination in accordance with IWA-5241 of Section XI, 2013 Edition, insulation will 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.

1.6.1.15 As required by 1 OCFR50.55a(b)(2)(xxviii), Seabrook Station will use the stated conditions when implementing Equation 2 in ASME Section XI, Appendix A-4300(b)(1).

1.6.1.16 10CFR50.55a (b)(2)(xxix) requires prior NRG authorization to implement Nonmandatory Appendix R, Risk-Informed Inspection Requirements for Piping. Because Seabrook Station is utilizing Code Case N-716-1 for Risk-Informed/Safety-Based lnservice Inspection, this condition is not applicable.

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Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision O September 30, 2021 1.6.1.17 As required by 1 OCFR50.55a(b)(2)(xxxi),

when installing a mechanical clamping device on an ASME BPV Code class piping system, Appendix W of Section XI will be treated as a mandatory appendix and all of the provisions of Appendix W shall be met for the mechanical clamping device being installed. Additionally, use of IWA-4131.1 ( d) of the 2013 Edition will not be utilized on small item Class 1 piping and portions of a piping system that form the containment boundary.

1.6.1.18 As required by 1 OCFR50.55a(b)(2)(xxxii), Seabrook Station will submit to the NRC Summary Reports and Owner's Activity Reports described in IWA-6230 within 90 calendar days of the completion of each refueling outage.

1.6.1.19 As required by 1 OCFR50.55a (b)(2)(xxxiii), Seabrook Station will not implement paragraph G-2216 in Appendix G of the 2013 Edition of Section XI.

1.6.1.20 As required by 1 OCFR50.55a (b)(2)(xxxiv), Seabrook Station will implement the conditions in 10CFR50.55a (b)(2)(xxxiv)(A) and (B) when utilizing Nonmandatory Appendix U of the 2013 Edition of Section XI.

1.6.1.21 As required by 1 OCFR50.55a (b)(2)(xxxv), Seabrook Station will implement the condition in 10CFR50.55a (b)(2)(xxxv)(A) when utilizing Nonmandatory Appendix A of the 2013 Edition of Section XI.

1.6.1.22 As required by 1 OCFR50.55a(b)(2)(xxxvi), Seabrook Station will obtain NRC approval under 1 OCFR50.55a(z) before using irradiated Ta and the associated RTTo in establishing fracture toughness of irradiated materials per paragraph A-4400 of Nonmandatory Appendix A of the 2013 Edition of Section XI.

1.6.1.23 As required by 1 OCFR50.55a(b)(2)(xxxviii), Seabrook Station will implement the conditions in 1 OCFR50.55a(b)(2)(xxxviii)(A) and (B) when utilizing Mandatory Appendix Ill, Supplement 2 of the 2013 Edition of Section XI.

1.6.1.24 As required by 1 OCFR50.55a (b)(2)(xli), Seabrook Station will not implement the provisions for accepting flaws by analytical evaluation during preservice inspection in IWB-3112(a)(3) and IWC-3112(a)(3) of Section XI, 2013 Edition.

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Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-S8K-1-Program Plan Revision 0 September 30, 2021 1.6.1.25 As required by 1 OCFR50.55a(b)(2)(xlii), Seabrook Station will implement the conditions in 1 OCFR50.55a(b)(2)(xlii)(A) and (8) when applying Table IW8-2500-1, Examination Category 8-F, Item Nos. 85.11 and 85. 71 requirements of the 2013 Edition of Section XI.

1.6.1.26 As required by 10CFR50.55a(g)(6)(ii)(D)(1 ), Seabrook Station will augment the inservice inspection program by implementing the mandatory examination criteria in ASME Code Case N-729-6 subject to the conditions specified in paragraphs 1 OCFR50.55a(g)(6)(ii)(D)(2) through 1 OCFR50.55a(g)(6)(ii)(D)(8) regarding reactor vessel head inspections.

1.6.1.27 As required by 1 OCFR50.55a(g)(6)(ii)(E)(1 ), Seabrook Station will augment the inservice inspection program by implementing the mandatory examination requirements of ASME Code Case N-722-1 subject to the conditions specified in paragraphs (g)(6)(ii)(E)(2) through (4) regarding visual inspections of reactor coolant pressure boundaries.

1.6.1.28 As required by 1 OCFR50.55a (g)(6)(ii)(F)(1 ), Seabrook Station will augment the inservice inspection program by implementing the mandatory examination requirements of ASME Code Case N-770-5, subject to the conditions specified in paragraphs (g)(6)(ii)(F)(2) and (4) through (10), and (12) through (16) regarding examination requirements for Class 1 piping and nozzle dissimilar-metal butt welds.

1. 7 System Classification Seabrook Station Unit 1 System Classification is described in UFSAR Section 3.2.2, which states, "Fluid system components important to safety are classified in accordance with the ANSI N18.2a-1975, "Revision and Addendum to Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants." This classification system is compatible with the requirements of NRG Regulatory Guide 1.26 and is submitted as an alternate acceptable method of meeting the intent of Regulatory Guide 1.26."

1.7.1 ASME Code Class The ASME Code Class for Seabrook Station systems and components is captured in UFSAR Table 3.2.2. Specific code classifications and associated boundaries are depicted on the plant Piping and Instrument Drawings (P&IDs) listed in Appendix C. Safety Class flags shown on these P&IDs are explained on PID-LEGEND2. Typically, systems and components on the P&IDs which are designated as Safety Class 1, 2, and 3 also correspond to ASME Class 1, 2, and 3, respectively.

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Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan

1. 7.2 Optional Construction Revision 0 September 30, 2021 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 and Class CC Components A 10CFR50.55a Final Rule dated August 8, 1996, mandated the inservice inspection of Class MC components in accordance with ASME Section XI, Subsection IWE. The Seabrook Station Unit 1 program for Subsection IWE, 3rd lnterval-IWE-SBK-1-Prog Plan, examinations specifically defines the classification of those areas examined.

A 1 OCFR50.55a Final Rule dated August 8, 1996, mandated the inservice inspection of Class CC components in accordance with ASME Section XI, Subsection IWL. The Seabrook Station Unit 1 program for Subsection IWL, 3rd lnterval-IWL-SEA-Prog Plan, examinations specifically defines the classification of those areas examined.

1.8 Inspection Program Plan Examinations for Class 1, 2, and 3 components and component supports are scheduled in accordance with ASME Section XI and the lnservice Inspection Program. This incorporates the criteria of IWB-2411, IWC-2411, IWD-2411, IWF-2410 and Tables IWB-2411-1, IWC-2411-1, IWD-2411-1 and IWF-2410-1 for the examination of Class 1, 2, and 3 components and their supports, respectively.

Examinations are scheduled based upon previous 10-Year intervals, to the extent practical and within the limits established in IWA-2420. Class 1 and 2 Examination Categories 8-F, 8-J, C-F-1 and C-F-2 piping weld examinations and Class 2 Category C-A and C-8 vessel weld examinations are based on Risk-Informed/Safety-Based selection criteria in accordance with Code Case N-716-1.

The 4th Interval Seabrook Station ISi schedule tables for examinations of the major components are located in the ISi scheduling database (IDDEAL). The ISi schedule tables for examinations provides a brief description of each component subject to examination, the required Code references, and any other pertinent information that is useful for determining examination requirements. The ISi scheduling database (IDDEAL) satisfies the requirements of IWA-2420(b)(1) through (6) respectively and is updated on an ongoing basis.

Page 17 of 66

Seabrook Station Unit 1 ISi Program Revision 0 September 30, 2021 Document No. 4th lnterval-ISl-SBK-1-Program Plan 1.9 Regulatory Guides The Regulatory Guides determined to be applicable to Seabrook Station Unit 1 for purposes of this ISi Program Plan are listed below:

Table 2 USNRC Regulatory Guides 1.14 Reactor Coolant Pump Flywheel Integrity 1.26 Quality Group Classifications 1.147 Section XI Code Case Acceptability 1.193 ASME Code Cases Not Approved for Use 1.65 Materials and Inspections for Reactor Vessel Closure Studs 1.10 ASME Section XI Code Cases ASME Section XI Code Cases applicable to the ISi Plan are shown below. Each of the Code Cases has been approved or conditionally approved and listed in USNRC Regulatory Guide 1.147. Code Cases not listed in Reg Guide 1.147 but implemented via a relief request or mandated by 1 OCFR50.55a, the implemented revision may continue to be utilized until the end of the current interval, even if later revisions of the code case is approved during that interval.

Table 3 Applicable Code Cases Number Code Case Title Repair Welding Using Automatic or Machine Gas Tungsten-Arc N-432-1 Welding (GTAW) Temper Bead Technique,Section XI, Division 1 (Approved without conditions in Regulatory Guide 1.147, Rev. 19)

Repair/Replacement Documentation Requirements and lnservice N-532-5 Summary Report Preparation and Submission,Section XI, Division 1 (Approved without conditions in Regulatory Guide 1.147, Rev. 19)

Alternative Requirements for Wall Thickness Restoration of Class N-561-2 2 and High Energy Class 3 Carbon Steel Piping,Section XI, Division 1 (Approved with conditions in Reg. Guide 1.147, Rev.19)

Alternative Requirements for Wall Thickness Restoration of N-562-2 Class 3 Moderate Energy Carbon Steel Piping,Section XI, Division 1 (Approved with conditions in Reg. Guide 1.147, Rev.

19)

Page 18 of 66

Seabrook Station Unit 1 ISi Program Revision 0 September 30, 2021 Document No. 4th lnterval-ISl-SBK-1-Program Plan Table 3 Applicable Code Cases Number Code Case Title Alternative Examination Requirements for Steam Generator N-593-2 Nozzle to Vessel Welds,Section XI, Division 1 (Approved with conditions in Reg. Guide 1.147, Rev. 19)

N-597-3 Requirements for Analytical Evaluation of Pipe Wall Thinning (Approved with conditions in Regulatory Guide 1.147, Rev. 19)

Ultrasonic Examination of Full Penetration Nozzles in Vessels, Examination Category B-D, Reactor Nozzle-to-Vessel Welds and N-613-2 Nozzle Inside Radius Section, Figs. IWB-2500-7(a), (b), (c) and (d)

Section XI, Division 1. (Approved without conditions in Regulatory Guide 1.147, Rev. 19)

N-639 Alternative Calibration Block Material (Approved with conditions in Regulatory. Guide 1.147, Rev. 19)

Alternative Requirements for Inner Radius Examination of Class 1 N-648-2 Reactor Vessel Nozzles,Section XI, Division 1 (Approved with condition in Regulatory Guide 1.147. Rev. 19)

Ferritic and Dissimilar Metal Welding Using SMAW Temper Bead N-651 Technique Without Removing the Weld Bead Crown for the First Layer Section XI, Division 1 (Approved without conditions in Reaulatorv Guide 1.147, Rev. 19)

Qualification Requirements for Full Structural Overlaid Wrought N-653-1 Austenitic Piping Welds,Section XI, Division 1 (Approved without conditions in Regulatory Guide 1.147, Rev. 19)

Alternative Requirements for Wall Thickness Restoration of Class N-661-3 2 and 3 Carbon Steel Piping for Raw Water Service,Section XI, Division 1 (Approved without conditions in Reg. Guide 1.147, Rev.

