NOC-AE-21003806, Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval

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Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval
ML21144A109
Person / Time
Site: South Texas  
Issue date: 05/20/2021
From: Georgeson C
South Texas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
35168498, NOC-AE-21003806
Download: ML21144A109 (271)
v • d • e


Text

Nuclear Operating Company South Texas Profect Electric Generating Station P.O. Box 289 Wadsworth, Texas 77483 May 20, 2021 NOC-AE-21003806 STI:35168498 10CFR50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 South Texas Project Units 1 and 2 Docket Nos. STN 50-498 and STN 50-499 Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval Pursuant to 10 CFR 50.55a(f)(4)(ii), STP Nuclear Operating Company (STPNOC) submits the South Texas Project (STP) Inservice Testing (1ST) snubber program for the fourth 10-year interval applicable to safety related seismic restraints (Snubbers) as described in Technical Requirements Manual section 3/4.7.9. The 1ST snubber program plan describes the programmatic aspects of inservice testing implemented with the fourth 10-year interval, which began September 25, 2020. STPNOC submits the attached program description in accordance with section ISTA-3200 of the 2012 Edition of the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code.

The 1ST program has been developed in accordance with the requirements of the 2012 Edition of the ASME OM Code, Subsections ISTA and ISTD with the inspection requirements of Code Case OMN-13, revision 2. STP Units 1 and 2 will also comply with the limitations and modifications to these requirements stated in 10 CFR 50.55a(b) related to implementation of the 2012 ASME OM Code. This portion of the 1ST program for Safety Related Seismic Restraints (Snubbers) is within the provisions of the ASME OM Code, requiring no NRC approval for implementation, and is provided for information only.

Pursuant to 10 CFR 50.55a(g)(4)(ii), STPNOC submits the Inservice Inspection Program Plan for STP Units 1 and 2. The updated Inservice Inspection Program will be conducted in accordance with the requirements of the 2013 Edition ofASME Section Xl except for alternatives presented in approved code cases, and 10 CFR 50.55a modifications and limitations, as listed in the attached program plan. This update is applicable to the fourth 10-year inspection interval, which began September 25,2020.

There are no commitments in this letter.

If there are any questions regarding this matter, please contact me at (361) 972-7806 or N.

Boehmisch at (361) 972-8172

\^d-ia^-

hristopher G^orgeson General Manager, Engineering Attachments
1. Inservice Inspection Program Plan for STP Units 1 and 2
2. Inservice Testing Program for STP Units 1 and 2 Snubber Inservice Test Plan

NOC-AE-21003806 Page 2 of 2 ec:

Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 1600 E. Lamar Boulevard Arlington, TX 76011-4511

NOC-AE-21003806 Attachment 1 Attachment 1 Inservice Inspection Program Plan for STP Units 1 and 2

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 1 of 188 INSERVICE INSPECTION PROGRAM PLAN FOR THE SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION UNITS 1 AND 2 STP TEN-YEAR ISI PLAN For the Fourth ISI Ten-Year Interval September 25, 2020 to September 8, 2029 For the Fourth CISI Ten-Year Interval September 9, 2019 to September 8, 2029 STP NUCLEAR OPERATING COMPANY Effective Date: September 25, 2020

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 2 of 188 REVIEW AND CONCURRENCE SHEET Prepared by: [Electronic Approval / Signature: CR 20-986-2] 12/03/2020 Eric Lantz (ISI Program Owner) Date Reviewed by: [Electronic Approval / Signature: CR 20-986-2] 01/06/2021 James Williams (NDE Level III) Date

[Electronic Approval / Signature: CR 20-986-2] 12/15/2020 Jim Heil (Surveillance Program Engineer) Date

[Electronic Approval / Signature: CR 20-986-2] 12/10/2020 Kellie Harris (RRA and Pressure Testing Program Engineer) Date

[Electronic Approval / Signature: CR 20-986-2] 01/06/2021 Mark Wales (Concrete Containment Engineer) Date

[Electronic Approval / Signature: CR 20-986-2] 12/10/2020 Mike Garner (Steam Generator and RCS Materials Engineer) Date Supervisory [Electronic Approval / Signature: CR 20-986-2] 01/14/2021 Review:

Clayton Bonnot (Supervisor, Testing/Programs Engineering) Date

[Electronic Approval / Signature: CR 20-986-2] 01/18/2021 Management Michael Chandler - (Strategic Engineering Manager) Date Review:

[Signature Documented: CR 20-986-3] 01/18/2021 ANII Review:

Date

March 22, 2021 Safarali (Safar) R. Shojaei, Testing/Program Engineering CTC- Contract B07185 STP Nuclear Operating Company PO Box 2890 Wadsworth, Texas 77483

Subject:

ANII Review and Acceptance: In-Service Inspection Program Plan for South Texas Project Electric Generating Station Units 1 and 2. Revision #10, effective date 09/25/2020.

This In-service Inspection (ISI) Program Plan outlines the requirements for the Nondestructive Examination ofASME Class 1, 2, and 3 Component Supports, Class CC/MC Concrete Containment Metal Liner, Repair / Replacement Activities for Class 1, 2, and 3 components and their supports, Class 1 Steam Generator Tubing, System Pressure Testing for leakage of Class 1, 2, and 3 components, and examination of Class 1, 2, and 3 component welds.

  • Units 1 & 2 Fourth Inspection Interval, Sept.25, 2020 thru Sept.8, 2029.
  • Concrete Containment Inspection activities (IWL) for the 35th and 40th year examinations. (In-Service Inspection Program Plan Appendix E)
  • Containment Metal Liner Inspection activities, Units 1 & 2, Second Inspection Interval, Sept. 9, 2019 to Sept 8, 2029. (In-service Inspection Program Plan, Appendix C & D)
  • Fourth Inspection Interval, ASME Section Xl, Rules for In-service Inspection of Nuclear Power Plant Components Code, 2013 Edition. (In-service Inspection Program Plan, Appendix A & B).
  • ASME Appendix VIII, Section Xl 2013 Edition, a requirement of 10CFR50.55a. (In-service Inspection Program Plan, Appendix G)
  • Augmented In-service Inspections (NRC request) "Reactor Coolant Pump Flywheel",

UT examinations. "Break Exclusion Zone Piping and EPRI Risk-lnform In-service Inspection", (Appendix A & B) "Reactor Vessel Head Inspections", ASME Code Case N-729-1. "Class One Welds fabricated with Alloy 600/82/182 Material", Code Case N-722-1.

  • "Alloy 600" NDE of pressure boundary locations not specified in the Code or other augmented ISI programs (In-service Inspection Program Plan Appendix I).
  • "Interval Outage Schedules" Component Support, Repair/Replacement, Steam Generator Tubing, System Pressure Testing, Weld, and Containment Metal Liner for Units 1 & 2 (In-service Inspection Program Plan, Appendix K).

OneCIS Insurance Company A Bmwn Vcrilus Cumpuny Main: (800) 579-3444 330 Lynnway, Suite 403 Fax: (781)584-1119 Lynn, MA 01901 \^^v.us.bure'Auveritay.com

"Examination Volume Figures" Risk Informed ISI Examination Volume (In-service Inspection Program Plan, Appendix L).

ASME Sect Xl- IWA-2110 Duties of the Inspector This report is submitted in accordance with ASME Code Section Xl 2013 Edition no Addenda, (IWA 2110) and is to document the review and acceptance of the In-service Inspection Program Plan, Rev # 10, Unit's 1 & 2, for the Fourth Inspection Interval.

This report is submitted in accordance with ASME Section Xl, 2013, [IWA-2110 (c)] and is to document my review of items identified in [IWA-2110 (a) (1)].

The "In-Service Inspection (ISI) Program Plan", Rev. #10, meets the requirements ofASME Section Xl, (IWA-2420) "Inspection Plans and Schedules" and (IWA-2430), "Inspection Intervals".

Please note that any revision to the above referenced In-Service Inspection Program Plan must be reviewed by the ANtl, in accordance with ASME Section Xl, [IWA-2110 (b)].

Respectfully O^L^c Robert (Bob) Winegarden Authorized Nuclear Inservice Inspector One CIS Insurance Company 361-972-7493 Office 919-800-1092 Cell Co: R. Offringa - One CIS / ASME Nuclear Manager G. Brouette - One CIS / ANII Supervisor C. Bonnot - STPEGS - Engineering Supervisor J. Williams - STP - NDE Inspection Program Engineer E. Lantz - STP - ISI Program Engineer

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 3 of 188 REVISION STATUS SHEET REVISION ISSUE DATE DESCRIPTION 10 01/21/2021 STP Ten-Year ISI/CISI Program Plan meeting the requirements of the ASME Boiler and Pressure Vessel Code Section XI 2013 Edition for the Fourth Ten Year Interval. Formatted for consistency with Inservice Inspection Programs prepared by Iddeal Concepts, Inc.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 4 of 188 Table of Contents 1.0 ASME Section XI Inservice Inspection Program ............................................................ 7 1.1 Purpose .................................................................................................................. 7 1.2 Scope ..................................................................................................................... 7 1.3 General................................................................................................................. 10 1.4 Inspection Intervals.............................................................................................. 10 1.5 ASME Section XI Code of Record for the ISI Interval ....................................... 13 1.6 10 CFR 50.55a conditions applicable to STP ...................................................... 14 1.7 ASME Section XI ISI Program Description........................................................ 15 1.8 Use of ASME Section V ...................................................................................... 19 1.9 Piping and Instrumentation Diagrams ................................................................. 20 1.10 Interpretations of the ASME Section XI Code .................................................... 30 1.11 Records, Reports, and Submittals ........................................................................ 30 1.12 Responsibilities.................................................................................................... 32 1.13 Administrative Controls ...................................................................................... 33 2.0 ASME Code Case Applicability .................................................................................... 33 2.1 Adoption of Code Cases ...................................................................................... 34 2.2 Regulatory Guide 1.147, Revision 19 Approved Code Cases ............................. 38 2.3 Code Cases Adopted Via NRC Approved Requests ........................................... 40 2.4 Code Cases required by 10 CFR 50.55a .............................................................. 40 3.0 Relief Requests............................................................................................................... 43 3.1 Request for Alternatives ...................................................................................... 43 3.2 Relief Requests Required due to Impracticality or Limited Examinations ......... 43 4.0 References ................................................................................................................... 47 5.0 AUGMENTED EXAMINATIONS ............................................................................... 49 5.1 Augmented Examinations Required by 10 CFR 50.55a...................................... 49 5.2 Augmented Examinations for External Commitments ........................................ 58 5.3 Owner Elected Examinations for Internal Commitments.................................... 67 5.4 License Renewal Examinations for Aging Management Commitments............. 67 6.0 ASME Systems & Examination Boundaries.................................................................. 68 6.1 ASME Class 1, 2 and 3 ........................................................................................ 68 6.2 Classification and Identification of Components ................................................ 69 7.0 Application Criteria and Code Compliance ................................................................... 70 7.1 ASME Section XI ................................................................................................ 70 8.0 Inservice Inspection Data Management Software.......................................................... 80 9.0 Risk-Informed ISI Program............................................................................................ 81

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 5 of 188 Table of Contents (continued)

TABLES Table 1.1-1 STP CISI Interval Schedule 11 Table 1.1-2 STP ISI Interval Schedule 12 Table 1.1-3 STP IWL Period Schedule 12 Table 1.2-1 STP ISI Component Scheduling 13 Table 1.9-1 Piping and Instrumentation Diagrams 21 Table 2.2-1 Code Cases Adopted from Regulatory Guide 1.147 38 Table 2.3-1 Code Cases Adopted Via NRC Approved Requests 41 Table 2.4-1 Code Cases Required by 10 CFR 50.55a 41 Table 3.0-1 STP Fourth 10-Year Interval Relief Requests 46 Table 5.2.2-1 Risk Ranking and Element Summary 59 Table 5.4-1 NUREG-1801 Program Elements 65 FIGURES Figure 1 STP ISI/CISI Program Plan 9 APPENDICIES Appendix A Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 1, Interval 4 Appendix B Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 2, Interval 4 Appendix C Inservice Inspection Summary Table - Containment Metal Liner - Unit 1, Interval 4 Appendix D Inservice Inspection Summary Table - Containment Metal Liner - Unit 2, Interval 4 Appendix E Inservice Inspection Summary Table - Concrete Containment - Unit 1, Interval 4 Appendix F Inservice Inspection Summary Table - Concrete Containment - Unit 2, Interval 4

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 6 of 188 Appendix G Appendix VIII Implementation Plan Appendix H BMI Commitment Implementation Plan & Historical Data Appendix I Alloy 600 Implementation Plan & Historical Data Appendix J Thermal Fatigue Implementation Plan Appendix K Interval Outage Schedules Appendix L Examination Volume Figures

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 7 of 188 1.0 ASME Section XI Inservice Inspection Program 1.1 Purpose The purpose of this South Texas Project Electric Generating Station (STPEGS) herein referred to as the South Texas Project (STP) Units 1 & 2 Inservice Inspection (ISI) and Containment Inservice Inspection (CISI) Program is to meet the code requirements for maintaining an ISI/CISI Program Plan for STP. This plan provides the overall ASME Section XI requirements for STP. In addition to meeting those requirements, the plan also addresses examinations that are performed to specific approved Code Cases in Section 2.1 and Augmented Examinations in Section 5.0 identified in regulatory commitments to the Nuclear Regulatory Commission (NRC). STP will document those examinations performed as an alternative to the code, which is the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code,Section XI 2013 Edition, Division 1, Rules for Inservice Inspection of Nuclear Power Plant Components [4.1], (Code Cases) and those exams performed in addition to the ASME Section XI, Code (NRC Commitments).

These ISI/CISI requirements are to be met using the ASME Code Section XI 2013 Edition [4.1],

which is the Code of Record for this Fourth1 ISI/CISI Ten-Year ISI Program Plan unless identified to be different within this ISI/CISI Plan and will be referred to herein and throughout this plan as ASME Section XI. This ASME Section XI, Edition is mandated for use by the NRC in the United States Code of Federal Regulations (CFR), in Title 10, Part 50, Section 55a, Codes and Standards (10 CFR 50.55a), [4.2].

This ISI/CISI Program Plan is written for the 4th 120-month or Ten-Year ISI Interval at STP and the Ten-Year CISI Interval has been incorporated into the Ten-Year ISI Interval, but has a slightly earlier start date. The coordination of refueling outages and periods within this current 4th ISI/CISI Interval for STP is shown in Table 1.1-1 STP CISI Interval Schedule and Table 1.1-2 STP ISI Interval Schedule.

1.2 Scope The scope of this ISI/CISI Program Plan includes Class 1, 2, and 3 pressure retaining components, their welded attachments and their supports, Class MC and CC pressure retaining components and their integral attachments, including metal shell and penetration liners of concrete containments and the post-tensioning systems of concrete containments, but does not require examination of Class MC metal shell and penetration liner supports of concrete containments per the provisions of 10 CFR 50.55a(g)(4)(v). This Program Plan also includes Augmented ISI Examinations requiring Nondestructive Examination (NDE) that are maintained and implemented by this ISI/CISI Program Plan.

1 STP has decided to label the Containment Inservice Inspection Interval as the fourth interval. By calendar years, this is the third interval, however to align with the labeling of the Inservice Inspection Interval both will be labeled as the fourth interval.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 8 of 188 This ISI/CISI Program Plan is controlled by the regulations that are in 10 CFR 50.55a. This plans objective is to provide a traceable link between the governing ASME Section XI requirements and the implementing procedures used for these requirements in order to ensure that Regulatory Rules and ASME Section XI requirements for the ISI/CISI of safety related systems, components and structures are being fulfilled.

These instructions provide the necessary guidance for Engineering Programs personnel at STP to ensure the following:

1) Conformance to Title 10, Section 50.55a of the Code of Federal Regulations (10 CFR 50.55a).
2) Conformance to ASME Section XI.
3) Conformance to station policies, practices and procedures.
4) The necessary technical content is included in this ISI/CISI Program Plan and its implementing procedures.
5) The proper ASME Section XI required ISI/CISI Examinations, Tests and Administrative Procedures are implemented.
6) The proper ASME Section XI Request for Alternatives and Relief Requests are submitted to and granted or approved by the Regulatory Authority.
7) The proper Examination and Test records and reports are maintained.

Figure 1, STP ISI/CISI Program Plan, illustrates how this ISI/CISI Program Plan effectively functions as a central source to help ensure all Regulatory Rules and STP requirements are incorporated into the overall ISI/CISI Program. This Ten-Year ISI/CISI Program Plan provides a useful aid in program self-assessments, procedure preparation and/or revision, management quick reference, and program familiarization.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 9 of 188 Figure 1 STP ISI/CISI Program Plan Examination ASME Code Method Section XI 2013 Edition Visual Code of Inspection Federal Program ANSI Regulations Specifications Inservice Title 10, Part Inspection Surveillance 50.55a Implement Plan Procedures Nuclear Plant Technical Examinations Regulatory Specifications Commission Testing Specifications Regulatory Updated Final Guides Safety Analysis 1.14 Report Administrative 1.26 Procedures 1.84 1.147 Relief Requests 1.193 1.200 Limited Examinations Authorized Nuclear Compliance Records & Reports Completed Inservice Inspector

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 10 of 188 1.3 General The STP Units 1 & 2 Nuclear Steam Supply System (NSSS) is a Westinghouse four loop Pressurized Water Reactor (PWR) design. South Texas Project Nuclear Operating Company (STPNOC) obtained the original full-power 40-year operating license for STP Units 1 & 2 on March 22, 1988 and March 28, 1989 respectively. The NRC Docket Number assigned to the original operating licenses was 50-498 (Unit 1) and 50-499 (Unit 2). On September 28, 2017 both units received a renewed operating license DPR-76 and DPR-80 for 20-years of additional operation.

1.4 Inspection Intervals Inservice Inspection Unit 1 For Unit 1, the initial or 1st 120-month/Ten-Year ISI Interval and ISI Program began on August 25, 1988 and ended September 24, 2000. The 1st interval was extended due to the unit being out of service continuously for 13 months. The interval was also extended for an additional 12 months as allowed by IWA-2400(c). The base code of record for the first ten-year interval was the 1983 Edition with Summer 1983 Addenda of ASME Section XI.

The 2nd ISI Interval began on September 25, 2000 and ended on September 24, 2010. The Code of Record was the 1989 Edition of ASME Section XI.

The 3rd ISI Interval began on September 25, 2010 and ended on September 24, 2020. The Code of Record was the 2004 Edition of ASME Section XI.

Inservice Inspection Unit 2 For Unit 2, the initial or 1st 120-month/Ten-Year ISI Interval and ISI Program began on June 19, 1989 and ended October 18, 2000. The 1st interval was extended due to the unit being out of service continuously for 16 months. The base code of record for the first ten-year interval was the 1983 Edition with Summer 1983 Addenda of ASME Section XI.

The 2nd ISI Interval began on October 19, 2000 and ended on October 18, 2010. The Code of Record was the 1989 Edition of ASME Section XI.

The 3rd ISI Interval began on October 19, 2010 and ended on October 18, 2020. The Code of Record was the 2004 Edition of ASME Section XI.

Containment Inservice Inspection Units 1 & 2 The NRC published a Final Rule under 61FR41303 that incorporated by reference the 1992 Edition with the 1992 Addenda Subsections IWE and IWL. Licensees were required to incorporate these subsections into their inservice inspection (ISI) programs. In additional, licensees were required to expedite implementation of the containment examinations and to complete the expedited examinations within 5 years of the effective date of the rule which was September 9, 1996. The initial or 1st 120-month/Ten-Year CISI Interval began on September 9, 1998 and ended on September 8, 2009. The 1st interval was extended as allowed by IWA-2430. The Code of Record was the 1992 Edition with the 1992 Addenda of ASME Section XI.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 11 of 188 The 2nd CISI Interval began on September 9, 2009 and ended on September 8, 2019. The Code of Record was the 2004 Edition of ASME Section XI.