19)

N-666-1 Weld Overlay of Class 1, 2, and 3 Socket Welded Connections (Approved with conditions in Regulatory Guide 1.147, Rev. 19)

N-695-1 Qualification Requirements for Dissimilar Metal Piping Welds (Approved with conditions in Regulatory Guide 1.147, Rev. 19)

Qualification Requirements for Mandatory Appendix VIII Piping N-696-1 Examinations Conducted From the Inside Surface (Approved with conditions in Regulatory Guide 1.147, Rev. 19)

Alternative Examination Coverage Requirements for Examination N-711-1 Category B-F, B-J, C-F-1, C-F-2, and R-A Piping Welds (Approved with condition.s in Regulatory Guide 1.14 7, Rev. 19)

Page 19 of 66

Seabrook Station Unit 1 ISi Program Revision 0 September 30, 2021 Document No. 4th lnterval-ISl-SBK-1-Program Plan Table 3 Applicable Code Cases Number Code Case Title N-716-1 Alternative Classification and Examination Requirements (Approved without conditions in Regulatory Guide 1.147, Rev. 19)

Additional Requirements for PWR Pressure Retaining Welds in N-722-1 Class 1 components Fabricated With Alloy 600/82/182 Materials,Section XI, Division 1

[Mandated with conditions in 1 OCFR50.55a(g)(6)(ii)(E)]

Alternative Examination Requirements for PWR Reactor Vessel N-729-6 Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration Welds,Section XI, Division 1 [Mandated with conditions in 1 OCFR50.55a(g)(6)(ii)(D)]

Alternative Class 1 System Leakage Test Pressure Requirements, N-731 Section XI, Division 1 (Approved without conditions in Regulatory Guide 1.147, Rev. 19)

Mitigation of Flaws in NPS 2 (DN 50) and Smaller Vessels and N-733 Piping By Use of a Mechanical Connection Modification (Approved without conditions in Regulatory Guide 1.14 7, Rev. 19)

N-735 Successive Inspections of Class 1 and 2 Piping Welds (Approved without conditions in Regulatory Guide 1.147, Rev. 19)

N-747 Reactor Vessel Head-to-Flange Weld Examinations (Approved without conditions in Regulatory Guide 1.147, Rev. 19)

N-751 Pressure Testing of Containment Penetration Piping (Approved with conditions in Regulatory Guide 1.147, Rev. 19)

Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Butt Welds Fabricated with N-770-5 UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities [Mandated with conditions in 1 OCFR50.55a(g)(6)(ii)(F)]

Alternative Requirements for Additional Examinations of Class 2 N-771 or 3 Items,Section XI, Division 1 (Approved without conditions in Regulatory Guide 1.147, Rev. 19)

Alternative Qualification Criteria for Eddy Current Examinations of N-773 Piping Inside Surfaces (Approved without conditions in Regulatory Guide 1.147, Rev. 19)

Page 20 of 66

Seabrook Station Unit 1 ISi Program Revision 0 September 30, 2021 Document No. 4th lnterval-ISl-SBK-1-Program Plan Table 3 Applicable Code Cases Number Code Case Title Alternative Requirements for Sleeve Reinforcement of Class 2 and N-786-1 3 Moderate-Energy Carbon Steel Piping,Section XI, Division 1 (Approved without conditions in Regulatory Guide 1.147, Rev. 19)

Alternative Requirements for Pad Reinforcement of Class 2 and 3 N-789-2 Moderate-Energy Carbon Steel Piping,Section XI, Division 1 (Approved without conditions in Regulatory Guide 1.147, Rev. 19)

Alternative Pressure Testing Requirements for Class 1 Piping N-798 Between the First and Second Vent, Drain, and Test Isolation Devices,Section XI, Division 1 (Approved without conditions in Regulatory Guide 1.147, Rev. 19)

Alternative Pressure Testing Requirements for Class 1 Piping N-800 Between the First and Second Injection Valves,Section XI, Division 1 (Approved without conditions in Regulatory Guide 1.147, Rev. 19)

Alternative to Class 1 Extended Boundary End of Interval or Class N-805 2 System Leakage Testing of the Reactor Vessel Head Flange 0-Ring Leak-Detection System,Section XI, Division 1 (Approved without conditions in Regulatory Guide 1.14 7, Rev. 19)

N-823-1 Visual Examination (Approved without conditions in Regulatory Guide 1.147, Rev. 19)

Alternative Requirements for Examination of Control Rod Drive N-825 Housing Welds,Section XI, Division 1 (Approved without conditions in Regulatory Guide 1.147, Rev. 19)

Direct Use of Master Fracture Toughness Curve for Pressure-N-830 Retaining Materials of Class 1 Vessels (Approved with conditions in Regulatory Guide 1.147, Rev. 19)

Similar and Dissimilar Metal Welding Using Ambient Temperature N-839 SMAW Temper Bead Technique (Approved without conditions in Regulatory Guide 1.147, Rev. 19)

Alternative Pressure Testing Requirements Following Repairs or N-843 Replacements for Class 1 Piping Between the First and Second Injection Isolation Valves (Approved with conditions in Regulatory Guide 1.147, Rev. 19)

Qualification Requirements for Bolts and Studs,Section XI, N-845 Division 1 (Approved without conditions in Regulatory Guide 1.147, Rev. 19)

Page 21 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Table 3 Applicable Code Cases Number Code Case Title Revision 0 September 30, 2021 Alternative Pressure Testing Requirements for Class 2 and 3 N-854 Components Connected to the Class 1 Boundary (Approved without conditions in Regulatory Guide 1.147, Rev. 19) 1.11 Plant Life Extension The purpose of the Renewed License Program (EN-AA-106) is to define the roles and responsibilities for the implementation of the License Renewal process and the actions that need to be completed for each unit after the Renewed Operating License is issued to include the post approval inspections and operation in the Period of Extended Operation (PEO).

The ISi Program will implement the NextEra Energy commitments to manage the effects of aging for systems/structures/components within the scope of license renewal. The Section XI Plan 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 Safety Evaluation Report Related to the License Renewal of Seabrook Station.

1.12 Successive Examinations The sequence of component examinations may be modified in accordance with the requirements of ASME Section XI, IWB-2420(a), IWC-2420(a), IWD-2420(a) and IWF-2420(a). This allows NextEra 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/Safety-Based ISi Program, the scheduling of Class 1 and 2 piping weld examinations will follow Code Case N-716-1 requirements, as the selection criteria are different than those stated in ASME Section XI. 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 NOE and Personnel Qualification/Certification All NOE will be performed in accordance with the requirements of ASME Section XI, 2013 Edition with the following modifications as required by 1 OCFR50.55a.

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Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 1.13.1 Alternative Examinations (IWA-4520(b)(2) and IWA-4521)

Seabrook Station will not apply the provisions in IWA-4520(b) (2) and IWA-4521 of the 2013 Edition allowing the substitution of ultrasonic examination for radiographic examination specified in the Construction Code. [Reference 1 OCFR50.55a (b)(2)(xix)].

1.13.2 System Leakage Tests for Repair Replacement Activities The NOE provision in IWA-4520(a)(2) requires use of the acceptance criteria of the 1992 Edition or later of Section Ill when performing system leakage tests after repair and replacement activities performed by welding or brazing on a pressure retaining boundary, [Reference 1 OCFR50.55a(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, per 1 OCFR50.55a (b)(2)(xxii).

1.13.4 Certification and Recertification (IWA-2314)

Level I and 11 nondestructive examination personnel and personnel qualified under the American Society for Nondestructive Testing Central Certification Program and ANSl/ASNT CP-189 shall be recertified by examination 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 licensee's facility. NextEra Energy will comply with these additional training requirements for personnel performing Section XI Appendix VIII, UT examinations.

NextEra Energy may also may use the annual practice requirements in VI 1-4240 of Appendix VI I of Section XI 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 provided that the supplemental practice is performed on material or welds that contain cracks, or by analyzing prerecorded data from material or welds that contain cracks. In either case, training must be completed no earlier than 6 months prior to performing ultrasonic examinations at a licensee's facility.

1.13.5.2 In September 1999, 10CFR50.55a incorporated an expedited Page 23 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision O September 30, 2021 implementation schedule for ASME Section XI, Appendix VIII.

NextEra Energy implemented the requirements in accordance with the expedited schedule within the third 10-year interval for Seabrook Station. For the fourth 10-year interval, NextEra Energy will implement the requirements of ASME Section XI, Appendix VII and VIII as modified by 10CFR50.55a.

2.0 Risk-Informed/Safety-Based {RIS_B) ISi Requirements 2.1 Seabrook Station Unit 1 is continuing to implement an alternative Risk-Informed/Safety-Based (RIS_B) lnservice Inspection Program for Class 1 and 2 piping welds and has extended this alternative to include Class 2 vessel welds in accordance with ASME Section XI Code Case N-716-1.

2.2 During the Third Interval the Seabrook Risk-Informed/Safety-Based ISi Program was developed based on the Electric Power Research Institute (EPRI) Topical Report (TR) 112657 Rev. B-A, [Ref. 18.30], with identified differences, and with additional guidance taken from ASME Code Case N-716 [Ref. 18.31]. By letter dated November 7, 2011 (Accession No. ML11319A016), supplemented by "M120308, M120308 - Affirmation Session: I. SECY-11-0085 NextEra Seaborok Appeals of LBP-11-2; Ii. SECY-12-0006 (Entergy) Commonwealth of Massachusetts' and [[Intervenor" contains a listed "[" character as part of the property label and has therefore been classified as invalid.'S Petitions for Review of LBP-11-35 and Related Filings|letter dated March 8, 2012]] (Accession No. ML12074A111), NextEra Energy Seabrook Station (Seabrook) submitted Request for Alternative 3AR-1 to the NRC, requesting relief from the ASME Section XI Code examination requirements for Class 1 and Class 2 piping weld (Examination Categories B-F, B-J, C-F-1, and C-F-2) inservice inspections by implementing a Risk-Informed, Safety-Based lnservice Inspection (RIS_B) Program.

The NRC published a Safety Evaluation dated June 21, 2012 (Accession No. ML121320552) authorizing the use of a Risk-Informed, Safety-Based inservice inspection (RIS_B) program for the third 10-year ISi interval at Seabrook.

2.3 For the Fourth Interval the RIS_B Program implemented ASME Code Case N-716-1

[Ref. 18.32] which provides alternative criteria for the examination of Class 2 vessel welds (Examination Categories C-A and C-B) as well as Class 1 and Class 2 piping weld (Examination Categories B-F, B-J, C-F-1, and C-F-2). Code Case N-716-1 also provides provisions for Class 2 bolting (Examination Category C-D), but Seabrook does not have any components in this Examination Category.

2.4 Code Case N-716-1 is acceptable without conditions in Regulatory Guide 1.147, Rev.

19 [Ref. 18.5]. As a result, a Relief Request is not required to implement the RIS_B Program for the Fourth Interval.

2.5 The RIS_B Program is a living program that is required to be monitored continuously for changes that could impact the basis for which welds are selected for examination.

Monitoring encompasses numerous facets, including the review of changes to the plant configuration, changes to operations that could affect the degradation assessment, a review of NOE results, a review of site failure information from the corrective action program, and a review of industry failure information from industry operating experience (OE). Also included is a review of PRA changes for their impact on the RIS_B program. These reviews provide a feedback loop such that new relevant information is obtained that will ensure that the appropriate identification of HSS piping locations selected for examination is maintained. As a minimum, this review will be conducted on an ASME period basis. In addition, more frequent Page 24 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 adjustment may be required as directed by NRC Bulletin or Generic Letter requirements, or by industry and plant-specific feedback. RIS_B Living Program Evaluations and Updates are performed in accordance with NEI 04-05, "Living Program Guidance To Maintain Risk-Informed lnservice Inspection Programs For Nuclear Plant Piping Systems" [Ref. 18.33], published April 2004. RIS_B Living Program Updates for the Fourth Interval will be included in Appendix B of this ISi Program Plan.

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

2.7 For Risk-Informed welds, the length for the UT examination volume shall be increased to include 1/2 inch beyond each side of the base metal thickness transition or counterbore. If a thickness transition or counterbore is not evident, the length for the UT examination volume shall be increased to include base material for a distance of 1 /2 inch from each weld toe.

2.8 Successive and Additional Examinations For the RIS_B application, Seabrook will meet the criteria of Code Case N-716-1, Section 6 for performing Successive and Additional examinations. In accordance with the Code Case, the following criteria apply:

2.8.1 Successive Inspections As an alternative to the successive inspection requirements of IWB-2420, IWC-2420, or IWD-2420, the following requirements shall be met.

(1) The sequence of piping examinations established during the first inspection interval using this Case shall be repeated during each successive inspection interval to the extent practical. The examination sequence may be modified to optimize scaffolding, radiological, insulation removal, or other considerations, provided the percentage requirements of IWB-2410 are met.

(2) If Examination Category R-A Piping Welds are accepted for continued service by analytical evaluation in accordance with IWB-3132.3 or IWB-3142.4, the areas containing flaws or relevant conditions shall be re-examined during the next three inspection periods.

(3) If Class 2, 3, or non-class vessels, pumps, valves, and pressure-retaining bolting are accepted for continued service by analytical evaluation in accordance with IWC-3122.3, or IWC-3132.3, as applicable, the areas containing flaws or relevant conditions shall be reexamined during the next inspection period.

(4) If the reexaminations required by 2.8.1 (2) reveal that the flaws or relevant conditions remain essentially unchanged, the examination schedule shall revert to the original schedule of successive inspections.

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Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 (5) If the reexaminations required by 2.8.1 (3) reveal that the flaws or relevant conditions remain essentially unchanged during the successive inspection period, the examination schedule shall revert to the original schedule of successive inspections.

2.8.2 Additional Examinations As an alternative to the additional examination requirements of IWB-2430, IWC-2430, or IWD-2430, the following requirements shall be met.

(1) Examinations performed, excluding Examination Categories B-P and C-H, or D-B that reveal flaws or relevant conditions exceeding the acceptance standards of Table IWB-3410-1, Table IWC-3410-1, or IWD-3410-1, as applicable, shall be extended to include a first sample of additional examinations during the current outage.

(a)

The inspection item to be examined in the first sample of additional examinations shall include HSS inspection items with the same postulated degradation mechanism in systems whose materials and service conditions are similar to the element that exceeded the acceptance standards.

(b)

The number of examinations required is the number of HSS inspection items with the same postulated degradation mechanism scheduled for the current inspection period. If there are not enough HSS inspection items to equal this number, Seabrook shall include remaining HSS inspection items and LSS inspection items within the Class 1, 2, and 3 systems subject to examination in accordance with Section XI, up to and including this number that are subject to the same degradation mechanism. This might require additional analysis of LSS components (e.g., degradation mechanism evaluation).

(2) If the additional examinations required by 2.8.2(1) reveal flaws or relevant conditions exceeding the acceptance standards of Table IWB-3410-1, Table IWC-3410-1, or IWD-3000 as applicable, the examinations shall be extended to include a second sample of additional examinations during the current outage.

(a)

The second sample of additional inspection items to be examined shall include all remaining HSS inspection items subject to the same degradation mechanism.

(b)

Seabrook shall also examine LSS inspection items identified with the same postulated damage mechanism within the Class 1, 2, and 3 systems subject to ex-amination in accordance with Section XI or document the basis for their exclusion. This might require additional analysis of LSS components (e.g., degradation mechanism evaluation).

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Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 (3) For the inspection period following the period in which the examination of 2.8.2(1) and (2) were completed, the examinations shall be performed as originally scheduled in accordance with IWB-2400.

3.0 Development of the Class 1 Examination Plan Plant controlled isometrics, P&IDs, component drawings, and plant walkdowns were utilized to develop the Seabrook ISi isometrics and drawings and the scope of examinations. During examinations, these documents will be used to locate and identify each component or part.

Other plant-controlled drawings or documents will be used when additional information is required.

Refer to the ISi scheduling database (IDDEAL) 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 The following components1 or parts of components are exempted from the volumetric, surface, VT-1 visual and VT-3 visual 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 (DN 25) and smaller, except for steam generator tubing; (2) Components and piping segments which have one inlet and one outlet, both of which are NPS 1 (ON 25) and smaller; (3) Components2 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 (DN 25) pipe.

(c)

Reactor vessel head connections and associated piping, NPS 2 (DN 50) and smaller, made inaccessible by control rod drive penetrations.

Page 27 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-S8K-1-Program Plan Revision 0 September 30, 2021 (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.

1The 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.

2For 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 ASME Section XI, 2013 Edition. The Summary Table for the major components for Seabrook Station Unit 1 is located in the ISi scheduling database (IDDEAL). The ISi scheduling database (IDDEAL) satisfies the requirements of IWA-2420(b)(1) through (6), respectively.

The Class 1 system boundaries are identified on the site P&IDs. Specific examinations are in accordance with the ASME 8&PV Code,Section XI, Table IW8-2500-1, as further described below.

3.3 Category B-A, Pressure Retaining Welds in Reactor Vessel Table 8-A provides the examination scope and schedule for Table IWB-2500-1, Examination Category 8-A, "Pressure Retaining Welds in Reactor Vessel". Refer to the table below for the applicable Relief Requests, Code Cases and Regulatory Requirements. The percentage of scheduled examinations for this Examination Category was developed in accordance with IW8-2411, "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.

Page 28 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-S8K-1-Program Plan Shell Welds 81.11 81.12 Head Welds 81.21 81.22 81.30 81.40 81.50 Circumferential1 Longitudinal1 Circumferential1 Meridional1 Shell-to-Flange Weld1 Head to Flange Weld1 Repair Welds in the 8eltline Region 3

9 2

8 1

0 Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric and Surface Volumetric Revision O September 30, 2021 R,elief Requ~st Number, <?c:>deCase or Regulatory

.Re uiremerit Item Number 81.50 and 81.51 beltline region repair welds are not applicable to the Seabrook Station Unit 1 design.

1Table IW8-2500-1, 8-A, Note (2), requires essentially 100% of all longitudinal and circumferential shell welds be examined. Note that the examinations of Item Nos. 81.21 and 81.22 Head Welds include the accessible length only.

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 8-B, "Pressure Retaining Welds in Vessels Other Than Reactor Vessels". Refer to the table below for the applicable Relief Requests, Code Cases and Regulatory Requirements.

The percentage of scheduled examinations for this Examination Category was developed in accordance with IWB-2411, "Inspection Program."

Page 29 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-S8K-1-Program Plan Pressurizer Shell to Head Welds 82.11 Circumferential 82.12 Longitudina11 Steam Generator Head Welds (Primary) 82.40 Steam Generator2 Tubesheet-To-Head Weld 2

2 4

Revision O September 30, 2021 Volumetric Volumetric Volumetric Relie(~equest Number, Code Case or Reg1,1latory Re uirement Item Number 82.21, 82.22, 82.31, 82.32, 82.51, 82.52, 82.60, 82.70 and 82.80 welds are not included in the Seabrook Station Unit 1 design.

Table IW8-2500-1, 8-8, Notes (2) and (4), Examine essentially 100% of the Pressurizer circumferential shell to head welds at both ends and 1 foot of one longitudinal weld adjacent to each shell to head weld.

2Table IW8-2500-1, 8-8, Notes (1) and (4), the examination may be limited to one vessel among the group of vessels performing a similar function. Examine essentially 100% of the Steam Generator tubesheet-to-head weld, Figure IW8-2500-6.

3.5 Category 8-D, Full Penetration Welded Nozzles Welds of Nozzle in Vessels Table 8-D provides the examination scope and schedule for Table IW8-2500-1, Examination Category 8-D, "Full Penetration Welded Nozzles in Vessels". Refer to the table below for the applicable Relief Requests. Code Cases and Regulatory Requirements.

The percentage of scheduled examinations for this Examination Category was developed in accordance with IW8-2411, "Inspection Program," subparagraph (a)(2),

which allows examinations to be partially deferred to the end of an inspection interval (RPV only).

Page 30 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-S8K-1-Program Plan Reactor Vessel 83.90 Nozzle-to-Vessel Welds2 83.100 Nozzle Inside Radius2 Pressurizer 83.110 Nozzle-to-Vessel Welds 83.120 Nozzle Inside Radius1 Steam Generator (Primary) 83.130 Nozzle-to-Vessel Welds 83.140 Nozzle Inside Radius1 8

Volumetric 8

VT-12 6

Volumetric 0

8 Volumetric 0

Revision 0 September 30, 2021 R~liefRequest Number~ Co~eCase or Regula~?ry Re uirerrient N-613-2 N-648-2 There are no Item Numbers 83.150, 3.160 welds at Seabrook Station Unit 1.

1Examination of these nozzle inner radius sections is no longer mandated by 1 OCFR50.55a (b)(2)(xxi)(A).

2Table IWB-2500-1, 8-D, Note (5), For PWRs in the second and successive inspection intervals, these examinations may be deferred to the end of the interval, provided no repair/replacement activities have been performed on the examination item, and no flaws or relevant conditions requiring successive inspections in accordance with IWB-2420(b) are contained in the examination item. For nozzle inner radius examinations, a VT-1 can be substituted for a volumetric in accordance with Code Case N-648-2.

3.6 Category B-F, Pressure Retaining Dissimilar Metal Welds These welds will be examined under the RIS_8 Program in accordance with Code Case N-716-1.

Page 31 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 3.7 Category B-G Pressure Retaining Bolting, Greater Than 2 inches 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 the table below for the applicable Relief Requests, Code Cases and Regulatory Requirements.

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.

Reactor Vessel B6.10 B6.20 B6.40 B6.50 Closure Head Nuts Closure Studs, in place1 Threads in Flange Closure Washers, Bushings2 Reactor Coolant Pump B6.180 B6.190 B6.200 Bolts and Studs1,3 Flange Surface, when connection disassembled4*5 Nuts, Bushings, and Washers 54 54 54 54 96 4

4 Visual, VT-1 Volumetric or Surface Volumetric Visual, VT-1 Volumetric or Surface Visual, VT-1 Visual, VT-1 There is no pressure retaining bolting within Item Numbers 86.60, 86.70, 86.80, 86.90, 86.100, 86.110, 86.120, 86.130, 86.140, 86.150, 86.160, 86.170, 86.210, 86.220 and 86.230 at Seabrook Station Unit 1.

1Table WB-2500-1, B-G-1, Note (1), Bolting may be examined in place under tension, when the connection is disassembled, or when the bolting is removed.

2Table IWB-2500-1, B-G-1, Note (2), Bushings are required to be examined only when the bolting is removed. Bushings may be examined in place.

3 Table 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.

Page 32 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 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.

4Table IWB-2500-1, B-G-1, Note (4), Visual examination of nuts, bushings, washers, and flange surfaces for heat exchangers, pumps, or valves is required only when the component is examined under Examination Category B-B, B-L-2, or B-M-2. Examination of a bolted connection is required only once during the interval.

5Table IWB-2500-1, B-G-1, Note (6), Examination includes 1 in. (25 mm) annular surface of flange surrounding each stud.

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 or valve is disassembled, or bolting is removed. Refer to the table below for the applicable Relief Requests, Code Cases and Regulatory Requirements.

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.

Pressurizer B7.20 Bolts, Studs, and Nuts1*2 Steam Generator B7.30 B7.50 Pumps B7.60 B7.70 Bolts, Studs, and Nuts1*2 Bolts, Studs, and Nuts1*3 Bolts, Studs, and Nuts1*2 Bolts, Studs, and Nuts1*2 1 closure Visual, VT-1 8 closures Visual, VT-1 6 flanges Visual, VT-1 4 closures Visual, VT-1 56 closures Visual, VT-1 Page 33 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-S8K-1-Program Plan Revision 0 September 30, 2021 There is no pressure retaining bolting within Item Numbers 87.10 or 87.40 at Seabrook Station Unit 1.

1Table IWB-2500-1, B-G-2, Note (1), Bolting is required to be examined only when a connection is disassembled, or bolting is removed.

2Table 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 8-A, 8-8, B-L-2, or B-M-2. Examination of bolted connection is required only once during the interval.

3Table 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.

3.9 Category 8-J, Pressure Retaining Welds in Piping These welds will be examined under the RIS_8 Program in accordance with Code Case N-716-1.

3.1 O Category 8-K, Welded Attachments for Vessels, Piping, Pumps, and Valves Table 8-K provides the examination scope and schedule for Table IWB-2500-1, Examination Category 8-K, "Welded Attachments for Vessels, Piping, Pumps, and Valves". Refer to the table below for the applicable Relief Requests, Code Cases and Regulatory Requirements.

Pressure Vessels

1------------------------------------------------------------------ --------------------------------------------- ---------------------------------------------- --------------------------------------------------------------------

810. 101,3 VesselWelded 5

Surface Attachments 810.202.3 Piping Welded Attachments Surface There are no Item Number 810.30 or 810.40 welded attachments at Seabrook Station Unit 1.

1Table IWB-2500-1, 8-K, Note (4), for multiple vessels of similar design, function and service, only one welded attachment of only one of the multiple vessels shall be selected for examination. For single vessels, only one welded attachment shall be selected for examination. The attachment selected for examination on one of the multiple vessels or the single vessel, as applicable, shall be an attachment under continuous load during normal system operation, or an attachment subject to a potential intermittent load (seismic, water hammer, etc.) during normal system operation if an attachment under continuous load does not exist.

Page 34 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 2Table IWB-2500-1, B-K, Note (5), for piping, pumps, and valves, a sample of 10% of the welded attachments associated with the component supports selected for examination under IWF-2510 shall be examined.

3Table IWB-2500-1, B-K, Note (6), Examination is required whenever component support member deformation, e.g., broken, bent, or pulled out parts, is identified during operation, refueling, maintenance, examination, or testing.

3.11 Category B-L-2, Pump Casings Table B-L-2 provides the examination scope and schedule for Table IWB-2500-1, Examination Category B-L-2, "Pump Casing".

The percentage of scheduled examinations for Examination Category B-L-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. Refer to the table below for the applicable Relief Requests, Code Cases and Regulatory Requirements.

Pumps 812.20 Pump Casing1*2 4

Visual, VT-3 1Table IWB-2500-1, B-L-2, Note (1), Examinations are limited to at least one pump in each group of pumps performing similar functions in the system, e.g., recirculating coolant pumps.