CISI Inspection Units 1 & 2 The 4th CISI Interval began on September 9, 2019 and is scheduled to continue through September 8, 2029 and the Code of Record for this interval is the 2013 Edition of ASME Section XI. The 4 th CISI Interval is divided into Inspection Periods as follows:

1st Period: From September 9, 2019 through September 8, 2022 (3 Years) 2nd Period: From September 9, 2022 through September 8, 2026 (4 Years) 3rd Period: From September 9, 2026 through September 8, 2029 (3 Years)

Outages during the 4th CISI Interval at STP are scheduled in Table 1.1-1.

TABLE 1.1-1 STP CISI Interval Schedule Interval Periods STP Outages Start Date Start Date To To Unit 1 Outages Unit 2 Outages End Date End Date 1st 1RE22 - Spring 2020 2RE20 - Fall 2020 09/09/19 to 09/08/22 1RE23 - Fall 2021 2RE21 - Spring 2021 09/09/19 1RE24 - Spring 2023 2RE22 - Fall 2022 To 2nd 1RE25 - Fall 2024 2RE23 - Spring 2024 09/08/29 09/09/22 to 09/08/26 1RE26 - Spring 2026 2RE24 - Fall 2025 3rd 1RE27 - Fall 2027 2RE25 - Spring 2027 09/09/26 to 09/08/29 1RE28 - Spring 2029 2RE26 - Fall 2028 ISI Inspection Units 1 & 2 The 4th ISI Interval began on September 25, 2020 and is scheduled to continue through September 08, 2029 and the Code of Record for this interval is the 2013 Edition of ASME Section XI. The Unit 1 & 2 ISI Intervals will end early per IWA-2430(c)(1) which will align both units for the ISI/CISI Inspection Intervals2. The 4th ISI Interval is divided into Inspection Periods as follows:

2 This shortening of the Unit 1 interval recovers the 1 year (12 month) allowance per IWA-2430(c)(1).

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 12 of 188 1st Period: From September 25, 2020 through September 24, 2023 (3 Years) 2nd Period: From September 25, 2023 through September 24, 2026 (3 Years) 3rd Period: From September 25, 2026 through September 08, 2029 (2 Yrs. 11 Months 14 days)

Outages during the 4th ISI Interval at STP are scheduled in Table 1.1-2.

TABLE 1.1-2 STP ISI Interval Schedule Interval Periods STP Outages Start Date Start Date To To Unit 1 Outages Unit 2 Outages End Date End Date 1st 1RE23 - Fall 2021 2RE21 - Spring 2021 09/25/20 to 09/24/23 09/25/20 1RE24 - Spring 2023 2RE22 - Fall 2022 To 1RE25 - Fall 2024 2RE23 - Spring 2024 09/08/29 2nd 09/25/23 to 09/24/26 1RE26 - Spring 2026 2RE24 - Fall 2025 3rd 1RE27 - Fall 2027 2RE25 - Spring 2027 09/25/26 to 09/08/29 1RE28 - Spring 2029 2RE26 - Fall 2028 Table 1.1-3 contains the IWL period dates for both units. The 35th and 40th year examinations will be completed under the 2013 Edition of ASME Section XI.

TABLE 1.1-3 STP IWL Period Schedule Unit 1 Unit 2 st st 1 Year completed 05/88 1 year completed 12/89 3rd Year completed 03/90 3rd Year completed 03/92 5th Year completed 04/92 5th Year completed 10/93 10th Year completed 08/98 10th Year completed 08/98 15th Year completed 02/04 15th Year completed 02/04 20th Year completed 01/09 20th Year completed 01/09 25th Year completed 06/14 25th Year completed 06/14 30th Year completed 03/18 30th Year completed 03/18

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 13 of 188 TABLE 1.1-3 STP IWL Period Schedule 35th Year scheduled 04/23 35th Year scheduled 04/23 40th Year scheduled 04/28 40th Year scheduled 04/28 TABLE 1.2-1 STP ISI Component Scheduling1 INSPECTION INSPECTION PERIOD MINIMUM MAXIMUM INTERVAL CALENDAR YEARS OF EXAMINATIONS EXAMINATIONS PLANT SERVICE WITHIN COMPLETED, %

CREDITED, %

THE INTERVAL 4th 3 16 50 4th 7 50 2 75 4th 10 100 100 1

The following are exempted from the percentage requirements of Table 1.2 -1 (a) Examination Categories B-N-1, B-P, B-Q, C-H, D-B and Welded Attachments of Examination Categories B-K, C-C, and D-A that are examined whenever component support member deformation, e.g., broken, bent, or pulled out parts, is identified during operation, refueling, maintenance, examination, or testing.

(b) Examinations partially deferred to the end of an inspection interval, as allowed by Examination Categories B-A, and B-D.

(c) Examinations deferred to the end of the inspection interval, as allowed by Examination Categories B-A, B-D, B-G-1, B-L-2, B-M-2, B-N-3, and B-O.

2 If the first period completion percentage for any examination category exceeds 34%, at least 16% of the required examinations shall be performed in the second period.

1.5 ASME Section XI Code of Record for the ISI Interval STP is required to update the ASME Section XI, ISI/CISI Program once every 120 months/Ten-Years. The regulations in 10 CFR 50.55a(g)(4) establish the effective ASME Code edition and addenda to be used by licensees for performing inservice inspections of components (including supports). Paragraph 50.55a(g)(4)(ii) requires the use of the latest edition and addenda that has been incorporated by 10 CFR 50.55a(a), 12 months before the start of the 120-month inspection interval.

This ASME Section XI reference requirement is considered the Code of Record.

CFR82FR32934 was published in July 2017 updating the implementation of Code Cases N-729 and N-770 to N-729-4 and N-770-2 respectively and incorporating the 2013 Edition with no addenda of

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 14 of 188 ASME Section XI among other changes. This Final Rule became effective August 17, 2017, and was in effect on September 9, 2018 for the CISI interval and September 25, 2019 for the ISI interval which was 12 months before the start of these intervals for STP. Subsequent to the publication of CFR82FR32935, CFR85FR26540 was published which updated the implementation of Code Cases N-729 and N-770 to N-729-6 and N-770-5 respectively and incorporated the 2017 Edition with no addenda of ASME Section XI. The effective date was June 3, 2020. Because STP CISI and ISI Intervals start on September 8, 2020, the code of record for the 4th interval will be the 2013 Edition with no addenda. STP will implement the latest endorsed Code Cases N-729-6 and N-770-5.

10 CFR 50.55a(g)(4)(iv) allows the use of subsequent editions of codes and addenda or portions thereof that are incorporated by reference subject to the conditions listed. The NRC has issued Regulatory Information Summary (RIS) RIS-2004-12 to provide guidance on how to use subsequent editions/addenda.

10 CFR.50.55a(g)(4)(v) with its provisions (A), (B), and (C) is applicable to STP and requires the inservice inspection, repair, and replacement requirements for the scope of the STP CISI Program portion of this ISI/CISI Program Plan to be as defined in the (A) First, (B) Second, and (C) Third provisions, of these requirements. Refer to Section 1.2 for the scope of the ISI/CISI Program.

Based on 10 CFR 50.55a(g)(4)(ii), the STP Ten-Year ISI/CISI Program Plan is required to meet the 2013 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI with No Addenda with the associated conditions contained in 10 CFR 50.55a(b)(2) as defined below. 10 CFR 50.55a conditions applicable to the System Pressure Testing and Repair/Replacement Activities are addressed in their applicable program procedures.

1.6 10 CFR 50.55a conditions applicable to STP 10 CFR 50.55a(a)(1)(ii)(C)(53), 2013 Edition.

10 CFR 50.55a(b)(2)(viii)(H), Each inaccessible area of concrete identified for evaluation under IWL-2512(a), or identified as susceptible to deterioration under IWL-2512(b), STP will provide the applicable information specified in paragraphs (b)(2)(viii)(E)(1), (2), and (3) in the Summary Report.

10 CFR 50.55a(b)(2)(viii)(I), During the period of extended operation of a renewed license under 10 CFR Part 54, STP will perform the technical evaluation under IWL-2512(b) of inaccessible below-grade concrete surfaces exposed to foundation soil, backfill, or groundwater at periodic intervals not to exceed 5 years. In addition, STP will examine representative samples of the exposed portions of the below-grade concrete, when such below-grade concrete is excavated for any reason.

10 CFR 50.55a(b)(2)(ix)(A)(2), For each inaccessible area identified for evaluation, STP will provide the information in (b)(2)(ix)(A)(2)(i), (ii), and (iii) in the Summary Report.

10 CFR 50.55a(b)(2)(ix)(B), STP may extend the maximum direct examination distance and may decrease the minimum illumination as long as the conditions or indications for which the visual examination is performed can be detected at the chosen distance and illumination.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 15 of 188 10 CFR 50.55a(b)(2)(ix)(J), if STP performs a major containment modification, the repair/replacement activity will be followed by a Type A test in accordance with 10 CFR part 50 Appendix J, Option A or Option B as applicable. When the Type A, B, or C test is performed, the test pressure and acceptance standard for the test will be in accordance with 10 CFR 50, Appendix J.

10 CFR 50.55a(b)(2)(ix)(K), STP has a total of 163 leak chase channels for each Unit that is included in this condition. STP will perform a general visual examination of these leak chase channels each interval complying with the percentage requirements of Table IWE-2411-1 of the 2017 Edition of ASME Section XI.

10 CFR 50.55a(b)(2)(xxii), The use of the provision in IWA-2220, Surface Examination, of Section XI, 2001 Edition through the latest edition and addenda incorporated by reference in paragraph (a)(1)(ii) of this section, that allows use of an ultrasonic examination is prohibited. STP will not implement UT as a Surface Examination.

10 CFR 50.55a(b)(2)(xxxii), STP will submit the Summary Reports described in IWA-6000 or Code Case N-532-5 within 90 calendar days of the completion of each refueling outage.

10 CFR 50.55a(a)(1)(iii), ASME Code Cases N-729-6, N-722-1 and N-770-5 apply to STP, with the applicable conditions as identified in 10 CFR 50.55a(g)(6)(ii)(D), (E) and (F).

1.7 ASME Section XI ISI/CISI Program Description The ASME Section XI Programs for an Inspection Interval is comprised of the following individual program sections. These program sections are separate documents or procedures, each bearing the title of the program.

  • ASME Section XI Containment Inservice Inspection Program (this is the CISI Program Section being addressed in this STP Ten-Year Plan)

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 16 of 188 For the purpose of clarification, the following definitions for terms used in this ASME Section XI ISI Program Plan are:

PROGRAM The term Program is used to provide the structure and methods for accomplishment of the objective of the program and is to be considered synonymous with the term Plan as used in ASME Section XI, Article IWA-2400.

SCHEDULE The term Schedule is used to define the detailed scheme of performing the required inspections over the Ten-Year ISI Interval.

Ten-Year ISI Program Description This Ten-Year ISI/CISI Program Plan details STP compliance with ASME Section XI IWA, IWB, IWC, IWD, IWE, IWF, and IWL for examination of ASME Class 1, 2, and 3 pressure retaining components and their supports and ASME Class MC and CC pressure retaining components and their welded attachments. This STP/CISI Ten-Year ISI Program Plan defines the ASME Class 1, 2, 3, MC, and CC components and the Code required examinations for each ASME Section XI Examination Category, including the Augmented Examination scope. The following is NOT included or addressed in this ISI/CISI Program Plan:

The snubber assembly [pin-to-pin] examination and testing requirements are NOT addressed in this ISI/CISI Program Plan. The extent, frequency, and acceptance standards for snubber assembly examination and testing will be in accordance with STP Technical Requirements Manual, Section 4.7.9.

The objective of the Ten-Year ISI/CISI Program Plan is to periodically perform NDE of ASME Class 1, 2, or 3 safety related components and supports or ASME Class MC or CC safety related components and their welded attachments to identify the presence of service related degradation.

The administrative procedures and Inspection Schedule described in this Ten-Year ISI/CISI Program Plan, combined with applicable STP approved vendor procedures, constitutes the ISI/CISI portion of the Ten-Year ISI/CISI Program required by the Updated Final Safety Analysis Report (UFSAR), [4.7], for STP UFSAR Sections 3.8.1, 5.2.4 and 6.6.

For convenience, this Ten-Year ISI/CISI Program Plan also contains Augmented Examinations that may be inside or outside the scope of 10 CFR 50.55a. These examinations may result from activities including, but not limited to, commitments made to the NRC outside the scope of 10 CFR 50.55a, internal commitments, license renewal commitments, or industry initiatives. These Augmented Examinations may use ASME Section XI techniques and procedures as defined in the commitment.

However, the requirements of ASME Section XI, including reporting, do not apply. Because these Augmented Examinations are not required by ASME Section XI they are not included in the summary totals for the specific ASME Section XI Examination Category.

The Ten-Year ISI/CISI Program Schedule for this program plan is contained in the IDDEAL Software Suite computer database as well as Appendix A and Appendix B. Within this database

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 17 of 188 required Supporting Documents per ASME Section XI, IWA-2425 are referenced and this information is retained at the plant site and is available for review.

Containment Inservice Inspection Program The Concrete Containment Program is developed and implemented in accordance with the requirements of the 2013 Edition of the ASME Section XI Code and 10 CFR 50.55a rulemaking.

Concrete Containment examinations, as required by Code Table IWL-2500-1 are scheduled and conducted using approved plant procedures. The Concrete Containment Program will be conducted in accordance with UFSAR 3.8.1, 0PSP09-TD-0001 Containment Tendon Test/End Anchorage and Adjacent Concrete Inspection, [4.15], and 4C23HCS0001 Inservice Surveillance of Containment Post Tensioning System, [4.16]. The scope of the Concrete Containment Program includes those components designated as Safety Class CC. The 4th Interval of the Concrete Containment inspection activities includes the 35th and 40th year examinations. The 40th year examinations extend through April 2028 for Unit 1 and Unit 2. Concrete Containment inspections were scheduled on a 1, 3 and 5 year schedule after the containment Structural Integrity Test, and every 5 years thereafter. The 1, 5 and 10 year examinations were completed under the requirements of R.G 1.35, Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containment Structures. The 15th through 30th year examinations were completed under ASME Section XI ISI program requirements. The 35th and 40th year examination will be completed under the 2013 Edition ASME Section XI program requirements.

The Containment Metal Liner Program is developed and implemented in accordance with the requirements of the 2013 Edition of the ASME Section XI Code and 10 CFR 50.55a rulemaking.

Containment Metal Liner examinations, as required by the Code Table IWE-2500-1 are scheduled and conducted using approved plant procedures. The Containment Metal Liner Program will be conducted in accordance with Technical Specifications Section 4.0.5 and UFSAR 3.9.1, 0PGP03-ZE-0075 Inservice Inspection Program for Containment Metal Liner [4.17], and PSP11-RC-0015 ASME Section XI Inservice Inspection (Surveillance) [4.18]. The scope of the Containment Metal Liner Program includes those components designated as Safety Class MC pressure retaining components and their integral attachments, and metallic shell and penetration liners of Class CC pressure retaining components and their integral attachments. The nominal duration of the FOURTH inspection interval for containment metal liner inspection activities is ten calendar years.

Refer to Table 1.1-1 for Unit 1 & 2 Interval 4 inspection interval/period start and end dates for Containment Metal Liner inspection activities. The containment metal liner is in the fourth inspection interval because the inspection program was implemented by 50.55a based on a final rule in September 1998.

NOTE STP is labeling the Containment Inservice Inspection (CISI) interval the fourth interval to align with the labeling of the ISI inspection interval. By calendar years this is the third 10 year interval, however for alignment with the ISI fourth 10 year interval, the IWE inspection interval will be

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 18 of 188 called the fourth interval. All requirements will be maintained for the 10 year interval. See below:

CISI 1st Interval 09/09/98 to 09/08/09 CISI 2nd Interval 09/09/09 to 09/08/19 CISI 4th Interval 09/09/19 to 09/08/29 Repair and Replacement Program Section Description ASME Section XI requirements for Class 1, 2 and 3 and MC and CC pressure retaining components and their supports, associated Repair/Replacement Activities are not contained in this plan. 0PGP03-ZE-0027, ASME Section XI Repair/Replacement Activity, [4.11] is the implementing procedure which describes the process for the Repair/Replacement Activity provisions of ASME Section XI, IWA-4000.

Repair/Replacement Activities performed by welding or brazing on pressure-retaining boundary SHALL be pressure tested in accordance with ASME Section XI, Article IWA-5000 and 0PGP03-ZE-0082 ASME Section XI Repair/Replacement Activity Pressure Testing, [4.32].

Snubber Program Section Description The Snubber Program requirements are not contained in this plan. Snubbers (pin-to-pin portion) will be examined and tested in accordance with plant Snubber Program, 0PGP03-ZE-0009, Snubber Testing Program, [4.13]. Snubber support hardware such as lugs, bolting, pins and clamps between the snubber pins and component (or the snubber pin and the building structure) will be examined in accordance with ASME Section XI, Subsection IWF, per this Program Plan.

Pressure Test Program Section Description ASME Section XI requirements for Class 1, 2 and 3 pressure testing are not contained in this plan.

0PGP03-ZE-0023, ASME Section XI, System Pressure Testing Program, [4.14] satisfies the requirements established in ASME,Section XI, IWA-5000, IWB-5000, IWC-5000, and IWD-5000.

The System Pressure Testing Program will be conducted in accordance with the Technical Specifications, Sections 4.0.5 and 3/4.4.10.

The scope of the System Pressure Testing Program includes those systems and components designated as Safety Class 1, 2, and 3 in accordance with Regulatory Guide 1.26, Revision 3, and includes instrument tubing that is designated as Safety Class 2 or 3. A listing of systems or portion of systems that are included in the scope of the System Pressure Testing program is provided below:

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 19 of 188 System Pressure Testing Program Scope Systems, or portions of systems, included within the scope of the System Pressure Testing Program:

AF Auxiliary Feedwater System AP Post-Accident Sampling System CC Component Cooling Water System CH Essential Chilled Water System CM Containment Hydrogen Monitoring System CS Containment Spray System CV Chemical and Volume Control System DG Standby Diesel Generators, including Subsystems EW Essential Cooling Water System FC Spent Fuel Pool Cooling and Cleanup System FW Feedwater System MS Main Steam System PS Primary Sampling System RC Reactor Coolant System RH Residual Heat Removal System SB Steam Generator Blowdown System SI Safety Injection System Note: The test boundaries subject to a VT-2 visual examination also include Safety Class 2 and 3 instrument tubing from the root valve up to and including the last instrument valve but not the instrument itself.

Pump and Valve Program Description The Inservice Testing (IST) Program requirements are not contained in this plan. 0PGP03-ZE-0015, Inservice Testing Program, [4.19] implements the requirements of the ASME OM Code.

Steam Generator Tube Surveillance Program Description The Steam Generator Tube Inspection Program is in accordance with Plant Technical Specifications,

[4.8] paragraphs T.S. 3/4.4.5, 3.4.6.2, 6.8.3 and 6.9.1.7 in lieu of ASME Section XI. Procedures 0PSP11-RC-0014 Steam Generator Inspection, 0PGP04-ZE-0305 Inservice Inspection Program for Steam Generator Tubing, and 0PGP03-ZO-0044 Steam Generator Management, [4.29, 4.30, and 4.31] implements these requirements.

1.8 Use of ASME Section V The Articles of ASME Section V referenced by Section XI SHALL be the 2013 Edition of ASME Section V for IWB, IWC, IWD, and IWF. ASME Section V Code Cases approved for use with the 2013 Edition of ASME Section V are acceptable for use at STP.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 20 of 188 1.9 Piping and Instrumentation Diagrams Table 1.9-1 provides a listing of the piping systems containing Class 1, 2, or 3 components. These piping systems and associated components are subject to inservice examination and testing in accordance with this Program Plan under one or more of the Code Examination Categories or Augmented programs. Also, Table 1.9-1 lists Piping and Instrumentation Diagrams (P&IDs) for these Class 1, 2, and 3 piping systems. Table 1.9-1 is arranged in alphabetical system abbreviation order and lists the P&IDs applicable to each system. P&IDs containing Class 1, 2, or 3 piping for more than one system will be listed in Table 1.9-1 for each applicable system.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 21 of 188 Table 1.9-1 Piping and Instrumentation Diagrams System System Drawing Sheet Abbr. Designation Number No. Drawing Title AF Auxiliary Feedwater 5S141F00024 1 Auxiliary Feedwater 5S141F00024 2 Auxiliary Feedwater 5S142F00024 1 Auxiliary Feedwater 5S142F00024 2 Auxiliary Feedwater 5S199F00020#1 Condensate Storage System (Note 1) 5S199F00020#2 Condensate Storage System (Note 1)

AP Post Accident Sampling 5Z549Z47501#1 Post Accident Sampling System 5Z549Z47501#2 Post Accident Sampling System 5Z169Z00046#1 Containment Hydrogen Monitoring System (Note 2) 5Z169Z00046#2 Containment Hydrogen Monitoring System (Note 2)

BA Breathing Air 5Q129F05044#1 Low Pressure Breathing Air System (Note 3) 5Q129F05044#2 Low Pressure Breathing Air System (Note 3)

CC Component Cooling 5R209F05017#1 Component Cooling Water System 5R209F05017#2 Component Cooling Water System 5R209F05018#1 Component Cooling Water System 5R209F05018#2 Component Cooling Water System 5R209F05019#1 Component Cooling Water System 5R209F05019#2 Component Cooling Water System

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 22 of 188 Table 1.9-1 Piping and Instrumentation Diagrams System System Drawing Sheet Abbr. Designation Number No. Drawing Title 5R209F05020#1 Component Cooling Water System 5R209F05020#2 Component Cooling Water System 5R209F05021#1 Component Cooling Water System 5R209F05021#2 Component Cooling Water System CH Essential Chilled Water 5V119V10001#1 Essential Chilled Water System 5V119V10001#2 Essential Chilled Water System 3V119V10002#1 Essential Chilled Water System 3V119V10002#2 Essential Chilled Water System 3V119V10003#1 Essential Chilled Water System 3V119V10003#2 Essential Chilled Water System 3V119V10004#1 Essential Chilled Water System 3V119V10004#2 Essential Chilled Water System CM Containment Hydrogen 5Z169Z00046#1 Containment Hydrogen Monitoring System Monitoring 5Z169Z00046#2 Containment Hydrogen Monitoring System CS Containment Spray 5N109F05037#1 Containment Spray System 5N109F05037#2 Containment Spray System 5N129F05013#1 Safety Injection System (Note 4) 5N129F05013#2 Safety Injection System (Note 4)

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 23 of 188 Table 1.9-1 Piping and Instrumentation Diagrams System System Drawing Sheet Abbr. Designation Number No. Drawing Title 5N129F05014#1 Safety Injection System (Note 4) 5N129F05014#2 Safety Injection System (Note 4) 5N129F05015#1 Safety Injection System (Note 4) 5N129F05015#2 Safety Injection System (Note 4)

CV Chemical and Volume 5R179F05005#1 Chemical & Volume Control System Control 5R179F05005#2 Chemical & Volume Control System 5R179F05006#1 Chemical & Volume Control System 5R179F05006#2 Chemical & Volume Control System 5R179F05007#1 Chemical & Volume Control System 5R179F05007#2 Chemical & Volume Control System 5R179F05008#1 Chem & Vol Control Sys BTRS Sub Sys 5R179F05008#2 Chem & Vol Control Sys BTRS Sub Sys 5R179F05009#1 Chemical & Volume Control System 5R179F05009#2 Chemical & Volume Control System DI Standby Diesel 5Q159F22543#1 Diesel Air Intake & Exhaust Systems Generator Combustion Air Intake 5Q159F22543#2 Diesel Air Intake & Exhaust Systems

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 24 of 188 Table 1.9-1 Piping and Instrumentation Diagrams System System Drawing Sheet Abbr. Designation Number No. Drawing Title DO Standby Diesel 5Q159F00045#1 1 Sdby Gen Fuel Oil Stor & Trans System Generator Fuel Oil 5Q159F00045#1 2 Sdby Gen Fuel Oil Stor & Trans System 5Q159F00045#2 1 Sdby Gen Fuel Oil Stor & Trans System 5Q159F00045#2 2 Sdby Gen Fuel Oil Stor & Trans System DW Demineralized Water 5S199F05034#1 Demin Water Dist Sys RCB FHB & MEAB (Note 3) 5S199F05034#2 Demin Water Dist Sys RCB FHB & MEAB (Note 3)

DX Standby Diesel 5Q159F22543#1 Diesel Air Intake & Exhaust Systems Generator Combustion Gas Exhaust 5Q159F22543#2 Diesel Air Intake & Exhaust Systems ED Radioactive Vents and 5Q069F05030#1 Radioactive Vents And Drains System (Note 3)

Drains 5Q069F05030#2 Radioactive Vents And Drains System (Note 3)

EW Essential Cooling Water 5Q159F22541#1 Standby Diesel Gen Sys Cooling Water (Note 5) 5Q159F22541#2 Standby Diesel Gen Sys Cooling Water (Note 5) 5R289F05038#1 1 Essential Cooling Water System - TRN 1A 5R289F05038#1 2 Essential Cooling Water System - TRN 1B 5R289F05038#1 3 Essential Cooling Water System - TRN 1C

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 25 of 188 Table 1.9-1 Piping and Instrumentation Diagrams System System Drawing Sheet Abbr. Designation Number No. Drawing Title 5R289F05038#2 1 Essential Cooling Water System - TRN 2A 5R289F05038#2 2 Essential Cooling Water System - TRN 2B 5R289F05038#2 3 Essential Cooling Water System - TRN 2C 5R289F05039#1 Essential Cooling Water System 5R289F05039#2 Essential Cooling Water System FC Spent Fuel Pool Cooling 5R219F05028#1 Spent Fuel Pool Cooling & Cleanup Sys 5R219F05028#2 Spent Fuel Pool Cooling & Cleanup Sys 5R219F05029#1 Spent Fuel Pool Cooling & Cleanup Sys 5R219F05029#2 Spent Fuel Pool Cooling & Cleanup Sys FP Fire Protection 5Q279F05047#1 FH,IVC, Contmnt Bldg Fire Protection Sys (Note 3) 5Q279F05047#2 FH,IVC, Contmnt Bldg Fire Protection Sys (Note 3)

FW Feedwater 5S139F00062#1 Feedwater System 5S139F00062#2 Feedwater System 5S139F00063#1 Feedwater System 5S139F00063#2 Feedwater System HC Containment Building 5V149V00018#1 Containment Bldg. HVAC System Normal Purge (Note 3)

HVAC 5V149V00018#2 Containment Bldg. HVAC System Normal Purge (Note 3) 5V149V00019#1 Containment Bldg. HVAC System Supplementary Purge (Note 3)

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 26 of 188 Table 1.9-1 Piping and Instrumentation Diagrams System System Drawing Sheet Abbr. Designation Number No. Drawing Title 5V149V00019#2 Containment Bldg. HVAC System Supplementary Purge (Note 3)

IA Instrument Air 5Q119F05040#1 Fuel Hndlng Bldg & RCB Inst Air System (Note 3) 5Q119F05040#2 Fuel Hndlng Bldg & RCB Inst Air System (Note 3)

IL Integrated Leak Test 5C560F05058 Containment Leak Rate Test Pressurization System (Note 3)

JW Standby Diesel 5Q159F22540#1 Standby Diesel Generator Sys Jacket Water Generator Jacket Water 5Q159F22540#2 Standby Diesel Generator Sys Jacket Water LU Standby Diesel 5Q159F22542#1 Standby Diesel Generator Sys Lube Oil Generator Lube Oil 5Q159F22542#2 Standby Diesel Generator Sys Lube Oil MS Main Steam 5S109F00016#1 Main Steam System 5S109F00016#2 Main Steam System 5S141F00024 1 Auxiliary Feedwater (Note 6) 5S141F00024 2 Auxiliary Feedwater (Note 6) 5S142F00024 1 Auxiliary Feedwater (Note 6) 5S142F00024 2 Auxiliary Feedwater (Note 6)

PO Reactor Coolant Pump 5R379F05042#1 Reactor C/P Oil Changing System (Note 3)

Oil Change-Out 5R379F05042#2 Reactor C/P Oil Changing System (Note 3)

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 27 of 188 Table 1.9-1 Piping and Instrumentation Diagrams System System Drawing Sheet Abbr. Designation Number No. Drawing Title PS Primary Sampling 5Z329Z00045#1 Primary Sampling System 5Z329Z00045#2 Primary Sampling System RA Radiation Monitoring 5V149V00017#1 HVAC React. Cntmnt Bldg. Sys. Composite (Note 7) 5V149V00017#2 HVAC React. Cntmnt Bldg. Sys. Composite (Note 7)

RC Reactor Coolant 5R149F05001#1 RCS Primary Coolant Loop 5R149F05001#2 RCS Primary Coolant Loop 5R149F05003#1 RCS Pressurizer 5R149F05003#2 RCS Pressurizer 5R149F05004#1 RCS Pressurizer Relief Tank 5R149F05004#2 RCS Pressurizer Relief Tank RD Reactor Coolant System 5R349F05046#1 RCS Vacuum Degassing System (Note 3)

Degassing 5R349F05046#2 RCS Vacuum Degassing System (Note 3)

RH Residual Heat Removal 5R169F20000#1 Residual Heat Removal System 5R169F20000#2 Residual Heat Removal System RM Reactor Makeup Water 5R279F05033#1 Reactor Makeup Water System 5R279F05033#2 Reactor Makeup Water System SA Station Air 5Q109F05041#1 FHB & RCB Service Air System (Note 3) 5Q109F05041#2 FHB & RCB Service Air System (Note 3)

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 28 of 188 Table 1.9-1 Piping and Instrumentation Diagrams System System Drawing Sheet Abbr. Designation Number No. Drawing Title SB Steam Generator 5S209F20001#1 Steam Generator Blowdown System Blowdown 5S209F20001#2 Steam Generator Blowdown System SD Standby Diesel 5Q159F22546#1 Standby Diesel Starting Air System Generator Starting Air 5Q159F22546#2 Standby Diesel Starting Air System SI Safety Injection 5N129F05013#1 Safety Injection System 5N129F05013#2 Safety Injection System 5N129F05014#1 Safety Injection System 5N129F05014#2 Safety Injection System 5N129F05015#1 Safety Injection System 5N129F05015#2 Safety Injection System 5N129F05016#1 Safety Injection System 5N129F05016#2 Safety Injection System SL Steam Generator Sludge 5S209F05057#1 Stm Gen Sludge Lancing & Chem Cleaning Sys Lancing (Note 3) 5S209F05057#2 Stm Gen Sludge Lancing & Chem Cleaning Sys (Note 3)

WL Liquid Waste Processing 5R309F05022#1 Liquid Waste Processing System (Note 3) 5R309F05022#2 Liquid Waste Processing System (Note 3)

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 29 of 188 Table 1.9-1 Piping and Instrumentation Diagrams System System Drawing Sheet Abbr. Designation Number No. Drawing Title Notes: 1. Includes AF piping.

2. Includes AP piping.
3. Class 2 containment penetration piping and isolation valves only.
4. Includes CS piping.
5. Includes EW piping.
6. Includes MS piping.
7. Includes RA piping; Class 2 containment penetration piping and isolation valves only.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 30 of 188 1.10 Interpretations of the ASME Section XI Code This section lists interpretations to the Code for specific portions of the ISI Program.

Code interpretations provide clarification to the intent of Code requirements. Although the NRC agrees with most interpretations, some are inconsistent with NRC requirements. NRC requirements SHALL be met. Interpretations serve to support the users understanding of Code requirements. Many interpretations address specific circumstances. Therefore, the context of the interpretation must be thoroughly understood prior to its application at STP. Code interpretations applicable to STP are listed in Table 1.10.

TABLE 1.10 ASME SECTION XI ISI INTERPRETATIONS Interpretation Interpretation Description / Subject Application No. Impact XI-1-04-26 IWA-2430(d)(1) (1995 Edition With the 1996 Addenda Welds -

Through the 2004 Edition With the 2005 Addenda) successive intervals XI-1-10-23 Table IWB-2500-1 (1989 Edition through the 2010 Edition ISI Welds -

with the 2011 Addenda) Core support structures XI-1-13-10R Examination of leak chase channel threaded plugs, caps, ISI Containment seals, or covers (1992 Edition 1992A through 2013 Edition)

XI-1-13-24 IWA-2210 (2013 Edition) NDE - Visual Examination XI-1-16-14 Calibration notch location requirement (Code Case N-845) NDE - UT XI-1-18-01 IWB-1220 Exemptions (1995 Edition with the 1995 ISI -

Addenda - 2013 Edition) Exemptions Notes: ISI - Inservice Inspection, NDE - Nondestructive Examination 1.11 Records, Reports, and Submittals The requirements of Code Case N-532-5 shall be met in lieu of the requirements of ASME Section XI, IWA-6210(c), (d), (e), and (f), IWA-6220, IWA-6230(b), (c), and (d), and IWA-6240(b). All other requirements of IWA-6000 and the other requirements of ASME Section XI applicable to records and reporting shall be met as described below.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 31 of 188 Records Records of examinations, tests, and repair/replacement activities shall be prepared in accordance with the governing procedure or program document.

Records and reports required by ASME Section XI and this program shall be maintained as a permanent plant record. They shall be filed in a manner to ensure accessibility by the Authorized Nuclear Inservice Inspector (ANII). The storage and maintenance of these records are under the auspices of the Quality Assurance Program.

Records and reports shall be either the original or a reproduced legible copy. Alternatively, they may be maintained in an electronic format provided the requirements of ASME Section XI, IWA-6320(a) are met. Radiographs may be microfilmed or digitally reproduced. Digital reproduction shall be in accordance with IWA-6320(b).

Reports and Submittals Reports and submittals comprise those documents or records that are required to be submitted to the NRC either on a recurring basis or as a result of activities described by Section XI. Reports shall be as described below. ASME Section XI, reports and submittals are provided to the NRC for Information Only to meet a specific Section XI requirement. NRC approval is not required.

In accordance with the ASME Section XI, Owners Responsibilities contained in IWA-1400(d) submittal of plans, schedules, and preservice and inservice inspection summary reports to the enforcement and regulatory authorities having jurisdiction at the plant site, if they are required by these authorities. Under this requirement submittal of these program documents is only required if these authorities require them to be submitted. Currently there are no requirements to submit this Ten-Year ISI/CISI Program Plan or any revisions used for this ISI/CISI Program Plan.

However, in 10 CFR 50.55a(b)(2)(xxxii), it requires that Summary Reports described in IWA-6000 must be submitted to the NRC as described in IWA-6240(a) and IWA-6240(b). Inservice inspection summary reports shall be submitted within 90 calendar days of the completion of each refueling outage.

This requirement is being met by STP with the use of Code Case N-532-5.

The Summary Reports that are required by ASME Section XI, IWA-6000 have been replaced by the Owners Activity Report, Form OAR-1, described by Code Case N-532-5. Form OAR-1 will be prepared, maintained, and submitted in accordance with the applicable requirements in the Code Case.

The Form OAR-1 shall be prepared to meet the requirements of the Code Case and submitted to the NRC within 90 calendar days of completing each refueling outage; refer to 10 CFR 50.55a(b)(2)(xxxii).

The report shall include all applicable activities of the operating cycle not included in the previous report.

When acceptance standards have been modified as a result of using smaller flaw sizes in developing the Pressure/Temperature Limit Curves in accordance with ASME Section XI, IWB-3410.2, the modified acceptance standards shall be filed with the NRC.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 32 of 188 Incomplete or Missing Examinations Resolution and tracking of incomplete or missed examinations (not exam limitations) shall be in accordance with STPs Corrective Action Program, [4.10] as described below:

Condition Report Requirements A Condition Report shall be developed in a timely manner. The Condition Report should contain the following:

a) The affected component.

b) The examination requirement that has not been, or will not be, met.

c) The reason for incomplete or missed examination.

d) Alternate examinations performed or recommended, (i.e. best effort vs. VT-1, etc.)

to include reasons why this is acceptable.

Relief Requests If a Request for Relief is required for an incomplete or missing examination, the following steps shall be completed:

a) The site should develop and submit the necessary documentation to the NRC3.

b) If the Request for Relief is granted by the NRC, then the approval should be incorporated into the program plan.

c) If the Request for Relief is not granted, the site should initiate a Condition Report.

Missed Examinations Which Cannot Be Made Up If it is discovered that a required examination has been missed and cannot be performed before the end of the Inspection Period in accordance with the ISI Plan, a Condition Report should be initiated.

NOTE The Inspection Period includes any extensions made within ASME Section XI and 10 CFR 50.55a provisions. The end of the Inspection Period does not occur until any applicable extensions are completed.

1.12 Responsibilities 1.12.1 Testing/Programs Engineering Group 3

For information on what the NRC expects to see in Coverage Relief Requests refer to the presentation made by Stephen Cumblidge to the Industry/NRC NDE technical Information Exchange Public Meeting on January 13-15, 2015 (ML15013A266)

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 33 of 188 The Testing/Program Engineering Group is responsible for the establishment and implementation of the ISI/CISI program. The following procedures detail the responsibilities related to implementation of the ISI/CISI Program:

  • 0PGP03-ZE-0075, Inservice Inspection Program for Containment Metal Liner

1.13 Administrative Controls This Ten-Year ISI/CISI Program Plan is written and implemented meeting the requirements of the following:

1. 0PGP04-ZE-0304, Inservice Inspection Program for Welds and Component Supports, [4.12]
2. 0PSP11-RC-0015, ASME Section XI Inservice Inspection (Surveillance), [4.18]
3. 0PGP03-ZE-0075, Inservice Inspection Program for Containment Metal Liner, [4.17]

This Ten-Year ISI/CISI Program Plan will be maintained current to reflect applicable changes to plant configuration through the STP Inservice Inspection Program Preparation and Change Control Process. All approved Changes since the last revision of this program document will be included in the next document revision.

Additions of items to this Ten-Year ISI/CISI Program Plan resulting from changes to the plant configuration will be incorporated and scheduled for inspection or examination in accordance with ASME Section XI, IWB/IWC/IWD-2411/IWE-2411/ IWF-2410 and IWL-2220.

This Ten-Year ISI/CISI Plan and subsequent revisions are subject to review by the Authorized Nuclear Inservice Inspector (ANII) as required by ASME Section XI, IWA-2110.

2.0 ASME Code Case Applicability This section contains ASME Section XI Code Cases applicable to the STP Fourth Ten-Year ISI/CISI Interval.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 34 of 188 2.1 Adoption of Code Cases ASME Section XI Code Cases adopted for ISI/CISI and related NDE activities for the ISI Interval are listed in Tables 2.2-1, 2.3-1, and 2.4-1. The use of Code Cases is in accordance with ASME Section XI, IWA-2440, 10 CFR 50.55a, and Regulatory Guide 1.147, [4.4]. As permitted by ASME Section XI and Regulatory Guide 1.147 or 10 CFR 50.55a, ASME Section XI Code Cases may be adopted and used as described below:

Adoption of Code Cases Listed for Generic Use in Regulatory Guide 1.147 Code Cases that are listed for generic use in the latest revision of Regulatory Guide 1.147 may be included in the ISI program provided any additional conditions specified in the Regulatory Guide are also incorporated. Table 2.2-1 identifies the Code Cases approved for generic use and adopted for the interval.