2Table WB-2500-1, B-L-2, Note (2), Examination is required only when a pump is disassembled for maintenance, or repair. Examination of the internal pressure boundary shall include the internal pressure retaining surfaces made accessible for examination by disassembly. If a partial examination is performed and a subsequent disassembly of that pump allows a more extensive examination, an examination shall be performed during the subsequent disassembly. A complete examination is required only once during the interval.

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. Refer to the table below for the applicable Relief Requests, Code Cases and Regulatory Requirements.

Page 35 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan 812.50 Valve body, exceeding NPS 4 ON 100 1*2 33 Revision 0 September 30, 2021 Visual, VT-3

£telief Request Number, Gode Case

(>r ~ef1u1at()ry Re uirement 1Table IWB-2500-1, B-M-2, Note (2), Examination is required only when a valve is disassembled for maintenance, or repair. Examination of the internal pressure boundary shall include the internal pressure retaining surfaces made accessible for examination by disassembly. If a partial examination is performed and a subsequent disassembly of that valve allows a more extensive examination, an examination shall be performed during the subsequent disassembly. A complete examination is required only once during the interval.

2Table IWB-2500-1, B-M-2, Note (3), Examinations are limited to at least one valve within each group of valves that are of the same size, constructural design (such as globe, gate, or check valves), and manufacturing method, and that perform similar functions in the system (such as containment isolation and system overpressure protection). These valve groupings are shown in Table 4, which follows.

Manufacturer Valve Number Type &Size RC-V-22 Westinghouse RC-V-23 12" Gate Valve RC-V-87 RC-V-88 RC-V-115 2

Crosby RC-V-116 6" Relief Valve RC-V-117 RH-V-15 RH-V-29 3

Westinghouse RH-V-30 6" Check Valve RH-V-31 RH-V-52 RH-V-53 RH-V-50 8" Check Valve RH-V-51 RH-V-59 4

Westinghouse RH-V-61 6" Gate Valve RH-V-63 RH-V-65 Page 36 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Group Number 5

6 Manufacturer Westinghouse Westinghouse Valve Number Sl-V-3 Sl-V-17 Sl-V-32 Sl-V-47 Sl-V-5 Sl-V-6 Sl-V-20 Sl-V-21 Sl-V-35 Sl-V-36 Sl-V-50 Sl-V-51 Sl-V-82 Sl-V-87 Revision 0 September 30, 2021 Type& Size 1 O" Gate Valve 1 O" Check Valve 6" Check Valve 3.13 Categories B-N-1, B-N-2 & B-N-3: Interior of Reactor Vessel, Welded Core Support Structures and Interior Attachments to Reactor and Vessels, Removable Core Support Structures Table IWB-2500-1 for Categories B-N-1, B-N-2 & B-N-3 provides the examination scope and schedule for "Interior of Reactor Vessel, "Welded Core Support Structures and Interior Attachments to the Reactor Vessels" and "Removable Core Support Structures".

The percentage of scheduled examinations for this Examination Category is not applicable in accordance with IWB-2411, "Inspection Program," subparagraph (a)(1) and (a)(3). To reduce radiation exposure, 100% of the Category B-N-2 and B-N-3 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.

Refer to the table below for the applicable Relief Requests, Code Cases and Regulatory Requirements.

Page 37 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-S8K-1-Program Plan Parts Examined 813.10 (B-N-1) Vessel lnterior1 1

Visual, VT-3 Revision 0 September 30, 2021 813.60 813.70

( B-N-2) Interior Attachments Beyond Beltline Region2 (B-N-3) Core Support Structure3 6

Visual, VT-3 Visual, VT-3 Item Numbers 813.20, 813.30, 813.40 and 813.50 are not applicable to Seabrook Station Unit 1.

1Table IWB-2500-1, B-N-1, Notes (1) and (3), Examinations include a 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. Examination shall be performed at the 1st refueling outage, and subsequent refueling outages at approximately 3 year intervals.

2Table IWB-2500-1, B-N-2, Note (2), Examinations include a VT-3 visual examination of interior attachments beyond the beltline region once per interval.

3Table IWB-2500-1, B-N-3, Note (3), Examinations include a VT-3 visual examination of the core support structure once per interval. The structure shall be removed from the reactor vessel for examination.

3.14 Category 8-0, Pressure Retaining Welds in Control Rod Drive and Instrument Housings Table IW8-2500-1 for Category 8-0 provides the examination scope and schedule for "Pressure Retaining Welds in Control Rod Drive and Instrument Housings."

The percentage of scheduled examinations for this Examination Category is not applicable in accordance with IW8-2411, "Inspection Program," subparagraph (a)(3).

The required examinations for this Examination Category may be deferred to the end of the inspection interval. Refer to the table below for the applicable Relief Requests, Code Cases and Regulatory Requirements.

814.20 Welds in Control Rod Drive (CRD) Housings 20 Page 38 of 66 Volumetric or Surface 1

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-S8K-1-Program Plan Revision 0 September 30, 2021 Seabrook Station Unit 1 has 20 control rod housings on the periphery with 1 weld per housing and no Category 14.21 lncore Instrumentation (ICI) Housing welds greater than or equal to 2" NPS.

1Table IW8-2500-1, 8-0, Note (1), The surface examination method shall be performed on the inside diameter of the penetration nozzle housing welds as shown in Figure IW8-2500-18 for examination surface area C-D.

3.15 Category 8-P, All Pressure Retaining Components Table 8-P provides the examination scope and schedule for Table IW8-2500-1, Examination Category 8-P, "All Pressure Retaining Components. Refer to the table below for the applicable Relief Requests, Code Cases and Regulatory Requirements.

815.10 Class 1 System Various Visual, VT-2 N-731, N-798, N-800, Leakage Test1*3 815.20 Class 1 System Various Visual, VT-2 N-731, N-798, N-800, Leakage Test2*3 1Table IW8-2500-1, 8-P, Notes (1) and (2): The VT-2 Visual examination shall be performed in accordance with IWA-5240. The system leakage test per IW8-5220 shall be conducted prior to plant startup following each refueling outage.

2 Table IW8-2500-1, 8-P, Notes (1) and 3: The VT-2 Visual examination shall be performed in accordance with IWA-5240. The system leakage test of IW8-5220 of the boundary of IWB-5222(b) shall be performed at or near the end of the interval.

3 Per IWA-5241 (f), for insulated components in systems borated for the purpose of controlling reactivity, insulation shall be removed from pressure retaining bolted connections for VT-2 visual examination unless material requirements are met.

3.16 Category 8-Q, Steam Generator Tubing Table IW8-2500-1 provides the examination scope and schedule for Examination Category 8-Q, "Steam Generator Tubing" The extent and frequency of steam generator tubing surveillance requirements, Item No. 816.20 are contained in plant Technical Specification 6.7.6.k. The Steam Generator Program, which includes the requirements for the steam generator examinations. Administrative requirements associated with ASME Section XI are addressed by this document. Refer to the table below for the applicable Relief Requests, Code Cases and Regulatory Requirements.

Page 39 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan 816.20 Steam Generator Tubing in U-Tube Design1 4

Volumetric Revision O September 30, 2021 N/A 1Table IW8-2500-1, 8-Q, Note (1 ): The extent and frequency of examination shall be governed by the plant Technical Specifications.

3.17 Category R-A, Risk-Informed/Safety-Based lnservice Inspection As discussed in Section 2.0, starting in the Fourth Interval the Seabrook Station Risk-Informed/Safety-Based application is in accordance with ASME Section XI Code Case N-716-1. The RIS_B Program supersedes the ASME XI examination selection requirements of Examination Categories B-F, B-J, C-A, C-B, C-F-1 and C-F-2.

The tables shown below indicate the required nondestructive examination requirements for welds subject to Code Case N-716-1. All welds are still subject to VT-2 pressure testing regardless of whether they are High Safety Significant or Low Safety Significant.

Table R-A-1 provides the examination scope for High Safety Significant Class 1 and 2 piping welds as an alternative to Table IWB-2500-1, Examination Categories B-F, B-J, C-F-1 and C-F-2.

Table R-A-2 provides the examination scope for Low Safety Significant Class 1 and 2 piping welds as an alternative to Table IWB-2500-1, Examination Categories B-F, B-J, C-F-1 and C-F-2.

Table R-A-3 provides the examination scope for High Safety Significant Class 2 vessel welds as an alternative to Table IWC-2500-1, Examination Categories C-A and C-B.

Table R-A-4 provides the examination scope for Low Safety Significant Class 2 vessel welds as an alternative to Table IWC-2500-1, Examination Categories C-A and C-B.

Page 40 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan R1.11 Welds Subject to 151*

Thermal Fatigue R1.12 Item No Not Used NIA R1.13 Welds Subject to 0

Erosion-Cavitation Welds Subject to R1.14 Crevice Corrosion 0

Cracking Welds Subject to Primary water R1.15 Stress Corrosion 8

Cracking (PWSCC)

Welds Subject to lntergranular or R1.16 Transgranular 7

Stress Corrosion Cracking (IGSCC om TGSCC)

Welds Subject to Localized Corrosion R1.17

[Microbiologically 0

Influenced Corrosion (MIC) or Pitting]

Welds Subject to Per FAC R1.18 Flow Accelerated Program Corrosion (FAC)

Welds Subject to R1.19 External Chloride 0

Stress Corrosion Cracking Welds Not Subject R1.20 to a Degradation 932 Mechanism Volumetric NIA Volumetric Volumetric Volumetric per PWSCC Program Volumetric Visual, VT-3 Internal Surface or Volumetric Per FAC Program Surface Volumetric Revision 0 September 30, 2021

- .. Relief Re(ju.est

/Nu~J:)ef;.()cide ca~e*

~r ~egljl~to'..Y

Re* uireineht

Code Case N-716-1 Code Case N-716-1 Code Case N-716-1 Code Case N-716-1 Code Case N-716-1 Code Case N-716-1 Code Case N-716-1 Code Case N-716-1 Code Case N-716-1 Code Case N-716-1

Of the 151 welds listed under Item No. R1.11, twelve of them were also assigned lntergranular Stress Corrosion Cracking (Item No. R 1.16) as a potential degradation Page 41 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 mechanism. The higher of the Item Nos. (R 1.11) was assigned administratively, but both degradation mechanisms are considered during the RIS_B application.

R0.00 C1.10 C1.20 C1.30 C2.21 C2.22 R0.00 LSS Class 1 & 2 Piping Welds HSS Class2 Vessel Shell Circumferential Welds HSS Class 2 Vessel Head Circumferential Welds HSS Class 2 Vessel Tubesheet-to-Shell Welds HSS Class 2 Vessel Nozzle-to-Shell Welds HSS Class2 Vessel Nozzle Inside Radius Section LSS Class 2 Vessel Welds 1970 12 4

4 8

4 23 Page 42 of 66 None Volumetric Volumetric Volumetric Surface and Volumetric Volumetric None

. \\... 8~1ie{8e'quest

Nurnb~r, Coae 9ase c)fRe9u1a.tory..

Re uirement Code Case N-716-1 Code Case N-716-1 Code Case N-716-1 Code Case N-716-1 Code Case N-716-1 Code Case N-716-1 Code Case N-716-1

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan 4.0 Development of the Class 2 Examination Plan Revision 0 September 30, 2021 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.

Refer to the ISi scheduling database (IDDEAL) 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. IWC-1220 of ASME Section XI, 2013 Edition lists the 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 Systems1 (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 (DN 100) and smaller.

(3)

Components2 and piping segments which have multiple inlets or multiple outlets, whose cumulative cross-sectional area does not exceed the cross-sectional area defined by the OD of NPS 4 (ON 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 (ON 40) and smaller.

(3)

Components2 and piping segments which have multiple inlets or multiple outlets, whose cumulative cross-sectional area does not exceed the cross-sectional area defined by the OD of NPS 4 (ON 40) pipe.

Page 43 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 (c)

Vessels, piping, pumps, valves, other components, and component connections of any size in statically pressurized, passive (i.e., no pumps) safety injection systems3 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.

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

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

3Statically 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 Accumulator Tank Sl-TK-9C & piping to Valves V36, V31, V37 Containment Spray from Valve V-11 to spray headers inside containment Containment Spray from Valve V-17 to spray headers inside containment

,.Exemption

Criteria IWC-1221 (c)

IWC-1221 (d)

IWC-1221 (d) 4.1.2 IWC-1222, Components within Systems or Portions of Systems Other Than RHR, ECC, and CHR Systems1 (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.

(3)

Components2 and piping segments which have multiple inlets or multiple 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:

Page 44 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 (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.

(3)

Components2 and piping segments which have multiple inlets or multiple 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.

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

2For 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.

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 ASME Section XI, 2013 Edition. The Summary Table for the major components at Seabrook Station are located in the ISi scheduling database (IDDEAL). The ISi scheduling database (IDDEAL) satisfies the requirements of IWA-2420(b)(1) through (6), respectively.

The Class 2 system boundaries are identified on the site P&ID drawings. Specific examinations are in accordance with the ASME B&PV Code,Section XI, Table IWC-2500-1, as further described below.

Page 45 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 4.3 Category C-A, Pressure Retaining Welds in Pressure Vessels These welds will be examined under the RIS_B Program in accordance with Code Case N-716-1.

4.4 Category C-8, Pressure Retaining Nozzle Welds in Pressure Vessels These welds will be examined under the RIS_B Program in accordance with Code Case N-716-1.

4.5 Category C-C, Welded Attachments for Pressure 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 Pressure Vessels, Piping, Pumps, and Valves". Refer to the table below for the applicable Relief Requests, Code Cases and Regulatory Requirements.

C3.10 C3.20 Pressure Vessel Welded Attachments 1 *2 Piping Welded Attachments 1 *3 2

25 Surface Surface

Reli~f ~eque~t

.Num.b~r1 Cod.e. Case or ~(i)gulat~ry Re ufrement There are no Item Number C3.30 or C3.40 parts at Seabrook Station Unit 1.

1Table IWC-2500-1, C-C, Note (5), Examinations are required whenever component support member deformation, e.g., broken, bent, or pulled out parts, is identified during operation, refueling, maintenance, examination, or testing.

2Table IWC-2500-1, C-C, Note (6), For multiple vessels of similar design, function and service, only one of the welded attachments of only one of the multiple components requires examination.

For single vessels, only one welded attachment shall be selected for examination. The attachment selected for examination on one of the multiple vessels or the single vessel, as applicable, shall be an attachment under continuous load during normal system operation, or an attachment subject to a potential intermittent load (seismic, water hammer, etc.) during normal system operation if an attachment under continuous load does not exist.

3Table IWC-2500-1, C-C, Note (7), For piping, pumps, and valves, a sample of 10% of the welded attachments associated with the component supports selected for examination under IWF-2510 shall be examined.

Page 46 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 4.6 Category C-D - Pressure Retaining Bolting > 2" in Diameter Examination Category C-D is not applicable at Seabrook Station Unit 1.

4.7 Category C-F-1, Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping These components will be examined under the RIS_B Program in accordance with Code Case N-716-1.

4.8 Category C-F-2, Pressure Retaining Welds in Carbon or Low Alloy Steel Piping These components will be examined under the RIS_B Program in accordance with Code Case N-716-1.

4.9 Category C-H, All Pressure Retaining Components Table C-H provides the examination scope and schedule for Table IWC-2500-1, Examination Category C-H, "All Pressure Retaining Components." Refer to the table below for the applicable Relief Requests, Code Cases and Regulatory Requirements.

System leakage tests will be performed in accordance with the rules of Section XI as modified by IWA-511 O(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).

C7.10 Class 2 Pressure Retaining Parts2 Various Visual, VT-21

...** Re,HefR~qll~st.

Nµrnber;C()de Case

, qr~~gulatory Reuk~mel"lt Code Case N-805 1Table IWC-2500-1, C-H, Note (1 ), requires the VT-2 examination during the IWC-5220 System Leakage Test to be performed in accordance with IWA-5240.

2 Per IWA-5241(f), for insulated components in systems borated for the purpose of controlling reactivity, insulation shall be removed from pressure retaining bolted connections for VT-2 visual examination unless material requirements are met.

Page 47 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan 5.0 Development of the Class 3 Examination Plan Revision 0 September 30, 2021 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. Refer to the ISi scheduling database (IDDEAL) 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 UFSAR Section 3.2.2 and ASME Section XI, Table IWD-2500-1.

5.1 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 5.2 Class 3 Code Exemptions and Exclusions The following Class 3 exemption criteria are applicable. Paragraph IWD-1220 of ASME Section XI, 2013 Edition lists those piping segments and components exempt from examination.

5.2.1 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 (ON 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 (ON 100) pipe.

(d)

Components1 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 Page 48 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision O September 30, 2021 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.

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

The following Class 3 components are exempt from examination.

Spent Fuel Pool Cooling Components on PID-1-SF-F20482 5.2.2 IWD-5222 Boundaries IWD-1220(d)

(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 non-closed 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.

Page 49 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan 5.3 Component Examination Basis Revision O September 30, 2021 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 ASME Section XI, 2013 Edition. The Summary Table for the major components for Seabrook Station Unit 1 are located in the ISi scheduling database (IDDEAL). The ISi scheduling database satisfies 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.

5.4 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". Refer to the table below for the applicable Relief Requests, Code Cases and Regulatory Requirements.

Examinations required in accordance with Table IWD-2500-1:

01.10 01.20 Vessel Welded Attachments 1 *2*3 Piping Welded Attachments1*2.4 6

Visual, VT-1 107 Visual, VT-1 J~.eliet ~equ,est Nu111b~r *. C,<)cle Cas¢ or R~gulatorf Re

uirement The Seabrook Station Unit 1 design does not include Item Numbers 01.30 and 01.40 welded attachments.

1Table IW0-2500-1, 0-A, Note (4) Selected samples of welded attachments shall be examined each inspection interval.

2Table IW0-2500-1, 0-A, Note (5) Examination is required whenever component support member deformation, e.g., broken, bent, or pulled out parts, is identified during operation, refueling, maintenance, examination, or testing.

3Table IW0-2500-1, 0-A, Note (6), all welded attachments selected for examination shall be those most subject to corrosion, as determined by the Owner, such as the welded attachments of the Service Water or Emergency Service Water systems. For multiple vessels of similar design, function and service, the welded attachments of only one of the multiple vessels shall be selected for examination. For single vessels, only one welded attachment shall be selected for examination. The attachment selected for examination on one of the multiple vessels or the single vessel, as applicable, shall be an attachment under continuous load during normal system operation, or an attachment subject to a potential intermittent load Page 50 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 (seismic, water hammer, etc.) during normal system operation if an attachment under continuous load does not exist.

4Table WD-2500-1, D-A, Note (7), For piping, pumps, and valves, a sample of 10% of the welded attachments in systems the Owner has determined the welded attachments to be subject to corrosion, such as the Service Water or Emergency Service Water Systems, shall be selected for examination.

5.5 Category D-B, All Pressure Retaining Components Table D-8 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 the table below for the applicable Relief Requests, Code Cases and Regulatory Requirements.

02.10 Class 3 Pressure Retaining Parts1.2 Various Visual, VT-2 1Table IWD-2500-1, Category D-8 requires a System Leakage Test to be performed in accordance with IWD-5220 once each inspection period.

2 Per IWA-5241 (f), for insulated components in systems borated for the purpose of controlling reactivity, insulation shall be removed from pressure retaining bolted connections for VT-2 visual examination unless material requirements are met.

6.0 IWE Metal Containment Requirements The requirements for Code Class MC, Metal Containment components are found in the Seabrook Station Unit 1 Third Interval Containment Building Metal Containment lnservice Inspection Program Plan, 3rd lnterval-IWE-SBK-1-Program Plan, which is administered separately. This document establishes the administrative, managerial, and implementation control for the IWE Containment Inspection Program for the Third 10-year lnservice Inspection interval.

7.0 Development of Component Supports Examination Plan Plant controlled isometrics, P&IDs, component drawings, and plant walkdowns were used to develop the ISi isometrics and ISi drawings as well as the scope of examinations. During examinations, these documents will be used to locate and identify each component support.

Other plant-controlled drawings or documents will be used when additional information is required. Refer to the ISi scheduling database (IDDEAL) for a complete listing of component supports 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 UFSAR Section 3.2.2 and ASME Section XI, Table IWF-2500-1.

Page 51 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan 7.1 Code Exemptions for Supports Revision 0 September 30, 2021 The following Component Support exemption criteria are applicable. Paragraph IWF-1230 of ASME Section XI, 2013 Edition lists those component supports exempt from examination.

7.1.1 IWF-1230 Supports Exempt from Examination1 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.

1Examination and test requirements for snubbers can be found in the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code).

7.2 Support Examination Basis This section describes Examination Category F-A, Supports examination basis. The required percentage of examinations and any limitations are described. All other requirements are found in ASME Section XI, 2013 Edition. The Summary Tables for the major components for Seabrook Station 3 and 4 are located in the ISi scheduling database (IDDEAL). The ISi scheduling database satisfies the requirements of IWA-2420(b)(1) through (6), respectively. A discussion of F-A supports subject to examination and testing is described in detail in subsections 7.2.1, 7.2.2 and 7.3 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 and applicable Notes, as indicated below. The term "component support" includes supports for such items as vessels, pumps and valves and supports for piping. Note that piping supports are treated separately for selection purposes.

Component supports selected and examined are those supports for components that are required to be examined in accordance with the following:

(a)

IWB-2500, IWC-2500 and IWD-2500 "Examination and Inspection Requirements" and IWE-2500, Examination and Pressure Test Requirements" (1)

Piping supports are selected in accordance with the percentages and sampling requirements of Table IWF-2500-1 from the population of system piping not exempted per IWB-Page 52 of 66

Seabrook Station Unit 1 ISi Program Revision 0 September 30, 2021 Document No. 4th lnterval-ISl-SBK-1-Program Plan 1220, IWC-1220, IWD-1220 and IWE-1220, in accordance with IWF-2510, "Supports Selected for Examination."

(2)

Piping support examinations will be in accordance with Table IWF-2500-1, Examination Category F-A, and will include 25%

of Class 1 supports (Item No. F1.10), 15% of Class 2 supports (Item No. F1.20), and 10% of Class 3 supports (Item No.

F1.30) on non-exempt piping.

(3)

Examinations will also include selection of Class 1, 2, 3, and MC component supports other than piping supports, Item No.

1.40, Supports other than Piping Supports. The examinations are limited to supports of non-exempt components per IWB-1220, IWC-1220, IWD-1220, and IWE-1220 in accordance with IWF-2510, "Supports Selected for Examination".

(4)

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. Note that support type and function is captured by the Item No. suffix described in 7.2.2 below.

(5)

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.

(6)

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 by component support function in the Fourth Ten-Year Interval lnservice Inspection Program Plan and lnservice Inspection Schedule. The support type is included as a suffix to the Item No., for example.

F1.1 OA, F1.1 OB and F1.1 OC) and is defined as follows:

A - Class 1 Deadweight hangers and one-directional restraints B - Class 1 Restraints (multi-directional)

F1.10 Class 1 327 Visual, VT-3 F1.20 Class 2 908 Visual, VT-3 Page 53 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan F1.30 Class 3 F1.40 Supports Other Than Piping Supports 7.3 Snubbers 409 53 Revision 0 September 30, 2021 Visual, VT-3 Visual, VT-3 Snubbers are functionally tested under the Snubber Program, which is administered separately. Visual, VT-3, examinations are performed on snubbers (pin-to-pin) as required by the OM Code, Subsection ISTD. Snubber attachment hardware (pin-to-pipe and pin-to-structure) is examined under the ISi Program per ASME Section XI, Subsection IWF. If welded attachments are present, they will be examined under the Class 1, 2, 3, F-A Examination Category, as applicable.

8.0 IWL Concrete Containment Requirements The requirements for Code Class CC, Concrete Containment, are found in the Seabrook Station Unit 1 Concrete Containment lnservice Inspection Program, 13-ISl/IWL-SBK-1 which is administered l separately and establishes the administrative, managerial, and implementation control for the IWL Containment Inspection Program Plan.

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 Seabrook Station Unit 1 lnservice Inspection Program Plan Basis for Augmented Examination of additional components and systems.

Page 54 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan 9.1 Class 1 Components 9.1.1 Reactor Coolant Pump Flywheels Revision 0 September 30, 2021 The Seabrook Reactor Coolant Pump Flywheels will be examined in accordance with Seabrook Technical Specification 6.7.6.m, which requires the following examinations:

Each reactor coolant pump flywheel shall be inspected at least once every 20 years. This inspection shall be by either of the following examinations:

a) An in-place examination, utilizing ultrasonic testing, over the volume from the inner bore of the flywheel to the circle of one-half the outer radius; or b) A surface examination, utilizing magnetic particle testing and/or penetrant testing, of the exposed surfaces of the disassembled flywheel.