Adoption of Code Cases Not Approved in Regulatory Guide 1.147 Certain Code Cases that have been approved by the ASME Board of Nuclear Codes and Standards may not have been reviewed and approved by the NRC Staff for generic use and listed in Regulatory Guide 1.147. Use of such Code Cases may be requested in the form of a Request for Alternative in accordance with 10 CFR 50.55a(z). Once authorized/approved, these Requests for Alternatives will be available for use until such time that the Code Cases are adopted into Regulatory Guide 1.147, at which time compliance with the provisions contained in the Regulatory Guide are required.

Table 2.3-1 identifies those Code Cases that have been requested through a Request for Alternative.

For convenience to the user of this ISI/CISI Program Section, the appropriate internal correspondence number is provided to assist in retrieval of the request from Document Control. All other Requests for Alternatives and Requests for Relief (those not associated with NRC approval of Code Cases) are addressed in Section 3.0.

Adoption of Code Cases Mandated by 10 CFR 50.55a Code Cases required by rule in 10 CFR 50.55a are incorporated into the ISI Program and implemented at the specified schedule. Code Cases currently required by 10 CFR 50.55a are identified in Table 2.4-1.

Use of Annulled Code Cases As permitted by Regulatory Guide 1.147, Code Cases that have been adopted for use in the current inspection interval that are subsequently annulled by ASME may be used for the remainder of the interval.

Code Case Revisions Initial adoption of a Code Case requires use of the latest revision of that Code Case listed in Regulatory Guide 1.147. However, if an adopted Code Case is later revised and approved by the NRC, then either the earlier or later revision may be used as permitted by Regulatory Guide 1.147.

An exception to this provision would be the inclusion of any conditions on the later revision

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 35 of 188 necessary to enhance safety. In this situation, the conditions imposed on the later revision must be incorporated into the program.

Adoption of Code Cases Issued Subsequent to Filing the Inservice Inspection Plan Code Cases issued by ASME subsequent to filing4 the Inservice Inspection Plan with the NRC may be incorporated within the provisions of paragraphs 2.1.1 or 2.1.2 by revision to the ISI Plan. Any subsequent Code Cases shall be incorporated into the program and identified in either Table 2.2-1 or 2.3-1, as applicable, prior to their use.

Non Inservice Inspection Code Cases Only Code Cases applicable to ISI/CISI and related NDE requirements and Flaw Evaluations for Class 1, 2, and 3 components and their supports are included in Table 2.2-1, 2.3-1 and 2.4-1.

Code Cases Not Approved for Generic Use by the NRC Code Cases that have been approved by the ASME Board on Nuclear Codes and Standards may not be approved by the NRC Staff for generic use. These Code Cases are listed in Regulatory Guide 1.193, ASME Code Cases Not Approved for Use, [4.20]. However, the NRC may approve their use in specific cases. Code Cases listed in Regulatory Guide 1.193 will not be used at STP without an approved Request for Alternative in accordance with 10 CFR 50.55a(z).

4 The NRC no longer requires filing or submittal of the ISI Program Plan.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 36 of 188 2.2 Regulatory Guide 1.147, Revision 19 Approved Code Cases Table 2.2 Code Cases Adopted from Regulatory Guide 1.147 Code Case Affected Program Title NRC Conditions Number Area N-513-4 Evaluation of Criteria for Temporary Acceptance of Flaws in Moderate None Energy Class 2 or 3 Piping,Section XI, Division 1.

N-532-5 Repair/Replacement Activity Repair/Replacement None Documentation Requirements and Program & ISI Summary Inservice Inspection Summary Report Report Preparation and Submission N-593-2 Examination Requirements for Steam 1. Essentially 100% (not less than NDE Examination Volume Generator Nozzle-to-Vessel Welds 90%) of the examination volume A-B-C-D-E-F-G-H must be inspected.

2. The examination volume specified in Section XI, Table IWB-2500-1, Examination Category B-D, must be used for the examination of steam generator nozzle-to-vessel welds at least once prior to using the reduced examination volume allowed by Code Case N-593-2.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 37 of 188 Table 2.2 Code Cases Adopted from Regulatory Guide 1.147 Code Case Affected Program Title NRC Conditions Number Area N-613-2 Ultrasonic Examination of Full None NDE Examination Penetrations Nozzles in Vessels, Volume - Class 1 Examination Category B-D, Reactor Nozzle-to-Vessel and Nozzle Inside Radius Section, Figs. IWB-2500-7(a),

(b), (c), and (d)

N-639 Alternative Calibration Block Material Chemical ranges of the calibration Weld Examinations -

block may vary from the materials Cal. Blocks specification if (1) it is within the chemical range of the component specification to be inspected, and (2) the phase and grain shape are maintained in the same ranges produced by the thermal process required by the material specification.

N-648-2 Alternative Requirements for Inner In lieu of a UT examination, Weld Examinations - Class Radius Examination of Class 1 Reactor licensees may perform a VT-1 1 RPV Vessel Nozzles examination in accordance with the code of record for the Inservice Inspection Program utilizing the allowable flaw length criteria of Table IWB-3512-1 with limiting assumptions on the flaw aspect ratio.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 38 of 188 Table 2.2 Code Cases Adopted from Regulatory Guide 1.147 Code Case Affected Program Title NRC Conditions Number Area N-653-1 Alternative Requirements for Inner None Class 1 & 2 Piping Radius Examination of Class 1 Reactor Welds Vessel Nozzles N-716-1 Alternative Piping Classification and None Class 1 & 2 Piping Examination Requirements Welds N-731 Alternative Class 1 System Leakage None Pressure Testing Test Pressure Requirements N-771 Alternative requirements for None Class 2 and 3 Items Additional Examination of Class 2 and 3 Items N-773 Alternative Qualification Criteria for None Piping Inside Surfaces Eddy Current Examinations of Piping Inside Surfaces N-798 Alternative Pressure Testing None Pressure Testing Requirements for Class 1 Piping Between the First and Second Vent, Drain, and Test Isolation Devices N-800 Alternative Pressure Testing None Pressure Testing Requirements for Class 1 Piping Between the First and Second Injection Valves

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 39 of 188 Table 2.2 Code Cases Adopted from Regulatory Guide 1.147 Code Case Affected Program Title NRC Conditions Number Area N-805 Alternative to Class 1 Extended None Pressure Testing Boundary End of Interval or Class 2 System Leakage Testing of the Reactor Vessel Head Flange O-Ring Leak-Detection System N-823-1 Visual Examination None NDE Examination - VT-1, VT-2, VT-3 N-825 Alternative Requirements for None NDE Examination:

Examination of Control Rod Drive Category B-O Housing Welds,Section XI, Division 1 Item No. B14.20 N-831 Ultrasonic Examination in lieu of None NDE Examination -

Radiography for Welds in Ferritic Pipe Ultrasonic vs.

Radiography N-845 Qualification Requirements for Bolts None Class 1 & 2 Piping Bolts and Studs and Studs

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 40 of 188 2.3 Code Cases Adopted Via NRC Approved Requests The following ASME Code Cases are not contained in Regulatory Guide 1.147, Revision 18, [4.4] and require a request for alternative prior to implementation. Refer to Section 3.0 of this plan for the applicable requests.

Table 2.3 Code Cases Adopted Via NRC Approved Requests Code Case Request for Affected Program Title Number Alternative No. Area Internal Repair of Buried Class 2 & 3 Piping CFRP ECW Buried N-871 Using Carbon Fiber Reinforced Polymer RR-ENG-3-24 Pipe Composites Ultrasonic Examination in Lieu of RR-ENG-4-04 Ferritic or Austenitic N-831-1 Radiography for Ferritic or Austenitic Pipe (Not Yet Approved) Piping 2.4 Code Cases required by 10 CFR 50.55a The following ASME Code Cases are not contained in Regulatory Guide 1.147, Revision 18, [4.4], but are mandated in 10 CFR 50.55a.

Table 2.4 Code Cases Required by 10 CFR 50.55a Code Case Affected Program Title Notes Number Area N-722-1 Additional Examinations for PWR Pressure Conditions specified in Class 1 Weld Retaining Welds in Class 1 Components paragraphs (g)(6)(ii)(E)(2) Examinations Fabricated With Alloy 600/82/182 Materials through (4) of 10 CFR 50.55a.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 41 of 188 Table 2.4 Code Cases Required by 10 CFR 50.55a Code Case Affected Program Title Notes Number Area N-729-6 Alternative Examination Requirements for Conditions specified in Class 1 Weld PWR Reactor Vessel Upper Heads With paragraphs (g)(6)(ii)(D)(2) Examinations Nozzles Having Pressure-Retaining Partial- through (4) of 10 CFR Penetration Welds 50.55a.

N-770-5 Alternative Examination Requirements and Class 1 Piping Weld Conditions specified in Acceptance Standards for Class 1 PWR Piping Examinations paragraphs (g)(6)(ii)(F)(2) and Vessel Nozzle Butt Welds Fabricated With through (16) of 10 CFR UNS N06082 or UNS W86182 Weld Filler 50.55a.

Material With or Without Application of Listed Mitigation ActivitiesSection II, V, and IX Code Cases do NOT need a request for alternative for implementation. The Section II, V, and IX Code Cases adopted for the ISI/CISI Program Plan are listed in Table 2.5.1.

Table 2.5 Section II, V, and IX Code Cases Code Case Title Affected Program Area Number 2142-3 F-Number Grouping for Ni-Cr-Fe, Classification UNS Repair/Replacement Program - Welding N06052 Filler Metal,Section IX (Applicable to All Sections, including Section III, Division 1, and Section XI)

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 42 of 188 Table 2.5 Section II, V, and IX Code Cases Code Case Title Affected Program Area Number 2143-1 F-Number Grouping for Ni-Cr-Fe, Classification UNS Repair/Replacement Program - Welding W86152 Welding Electrode,Section IX (Applicable to All Sections, including Section III, Division 1, and Section XI) 2476 Radiography Using Phosphor Imaging Plate,Section V NDE

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 43 of 188 3.0 Relief Requests Throughout this ISI/CISI Program Plan, the term Relief Request is used interchangeably referring to submittals to the NRC requesting permission to deviate from either an ASME Section XI requirement, a 10 CFR 50.55a rule, or to use provisions from editions of Section XI not approved by the NRC as referenced in 10 CFR 50.55a(b). However, when communicating with the NRC and in written requests to deviate, the terms as defined below must be used for clarity and to satisfy 10 CFR 50.55a. Submittals to the NRC must clearly identify which of the below rules are being used to request the deviation.

Table 3.0-1 contains an index of Relief Requests written in accordance with 10 CFR 50.55a(a)(g)(5)(iii) and Requests for Alternatives per 10 CFR 50.55a(z). The applicable STP submittal and NRC Safety Evaluation Report (SER) correspondence numbers are also included for each request.

3.1 Request for Alternatives When seeking an alternative to the rules contained in 10 CFR 50.55a(b) through (h) the request is submitted under the provision of 10 CFR 50.55a(z). Once approved by the Director, Office of Nuclear Reactor Regulation, the alternative may be incorporated into the ISI/CISI program. These types of requests are typically used to request use of Code Cases, Code Editions, or Addenda not yet approved by the NRC. Request for Alternatives must be approved by the NRC prior to their implementation or use. Within the provisions of 10 CFR 50.55a(z) there are two specific methods of submittal:

10 CFR 50.55a(z)(1) Acceptable level of quality and safety. The proposed alternative would provide an acceptable level of quality and safety.

10 CFR 50.55a(z)(2) Hardship without a compensating increase in quality and safety. Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

3.2 Relief Requests Required due to Impracticality or Limited Examinations 10 CFR 50.55(a)(g)(5)(iii) and (iv) allows relief to be requested in instances when a Code requirement is deemed impractical with (iv) being specific to examination requirements that are determined to be impractical. The provisions of these two paragraphs are typically used to address impracticalities like limited examination coverage. Under 10 CFR 50.55(a)(g)(5)(iii) or (iv), relief requests for impracticality determinations must be submitted for NRC review and approval no later than 12 months after the expiration of the initial or subsequent 120-month inspection interval for which relief is sought.

In cases where conformance with an ASME Section XI requirement for inservice inspection is considered impractical, STP will notify the NRC and submit information to support the

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 44 of 188 determination, as required by 10 CFR 50.55a(g)(5). The submittal of this information will be referred to as a Request for Relief.

In the event that the entire examination volume or surface (as defined in the ASME Code) cannot be examined due to interference by another component or part geometry in accordance with ASME Section XI IWA-2200(c), a request for relief will be submitted. ASME Section XI IWA-2200(c) does not apply to the bare metal visual examinations required by Code Case N-729-6. When performing visual examinations to meet N-729-6, the requirements of N-729-6 shall be used for determining allowance for partial examination of the required surface.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 0 Page 45 of 188 Table 3.0-1 STP Fourth 10-Year Interval Relief Requests NRC SER Relief Request Relief Request Description STP Correspondence Correspondence RR-ENG-3-24 10 CFR 50.55a(z) Request - Proposed Alternative to NOC-AE-19003684 ML20227A385 ASME Boiler & Pressure Vessel Code Section XI NOC-AE-19003696 Requirements for Repair/Replacement of Essential Cooling Water (ECW) System Class 3 Buried Piping RR-ENG-4-01 10 CFR 50.55a(z) Request - Alternative Requirements for Not Yet Submitted Nondestructive Examination of Steam Generator Main Steam Nozzle Inner Radius Sections.

RR-ENG-4-02 10 CFR 50.55a(z) Request - Alternative Requirements regarding Not Yet Submitted alternative UT for Reactor Pressure Vessel Flange Insert Non-Destructive Examination.

RR-ENG-4-03 10 CFR 50.55a(z) Request - Alternative Requirements for Not Yet Submitted Examination of CRD Housing Welds RR-ENG-4-04 N-831-1 Ultrasonic Examination in Lieu of Radiography for Not Yet Submitted Ferritic or Austenitic Pipe

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 0 Page 46 of 188 Table 3.0-1 STP Fourth 10-Year Interval Relief Requests NRC SER Relief Request Relief Request Description STP Correspondence Correspondence RR-ENG-IWL-01 10 CFR 50.55a(a)(3)(i) Request - Alternate Requirements Original Request dated SER dated regarding examination of tendons that cannot be accessed safely 07/10/2000 - (NOC- 03/15/2001 (TAC at power due to proximity to PORVs above IVC roof. Instead of AE-00000868) - NOS. MA9508 and examining them during outages per IWL-2420(c), substitute MA9509) and (ML003732928) and tendons will be examined. (NRC authorized in the 1st 10-Year (ML010740230)

Interval without any expiration date and therefore is approved to Amended Request AE-NOC-01000790 the end of the plant life for STP Units 1 & 2). dated 09/14/2000 -

NOC-AE-00000921 -

(ML003754691)

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 47 of 188 4.0 References

[4.1] American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code Section XI, 2013 Edition, Division 1, Rules for Inservice Inspection of Nuclear Power Plants

[4.2] Title 10, Code of Federal Regulations, Part 50.55a Codes and Standards

[4.3] Regulatory Guide 1.14, Revision 1, Reactor Coolant Pump Flywheel Integrity

[4.4] Regulatory Guide 1.147 Revision 18, Inservice Inspection Code Case Acceptability Section XI, Division 1

[4.5] Regulatory Guide 1.26, Quality Group Classifications and Standards for Water-Steam, and Radioactive-Waste-Containing Components of Nuclear Power Plants

[4.6] EPRI Report 1006937, Extension of the EPRI Risk-Informed Inservice Inspection (RI-ISI)

Methodology to Break Exclusion Region (BER) Programs, Rev. 0-A, August 2002

[4.7] STP Updated Final Safety Analysis Report (UFSAR)

[4.8] STP Plant Technical Specifications (TS)

[4.9] NULL - Reserved

[4.10] 0PGP03-ZX-0002, Condition Reporting Process

[4.11] 0PGP03-ZE-0027, ASME Section XI Repair/Replacement Activities

[4.12] 0PGP04-ZE-0304 Inservice Inspection for Welds and Component Supports

[4.13] 0PGP03-ZE-0009, Snubber Testing Program

[4.14] 0PGP03-ZE-0023, System Pressure Testing Program

[4.15] 0PSP09-TD-0001 Containment Tendon Test/End Anchorage and Adjacent Concrete Inspection

[4.16] 4C23HCS0001 Inservice Surveillance of Containment Post Tensioning System

[4.17] 0PGP03-ZE-0075 Inservice Inspection Program for Containment Metal Liner

[4.18] 0PSP11-RC-0015 ASME Section XI Inservice Inspection (Surveillance)

[4.19] 0PGP03-ZE-0015, Inservice Testing Program

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 48 of 188

[4.20] Regulatory Guide 1.193, ASME Code Cases Not Approved for Use

[4.21] NUREG-0800, Standard Review Plan for Review of Safety Analysis Reports for Nuclear Power Plants

[4.22] MRP-146 Rev. 2 Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines.

[4.23] MRP-227-A Reactor Internals Inspection and Evaluation (I&E) Guidelines

[4.24] WCAP-14535A, Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination

[4.25] WCAP-14572 Revision 1-NP-A Addendum 1 [4.23], Addendum to Westinghouse Owners Group Application of Risk-Informed Methods to Piping Inservice Inspection Topical Report to Address Changes to augmented Inspection Requirements

[4.26] WCAP-16913-P Operability Assessment and Plant Applicability Evaluation for Pressurizer Heater Sleeve Leakage in Westinghouse Designed Pressurizers

[4.27] ER-AA-TFM-10 Thermal Fatigue Management Program

[4.28] NUREG-0612 Control of Heavy Loads

[4.29] 0PSP11-RC-0014, Steam Generator Inspection

[4.30] 0PGP04-ZE-0305, Inservice Inspection Program for Steam Generator Tubing

[4.31] 0PGP03-ZO-0044, Steam Generator Management Program

[4.32] 0PGP03-ZE-0082 ASME Section XI Repair/Replacement Activity Pressure Testing

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 49 of 188 5.0 AUGMENTED EXAMINATIONS This Ten-Year ISI Program Section contains augmented examinations that may be inside or outside the scope of 10 CFR 50.55a. These augmented examinations may result from activities including, but not limited to meeting the requirements of 10 CFR 50.55a or commitments made outside of 10 CFR 50.55a, or those made based on other document requirements, internal commitments, license renewal commitments, or industry initiatives. Augmented examinations may be required to use ASME Section XI techniques and procedures or those as defined in the commitment, however, the requirements of ASME Section XI, including reporting, do NOT apply when these examinations are required outside of 10 CFR 50.55a.

For other augmented examinations that are NOT required by 10 CFR 50.55a and ASME Code requirements such asSection XI and its Code Cases, they are NOT required to be included in the summary totals for a specific examination category. These augmented examinations may be required to use ASME Section XI techniques and procedures or those as defined in the commitment, however, the requirements of ASME Section XI, including reporting, do NOT apply when these examinations are required outside of 10 CFR 50.55a. Changes to these examination requirements and schedules that are outside of 10 CFR 50.55a may be required to be evaluated using the 10 CFR 50.59 screening/review process unless otherwise specified.

Augmented examinations are considered in one of the following four categories:

5.1 Augmented Examinations Required by 10 CFR 50.55a; 5.2 Augmented Examinations for External Commitments; 5.3 Owner Elected Examinations for Internal Commitments; and 5.4 License Renewal Examinations for Aging Management Commitments.

These four types of augmented examinations are described in Sections 5.1, 5.2, 5.3 and 5.4, respectively.

In addition, all the augmented examinations described below are tracked or included in an Augmented Examination Summary contained in Appendix A and Appendix B.