Schedule identifier - Category "AUG", Item "RG 1.14" 9.1.2 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 The augmented examination of reactor coolant pressure boundary components fabricated with Alloy 600/82/182 in accordance with Code Case N-722-1 is mandated by 1 OCFR50.55a(g)(6)(ii)(E) and includes the following Seabrook Station items: RPV Bottom-Mounted Instrumentation (BMI) penetrations and Steam Generator Bottom channel head drain tube penetration. Note that Visual examinations of the RV Hot Leg Nozzle-to-Pipe Connections and RV Cold Leg Nozzle-to-Pipe Connections are no longer required because these joints have been mitigated by stress improvement (MSIP). The required inspections are limited to periodic visual examinations (VE). The required examination for the Bottom-Mounted Instrumentation is every other outage and every outage per Westinghouse recommendation for the Steam Generator bottom channel drains.

Schedule Identifier: Category "AUG, Item B15.80 Schedule Identifier: Category "AUG", Item B15.120 9.1.3 Code Case N-729-6 -Alternative Examination Requirements for PWR Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration Welds,Section XI, Division 1 The augmented examination of the Reactor Vessel Upper Head Nozzles Penetrations in accordance with Code Case N-729-6 is mandated by 1 OCFR50.55a (g)(6)(ii)(D) and includes bare metal visual (BMV) examinations of the Reactor Vessel Head; a volumetric examination (UT) and where applicable, and an eddy current examination (ET) may be used. If a surface examination is being substituted for a volumetric examination on a portion of Page 55 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 a penetration nozzle that is below the toe of the J-groove weld the surface examination shall be on the penetration nozzle inside and outside wetted surface.

Scheduler Identifier: Category "AUG". Item B4.10 Scheduler Identifier: Category "AUG". Item B4.20 9.1.4 Code Case N-770 Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Butt Welds Fabricated with UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities The augmented examination of Class 1 piping and nozzle dissimilar-metal butt welds in accordance with Code Case N-770-5 is mandated by 1 OCFR50.55a(g)(6)(ii)(F) and include the pressurizer nozzle-to-safe end butt welds for the Surge, Safety A, Safety B, Safety C, Relief, and Spray nozzles which were mitigated with a full structural weld overlay (SWOL) applied in Spring 2008 that includes Alloy 52, a PWSCC resistant material, and are thereby classified and volumetrically examined in accordance with Code Case N-770-5 as Inspection Item C-1. Also included are the Reactor Vessel Cold Leg Inlet and Hot Leg Outlet nozzle-to-safe end welds classified as Inspection Items D and E, based on the criteria of Code Case N-770-5, which require volumetric examinations. The "D" hot leg safe-end to nozzle weld was mitigated by stress improvement in 2009 after a flaw was identified and the remaining safe-end to nozzle welds were mitigated by stress improvement during OR17, Fall 2015.

Scheduler Identifier: Category "AUG", Item C-1 Scheduler Identifier: Category "AUG", Item D Scheduler Identifier: Category "AUG", Item E 9.1.5 Westinghouse Technical Bulletin TB-07-02 Rev. 2, TB-07-02 Rev. 3, NSAL 18-1 with EPRI Letter 2018-027 and NSAL 20-1

1. Westinghouse Technical Bulletin TB-07-02 Rev. 3 Westinghouse issued this Technical Bulletin for those nuclear plants with original closure heads. The Bulletin reads: "Plants that have not replaced the RV head and have upper head cross-flow velocities that are judged conducive to OD and ID thermal sleeve wear should, as identified in Table 1 (susceptible to ID and OD thermal sleeve wear), visually inspect the sleeved penetrations in the two outermost concentric rows of penetrations at their next refueling outage.

If no wear is observed, subsequent inspection may be performed in conjunction with other NRC head inspection requirements". Seabrook implementation is as follows:

Seabrook performed these examinations during Spring 2014 (OR 16 -

Work Order 40105740 and results summarized in AR1958085). All 32 of the thermal sleeves visually examined showed signs of wear on the Page 56 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 thermal sleeve OD where the sleeve exits the penetration. This inspection showed that SBK is experiencing the flow induced vibration that can lead to thermal sleeve wear (wall thinning) and potentially thermal sleeve flange wear. This completed the first portion of the examination requirement of the Technical Bulletin.

Due to the observed wear identified during OR16, the scope from TB 2 Rev 3 was included in the CC N-729-4 RPV under head ultrasonic examination.

A visual examination and wear measurement were performed for the ID/OD RPV head thermal sleeve during the Spring 2020 OR20 refueling outage.

Where OD and ID wear was observed, the thermal sleeve with the worst wear was ultrasonically measured to determine the wear scar. The most significant wear was located at the center penetrations 1-9.

The next recommended examination is scheduled for Spring 2024 (OR25) and tracked per AR02353824.

2. Nuclear Safety Advisory Letter NSAL 18-1 On May 24, 2018, Westinghouse reported of a potential defect per 1 OCFR Part 21 (EN 53422, Adams Accession No. ML18143B678 and Seabrook's documentation of the potential defect, AR02265706) associated with thermal sleeve wear. Operating experience (OE) has shown that wear of the thermal sleeve in the control rod drive mechanism (CROM) penetration tube could result a severed thermal sleeve flange and a stuck control rod. Subsequently, Westinghouse issued a Nuclear Safety Advisory Letter NSAL 18-1 which provides inspection recommendation to detect thermal sleeve flange wear prior to failure, based on plant design and age of the RV head.

NSAL 18-1 was issued to provide timely inspection recommendations to identify thermal sleeve flange wear prior to flange separation based on reactor design (T-Hot Heads and T-Cold Heads) and operating time (EFPY) for the installed RV head. The NSAL 18-1 classified Seabrook in the higher susceptibility Table I list of plants (T-Cold RV heads) for RV head thermal sleeve flange wear. The higher susceptibility is due to high core bypass flow to the RV upper head for T-Cold RV heads, which results in higher flow induced vibration and greater thermal sleeve flange wear.

The Westinghouse Technical Bulletin also required Seabrook "To check for upper flange wear, plants indicated with partial-length CROM thermal sleeves in Table 1 (Seabrook) should perform measurements of the vertical location of the thermal sleeve guide funnels during their next outage after 25 effective-full-power years (EFPY) or prior to (and including) the outage season of spring 2017 (whichever occurs second).

At the fall 2018 RFO (OR19), Seabrook will have 24.49 EFPY on the installed RV head. The NSAL states that no action is needed until the plant has exceeded 25 EFPY on the installed head. However, EPRI Letter 2018-027 upgraded the NSAL 18-1 requirement to a NEI 03-08 "Needed Recommendations" and changed the NSAL initial inspection recommendations timing from 25 EFPY to 20 EFPY.

Page 57 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021

3. SEA AR2272677-01 Fall 2018 OR19 NEI 03-08 "Needed Recommendations":

NSAL 18-1:

Recommendation 1.a) Prior to performing measurements of flange wear, plants should establish measurement acceptance criteria to prevent thermal sleeve flange separation. The acceptance criteria established in PWROG-16003-P can be used for assessing the wear condition. These criteria were developed based on the thermal sleeve flange separation and was not considered a safety significant event. As such, the criteria were developed to prevent separation during normal/upset operation conditions and did not consider faulted conditions. However, a preliminary evaluation shows that load increases associated with faulted conditions can likely be offset by reductions in analysis conservatisms such that these criteria will remain applicable upon inclusion of faulted loads.

PWROG-16003-P will be updated to include faulted conditions in the acceptance criteria.

Recommendation 2.a) During OR19 (Fall 2018) perform measurements of the lowering of all thermal sleeves using the methods such as laser scanning to resolve small elevation differences.

This will establish a baseline for the plant which can be used to assess the current condition of the thermal sleeves and to determine plant-specific wear rates which can be used in establishing the frequency of conducting subsequent measurements.

Seabrook performed laser measurements of the potential thermal sleeve drop during the OR19 Fall 2018 refueling outage. Wear was identified on the CRDMs closest to the center of the reactor vessel closure head (RVCH) at penetrations 7, 8, 15, 5 and 6. The highest measured wear is 0.595-inches at penetration 7. There is a total of 5 (five) penetrations exceeding 0.500-inches of wear. AR02273689 was written to track the laser measurement examinations, evaluate and track frequency. The next examination is scheduled for OR21 (Fall 2021).

The as-built measurements and nominal values are located in FP52819, FP52820 and FP56128.

Recommendation 3.a) In the event of a plant shutdown between refueling outages, without head removal and prior to the first measurement of thermal sleeve flange wear, perform rod exercises to ensure that the rods move freely in and out of the core prior to restart. For example, the standard Technical Specifications require exercising each individual control rod by moving each control rod ten steps in either direction.

Page 58 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021

4. SEA AR02345224 Fall 2021 OR21 NSAL 20-1 Recommendation:

August 14, 2020, Westinghouse issued NSAL-20-1, "Reactor Head Control Rod Drive Mechanism Penetration Thermal Sleeve Cross-sectional Failure." Seabrook is susceptible to this failure when combined with the thermal sleeve wear discussed in NSAL-18-1.

Due to the observed wear measurements during the Fall 2018 (OR19) laser measurements, NSAL-20-1 recommends performing a visual examination similar to a VT-3 one-cycle before reaching the 0,80-inch flange lowering criterion. Seabrook will perform a visual examination during the Fall 2021 (OR21) refueling outage as well as performing laser measurements to identify changes in the results from OR 19. Reference (AR02303559 - WO 40652959 and AR02349520 -WO 40711403)

Scheduler Identifier: Category "AUG", Item TB-07-2 Scheduler Identifier: Category "AUG", Item NSAL-18-1 Scheduler Identifier: Category "AUG", Item NSAL-20-1 9.1.6 MRP-146 - Management of Thermal Fatigue in Normally Stagnant Non-lsolable RCS Branch Lines This report provides needed guidelines and other good practice recommendations for evaluation 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.

Scheduler Identifier: Category "MRP-146", Item MRP-146 9.1. 7 WCAP-16913-P - Operability Assessment and Plant Applicability Evaluation for Pressurizer Heater Sleeve Leakage in Westinghouse Designed Pressurizers This report provides "needed" requirements necessary to address the potential for primary coolant leakage from pressurizer heater sleeves as the result of circumferentially oriented stress corrosion cracking, which could result in heater sleeve ejection if not detected before the cracks reach the critical flaw size. Each PWR with stainless steel heater sleeves is required to conduct a visual inspection (VT-2 in accordance with IWA-2212 of Section XI of the ASME Code) of the visible, without removal of insulation, portion of all heater sleeves and adjacent and nearby insulation for evidence of primary coolant leakage of all heater sleeves each refueling outage after January 1, 2010. Per the implementation protocol of the NEI 03-08 initiative, these guidelines are "needed" actions for PWR licensees.

Scheduler Identifier: Category "AUG", Item WC16913P Page 59 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan 9.2 Class 2 Components 9.2.1 NRC Bulletin 79-13 and Information Notice 93-20 Revision 0 September 30, 2021 Augmented Feedwater Examinations, as a result of a continuation of NRC Bulletin 79-13, and NRC Information Notice 93-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators. Seabrook will perform a continuous ultrasonic examination starting at the Feedwater Nozzle ramp and extending out to a point of 6 inches on the elbow. This examination is required on one steam generator nozzle ramp area every refueling outage. Examinations will be performed in conjunction with the Code examination schedule.

Scheduler Identifier: Category "AUG", Item IE79-13 9.2.2 Assessment of RHR Mixing Tee Thermal Fatigue in PWR Plants

[MRP-192]

This report provides "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 "good practice" actions for PWR licensees.

On May 28, 2015, MRP 2015-019 was published requesting expansion of the examination volume requirement. Due to possible under low branch flow conditions, cracking could initiate at upstream piping welds. Based on these observations, the recommended examination volume is being expanded to include areas of observed and potential cracking in the two upstream welds.

(AR 02051823).

Seabrook will examine the welds on a 10-year frequency. The next examination is scheduled for Spring 2025 (OR25).

Scheduler Identifier: Category "AUG", Item M RP-192 9.2.3 Risk Informed BER Piping (RI-BER)

For main steam and feedwater piping penetrating containment, no breaks were postulated between the first pipe whip restraint inside the containment and the five-degree restraint outside containment. To protect against postulated piping failures, this piping is subject to augmented inservice inspection as defined in the Risk-Informed ISi Break Exclusion Region (BER) evaluation, EE-07-035. This is a separate program from the Risk Informed ISi Program. This requirement is identified in the USFAR 6.6.8.