5.1 Augmented Examinations Required by 10 CFR 50.55a These augmented examinations are conducted to meet a requirement in 10 CFR 50.55a. Typically these are requirements imposed by the NRC to enhance existing ASME Section XI examination requirements.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 50 of 188 5.1.1 Augmented ISI Requirements per ASME BPV Code Case N-722 Reactor Coolant Pressure Boundary Visual Examinations of Reactor Vessel Bottom Head, Steam Generators and Piping Components Source Documents: Code Case N-722-1 Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials,Section XI, Division 1.

Commitment No.: None, NRC Mandatory per 10 CFR 50.55a(g)(6)(ii)(E)(1).

Associated Documents: None, Conditions in 10 CFR 50.55a(g)(6)(ii)(E)(2) through (4)].

Purpose:

Implementation of Code Case N-722-1 is to ensure the integrity of the Alloy 600/82/182 components.

Scope: Table 1 of Code Case N-722-1 lists the parts to be examined, but not all of the parts listed in the code case contain components with Alloy 600/82/182 materials at STP. STP has no Pressurizer or Steam Generator welds applicable to Code Case N-722-1. For STP the following components apply and are listed with their Item Numbers from the code case:

Item Description Unit 1 Unit 2 Parts No. Total No. Total No.

Examined B15.80 RPV bottom-mounted instrument 58 58 Reactor penetrations Vessel Note: Refer to Appendix A (Unit 1) and Appendix B (Unit 2) for the total number of items tracked under this augmented program.

Method: Visual, VE as specified in Code Case N-722-1. The Visual Examination (VE) performed on Alloy 600/82/182 components for evidence of pressure boundary leakage and corrosion on adjacent ferritic steel components shall consist of the following:

(a) A direct VE of the bare-metal surface performed with the insulation removed. Alternatively, the VE may be performed with insulation in place using remote visual inspection equipment that provides resolution of the component metal surface equivalent to a bare-metal direct VE.

(b) The VE may be performed when the system or component is depressurized.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 51 of 188 (c) The direct VE shall be performed at a distance not greater than 4 ft from the component and with a demonstrated illumination level sufficient to allow resolution of lower case characters having a height of not greater than 0.105 in.

Industry Code or Standards: ASME Code Section XI, 2013 Edition.

Frequency: Table 1 of Code Case N-722-1 provides the frequency for the Visual, VE per each Item Number. B15.80 is required to be examined every other refueling outage.

Acceptance Criteria or Standard: The acceptance standard for the Visual, VE is contained in IWB-3522 of Section XI as listed in Table 1 of Code Case N-722-1 and is to be applied subject to the conditions in 10 CFR 50.55a(g)(6)(ii)(E)(2), (3), and (4) as identified below:

10 CFR 50.55a(g)(6)(ii)(E)(2) If a visual examination determines that leakage is occurring from a specific item listed in Table 1 of ASME Code Case N-722-1 that is not exempted by the ASME Code Section XI, IWB-1220(b)(1), additional action must be performed to characterize the location, orientation, and length of a crack or cracks in Alloy 600 nozzle wrought material and location, orientation, and length of crack or cracks in Alloy 82/182 butt welds. Alternatively, licensees may replace the Alloy 600/82/182 materials in all the components under the item number of the leaking component.

10 CFR 50.55a(g)(6)(ii)(E)(3) If the actions in paragraph (g)(6)(ii)(E)(2) of this section determine that a flaw is circumferentially oriented and potentially a result of primary water stress corrosion cracking, licensees must perform non-visual NDE inspections of components that fall under that ASME Code Case N-722-1 item number. The number of components inspected must be equal or exceed the number of components found to be leaking under that item number. If circumferential cracking is identified in the sample, non-visual NDE must be performed in the remaining components under that item number.

10 CFR 50.55a(g)(6)(ii)(E)(4) If ultrasonic examinations of butt welds are used to meet the NDE requirements in paragraphs (g)(6)(ii)(2) or (3) of this section, they must be performed using the appropriate supplement of Section XI, Appendix VIII, of the ASME BPV Code.

Regulatory Bases: 10 CFR 50.55a(g)(6)(ii)(E)(1) All licensees of pressurized water reactors must augment their inservice inspection program by implementing ASME Code Case N-722-1, subject to the conditions specified in paragraphs (g)(6)(ii)(E)(2) through (4) of this section. The inspection requirements of ASME Code Case N-722-1 do not apply to components with pressure retaining welds fabricate with Alloy 600/82/182 materials that have been mitigated by weld overlay or stress improvement.

5.1.2 Augmented ISI Requirements per ASME BPV Code Case N-729 Reactor Vessel Head Inspections

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 52 of 188 Source Documents: 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.

Commitment No.: None, NRC Mandatory per 10 CFR 50.55a(g)(6)(ii)(D)(1).

Associated Documents: None, Conditions in 10 CFR 50.55a(g)(6)(ii)(D)(2) through (8).

Purpose:

The application of ASME Code Case N-729-1 was originally deemed necessary by the NRC because the inspections required by the 2004 Edition of the ASME Code,Section XI were not written to address degradation of the RPV upper head penetration nozzles and associated welds by Primary Water Stress Corrosion Cracking (PWSCC). Because this same situation exists with the use of the 2013 Edition of ASME Code,Section XI, which is now the required Code of Record for this ISI Program, the safety consequences of inadequate inspections are still a NRC concern. The NRC has now updated the requirements to mandate the use of ASME Code Case N-729-6 to continue to address their concern and to maintain an effective long-term inspection program for the RPV upper head penetration nozzles and associated welds in pressurized water reactors.

Scope: The RPV Head Outside Diameter (OD) Surface and the RPV Head Penetrations. STP has replaced their Unit 1 RPV head in October 2009 and Unit 2 in April 2010 so the applicable Item Nos. from Table 1 of Code Case N-729-6 are B4.30 and B4.40.

Item Parts Examined Unit 1 Unit 2 No. Total No. Total No.

B4.30 Head with nozzles and partial 68 68 penetration welds of PWSCC resistant materials B4.40 Nozzles and partial penetration 64 64 welds of PWSCC resistant materials in head.

Note: Refer to Appendix A (Unit 1) and Appendix B (Unit 2) for the total number of items tracked under this augmented program.

Method: Visual VE, Volumetric and/or Surface as identified in Table 1 of Code Case N-729-6.

10 CFR 50.55a(g)(6)(ii)(D)(5) Peening This condition is not applicable to STP.

10 CFR 50.55a(g)(6)(ii)(D)(6) Baseline Examinations. This condition is not applicable to STP.

10 CFR 50.55a(g)(6)(ii)(D)(7) Sister Plants. This condition states that Note 10 of Code Case N-729-6 shall not be implemented without NRCs approval. This condition is not applicable to STP.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 53 of 188 10 CFR 50.55a(g)(6)(ii)(D)(8) Volumetric Leak Path In lieu of paragraph 3200(b) requirement for a surface examination of the partial penetration weld, a volumetric leak path assessment of the nozzle may be performed in accordance with Note 6 of Table 1 of N-729-6. STP will consider this alternative.

Industry Code or Standards: ASME Code Section XI, 2013 Edition.

Frequency: Table 1 of Code Case N-729-6 provides the frequency for the Visual VE, Volumetric and/or Surface examinations with the implementation of the following NRC conditions.

10 CFR 50.55a(g)(6)(ii)(D)(3) Bare metal visual frequency. This condition only applies to Item B4.10 which is not applicable to STP.

Acceptance Criteria or Standard: Code Case N-729-6, -3000 Acceptance Standards including the following conditions.

10 CFR 50.55a(g)(6)(ii)(D)(2) Appendix I use. If STP uses Appendix I of ASME BPV Code Case N-729-4 Section I-3000 will be implemented to define an alternative examination area or volume.

10 CFR 50.55a(g)(6)(ii)(D)(4) Surface exam acceptance criteria. In addition to the requirements of Paragraph -3132.1(b) of ASME BPV Code Case N-729-6, a component whose surface examination detects rounded indications greater than allowed in Paragraph NB-5352 in size on the partial-penetration or associated fillet weld shall be classified as having an unacceptable indication and corrected in accordance with the provisions of paragraph -3132.2 of ASME BPV Code Case N-729-6.

Regulatory Bases: 10 CFR 50.55a(g)(6)(ii)(D)(1) Implementation. Holders of operating licenses or combined licenses for pressurized-water reactors as of or after June 3, 2020, shall implement the requirements of ASME BPV Code Case N-729-6 instead of ASME BPV Code Case N-729-4, subject to the conditions specified in paragraphs (g)(6)(ii)(D)(2) through (8) of this section, by no later than one year after June 3, 2020. All previous NRC-approved alternatives from the requirements of paragraph (g)(6)(ii)(D) of this section remain valid.

5.1.3 Augmented ISI Requirements per ASME BPV Code Case N-770 Examination Requirements for Class 1 Piping and Nozzle Dissimilar Metal Butt Welds Source Documents: ASME Code Case N-770-5 Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities,Section XI, Division 1.

Commitment No.: None, NRC Mandatory per 10 CFR 50.55a(g)(6)(ii)(F)(1).

Associated Documents: None, Conditions in 10 CFR 50.55a(g)(6)(ii)(F)(2)(i), (F)(2)(iii) through (v), (4),

(6), and (13) currently apply at STP and conditions in (F)(2)(ii), (5), (7), (8), (9), (10), (12), (14), (15),

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 54 of 188 and (16) may apply if the scope of these conditions becomes applicable at STP during the Fourth Ten Year ISI Interval.

Purpose:

Implementation of Code Case N-770-5 is to ensure the structural integrity of Alloy 82/182 butt welds. Code Case N-770-5 addresses degradation of Alloy 82/182 butt welds by PWSCC, and the safety consequences of inadequate inspection can be significant. This degradation mechanism increases the probability of a loss of coolant accident.

Scope: Class 1 PWR piping and vessel nozzle butt welds fabricated with Alloy 82/182 materials, with or without application of mitigation activities.

Unit 1 Parts Examined Item Weld IDs No.

Uncracked butt weld mitigated D RPV1-N1ASE, RPV1-N1BSE, RPV1-with stress improvement (Hot N1CSE, RPV1-N1DSE Legs)

Uncracked butt weld mitigated D RPV1-N2ASE, RPV1-N2BSE, RPV1-with stress improvement (Cold N2CSE, RPV1-N2DSE Legs)

Cracked butt weld reinforced by F-1 PRZ-1-N1-SE-WOL, 1-WOL-(N1),

full structural weld overlay of PRZ-1-N2-SE-WOL, 14-WOL-(N2),

Alloy 52/152 material PRZ-1-N3-SE-WOL, 1-WOL-(N3),

PRZ-1-N4A-SE-WOL, 1-WOL-(N4A),

PRZ-1-N4B-SE-WOL, 1-WOL-(N4B),

PRZ-1-N4C-SE-WOL. 1-WOL-(N4C)

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 55 of 188 Unit 2 Parts Examined Item Weld IDs No.

Unmitigated butt weld at Hot Leg D RPV2-N1ASE, RPV2-N1BSE, RPV2-operating temperature <625°F N1CSE,RPV2-N1DSE Unmitigated butt weld at Cold D RPV2-N2ASE, RPV2-N2BSE, RPV2-Leg operating temperature N2CSE, RPV2-N2DSE

>525°F and <580°F Cracked butt weld reinforced by F-1 PRZ-2-N1-SE-WOL, 1-WOL-(N1),

full structural weld overlay of PRZ-2-N2-SE-WOL, 14-WOL-(N2),

Alloy 52/152 material PRZ-2-N3-SE-WOL, 1-WOL-(N3),

PRZ-2-N4A-SE-WOL, 1-WOL-(N4A),

PRZ-2-N4B-SE-WOL, 1-WOL-N4B),

PRZ-2-N4C-SE-WOL, 1-WOL-N4C)

Note: Refer to Appendix A (Unit 1) and Appendix B (Unit 2) for the total number of items tracked under this augmented program.

Method: Visual Examination (VE), Ultrasonic, and/or Surface as identified in Table 1 of Code Case N-770-5.

Industry Code or Standards: ASME Code Section XI, 2013 Edition.

Frequency: Examination frequency is per Table 1 of Code Case N-770-5 depending on the Inspection Item assigned to each weld. The Hot and Cold Leg Nozzle-to-Safe end welds received MSIP in 1RE20 for Unit 1 and 2RE20 for Unit 2.

Acceptance Criteria or Standard: Visual Examination (VE) per -3140 and surface/volumetric (i.e.,

required ultrasonic examination) -3130 of Code Case N-770-5 as modified by 10 CFR 50.55a(g)(6)(ii)(F)(2) through (16) below:

Conditions that currently apply to STP are:

10 CFR 50.55a(g)(6)(ii)(F)(2) Categorization. (i) Welds that have been mitigated by the Mechanical Stress Improvement Process (MSIPTM) may be categorized as Inspection Items D or E, as appropriate, provided the criteria in Appendix I of the code case have been met.

(iii) Other mitigated welds shall be identified as the appropriate inspection item of the NRC authorized alternative or NRC-approved code case for the mitigation type in Regulatory Guide 1.147.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 56 of 188 (v)Paragraph -1100(e) of ASME BPV Code Case N-770-5 shall not be used to exempt welds that rely on Alloy 82/182 for structural integrity from any requirement of this section. STP will not implement -

1100(e).

10 CFR 50.55a(g)(6)(ii)(F)(4) Examination coverage. When implementing Paragraph -2500(a) of ASME BPV Code Case N-770-5, essentially 100 percent of the required volumetric examination coverage shall be obtained, including greater than 90 percent of the volumetric examination coverage for circumferential flaws. Licensees are prohibited from using Paragraphs -2500(c) and -2500(d) of ASME BPV Code Case N-770-5 to meet examination requirements.

10 CFR 50,55a(g)(6)(ii)(F)(6) Reporting requirements. The licensee will promptly notify the NRC regarding any volumetric examination of a mitigated weld that detects growth of existing flaws in the required examination volume that exceed the previous IWB-3600 flaw evaluations, new flaws, or any indication in the weld overlay or excavate and weld repair material characterized as stress corrosion cracking. Additionally, the licensee will submit to the NRC a report summarizing the evaluation, along with inputs, methodologies, assumptions, and causes to the new flaw or flaw growth within 30 days following plant startup.

Conditions that may apply to STP if the scope of these conditions becomes applicable:

10 CFR 50.55a(g)(6)(ii)(F)(2)(ii) Categorization. In order to be categorized as peened welds, in lieu of inspection category L requirements and examinations, welds must meet the performance criteria, qualification and examination requirements as stated by MPR-335, Revision 3-A, with the exception that no plant-specific alternative is required. STP currently has no peened welds where the scope of this condition would apply.

10 CFR 50.55a(g)(6)(ii)(F)(2)(iv) All other butt welds that rely on Alloy 82/182 for structural integrity shall be categorized as Inspection Items A-1, A-2, or B as appropriate. STP does not have any of these welds.

10 CFR 50.55a(g)(6)(ii)(F)(5) Inlay/onlay inspection frequency. All hot-leg operating temperature welds in Inspection Items G, H, J, and K shall be inspected each inspection interval. A 25 percent sample of Inspection Items G, H, J, and K cold-leg operating temperature welds shall be inspected whenever the core barrel is removed (unless it has already been inspected within the past 10 years) or within 20 years, whichever is less. STP currently has no inlay/onlay welds where the scope of this condition would apply.

10 CFR 50.55a(g)(6)(ii)(F)(7) Defining "t". For Inspection Items G, H, J, and K, when applying the acceptance standards of ASME BPV Code,Section XI, IWB-3514, for planar flaws contained within the inlay or onlay, the thickness "t" in IWB-3514 is the thickness of the inlay or onlay. For planar flaws in the balance of the dissimilar metal weld examination volume, the thickness "t" in IWB-3514 is the combined thickness of the inlay or onlay and the dissimilar metal weld. STP currently has no inlay/onlay

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 57 of 188 welds where the scope of this condition would apply.

10 CFR 50.55a(g)(6)(ii)(F)(8) Optimized weld overlay examination. Initial inservice examination of Inspection Item C-2 welds shall be performed between the third refueling outage and no later than 10 years after application of the overlay. STP currently has no optimized weld overlays where the scope of this condition would apply.

10 CFR 50.55a(g)(6)(ii)(F)(9) Deferral. (i) The initial inservice examination of optimized weld overlays

, Inspection Item C-2 shall not be deferred. STP currently has no optimized weld overlays where the scope of this condition would apply.

(ii) Volumetric inspection of peened dissimilar metal butt welds shall not be deferred. STP currently has no peened welds where the scope of this condition would apply.

(iii) For inspection Item M-2, N-1, and N-2 welds, the second required inservice volumetric examination shall not be deferred. STP currently has no excavated weld repairs where the scope of this condition would apply.

10 CFR 50.55a(g)(6)(ii)(F)(10) Examination technique. Note 14(b) of Table 1 and Note (b) of Figure 5(a) of ASME BPV Code Case N-770-5 may only be implemented if the requirements of Note 14(a) of Table 1 of ASME BPV Code Case N-770-5 cannot be met. STP currently has no optimized weld overlays where the scope of this condition would apply.

10 CFR 50.55a(g)(6)(ii)(F)(12) Stress improvement inspection coverage. Under Paragraph I.5.1 (I-5100 in N-770-5), for cast stainless steel items, the required examination volume shall be examined by Appendix VIII procedures to the maximum extent practical including 100 percent of the susceptible material volume. STP currently has no welds with stress improvement associated with cast stainless steel where the scope of this condition would apply.

10 CFR 50.55a(g)(6)(ii)(F)(13) Encoded ultrasonic examination. Ultrasonic examinations of nonmitigated or cracked mitigated dissimilar metal butt welds in the reactor coolant pressure boundary must be performed in accordance with the requirements of Table 1 for Inspection Item A-1, A-2, B-1, B-2, E, F-2, J, K, N-1, N-2 and O. Essentially 100 percent of the required inspection volume shall be examined using an encoded method.

10 CFR 50.55a (g)(6)(ii)(F)(14) Excavate and weld repair cold leg. For cold leg temperature M-2, N-1, and N-2 welds, initial volumetric inspection after application of an excavate and weld repair (EWR) shall be performed during the second refueling outage. STP currently has no excavated weld repairs where the scope of this condition would apply.

10 CFR 50.55a(g)(6)(ii)(F)(15) Cracked excavate and weld repair. In lieu of the examination requirements for cracked welds with 360 excavate and weld repairs, Inspection Item N-1 of Table 1, welds shall be examined during the first or second refueling outage following EWR. Examination volumes that

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 58 of 188 show no indication of crack growth or new cracking shall be examined once each inspection interval thereafter. STP currently has no excavated weld repairs where the scope of this condition would apply.

10 CFR 50.55a(g)(6)(ii)(F)(16) Partial arc excavate and weld repair. Inspection Item O cannot be used without NRC review and approval. STP currently has no partial arc excavate and weld repairs where the scope of this condition would apply.

Regulatory Bases: 10 CFR 50.55a(g)(6)(ii)(F) Examination requirements for Class 1 piping and nozzle dissimilar-metal butt welds. (g)(6)(ii)(F)(1) Implementation. Holders of operating licenses or combined licenses for pressurized-water reactors as of or after June 3, 2020, shall implement the requirements of ASME BPV Code Case N-770-5 instead of ASME BPV Code Case N-770-2, subject to the conditions specified in paragraphs (g)(6)(ii)(F)(2) through (16) of this section, by later than one year after June 3, 2020. All NRC authorized alternatives from previous version of paragraph (g)(6)(ii)(F) of this section remain applicable.

5.2 Augmented Examinations for External Commitments This type of augmented examination is conducted to meet a commitment made to a source outside the utility.

Typically these are commitments made to the NRC in response to regulatory documents such as Generic Letters, Bulletins and NUREGs or other Industry Groups such as NEI or MRP.

5.2.1 Reactor Coolant Pump Flywheels Source Documents: Technical Specifications 4.4.10 Reactor Coolant Pump Flywheel Inspection Program.

Commitment No.: None.