Seabrook has 42 welds selected in the High Energy line break exclusion category to be examined within the 10-yr inservice inspection interval. It should be noted that Risk-Informed Break Exclusion Region (RI-BER) application is not subsumed by the RIS_B application. Even though both Page 60 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 programs address the performance of risk-informed examinations on high energy piping, there are distinct differences such as the 4" NPS size cut-off in the RIS_B application. Therefore, the RI-BER application shall remain in effect, although the RI-BER and RIS_B applications may be performed concurrently.

Scheduler Identifier: Category "AUG", Item RI-BER 10.0 Evaluation/Acceptance Criteria NextEra Energy will perform non-destructive examinations using visual, surface (Penetrant and Magnetic Particle), and volumetric (Ultrasonic, Radiography, and Eddy Current) techniques. Other NOE techniques may be utilized when required.

During inservice inspections, NOE 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 Articles IWA-3000, IWB-3000, IWC-3000, IWD-3000 and IWF-3000, as applicable.

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.

10.3 Successive Examination for Components Where components are accepted for continued service by analytical evaluation, IWB-2420(b), IWC-2420(b), IWD-2420(b) and 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. Alternatively, Page 61 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 acoustic em1ss1on may be used to monitor growth of existing flaws in accordance with IWA-2234. For vessel welds, the three successive inspections are not required if the conditions in IWB-2420(b)(1) and (2) are met.

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. Alternatively, acoustic emission may be used to monitor growth of existing flaws in accordance with IWA-2234. For vessel welds, the successive inspection is not required the conditions in IWC-2420(b)(1) and (2) are met.

10.3.3 Class 3 Components (IWD-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 IWD-2400. If the flaws or relevant conditions remain essentially unchanged or the flaw growth is within the growth predicted by the analytical evaluation, for the next inspection period, then the component examination schedule may revert to the original schedule of successive inspections or the inspection interval defined by the analytical evaluation, whichever is limiting.

10.3.4 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 ASME Section XI, 2013 Edition and the Repair and Replacement Program for Seabrook Station Unit 1 shall be met for Class 1, 2, 3, MC components and their supports and Class CC components. MA 6.2, "ASME Section XI Repair/Replacement Program" details specific requirements for the repair, replacement, or modification of ISi components and component supports.

Page 62 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan 12.0 Relief Requests Revision O September 30, 2021 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 1 OCFR50.55a. Relief requests will be reviewed for completeness, technical adequacy, and implementation. Reviewers may be the site ISi Coordinators, the ISi Specialist, NOE 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 (if unable to meet Code examination requirements).

12.2 The request for use of an alternative, hardship or impracticality 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 Boundary Classifications The code required boundaries for all Class 1, 2, and 3 systems are denoted on Piping and Instrument Diagrams (P&IDs). A Listing of the P&IDs is included in Appendix C.

14.0 Weld/Support Location Maps Weld/Support location maps indicating components, areas, weld locations, and other information pertinent to the performance of the inservice nondestructive examinations are controlled. A listing of weld/support location maps applicable to the scheduled components is included in Appendix D and E.

15.0 Addition of Welds, Components, and Components Supports The rules for selection and scheduling of examinations for new welds and other items shall be in accordance with subparagraphs IWB-2411 (b), IWC-2411 (b), IWD-2411 (b). The rules for selection and scheduling of examinations for new component supports shall be in accordance with subparagraph IWF-2410(c).

16.0 Ultrasonic Calibration Blocks Ultrasonic calibration blocks for each component subject to volumetric examination are maintained at the plant site. The exception to this requirement would be blocks created for special configur9tions or alternative blocks allowed by Appendix VIII for calibration. These blocks may be used between sites, as applicable. Blocks from other sources may be used, if qualified. A listing of applicable ultrasonic calibration blocks is included in Appendix E.

Page 63 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan 17.0 Records 17.1 General Revision 0 September 30, 2021 Records of lnservice 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 or the alternative requirements in Code Case N-532-5.

17.2 Nondestructive Examinations Completed NOE examination data packages shall be submitted to the ISi Specialist following completion of the inservice examination activity.

17.3 Final Reports 17.3.1 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 systems (c)

Snubber examinations and tests (d)

System pressure tests (e)

Eddy current examinations (f)

Repairs and replacements 17.3.2 The final reports shall contain, as a minimum, the information required in the NIS-1 or OAR-1 (per Code Case N-532-5 as accepted in NRG Reg. Guide 1.147).

17.4 lnservice Inspection Summary Report NextEra Energy shall forward a summary report, Forms 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, which is accepted in NRG Reg. Guide 1.147, as applicable.

17.5 NIS-2 or NIS-2A Reports NIS-2 Forms or an NIS-2A Form per Code Case N-532-5 will be completed for each repair or replacement activity.

Page 64 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan 18.0 References Revision O September 30, 2021 The lnservice Inspection Program Plan for Class 1, 2, and 3 components and component supports were 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.

18.1 United States Code of Federal Regulations, Title 10, Part 50, Section 55a, (1 OCFR50.55a), Codes and Standards, published January 1, 2020, as modified by Final Rules dated March 16, 2020 [85 FR 14756] and May 4, 2020, [85 FR 26576],

June 3, 2020 [85 FR34088] and October 16, 2020 [85 FR 65662].

18.2 American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Division 1, 2013 Edition.

18.3 American Society of Mechanical Engineers (ASME)Section XI Code, 2010 Edition.

18.4 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.

18.5 USNRC Regulatory Guide 1.147, lnservice Inspection Code Case Acceptability ASME Section XI, Revision 19.

18.6 USNRC Regulatory Guide 1.178 - An Approach for Plant-Specific Risk Informed Decision Making lnservice Inspection of Piping.

18.7 USNRC Regulatory Guide 1.193 - ASME Code Cases Not Approved for Use, Revision 6.

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

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

18.10 Nondestructive Evaluation: Performance Demonstration Initiative (PDI) Comparison to ASME Section XI, Appendix VIII 2013 Edition and 10CFR50.55a, Year 2017.

EPRI, Palo Alto, CA 2012 1026510.

18.11 Seabrook Station Updated Final Safety Analysis Report, Revision 19.

18.12 Seabrook Station Technical Specifications, December 2019.

18.13 Safety Evaluation Report Related to the License Renewal of Seabrook Station, review of information through July 2018.

18.14 Generic Aging Lessons Learned (GALL) Report.

18.15 Seabrook Station Document - MA 6.1, "Implementation Procedure for lnservice Inspection of Class 1, 2, and 3 Components and Primary Containment Structures".

Page 65 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 18.16 Seabrook Station Document -

MA 6.2, "ASME Section XI Repair/Replacement Program."

18.17 NextEra Energy Nuclear Fleet Procedure -

EN-AA-106, "Renewed License Program".

18.18 MRP-146, "Materials Reliability Program: Management of Thermal Fatigue in Normally Stagnant Non-lsolable Reactor Coolant System Branch Lines (MRP-146, Revision 2)", EPRI, Palo Alto, CA: 2016. 3002007853.

18.19 Nuclear Energy Institute NEI 04-05, "Living Program Guidance to Maintain Risk-Informed lnservice Inspection Programs for Nuclear Plant Piping Systems", April 2004.

18.20 Nuclear Energy Institute NEI 03-08, Guideline for the Management of Materials Issues", Revision 3, dated February 2017.

18.21 MRP-192- "Materials Reliability Program: Assessment of RHR Mixing Tee Thermal Fatigue in PWR Plants (MRP-192, Revision 3)", EPRI, Palo Alto, CA: 2018.

3002013266.

18.22 WCAP-16913-P, Revision 1 "Operability Assessment 'and Plant Applicability Evaluation for Pressurizer Heater Sleeve Leakage in Westinghouse Designed Pressurizers" April 2009, PA-MSC-0316.

18.23 Seabrook Station Document 3rd lnterval-IWE-SBK-1-Program Plan, "Seabrook Station Unit 1 Third IWE Inspection Interval Program Plan."

18.24 Seabrook Station Document 3rd lnterval-IWL-SEA-Prog Plan, "Seabrook Unit 1 Third Interval Containment Concrete IWL Program".

18.25 NextEra Energy Nuclear Fleet Procedure - ER-AA-118, "ASME Section XI lnservice Inspection Program".

18.26 NSAL-18-1 Revision 0, "Thermal Sleeve Flange Wear Leads to Stuck Control Rod" 18.27 TB-07-2, Revision 3, "Reactor Vessel Head Adapter Thermal Sleeve Wear

18.28 EPRI Topical Report TR-112657, "Revised Risk-Informed lnservice Inspection Evaluation Procedure", Revision 8-A, December 1999 18.29 ASME Code Case N-716, "Alternative Piping Classification and Examination Requirements,Section XI, Division 1", Approval Date: April 19, 2006 18.30 ASME Code Case N-716-1, "Alternative Classification and Examination Requirements,Section XI, Division 1", Approval Date: January 27, 2013 Page 66 of 66

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Appendix A Seabrook S.tation Unit 1

. Relief.Requests Relief Request Description Number 41R-01 Examination Category F-A, Pressurizer Seismic Supports 41R-02 Code Case N-729-6 Relief From Ultrasonic Examination Distances on Five Penetrations (74, 75, 76, 77, and 78) 41R-03 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds Page A1 of A4 Revision O September 30, 2021 Status In the Course of Development In the Course of Development In the Course of Development

Seabrook Station Unit 1 ISi Program Document No. 4th I nterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 Relief Request No. 41R-01 Examination Category F-A, Pressurizer Seismic Supports (Reserved for Future Incorporation)

Page A2 of A4

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 Relief Request No. 41R-02 Code Case N-729-6 Relief from Ultrasonic

/

Examination Distances on Five Penetrations (74, 75, 76, 77, and 78)

(Reserved for Future Incorporation)

Page A3 of A4

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Revision 0 September 30, 2021 Relief Request No. 41R-03 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques In Lieu of Radiography for Ferritic and Austenitic Welds (Reserved for Future Incorporation)

Page A4 of A4

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-S8K-1-Program Plan Appendix B Risk Informed 1st Period Update (Reserved for Future Incorporation) 81 of 81 Revision 0 September 30, 2021

Seabrook Station Unit 1 ISi Program Revision 0 September 30, 2021 Document No. 4th lnterval-ISl-SBK-1-Program Plan Appendix C Seabroo.k Station Boundary Classification Drawings P & ID Number P & ID Title 1-MS-D20581 Main Steam System Main Steam Headers 1-MS-D20582 Main Steam System Emergency Feedwater Pump Supply 1-MS-D20583 Main Steam System Manifold & H.P. Turbine Piping 1-MS-D20587 Main Steam System Main Steam Drains 1-NG-D20135 Nitrogen Gas 1 NG D20136 Nitrogen Gas 1-RC-D20841 Reactor Coolant System Loop No. 1 1-RC-D20842 Reactor Coolant System Loop No. 2 1-RC-D20843 Reactor Coolant System Loop No. 3 1-RC-D20844 Reactor Coolant System Loop No. 4 1-RC-D20845 Reactor Coolant System Reactor Vessel 1-RC-D20846 Reactor Coolant System Pressurizer 1-RH-D20662 Residual Heat Removal System Train A 1-RH-D20663 Residual Heat Removal System Train B Cross-Tie 1-RMW-D20360 Reactor Make Up Water System 1-SA-D20652 Service Air System Misc. Buildings 1-SB-D20626 Steam Generator Slowdown 1-SF-D20482 Spent Fuel Pool Cooling and Clean-Up System 1-SF-D20484 Spent Fuel Pool Cooling and Clean-Up System 1-Sl-D20446 Safety Injection System Intermediate Head Injection System 1-Sl-D20447 Safety Injection System High Head Injection System 1-Sl-D20450 Safety Injection System Low Head Injection (Accumulators) Detail 1-SS-D20518 Sample System Nuclear Normal Operation 1-SS-D20519 Sample System Nuclear Sample Panel CP-166A 1-SS-D20520 Sample System Nuclear-Post Accident 1-SW-D20794 Service Water System Nuclear 1-SW-D20795 Service Water System Nuclear Page C1 of C2

Seabrook Station Unit 1 ISi Program Revision 0 September 30, 2021 Document No. 4th lnterval-ISl-SBK-1-Program Plan Appendix C Seabrook Station Boundary Classification Drawings P &.ID Number P & ID Title 1-SW-D20796 Service Water System Nuclear 1-VG-D20780 Vent Gas System 1-WLD-D20218 Waste Processing Liquid Drains Reactor Coolant System 1-WLD-D20219 Waste Processing Liquid Drains Containment Building Sumps 1-WLD-D20221 Waste Processing Liquid Drains RHR Equipment Valves 1 & 2 1-WLD-D20222 Waste Processing Liquid Drains Primary Auxiliary Bldg.