Associated Documents: Reactor Coolant Pump (RCP) UFSAR Section 3.12 and NRC Regulatory Guide 1.14 addressed in the UFSAR Table 3.12-1.

Purpose:

The RCP motor flywheels are examined due to a concern about high-energy missiles inside containment that could potentially damage and cause the simultaneous failure of multiple trains of multiple safety-related systems. STP takes partial exception to RG 1.14.

Scope: This program provides for the inspection of each reactor coolant pump flywheel by UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius once every 10 years and shall comply with RG 1.14, Revision 1, August 1975, positions C.4.b (3), (4),

and (5).

Note: Refer to Appendix A (Unit 1) and Appendix B (Unit 2) for the total number of items tracked under this augmented program.

Method: Ultrasonic Examination.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 59 of 188 Industry Code or Standards: ASME Code Section XI, 2013 Edition (For guidance only not a Code required examination).

Frequency: Each RCP Flywheel at least once every 10 years per the Surveillance Frequency Control Program as referenced in Technical Specifications 4.4.10.

Acceptance Criteria or Standard: Any flaws detected during examination shall be forwarded to STP Engineering for resolution.

Regulatory Bases: The regulatory basis for this augmented examination program is per the Technical Specifications Section 4.4.10.

5.2.2 Break Exclusion Zone (BEZ Examinations)

Source Documents: NUREG 0800, Standard Review Plan (SRP) 3.6.1 Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment, 3.6.2 Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping and SRP 6.6 Inservice Inspection of Class 2 and 3 Components, Revision 1 - July 1981, included in the STP UFSAR Sections 3.6.2 and 6.6.8. Condition Report Engineering Evaluation (CREE) 08-6765-3 documents the evaluation and acceptance of the Risk-Informed Inservice Inspection (RI-ISI) Break Exclusion Zone (BEZ) STP Programs which are also referred to as the Break Exclusion Region (BER)

Programs by EPRI and ASME.

Commitment No.: None, NEI 03-08 Mandatory, Needed or Good Practice.

Associated Documents: EPRI Topical Report TR-1006937 Extension of the EPRI Risk-Informed Inservice Inspection (RI-ISI) Methodology to Break Exclusion Region (BER) Programs, Rev. O-A and ASME BPV Code Case N-716-1 Alternative Classification and Examination RequirementsSection XI, Division 1.

Purpose:

Implementation of a RI-ISI Program for BEZ welds using the methodology of EPRI Topical Report TR-1006937 Extension of the EPRI Risk-Informed Inservice Inspection (RI-ISI) Methodology to Break Exclusion Region (BER) Programs, Rev. O-A, which also exceeds the requirements of Code Case N-716-1 for the BEZ Main Steam System and Main Feedwater System weld selections at STP.

Scope: Includes recommended examination selections at Units 1 and 2 shown in Table 5.2.2-1 Risk Ranking and Element Selection Summary below with 7 welds selected on the Main Steam System (excluding longitudinal seams) and 4 welds selected on the Main Feedwater System all outside containment in the Isolation Valve Compartments (IVCs). These BEZ welds are categorized as Low Safety Significant (LSS) with a low risk determination and do NOT require volumetric examination per Code Case N-716-1, but are recommended examinations to be performed based on the VENDREC File#

D070907036 detailed below. The recommended 10% weld examination selection criteria is comparable

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 60 of 188 with the RI-ISI examination selection requirements in Code Case N-716-1, which are being implemented for the Fourth Ten-Year Inspection Interval at STP.

However, in paragraph 4(b)(5) of Code Case N-716-1 it states that For each system within the break exclusion region, at least 10% of the piping welds shall be selected, where the term piping welds applies to only High Safety Significant (HSS) welds, but at STP these welds are all LSS.

Understanding this requirement above does not apply to LSS welds, STP has decided to perform the recommended examination selections as shown in Table 5.2.2-1. These recommended selections are supported by the use of the RI-ISI Methodology that is documented in the South Texas Project Electric Generating Station Units 1 and 2 BER Evaluation - Vendor Record Type: VENDREC File#

D070907036, dated, October 18, 2007, and the fact that the STP UFSAR Section 6.6.8 states All welds located in appropriate high-energy piping for which no breaks are postulated will be examined using volumetric examination techniques. This examination will apply to all piping circumferential butt welds and longitudinal butt welds. Under this augmented scope, 100 percent volumetric examination will be performed during the PSI and once in each 10-year interval or as required per the Risk-Informed process for piping outlined in EPRI Topical Report TR-1006937, which was implemented using a recommended 10% examination selection per VENDREC File# D070907036 as referenced above.

Additionally, piping longitudinal butt or seam welds are only required to be examined at the intersection of circumferential welds as depicted in the figures of Section XI, 2013 Edition that are required to be used in Code Case N-716-1.

Table 5.2.2-1 Risk Ranking and Element Summary Unit 1 Unit 2 System RC DM Weld Group Welds Selected Welds Selected 30-inch 36 4 36 4 MS - Main 16-inch 9 1 9 1 6 None Steam 6-inch 20 2 20 2 Long-seam 48 0 48 0 FW - Main 6 None 18-inch 36 4 38 4 Feedwater RC = Risk Category DM = Degradation Mechanism Note: Refer to Appendix A (Unit 1) and Appendix B (Unit 2) for the total number of items tracked under this augmented program.

Method: Volumetric Examination > 4NPS.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 61 of 188 Industry Code or Standards: ASME Code Section XI, 2013 Edition.

Frequency: Each Inspection Interval as defined by Section XI, IWA-2430.

Acceptance Criteria or Standard: NUREG 0800, SRP 6.6,Section XI, IWC-3000.

Regulatory Bases: NUREG 0800, SRP 3.6.1, 3.6.2, and 6.6, Revision 1.

5.2.3 MRP-146 Examinations Source Documents: MRP-146 Rev. 2, Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines.

Commitment No.: None, NEI 03-08 Mandatory, Needed or Good Practice.

Associated Documents: NEI 03-08 Guideline for the Management of Material Issues, Reference STP Procedure Reactor Coolant System Material Management Program (0PGP04-ZA-0013).

Purpose:

The purpose of this augmented examination is to perform Ultrasonic Examination (UT) of portions of piping that were assessed to possibly be susceptible to thermal fatigue in normally stagnant, non-isolable RCS branch lines.

Scope: Components in normally stagnant non-isolable Reactor Coolant System branch lines that are susceptible to thermal fatigue.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 62 of 188 Unit 1 Summary No. Comp. Component Scheduling Notes ID Description 2 Pipe-Elbow Examine Every Outage 1-WD-105260 2 Pipe-Elbow Examine Every Outage 1-WD-105620 3 Elbow-Pipe Examine Every Outage 1-WD-105630 1 Branch 2 Drain Line on Bottom of Intermediate 31 1-WD-108400 Connection to Examination of 2-RC-1419-BB1 Weld is Bent Pipe performed during 2-RC-1418-BB1 Weld 1 Examination. Scheduled Every Outage 1 2-In. Branch Scheduled Every Outage 1-WD-109000 Connection to Bent Pipe 1 Branch Scheduled Every Outage 1-WD-110200 Connection to Bent Pipe Unit 2 Summary No. Comp. Component Scheduling Notes ID Description 2 Pipe-Elbow Examine Every Outage 2-WD-105260 2 Pipe-Elbow Examine Every Outage 2-WD-105620 3 Elbow-Pipe Examine Every Outage 2-WD-105630 3 RCS Branch 2 Drain Line on Bottom of Intermediate 31 2-WD-108420 Connection Examination of 2-RC-2419-BB1 Weld is Elbow-Pipe performed during 2-RC-2418-BB1 Weld 1 Examination. Scheduled Every Outage

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 63 of 188 Unit 2 Summary No. Comp. Component Scheduling Notes ID Description 3 RCS Branch Scheduled Every Outage 2-WD-109020 Connection Elbow-Pipe 3 RCS Branch Scheduled Every Outage 2-WD-110220 Connection Elbow-Pipe Note: Refer to Appendix A (Unit 1) and Appendix B (Unit 2) for the total number of items tracked under this augmented program.

Method: Volumetric Examination UT.

Industry Code or Standards: ASME Code Section XI, 2013 Edition.

Frequency: As determined through the fatigue management program.

Acceptance Criteria or Standard: As determined through the fatigue management program.

Regulatory Bases: The regulatory basis for this augmented examination program is a Needed requirement of an NEI 03-08 issue program 5.2.4 MRP-192 Examinations Source Documents: MRP-192 Rev. 3 Assessment of RHR Mixing Tee Thermal Fatigue in PWR Plants.

Commitment No.: None, NEI 03-08 Mandatory, Needed or Good Practice.

Associated Documents: NEI 03-08 Guideline for the Management of Material Issues, that cites MRP-192 Rev. 2 as an issue program.

Purpose:

To provide Management of Thermal Stratification Fatigue Mixing Tee Examination Volumes.

Scope: Provides examination volume inspection requirements for locations determined to be potentially subject to RHR Mixing Tee Thermal Fatigue.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 64 of 188 Unit 1 Summary Comp. Component Scheduling Notes No. ID Description 5 Tee to Pipe Mixing Tee - Inspect as required 1-WD-611640 based on run time.

Unit 2 Summary Comp. Component Scheduling Notes No. ID Description 5 Tee to Pipe Mixing Tee - Inspect as required 2-WD-611640 based on run time.

Note: Refer to Appendix A (Unit 1) and Appendix B (Unit 2) for the total number of items tracked under this augmented program.

Method: Volumetric Examination UT.

Industry Code or Standards: ASME Code Section XI, 2013 Edition Frequency: Based on the Run Time.

Acceptance Criteria or Standard: As determined through the fatigue management program.

Regulatory Bases: The regulatory basis for this augmented examination program is a Good Practice requirement of an NEI 03-08 issue program.

5.2.5 NSAL 06-8: Pressurizer Heater Sleeves Source Documents: Westinghouse Nuclear Advisory Letter, NSAL-06-8 Commitment No.: None Associated Documents: TPNS: 1R111NPZ101A

Purpose:

Bare Metal Visual examination looking for boric acid deposits Scope: Pressurizer Heater Sleeves

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 65 of 188 Unit 1 Summary Comp. ID Component Scheduling Notes No. Description 1-A600- PRZ Pressurizer Bare Metal Visual of first row 105500 HEATERS Heater exposed heaters and accessible Sleeves portion of heaters on outer 2 rows.

Ref. Westinghouse NSAL 06-8 Rev.

1 Unit 2 Summary Comp. ID Component Scheduling Notes No. Description 2-A600- PRZ Pressurizer Bare Metal Visual of first row 105500 HEATERS Heater exposed heaters and accessible Sleeves portion of heaters on outer 2 rows.

Ref. Westinghouse NSAL 06-8 Rev.

1 Note: Refer to Appendix A (Unit 1) and Appendix B (Unit 2) for the total number of items tracked under this augmented program.

Method: Bare Metal Visual Examination Industry Code or Standards:

Frequency: Once per Interval Acceptance Criteria or Standard: No identified leakage Regulatory Bases: None 5.2.6 Degradation of Leak Chase Channel Systems Source Documents: 10 CFR 50.55a(b)(2)(ix)(K) Metal Containment Examinations: Eleventh provision Note: The NRC has mandated the implementation of Section XI 2017 Edition for the examination of the Leak Chase Channel Moisture Barriers.

Commitment No.: None

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 66 of 188 Associated Documents: ASME Code Section XI, 2017 Edition, Subsection IWE requirements for Moisture Barriers will be applied in the Fourth Ten-Year Interval5 to the cover plates of the Leak Chase Channel System connections. NRC position on these requirements is now documented per 10 CFR 50.55a(b)(2)(ix)(K).

Purpose:

Recent OE includes several examples of moisture intrusion against portions of the containment liner or vessel through boundaries that are outside of the ASME code boundary. The OE included several instances of issues allowing moisture to intrude into inaccessible areas of leak chase channels as well as at least one instance of moisture intrusion past a concrete to concrete floor interface. To identify possible degradation associated with Leak Chase Channel System connections by the examination of their cover plates that are NOT seal welded.

Scope: There are 163 Leak Chase Channel System cover plates at each STP Unit 1 and Unit 2.

Examination shall include the moisture barrier materials (caulking, gaskets, coatings, etc.) that prevent water from accessing the embedded containment liner with the leak chase channel system.

Note: Refer to Appendix C (Unit 1) and Appendix D (Unit 2) for the total number of items tracked under this augmented program.

Method: General Visual of cover plate of the Leak Chase Channel System. Caps of stub tubes extending to or above the concrete floor interface may be inspected provided the configuration of the cap functions as a moisture barrier. Leak chase channel system closures need not be disassembled for performance of examinations if the moisture barrier material is clearly visible without disassemble, or coatings are intact.

Industry Code or Standards: ASME Code Section XI, 2013 Edition for guidance.

Frequency: General Visual examination once each Inspection period.

Acceptance Criteria or Standard: The closures are acceptable if no damage or degradation exists that would allow intrusion of moisture against inaccessible surfaces of the metal containment shell or liner within the leak chase channel system. Examinations that identify flaws or relevant conditions shall be extended in accordance with paragraph IWE-2430 of the 2017 Edition of Section XI.

Regulatory Bases: 10 CFR 50.55a(b)(2)(ix)(K) 5 STP has decided to name the CISI Interval beginning in year 2020 as the Fourth Interval.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 67 of 188 5.3 Owner Elected Examinations for Internal Commitments This type of augmented examination is conducted to meet a commitment made internally at the plant.

These typically involve examinations resulting from Condition Reports or similar documents that identify conditions in the plant that warrant monitoring, but are outside the scope of ASME Section XI. STP currently has no Owner Elected Examinations.

5.4 License Renewal Examinations for Aging Management Commitments This type of augmented examination is conducted to ensure the integrity of components during the renewed license Period of Extended Operation (PEO). This type of augmented examination typically involves components or criteria that are beyond those of ASME Section XI, but in some cases may supplement existing Code or regulatory requirements. The associated documents detailing these requirements for the ISI and CISI Programs are:

LRI.19A.1.1 ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD LRI.19A.1.27 ASME Section XI, Subsection IWE LRI.19A.1.28 ASME Section XI, Subsection IWL LRI.19A.1.29 ASME Section XI, Subsection IWF 5.4.6 License Renewal Commitment 42 - ISI Program: Examination of RPV Stud Insert #30 - Unit 2 Only Source Documents: UFSAR, Chapter 19: License Renewal, Programs that Manage the Effects of Aging on structures and Components within the Scope of License Renewal, and Table 19A.4-1, License Renewal Commitments.

Commitment No.: Item # 42, License Renewal Section, B2.1.3 as described in SER Section 3.0.3.2.2.

Associated Documents: Generic Aging Lessons Learned (GALL Report - Final Report (NUREG-1801-2, Revision 2)Section XI.M3, Reactor Head Closure Studs. and CR-12-15170.

Purpose:

This augmented program is to perform a remote VT-1 of Stud Insert #30 (Unit 2 only) concurrent with the volumetric examination once every 10 years to verify no additional loss of bearing surface area.

This program was started in the (Third Interval) 10-year ASME Section XI inspection interval.

Scope: Stud Insert #30.

Method: Remote Visual, VT-1 concurrent with a Volumetric, UT.

Industry Code or Standards: ASME Code Section XI, 2013 Edition.

Frequency: Once every 10 years.

Acceptance Criteria or Standard: ASME Code Section XI, 2013 Edition Regulatory Bases: License Renewal Commitment 42.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 68 of 188 6.0 ASME Systems & Examination Boundaries 6.1 ASME Class 1, 2 and 3 This section defines those systems that are designated as ASME Class 1, 2, or 3 and provides justification for their inclusion or exclusion within the Ten-Year ISI Program. Several STP systems or portions of systems are excluded from system and component NDE as allowed by Articles IWB-1200, IWC-1200, and IWD-1200. However, these portions of systems are not excluded from the pressure testing requirements of ASME Section XI, except as allowed by IWA-5000, IWB-5000, IWC-5000, and IWD-5000. ASME Section XI defines the inspection requirements for each of the ASME Code Classes within the inspection interval.

The quality group classification system for water, steam, and radioactive waste containing components important to the safety of water-cooled nuclear power plants is established by NRC Regulatory Guide 1.26, in conjunction with 10 CFR 50.55a. Regulatory Guide 1.26, Quality Group Classification and Standards Rev. 3, defines the Quality Group Classification System consisting of four Quality Groups, A through D. Quality Group A is defined as Reactor Coolant Pressure Boundary by 10 CFR 50.2. The definitions of Groups B, C, and D (Class 2, Class 3 and ISI non-classed, respectively) are provided by Regulatory Guide 1.26.

Piping and components subject to inservice inspection are shown on the system Piping and Instrumentation Diagrams listed in Section 2.1. Pursuant to 10 CFR 50.55a, the inservice inspection requirements of the Code have been assigned to these piping lines and components within the constraints of existing plant design.

Per IWA-1400(a) of Section XI, it is the owner's responsibility to determine the appropriate Code Classes for each component and to identify the system boundaries subject to inspection. IWA-1400(a), Endnote 1, states that classification criteria are specified in 10 CFR 50. This reference is actually to Footnote 7 of 10 CFR 50.55a, which refers to Regulatory Guide 1.26, [4.5] and Section 3.2.2 of NUREG-0800, [4.21]. The system classifications for the Inservice Inspection Plan are based on the requirements of 10 CFR 50 and Regulatory Guide 1.26.

  • The Class 1 system boundaries were developed based on the 10 CFR 50.2, Reactor Coolant Pressure Boundary definition.

The component classifications of ASME Code Class 1, 2, or 3 determine the rules and requirements for inspection and define the Section XI examination boundaries. Because early vintage nuclear plants were designed and constructed before Section III of the ASME BPV Code was incorporated into 10 CFR 50.55a, the ASME Section XI Code Classifications for ISI may differ from the original design classifications. Therefore, while the ASME Code Classifications determine the rules for repairs and replacements and the component inspection requirements, repairs and replacements are generally performed to meet the specifications of the original design code.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 69 of 188 In order to avoid confusion between ASME Code Class for design (typically ASME Section III) and ASME Code Class for ISI (ASME Section XI), STP is utilizing ISI Class 1, 2, and 3 terminologies for the application of ASME Section XI ISI requirements.

Components considered to be optionally classified as ASME Code Class may be excluded from the Section XI ISI Program per IWA-1320(e).

System boundary diagrams were developed to identify the ASME Code Class 1, 2, and 3 systems. These systems and components are referred to as ISI Class 1, ISI Class 2 or ISI Class 3 and are subject to the requirements of ASME Section XI, Subsections IWB, IWC, IWD, and IWF.

The ISI of Class 1, 2, and 3 pressure retaining components and their supports which are exempt from examination are those which meet the criteria of ASME Section XI, IWB-1220, IWC-1220 and IWD-1220 and for supports IWF-1230.

6.2 Calibration Standards Whenever possible, ultrasonic (UT) calibration blocks used during the previous examination(s) will be used for the current interval examination. It is recognized that emergent performance-based ultrasonic techniques mandated by the implementation of ASME Section XI, Appendix VIII may require calibration on newly developed UT calibration standard designs. Ultrasonic sensitivity for calibration for the UT examination of piping welds and weld deposited structural weld overlays may be performed using the specialized and/or alternative calibration blocks as required or permitted by Performance Demonstration Initiative (PDI) UT examination procedures. In all cases, the STP Lead Level II or Level III individual will specify and/or approve the applicable calibration standard(s) for UT examinations. The specific calibration standard used for a scheduled examination will be identified on the IDDEAL examination report.

6.3 Classification and Identification of Components Components subject to test will be classified into Code Examination Categories and tested in accordance with the requirements of Code Tables: IWB-2500-1 (Class 1), IWC-2500-1 (Class 2), IWD-2500-1 (Class 3), IWE-2500-1 (Class MC), IWF-2500-1 (Component Supports), and IWL-2500-1 (Class CC). The classified components are identified, scheduled and tracked in IDDEAL Software database.

Individual examination plans will be issued for each outage for implementation of scheduled examinations and will meet the requirements of the Code. Appendix K identifies outage schedules for the applicable inspection interval.

  • The examination plan identifies components scheduled for examination based on the IDDEAL Software database implementation schedule, Code examination category and item number, examination or test to be performed and extent of examination, identification of drawings, list of examination procedures, and identification of calibration blocks [IWA-2420(b)].

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 70 of 188 CREE 08-9676-16 determined Inservice Inspection boundary table (line list) exemption criteria for the Component Support and Welds third interval inspection activities.

  • Welds/component supports or portions of welds/component supports that are inaccessible due to being encased in concrete, buried underground, located inside a penetration, or encapsulated by guard piping are exempt from examination. [IWB-1220(d), IWC-1223, IWD-1220(e), IWF-1230]Component supports exempt from examination requirements are those connected to piping and other items exempted from volumetric, surface, VT-1 or VT-3 visual examination by IWB-1220, IWC-1220, IWD-1220, and IWE-1220, as described in IWF-1230.

7.0 Application Criteria and Code Compliance 7.1 ASME Section XI The following provides a summary of the application of the ASME Code,Section XI, requirements used for the STP Ten-Year Interval to be applied per this ISI/CISI Program Plan. Class 1, 2, and 3 components and their component supports were selected for examination per the requirements of ASME Section XI, Tables IWB-2500-1, IWC-2500-1, IWD-2500-1 and IWF-2500-1, respectively. Class MC and Metallic Liners of concrete containments and their welded attachments were selected for examination per the requirements of ASME Section XI, Tables IWE-2500-1 and IWL-2500-1 respectively. The application and distribution of examinations for this interval is based upon Articles IWB-2411, IWC-2411, IWD-2411, IWE-2411, IWF-2410, and IWL-2400 of Section XI. Augmented Examinations will align with the ASME Section XI interval unless stated otherwise in the document that governs the specific criteria for the examinations. There may be instances when Augmented Examinations and ASME Section XI examinations coincide for the same component. Examinations should be performed concurrently to optimize examination resources to the extent practical.

If there are less than three items or welds to be examined in an Examination Category, the items or welds may be examined in any two periods or in any one period if there is only one item or weld in lieu of the percentage requirements in IWB-2411-1, IWC-2411-1, IWD-2411-1, IWE-2411-1, or IWF-2410-1.

The results of this application are summarized by ASME Category and Item number and are contained within Appendices A, B, C, D, E, and F. The items in these Appendices only contain those ASME Item Numbers that are relevant to STP Units 1 or 2.

All the Examination Category selections that have been made in this section meet the requirements of ASME Section XI, and/or as specifically applicable to those requirements applied from Code Cases, Relief Requests, or rules contained in 10 CFR 50.55a.

7.2 EXAMINATION CATEGORY B-A - PRESSURE RETAINING WELDS IN REACTOR VESSEL The Reactor Vessel examinations are scheduled on the reactor pressure vessel to meet ASME Section XI as required by 10 CFR 50.55a. The RPV shell examinations are conducted from the internal surfaces utilizing remote examination equipment and techniques. Those areas of the bottom head which are obstructed from a complete Inside Diameter (ID) examination may be supplemented from the OD as practical.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 71 of 188 Examination Category B-A weld examinations were deferred under RR-ENG-3-14 on July 24, 2018 (ML18177A425) from the third interval to the fourth interval ending with Unit 1 to August 20, 2027 and Unit 2 to December 15, 2028. This means that the Category B-A Examinations are required to be completed prior to these dates. This includes the following welds:

Examination Item Unit 1 Unit 2 Description Category Number Weld ID Weld ID RPV1-103-121 RPV2-103-121 Circumferential Shell Welds B-A B1.11 RPV1-101-171 RPV2-101-171 RPV1-101-141 RPV2-101-141 RPV1-101-122A RPV2-101-122A Longitudinal Shell Welds thru -122C thru -122C RPV1-101-124A RPV2-101-124A B-A B1.12 thru -124C thru -124C RPV1-101-142A RPV2-101-142A thru -142C thru -142C Circumferential Head Welds B-A B1.21 RPV1-102-151 RPV2-102-151 RPV1-101-154A RPV2-101-154A Meridional Head Welds B-A B1.22 thru -154D thru -154D B-A B1.30 RPV1-101-121 RPV2-101-121 Shell-to-Flange Weld STP has elected to perform the examinations for Unit 1 in 1RE26 scheduled in the Spring of 2026 and for Unit 2 in 2RE25 which is scheduled in the Spring of 2027.

Item No. B1.40 Head-to-Flange weld is no longer applicable to STP as the replacement heads do not contain this weld.

7.3 EXAMINATION CATEGORY B-B - PRESSURE RETAINING WELDS IN VESSELS OTHER THAN REACTOR VESSELS ASME Section XI, Examination Category B-B requires that pressurizer welds and primary side steam generator welds be examined during the inspection interval. The examination may be limited to one vessel among the group of vessels performing a similar function.

PRESSURIZER ASME Section XI requires examination of both shell-to-head welds and one foot of one intersecting longitudinal weld per head. Both shell-to-head welds are selected meeting the 100% requirement. There is one longitudinal weld to each shell-to-head weld. One foot of these intersection welds are selected for examination.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 72 of 188 STEAM GENERATORS There is one Class 1 Examination Category B-B, Channel Head to Tubeplate weld on each of the four steam generators (S/G). Category B-B, Note (1) allows the examination be limited to one vessel among a group of vessels performing a similar function or 25%. One of the Channel Head to Tubeplate welds is selected for examination, thus meeting the one vessel among a group of vessels performing a similar function or 25% requirement.

7.4 EXAMINATION CATEGORY B-D - FULL PENETRATION WELDED NOZZLES IN VESSELS This category applies to the reactor vessel, pressurizer, and steam generators. ASME Section XI does not allow the deferral of these examinations, except for nozzle to reactor vessel welds and inside radius sections.

Table IWB-2500-1, Category B-D, Note (3), allows partial deferral if the nozzle weld is examined by the straight beam ultrasonic method from inside the nozzle bore, the remaining examinations required from the shell inside diameter may be performed at or near the end of the interval.

For the RPV, Examination Category B-D weld examinations were deferred under RR-ENG-3-14 on July 24, 2018 (ML18177A425) from the third interval to the fourth interval ending with Unit 1 to August 20, 2027 and Unit 2 to December 15, 2028. This includes the following welds:

Examination Item Unit 1 Unit 2 Description Category Number Weld ID Weld ID RPV1-105-121A RPV2-105-121A B-D B3.90 Inlet Nozzle-to-Shell Weld thru -121D thru -121D RPV1-107-121A RPV2-107-121A B-D B3.90 Outlet Nozzle-to-Shell Weld thru -121D thru -121D RPV1-N2AIR thru RPV2-N2AIR thru B-D B3.100 Inlet Nozzle Inner Radii RPV1-N2DIR RPV2-N2DIR RPV1-N1AIR thru RPV2-N1AIR thru B-D B3.100 Outlet Nozzle Inner Radii RPV1-N1DIR RPV2-N1DIR The Reactor Vessel Nozzle Inner Radii will be examined using the Visual, VT-1 Examination per Code Case N-648-2. The volumetric examination will be performed with the reduced volume as identified in Code Case N-613-2.

The Replacement Steam Generators do not have any Nozzle-to-Vessel Welds. The Pressurizer Nozzle-to-Vessel Welds will be 100% examined during the interval.

7.5 EXAMINATION CATEGORY B-F - PRESSURE RETAINING DISSIMILAR METAL WELDS IN VESSEL NOZZLES This category addresses Nozzle-to-Safe End Welds and Piping Welds. STP is using Code Case N-716-1 to implement a RI-ISI program. All Examination Category B-F Welds have been re-categorized as R-A welds

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 73 of 188 in accordance with Code Case N-716-1. Therefore no examinations will be performed per Examination Category B-F.

7.6 EXAMINATION CATEGORY B-G PRESSURE RETAINING BOLTING, GREATER THAN 2 in.

(50 mm) IN DIAMETER The RV Studs, Nuts, Washers, Threads in Flange, and Bushings are scheduled. Request for Alternative RR-ENG-4-02 is used for the Roto-Lok Bushing which requires a volumetric examination in conjunction with the RPV Threads in Flange examination. For Volumetric examination of Pump Studs, one of four sets of reactor coolant pump studs is selected for volumetric examination. For the visual examination of pump bolting and flange surface, one of the reactor coolant pumps will be examined, only if disassembled. This is the same requirement as for Examination Category B-L-2. All other B-G-1 components are scheduled for examination.

7.7 EXAMINATION CATEGORY B-G PRESSURE RETAINING BOLTING, 2 in. (50 mm) AND LESS IN DIAMETER This category includes pressurizer manway, steam generator manways, piping, reactor coolant pump seal bolting, and valve bolting. Examinations will be conducted as required in Table IWB-2500-1 of ASME Section XI. This bolting will only be examined if associated connections are disassembled.

For components other than piping, bolting examinations will be required only when the component is examined under Examination Category B-B, B-L-2, or B-M-2. STP has grouped B-G-2 bolting in accordance with components examined under Examination Category B-B, B-L-2, or B-M-2.

7.8 EXAMINATION CATEGORY B-J - PRESSURE RETAINING WELDS IN PIPING This category addresses piping welds. STP is utilizing Code Case N-716-1 to implement a RI-ISI program.

All Examination Category B-J Welds have been re-categorized as R-A welds in accordance with Code Case N-716-1. Therefore no examinations will be performed per Examination Category B-J.

7.9 EXAMINATION CATEGORY B-K - WELDED ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES Examination Category B-K of ASME Section XI requires examination of Welded Attachments. For vessel welded attachments, Note (4) allows 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. STP has nine welded attachments on the Pressurizer and no welded attachments on each Reactor Vessel or the Steam Generator. One welded attachment on the Pressurizer is selected for examination or 11% of the welded attachments. The welded attachment selected for examination is the attachment associated with the Support Skirt.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 74 of 188 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. STP does not have any Class 1 piping, pump, or valve welded attachments.

CAUTION Additionally, per 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. These conditions may be identified outside of the normally scheduled examinations of welded attachments within this Examination Category B-K.

7.10 EXAMINATION CATEGORY B-L PUMP CASINGS This category involves reactor coolant pumps and requires visual, VT-3 examination on pump internal surfaces when disassembled. The reactor coolant pumps are the only ASME Code Class 1 pumps.

B-L-2 requires examination of one pump in each group of pumps performing similar functions in the system.

However, this examination is only required when a pump is disassembled for maintenance, or repair.

Currently none of the four Reactor Coolant Pump internal surfaces have been selected. This requirement will be met during disassembly for maintenance or repair.

7.11 EXAMINATION CATEGORY B-M VALVE BODIES Examinations will be conducted as required in Table IWB-2500-1. There are thirty-one valves at each Unit within this examination category. The valves are placed into eight groups and are identified in the IDDEAL Software Suite, computer program.

B-M-2 examinations are limited to at least one valve within each group of valves that are of the same size, constructural design, and manufacturing method and that perform similar functions in the system. However, this examination is only required when a valve is disassembled for maintenance, or repair. Currently no valve body internal surfaces have been selected. This requirement will be met during disassembly for maintenance or repair.

7.12 EXAMINATION CATEGORY B-N REACTOR VESSEL INTERIOR These examinations will be conducted each inspection period.

7.13 EXAMINATION CATEGORY B-N WELDED CORE SUPPORT STRUCTURES AND INTERIOR ATTACHMENTS TO REACTOR VESSELS Examination will be conducted during the outage to coincide with the 10-year inspection of the reactor vessel.

STP has no Item No. B13.50 Interior attachments within the beltline region. There are six welded attachments beyond the beltline region which are scheduled.

In addition, Bottom Mounted Instrument (BMI) Penetrations 1 and 46 (Unit 1 only) are scheduled once per interval.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 75 of 188 7.14 EXAMINATION CATEGORY B-N REMOVABLE CORE SUPPORT STRUCTURES Examination will be conducted during the outage to coincide with the 10-year inspection of the reactor vessel.

7.15 EXAMINATION CATEGORY B-O - PRESSURE RETAINING WELDS IN CONTROL ROD DRIVE AND INSTRUMENT NOZZLE HOUSINGS ASME Section XI requires volumetric or surface examination of 10% of peripheral control rod drive housings (B14.20) and in-core instrument housings (B14.21) during the inspection interval.

Item No. B14.20 There are twenty-four peripheral Control Rod Drive Housings (CRDHs) on the reactor vessel head with two welds on each CRDH. To meet the Code requirements three of the CRDHs have been selected for examination, each with two welds for a total of six welds requiring examination. Code Case N-825 will be used as an alternative to determine the numbers of CRDHs to be examined to equal 10% of the combined length of each weld configuration. STP has scheduled six CRDHs (upper and lower welds) to equal the 10%

of the combined length for each weld configuration.

Item No. B14.21 There are four Core Exit Thermocouple Penetrations (CET) and three Internal Disconnect Device Penetrations (IDD) on the reactor vessel head with one weld on each CET and IDD. To meet the Code requirement one of the IDDs have been selected for examination.

7.16 EXAMINATION CATEGORY B-P - ALL PRESSURE RETAINING COMPONENTS The pressure testing program at STP, 0PGP03-ZE-0023, System Pressure Testing Program, [4.14] meets the requirements of ASME Section XI for Class 1 systems.

7.17 EXAMINATION CATEGORY B-Q - STEAM GENERATOR TUBING The Steam Generator Tube inspection program at STP is governed by Plant Technical Specifications, [4.8],

3/4.4.5.

7.18 EXAMINATION CATEGORY C-A - PRESSURE RETAINING WELDS IN PRESSURE VESSELS This category applies to the steam generators (secondary side), and residual heat removal heat exchangers.

STP has developed a Code Case N-716-1 RI-ISI program. The residual heat removal heat exchangers were evaluated as Low Safety Significant (LSS) and therefore no examinations are required. The steam generators were evaluated as High Safety Significant (HSS) and therefore required examinations in accordance with Category C-A. The Extent of Examination in Table IWC-2500-1, Examination Category C-A only requires examination of Cylindrical-shell-to-conical-shell-junction welds and shell (or head)-to-flange welds, Head to shell welds and Tubesheet-to-shell welds. Note (4) states: In the case of multiple vessels of similar design, size, and service, the required examinations may be limited to one vessel or distributed among the vessels.

There are two circumferential welds (Item C1.10) on each Steam Generator (Barrel B to Transition Cone and Transition Cone to Barrel H); therefore 2 of 8 welds are selected for examination.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 76 of 188 There is one weld to the top head, Barrel J to Head (Item C1.20) on each Steam Generator; therefore 1 of 4 welds is selected for examination.

There is one Tubeplate to Lower Shell Barrel A. Weld (Item C1.30) on each steam generator. One Weld on one of the steam generators is selected for examination.

7.19 EXAMINATION CATEGORY C-B - PRESSURE RETAINING NOZZLE WELDS IN VESSELS This category applies to steam generators and residual heat removal heat exchangers. STP has developed a Code Case N-716-1 RI-ISI program. The residual heat removal heat exchangers were evaluated as Low Safety Significant (LSS) and therefore no examinations are required. The steam generators were evaluated as High Safety Significant (HSS) and therefore required examinations in accordance with Category C-B.

Note (4) in Table IWC-2500-1, Category C-B, excludes manways and handholes. Note (3) requires that nozzles selected initially for examination shall be reexamined in the same sequence over the service life of the component, to the extent practical. Note (2) allows that in the case of multiple vessels of similar design, size, and service the required examinations may be limited to one vessel or distributed among the vessels.

There is one NPS 18 Feedwater nozzle-to-vessel weld and inner radius section, one NPS 6 Auxiliary Feedwater (there is no inner radius examination required as the nozzle is < NPS 12) and one NPS 30 Main Steam Outlet (nozzle is cast so there is no nozzle-to-vessel weld), but there is an inside radius section on each Steam Generator. Request for Alternative RR-ENG-4-01 was submitted to not perform the Main Steam Nozzle Inner Radius Section. One Feedwater nozzle-to-vessel weld (including inner radius) and one Auxiliary Feedwater nozzle-to-vessel weld on one Steam Generator is selected for examination.

7.20 EXAMINATION CATEGORY C-C - WELDED ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES Examination Category C-C of ASME Section XI requires examination of Welded Attachments. For vessel welded attachments, Note 6 allows 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.

There are four Steam Generators with two welded attachments each. There are three Residual Heat Removal Heat Exchangers with two welded attachment each. Therefore 1 of the welded attachments on one of the Steam Generators and one of the RHR Heat Exchangers is selected for examination, or 2 of 13 welded attachments or 15.3%.

For piping inspection, a sample of 10% of the welded attachments shall be examined.

There are three RHR Pumps with three welded attachments each. Therefore 1 of the welded attachments on one of the RHR Pumps is selected for examination or 1 of 9 welded attachments or 11%.

CAUTION Additionally, per 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. These conditions may be identified outside of the normally scheduled examinations of welded attachments within this Examination Category C-C.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 77 of 188 STP has no valve welded attachments.

7.21 EXAMINATION CATEGORY C-F PRESSURE RETAINING WELDS IN AUSTENITIC STAINLESS STEEL OR HIGH ALLOY PIPING This category addresses Class 2 piping welds. STP has developed a Code Case N-716-1 RI-ISI program.

Examination Category C-F-1 and these welds have been re-categorized as R-A welds in accordance with Code Case N-716-1. Therefore no examinations will be performed per Examination Category C-F-1.

7.22 EXAMINATION CATEGORY C-F PRESSURE RETAINING WELDS IN CARBON OR LOW ALLOY STEEL PIPING This category addresses Class 2 piping welds. STP has developed a Code Case N-716-1 RI-ISI program.

Examination Category C-F-2 and these welds have been re-categorized as R-A welds in accordance with Code Case N-716-1. Therefore no examinations will be performed per Examination Category C-F-2.

7.23 EXAMINATION CATEGORY C-H - ALL PRESSURE RETAINING COMPONENTS The pressure testing program at 0PGP03-ZE-0023, System Pressure Testing Program, [4.14] meets the requirements of ASME Section XI for Class 2 systems.

7.24 EXAMINATION CATEGORY D-A - WELDED ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES Examination Category D-A of ASME Section XI, requires examination of Welded Attachments.

Unit 1 There are three Cooling Water Heat Exchangers with one welded attachment each, one Cooling Water Surge Tanks with one welded attachment, and one Essential Cooling Water Self Clean Strainer with one welded attachment. One welded attachment on each of the groups of vessels is selected for examination or 3 of 5 or 60%.

Unit 2 There is one Cooling Water Surge Tank and one Essential Cooling Water Self Clean Strainer with one welded attachment each. The welded attachment on each is selected for examination.

Units 1 and 2 For piping, inspections of 10% of the total population of welded attachments are required and have been selected. The selections are proportional to the total number of nonexempt welded attachments in each system. - STP has no pump or valve welded attachments.

CAUTION Additionally, per 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. These conditions may be identified outside of the normally scheduled examinations of welded attachments within this Examination Category D-A.

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 78 of 188 7.25 EXAMINATION CATEGORY D-B - ALL PRESSURE RETAINING COMPONENTS The pressure testing program at 0PGP03-ZE-0023, System Pressure Testing Program, [4.14] meets the requirements of ASME Section XI for Class 3 systems.

7.26 EXAMINATION CATEGORY E-A - CONTAINMENT SURFACES Examination Category E-A of ASME Section XI requires 100% of the accessible surface areas of the containment liner to be examined with a General Visual examination each inspection period. The examination shall include all accessible interior and exterior surfaces of Class MC components, parts, and appurtenances. In addition, the moisture barriers shall be examined with a General Visual examination each inspection period. The moisture barrier materials are those intended to prevent intrusion of moisture against inaccessible areas of the pressure retaining shell or liner.