Page C2 of C2

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan AppendixD Seabrook Station Isometric and Component Drawings Drawing Number Drawing Title 1-NHY-2022991SI Main Steam Atmospheric Relief Piping 1-NHY-2023001SI Main Steam Atmospheric Relief Piping 1-NHY-202301 ISi Main Steam Line No. 4000 1-NHY-2023021SI Main Steam Line No. 4001 1-NHY-2023031SI Main Steam Line No. 4002 1-NHY-2023041SI Main Steam Line No. 4003 1-NHY-2023961SI Feedwater Line No. 4606 1-NHY-2023971SI Feedwater Line No. 4607 1-NHY-2023981SI Feedwater Line No. 4608 1-NHY-2023991SI Feedwater Line No. 4609 1-NHY-2024451SI Main Steam Safety Valve Discharge 1-NHY-650000 Excess Letdown Heat Exchanger CS-E-3 1-NHY-650004 Reactor Coolant Pumps RC-P-1A-D 1-NHY-6500051SI Reactor Coolant Pump Flywheel 1-NHY-6500061SI Pressurizer RC-E-10 1-NHY-6500071SI Reactor Vessel RC-E-1 1-NHY-6500081SI Reactor Vessel RC-E-1 1-NHY-650009 Reactor Vessel RC-E-1 1-NHY-650010 Reactor Vessel RC-E-1 1-NHY-650011 ISi Steam Generator RC-E-11A (typ.)

1-NHY-6500121SI Steam Generator RC-E-11A & 11 B 1-NHY-6500131SI Steam Generator RC-E-11 C & 11 D 650104-ISI Reactor CROM Weldment Platform 1-NHY-8000131SI RC System Line No. 13 1-NHY-8000151SI RC System Line No. 15 1-NHY-8000181SI RC System Line No. 18 1-NHY-800021 ISi RC System Line No. 21 1-NHY-8000301SI RC System Line No. 30 1-NHY-8000331SI RC System Line No. 33 1-NHY-8000441SI RC System Line No. 44 Page 01 of 05 Revision 0 September 30, 2021

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Appendix D Seabrook Station Isometric an.d Component Drawings Drawing Number Drawing Title 1-NHY-8000451SI RC System Line No. 45 1-NHY-8000481SI RC System Line No. 48 1-NHY-8000491SI RC System Line No. 49 1-NHY-8000581SI RC System Line No. 58 1-NHY-8000591SI RC System Line No. 59 1-NHY-8000621SI RC System Line No. 62 1-NHY-8000741SI RC System Line No. 7 4 1-NHY-8000751SI RC System Line No. 75 1-NHY-8000761SI RC System Line No. 76 1-NHY-8000801SI RC System Line No. 80 1-NHY-8000931SI RC System Line No. 93 1-NHY-8000941SI RC System Line No. 94 1-NHY-8000961SI RC System Line No. 96 1-NHY-8000971SI RC System Line No. 97 1-NHY-8000981SI RC System Line No. 98 1-NHY-800151 ISi RH System Line No. 151 1-NHY-8001521SI RH System Line No. 152 1-NHY-8001551SI RH System Line No. 155 1-NHY-8001571SI RH System Line No. 157 1-NHY-8001581SI RH System Line No. 158 1-NHY-8001591SI RH System Line No. 159 1-NHY-8001601SI RH System Line No. 160 1-NHY-800161 ISi RH System Line No. 161 1-NHY-8001621SI RH System Line No. 162 1-NHY-8001631SI RH System Line No. 163 1-NHY-8001671SI RH System Line No. 167 1-NHY-8001781SI RH System Line No. 178 1-NHY-8001791SI RH System Line No. 179 1-NHY-8001801SI RH System Line No. 180 1-NHY-800201 ISi SI System Line No. 201 Page 02 of 05 Revision 0 September 30, 2021

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan AppendixD Seabrook Station Isometric and Cornponent Drawings Drawing Number

,'~

Drawing Title 1-NHY-8002021SI SI System Line No. 202 1-NHY-8002031SI SI System Line No. 203 1-NHY-8002041SI SI System Line No. 204 1-NHY-8002501SI SI System Line No. 250 1-NHY-800251 ISi SI System Line No. 251 1-NHY-8002561SI SI System Line No. 256 1-NHY-8002571SI SI System Line No. 257 1-NHY-8002581SI SI System Line No. 258 1-NHY-8002591SI SI System Line No. 259 1-NHY-8002601SI SI System Line No. 260 1-NHY-800261 ISi SI System Line No. 261 1-NHY-8002701SI SI System Line No. 270 1-NHY-8002721SI SI System Line No. 272 1-NHY-8002731SI SI System Line No. 273 1-NHY-8002741SI SI System Line No. 274 1-NHY-8002751SI SI System Line No. 275 1-NHY-8003241SI CS System Line No. 324 1-NHY-8003251SI CS System Line No. 325 1-NHY-8003261SI CS System Line No. 326 1-NHY-8003271SI CS System Line No. 327 1-NHY-8003281SI CS System Line No. 328 1-NHY-8003291SI CS System Line No. 329 1-NHY-8003301SI CS System Line No. 330 1-NHY-800331 ISi CS System Line No. 331 1-NHY-8003551SI CS System Line No. 355 1-NHY-8003571SI CS System Line No. 357 1-NHY-8003581SI CS System Line No. 358 1-NHY-8003621SI CS System Line No. 362 1-NHY-8003631SI CS System Line No. 363 1-NHY-8003641SI CS System Line No. 364 1-NHY-8003651SI CS System Line No. 365 Page 03 of 05 Revision O September 30, 2021

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan AppendixD Seabrook Station Isometric and Component Drawings Drawing Number Drawing Title 1-NHY-8003661SI CS System Line No. 366 1-NHY-8003671SI CS System Line No. 367 1-NHY-8003681SI CS System Line No. 368 1-NHY-8003691SI CS System Line No. 369 1-NHY-8003701SI CS System Line No. 370 1-NHY-800371 ISi CS System Line No. 371 1-NHY-8003741SI CS System Line No. 374 1-NHY-8003751SI CS System Line No. 375 1-NHY-8003771SI CS System Line No. 377 1-NHY-8003531SI CS System Line No. 353 1-NHY-8004731SI CS System Line No. 473 1-NHY-801201 ISi CBS System Line No. 1201 1-NHY-8012021SI CBS System Line No. 1202 1-NHY-8012071SI CBS System Line No. 1207 1-NHY-8012081SI CBS System Line No. 1208 1-NHY-8012091SI CBS System Line No. 1209 1-NHY-8012101SI CBS System Line No. 1210 1-NHY-801211 ISi CBS System Line No. 1211 1-NHY-8012121SI CBS System Line No. 1212 1-NHY-8012131SI CBS System Line No. 1213 1-NHY-8012141SI CBS System Line No. 1214 1-NHY-8012151SI CBS System Line No. 1215 1-NHY-8012161SI CBS System Line No. 1216 1-NHY-8040001SI MS System Line No. 4000 1-NHY-804001 ISi MS System Line No. 4001 1-NHY-8040021SI MS System Line No. 4002 1-NHY-8040031SI MS System Line No. 4003 1-NHY-8046061SI FW System Line No. 4606 1-NHY-8046071SI FW System Line No. 4607 1-NHY-8046081SI FW System Line No. 4608 Page 04 of 05 Revision 0 September 30, 2021

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan Appendix D Seabrook Station Isometric and Component Drawings.

Drawing Number Drawing Title 1-NHY-804609181 FW System Line No. 4609 1-NHY-8055541SI Reactor Coolant Loop Weld ID 1-NHY-8055551SI Reactor Coolant Loop Weld Table 1-NHY-8600001SI RH Line No. 155 Weld Table 1-NHY-860001 ISi RH Line No. 158 Weld Table 1-NHY-8600021SI RH Line No. 48 Weld Table 1-NHY-8600031SI CS Line No. 369 Weld Table Page D5 of D5 Revision 0 September 30, 2021

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-S8K-1-Program Plan Appendix E Seabrook Station Unit 1 Ultrasonic Calibration Blocks Calibration Block ID Material Specification 06-02-02 1-RC-MM-427A SA-516 GR.70 1-RC-MM-4278 SA-533 GR. A 1-RC-MM-428A SA-533 GR. A 1-RC-MM-4288 SA-533 GR. 8 1-RC-MM-430A SA-508 196-101 SA-533 GR. 8 196-102 SA-533 GR. 8 196-103 SA-533 GR. 8 196-104 SA-533 GR. 8 196-201 SA-533 GR. 8 196-202 SA-508 196-206 SA-182 F-304 S8-1-C8S-HX SA-240 TP. 304 S8-1-RHR-HX SA-240 TP. 304 S8-10-140-SS SA-376 TP. 316 S8-10-40-SS SA-312 TP. 304 S8-10-80-CS SA-106 S8-10-XX1-CS-F SA-234 WP8 S8-12-140-SS SA-376 TP 316 S8-12-40-SS SA-312 TP 304 S8-14-160-SS SA-376 TP 304 S8-14-40-SS SA-358 TP 304 S8-16-100-CS SA-106 GR. 8 S8-16-STD-SS SA-358 TP 304 S8-18-100-CS SA-106 GR. 8 S8-18-XX1-CS SA-105 S8-3-160-SS SA-376 TP 316 Page E1 of E2 Revision O September 30, 2021 Block Description Pressurizer Head-to-Shell Weld Pressurizer Support Skirt Pressurizer Shell & Nozzle Steam Generator Steam Generator Steam Generator Primary Nozzle Reactor Pressure Vessel Reactor Pressure Vessel Reactor Pressure Vessel Reactor Pressure Vessel RPV Flange Ligament RPV Nozzle Safe End RPV CRD Mechanism Vessel Shell Vessel Shell Piping Class 1 & 2 Class 2 Thin Wall Piping Class 1 & 2 Piping Class 1 & 2 Piping Class 1 & 2 Class 2 Thin Wall Piping Class 1 & 2 Class 2 Thin Wall Piping Class 1 & 2 Class 2 Thin Wall Piping Class 1 & 2 Piping Class 1 & 2 Class 2 Thin Wall

Seabrook Station Unit 1 ISi Program Document No. 4th lnterval-ISl-SBK-1-Program Plan AppendixE Seabrook Station Unit 1 Ultrasonic Calibration Blocks Calibration Block ID Material Specification SB-3-40-SS SA-312 TP.304 SB-3-80-SS SA-312 TP.304 SB-30-XX1-CS SA-155 GR. KC70 SB-30-XX2-CS SA-106 GR.C SB-30-XX3-CS SA-105 SB-32-XX 1-CS SA-155 GR. KC70 SB-32-XX2-CS SA-155 GR. KC70 SB-4-160-SS SA-376 TP 316 SB-4-80-SS SA-312 TP 304 S B-6-160-SS SA-376 TP 316 SB-6-40-SS SA-312 TP 304 SB-6A-160-SS SB-8-160-SS SA-376 TP 316 SB-8-40-SS SA-312 TP 304 SB-IR-23-CS SA-508 CL 2 SB-IR-27-CS SA-508 CL 2 SB-IR-32-CS SA-508 CL 2 SB-RC-3 SA-182 F 304 SB-RC-4 SA-376 GR. 304 SB-RC-5 SA-351 GR.CF8A SB-RCP-BOL T SA-540 GR-B-24 SB-RV-STUD SA-540 GR-B-24 SE-IR-47-CS SA-508 CL 2 SB-PDl-304SS SB-PDl-316SS SB-PDl-516CS Page E2 of E2 Revision 0 September 30, 2021 Block Description Class 2 Thin Wall Class 2 Thin Wall Piping Class 1 & 2 Piping Class 1 & 2 Piping Class 1 & 2 Piping Class 1 & 2 Piping Class 1 & 2 Piping Class 1 & 2 Class 2 Thin Wall Piping Class 1 & 2 Class 2 Thin Wall Piping Class 1 & 2 Piping Class 1 & 2 Class 2 Thin Wall Pressurizer Spray Nozzles IR Pressurizer Safety Relief IR Pressurizer Surge Nozzle IR Piping Class 1 & 2 Piping Class 1 & 2 Piping Class 1 & 2 Reactor Coolant Pump Bolt Reactor Vessel Stud Steam Generator Feedwater IR Alternative ASME Block Alternative ASME Block Alternative ASME Block

SBK-L-21126, Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan

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SBK-L-21126, Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan

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