7.27 EXAMINATION CATEGORY E-C - CONTAINMENT SURFACES REQUIRING AUGMENTED EXAMINATION Examination Category E-C of ASME Section XI requires those surface areas subject to accelerated degradation and aging to be examined with a Visual VT-1 examination or Ultrasonic Thickness examination once per inspection period. STP currently does not have any areas in this examination category.

7.28 EXAMINATION CATEGORY F-A - SUPPORTS Examination Category F-A of ASME Section XI requires 25% of Class 1 Piping Supports, 15% of Class 2 Piping Supports, and 10% of Class 3 Piping Supports to be examined during the inspection interval. 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. The supports have been separated by type as defined in Note (1) to Examination Category F-A. This type has been added to the Item Number to clearly identify each support by type. Twenty-five percent (25%) of the Class 1 supports have been selected and are prorated by type and system. Fifteen percent (15%) of the Class 2 supports have been selected and are prorated by type and system. Ten percent (10%) of the Class 3 supports have been selected and are prorated by type and system.

Support Types A = One Directional B = Multi-Directional C = Thermal Movement For supports, other than piping supports, the components have been scheduled as follows:

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 79 of 188 Table IWF-2500-1 Note (5) requires only one component of multiple components of similar design, function, and service, to be scheduled for inspection.

84 of 225 non-piping supports are selected for examination or 37.3% of all non-piping supports.

7.29 EXAMINATION CATEGORY L-A - CONCRETE SURFACES Examination Category L-A of ASME Section XI requires those accessible concrete surface areas to be examined with a General Visual once every 5 years. The entire accessible concrete surface of the concrete containment is scheduled every 5 years. If there are any suspect areas, these are examined with a Detailed Visual every inspection interval. STP currently does not have any suspect areas.

Per IWL-2512 the Responsible Engineer shall evaluate suspect conditions and shall specify the type and extent of examinations, if any, required to be performed on inaccessible surface areas exempted by IWL-1220(c) and IWL-1220(d). 10 CFR 50.55a(b)(2)(viii) states in part Applicants or licensees applying Subsection IWL, 2007 Edition with the 2009 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1)(ii) of this section, must apply paragraph (b)(2)(viii)(H) and (I) of this section.

10 CFR 50.55a(b)(2)(viii)(H) states For each inaccessible area of concrete identified for evaluation under IWL-2512(a), or identified as susceptible to deterioration under IWL-2512(b), the licensee must provide the applicable information specified in paragraphs (b)(2)(viii)(E)(1), (2), and (3) of this section in the ISI Summary Report required by IWA-6000.

10 CFR 50.55a(b)(2)(viii)(I) states During the period of extended operation of a renewed license under part 54 of this chapter, the licensee must perform the technical evaluation under IWL-2512(b) of inaccessible below-grade concrete surfaces exposed to foundation soil, backfill, or groundwater at periodic intervals not to exceed 5 years. In addition, the licensee must examine representative samples of the exposed portions of the below-grade concrete, when such below-grade concrete is excavated for any reason.

7.30 EXAMINATION CATEGORY L-B - UNBONDED POST TENSIONING SYSTEM Examination Category L-B of ASME Section XI requires for containments with unbonded post-tensioning systems, the concrete surfaces and tendon end anchorage areas shall be examined for corrosion protection medium leakage, and the tendon end caps shall be examined for deformation.

Tendon end caps shall be removed for this examination if there is evidence of tendon end cap deformation.

7.31 EXAMINATION CATEGORY R-A The implementation of a Risked-Informed ISI Program utilizing ASME Code Case N-716-1 has been substituted for the current program for Class 1 and 2 piping (Examination Categories B-F, B-J, C-F-1 and C-F-2).

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 80 of 188 8.0 Inservice Inspection Data Management Software The Inservice Inspection Data Management software is comprised of a series of program modules assembled in a comprehensive software package entitled the Iddeal Software Suite. This software suite is web-based within the STP system and is accessible by any computer.

The Iddeal Software Suite has limited access to protect the contents of the databases. Access to the software is limited through the use of a user-defined password.

There are two version of the Iddeal Software Suite being utilized. The following programs are being used for the version 8 IDDEAL SOFTWARE SUITE:

  • IDDEAL - IDDEAL is used to track and progress completion of outage examinations.

Generates various reports to status examinations.

  • CERTWORKS - Maintains and tracks the personnel certifications of inspectors.
  • EQUIPWORKS - Maintains and tracks the NDE equipment certifications.
  • SNUBWORKS - Used to track all work associated with plant snubbers.

The following modules are being used for the version 9 IDDEAL SOFTWARE SUITE.

  • COMPONENTS - is used to identify all of the components that exist in the plant and being considered for the ISI Program.
  • LIBRARIES - is used to identify all of the requirements that could be applied to the components.
  • PROGRAMS - is used to create and maintain program manuals, scheduling, and completion of examinations for credit to those programs.
  • ACTIVITIES - is used to maintain and track examinations within an outage or other activity.
  • EQUIPMENT - is used to maintain and track the equipment used in performing the examinations (i.e. calibration blocks)

The Programs Module contains the STP information necessary to perform ISI and Augmented Programs.

The Iddeal Software Suite (both versions) houses the information below which meets the requirements of ASME Section XI, IWA-2420(b).

  • Identification of the components selected for examination and test, including successive exams from prior periods;
  • The Code requirements by examination category and item number for each component and the examination or test to be performed and the extent of the examination or test;
  • Identification of drawings showing items that require examination;

STPEGS Units 1 and 2 Inservice Inspection Program Plan Revision 10 Page 81 of 188

  • List of examination procedures;
  • Description of alternative examinations and identification of components to be examined using alternative methods;
  • Identification of calibration blocks used for ultrasonic examination of components.

9.0 Risk-Informed ISI Program STP has initiated a Risk-Informed ISI (RI-ISI) Program in compliance with Code Case N-716-1, approved in Regulatory Guide 1.147 Revision 18 listed in Table 2.2-1. Examination Categories and Item Numbers used for Risk-Informed components are identified in Appendices A and B.

9.1 Periodic Update Examination selections shall be reevaluated on the basis of inspection periods that coincide with the inspection program requirements of IWA-2431. For the inspection program, the third period reevaluation will serve as the subsequent inspection interval reevaluation.

The performance of each inspection period reevaluation may be accelerated or delayed by as much as one year. Each reevaluation shall consider the cumulative effects of previous reevaluations.

The reevaluation shall determine if any changes to the HSS/LSS categorization or examination selections need to be made by evaluation of the following:

(a) Plant design changes (e.g., physical: new piping or equipment installation; programmatic:

power uprating/18 to 24 month fuel cycle; and procedural; operating procedure changes).

(b) Changes in postulated conditions or assumptions (e.g., check valve seat leakage greater than previously assumed).

(c) Examination results (e.g., discovery of leakage or flaws).

(d) Failures in HSS or LSS components (e.g., plant-specific or industry occurrences of through-wall or through-weld leakage, failure due to a new degradation mechanism, or a non-postulated mechanism).

(e) PRA updates that would increase the scope (e.g., new initiating events, new system functions, more detailed model used, and initiating event and data changes).

(f) The impact of (a) through (e) on the change-in-risk evaluation

Page 82 of 188 APPENDIX A INSERVICE INSPECTION

SUMMARY

TABLE - COMPONENT SUPPORTS, STEAM GENERATOR TUBING, SYSTEM PRESSURE TESTING, AND WELD INSPECTIONS - UNIT 1, INTERVAL 4

Page 83 of 188 Appendix A Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 1, Interval 4 Number Number to Required to be Number to Number to be Number of Examination Examined or be Item Examined be Examined Examined in Category Description Exam Method Components in Percentage Scheduled Examined in Number During in First Second Item No. Required During the Third Interval Period Period Interval Period B-A Pressure Retaining Welds in Reactor Vessel Reactor Vessel B-A B1.11 Circumferential Shell Volumetric 3 3 100% 3 0 3 0 Welds Reactor Vessel B-A B1.12 Volumetric 9 9 100% 9 0 9 0 Longitudinal Shell Welds Reactor Vessel B-A B1.21 Circumferential Head Volumetric 1 1 100% 1 0 1 0 Welds Reactor Vessel Meridional B-A B1.22 Volumetric 4 4 100% 4 0 4 0 Head Welds Reactor Vessel Shell-to-B-A B1.30 Volumetric 1 1 100% 1 0 1 0 Flange Weld Category Total 18 18(1) 18 0 18 0 Cumulative Percentage 0% 100% 100%

Note 1: Examination Category B-A weld examinations were deferred under RR-ENG-3-14 to August 20, 2027 (ML18177A425). STP has elected to Notes for Cat. B-A perform the examinations in 1RE26 which is scheduled in the Spring of 2026.

B-B Pressure Retaining Welds in Vessels Other Than Reactor Vessels Pressurizer Shell-to-Head B-B B2.11 Volumetric 2 2 100% 2 1 1 0 Welds Circumferential Pressurizer Shell-to-Head B-B B2.12 Volumetric 2 2 100% 2 1 0 1 Welds Longitudinal Steam Generators (Primary B-B B2.40 Side) Tubesheet-to-Head Volumetric 4 1 25%(1) 1 0 0 1 Weld Category Total 8 5 5 2 1 2

Page 84 of 188 Appendix A Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 1, Interval 4 Number Number to Required to be Number to Number to be Number of Examination Examined or be Item Examined be Examined Examined in Category Description Exam Method Components in Percentage Scheduled Examined in Number During in First Second Item No. Required During the Third Interval Period Period Interval Period Cumulative Percentage 40% 60% 100%

Note 1: The examination may be limited to one vessel among the group of vessels performing a similar function. [Ref. Table IWB- 2500-1, Notes for Cat. B-B Examination Category B-B, Note (1)].

B-D Full Penetration Welded Nozzles in Vessels Reactor Vessel Nozzle-to-B-D B3.90 Volumetric 8 8(1) 100% 8 0 8 0 Vessel Welds Reactor Vessel Nozzle Visual, B-D B3.100 8 8(1) 100% 8 0 8 0 Inside Radius Section VT-1(2)

Pressurizer Nozzle-to-B-D B3.110 Volumetric 6 6 100% 6(3) 3 1 2 Vessel Welds Category Total 22 22 22 3 17 2 Cumulative Percentage(4) 14% 91% 100%

Note 1: Examination Category B-D weld examinations were deferred under RR-ENG-3-14 to August 20, 2027 (ML18177A425). STP has elected to perform the examinations in 1RE26 which is scheduled in the Spring of 2026.

Note 2: Visual, VT-1 Examination as allowed by Code Case N-648-2 with the NRC condition In lieu of a UT examination, licensees may perform a Notes for Cat. B-D VT-1 examination in accordance with the code of record for the Inservice Inspection Program utilizing the allowable flaw length criteria of Table IWB-3512-1 with limiting assumptions on the flaw aspect ratio.

Note 3: Deferral of examination to the end of interval is not permissible.

Note 4: Cumulative Percentage is provided for information as some of these items may be deferred to the end of the interval.

B-G-1 Pressure Retaining Bolting, Greater Than 2 in. (50 mm) in Diameter Reactor Vessel Closure B-G-1 B6.10 Visual, VT-1 36 36 100% 36 0 36 0 Head Nuts Reactor Vessel Closure B-G-1 B6.20 Volumetric(2) 37(3) 36 100%(1) 36 0 36 0 Studs

Page 85 of 188 Appendix A Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 1, Interval 4 Number Number to Required to be Number to Number to be Number of Examination Examined or be Item Examined be Examined Examined in Category Description Exam Method Components in Percentage Scheduled Examined in Number During in First Second Item No. Required During the Third Interval Period Period Interval Period Reactor Vessel Threads in B-G-1 B6.40 Volumetric 36 36 100%(4) 36 0 36 0 Flange Reactor Vessel Closure B-G-1 B6.50 Visual, VT-1 36(5) 36 100% 36 0 36 0 Washers Reactor Vessel Closure B-G-1 B6.50 Volumetric(7) 36 36 100% 36 0 36 0 Bushings B-G-1 B6.180 Pump Bolts and Studs Volumetric(2) 4(8) 1 25%(1)(9) 1 0 0 1 Pumps Flange Surface B-G-1 B6.190 when connection Visual, VT-1 4(6) 1 25%(10) 0 0 0 0 disassembled Category Total 152 146 145 0 144 1 Cumulative Percentage(11) 0% 99.3% 100%

Page 86 of 188 Appendix A Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 1, Interval 4 Number Number to Required to be Number to Number to be Number of Examination Examined or be Item Examined be Examined Examined in Category Description Exam Method Components in Percentage Scheduled Examined in Number During in First Second Item No. Required During the Third Interval Period Period Interval Period Note 1: Bolting may be examined in place under tension, when the connection is disassembled or when the bolting is removed.

Note 2: When bolts or studs are removed for examination, surface examination meeting the acceptance standards of IWB-3515 may be substituted for volumetric examination. [Ref. Table IWB-2500-1, Examination Category B-G-1, Note (7)].

Note 3: There is one spare RPV stud included in the total population but not scheduled.

Note 4: If STP decides to implement Code Case N-864, there would be no examination required.

Notes for Cat.B-G-1 Note 5: There are 36 Closure Washers and 36 Bushings. The Bushings are not required to be examined unless the bolting is removed.

Note 6: Not required unless the connection is disassembled.

Note 7: An Ultrasonic Examination (UT) of the RPV Roto-Lok flange inserts (bushings) in conjunction with the required UT on the RPV Threads in Flange will be performed per Request for Alternative RR-ENG-4-02.

Note 8: Each RCP Bolting (24 ea.) is represented as one record in the database.

Note 9: Volumetric examination of bolting of heat exchangers, pumps, or valves may be conducted on one heat exchanger, one pump, or one valve among a group of heat exchangers, pumps, or valves that are similar in design, type, and function. In addition, when the component to be examined contains a group of bolted connections of similar design and size, such as flanged connections, the examination may be conducted on one bolted connection among the group. [Ref. Table IWB-2500-1, Examination Category B-G-1, Note (3)].

Note 10: Visual examination of bolting for heat exchangers, pumps, and 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. [Ref. Table IWB-2500-1, Examination Category B-G-1, Note (4)].

Note 11: Cumulative Percentage is provided for information as some of these items are not required to be examined unless they are disassembled, and others can be deferred to the end of the interval.

B-G-2 Pressure Retaining Bolting, 2 in. (50 mm) and Less in Diameter Pressurizer Bolts, Studs, B-G-2 B7.20 Visual, VT-1 1 1 100%(1) 0(2) 0 0 0 and Nuts Steam Generators Bolts, B-G-2 B7.30 Visual, VT-1 8 2 25%(1) 0(2) 0 0 0 Studs, and Nuts B7.50 Piping Bolts, Studs, and B-G-2 Visual, VT-1 3 1(3) 33.3%(1) 0 0 0 0 GR.1 Nuts B7.50 Piping Bolts, Studs, and B-G-2 Visual, VT-1 4 1(3) 25%(1) 0 0 0 0 GR.2 Nuts

Page 87 of 188 Appendix A Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 1, Interval 4 Number Number to Required to be Number to Number to be Number of Examination Examined or be Item Examined be Examined Examined in Category Description Exam Method Components in Percentage Scheduled Examined in Number During in First Second Item No. Required During the Third Interval Period Period Interval Period Pumps Bolts, Studs, and B-G-2 B7.60 Visual, VT-1 4 1 25%(1) 0(2) 0 0 0 Nuts B7.70 Valves Bolts, Studs, and B-G-2 Visual, VT-1 3 1 33.3%(1) 0(2)(4) 0 0 0 GR. 1 Nuts B7.70 Valves Bolts, Studs, and B-G-2 Visual, VT-1 6 1 16.6%(1) 0(2)(4) 0 0 0 GR. 2 Nuts B7.70 Valves Bolts, Studs, and B-G-2 Visual, VT-1 3 1 33.3%(1) 0(2)(4) 0 0 0 GR. 3 Nuts B7.70 Valves Bolts, Studs, and B-G-2 Visual, VT-1 3 1 33.3%(1) 0(2)(4) 0 0 0 GR. 4 Nuts B7.70 Valves Bolts, Studs, and B-G-2 Visual, VT-1 6 1 16.6%(1) 0(2)(4) 0 0 0 GR. 5 Nuts B7.70 Valves Bolts, Studs, and B-G-2 Visual, VT-1 3 1 33.3%(1) 0(2)(4) 0 0 0 GR. 6 Nuts B7.70 Valves Bolts, Studs, and B-G-2 Visual, VT-1 3 1 33.3%(1) 0(2)(4) 0 0 0 GR. 7 Nuts B7.70 Valves Bolts, Studs, and B-G-2 Visual, VT-1 3 1 33.3%(1) 0(2)(4) 0 0 0 GR. 8 Nuts Category Total 50 14(1) 0 0 0 0 Cumulative Percentage 0 0% 0% 0%

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

Note 2: For components other than piping, examination of bolting is required only when the component is examined under Examination Category B-A, B-B, B-L-2, or B-M-2. Examination of bolted connection is required only once during the interval. [Ref. Table IWB-2500-1, Examination Notes for Cat.B-G-2 Category B-G-2, Note (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. [Ref. Table IWB-2500-1, Examination Category B-G-2, Note (3)].

Note 4: Only one valve of each group of valves is required as outlined in B-M-2.

Page 88 of 188 Appendix A Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 1, Interval 4 Number Number to Required to be Number to Number to be Number of Examination Examined or be Item Examined be Examined Examined in Category Description Exam Method Components in Percentage Scheduled Examined in Number During in First Second Item No. Required During the Third Interval Period Period Interval Period B-K Welded Attachments for Vessels, Piping, Pumps, and Valves Pressure Vessels Welded B-K B10.10 Surface 9(3) 1 11%(1)(2) 1 1 0 0 Attachments Category Total 9 1 1 1 0 0 Cumulative Percentage 100% 100% 100%

Note 1: 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 shall be an attachment under continuous load during normal system operation, or an attachment subject to a potential intermittent load (seismic, Notes for Cat. B-K water hammer, etc.) during normal system operation if an attachment under continuous load does not exist. The Pressurizer Skirt is selected.

Note 2: There are nine welded attachments on the Pressurizer.

Note 3: 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. [Ref. Table IWB-2500-1, Examination Category B-K, Note (6)].

B-L-2 Pump Casings Pump Casing B-L-2 B12.20 Visual, VT-3 4 1 25%(1)(2) 0 0 0 0 (B-L-2)

Category Total 4 1 0 0 0 0 Cumulative Percentage 0 0% 0% 0%

Note 1: Examinations are limited to at least one pump in each group of pumps performing similar functions in the system.

Notes for Cat. B-L-2 Note 2: Examination is required only when a pump is disassembled for maintenance or repair.

B-M-2 Valve Bodies

Page 89 of 188 Appendix A Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 1, Interval 4 Number Number to Required to be Number to Number to be Number of Examination Examined or be Item Examined be Examined Examined in Category Description Exam Method Components in Percentage Scheduled Examined in Number During in First Second Item No. Required During the Third Interval Period Period Interval Period B12.50 Valve Body, Exceeding B-M-2 Visual, VT-3 3 1 33.3%(1)(2) 0 0 0 0 Gr. 1 NPS 4 (DN 100) (B-M-2)

B12.50 Valve Body, Exceeding B-M-2 Visual, VT-3 6 1 16.6%(1)(2) 0 0 0 0 Gr. 2 NPS 4 (DN 100) (B-M-2)

B12.50 Valve Body, Exceeding B-M-2 Visual, VT-3 3 1 33.3%(1)(2) 0 0 0 0 Gr. 3 NPS 4 (DN 100) (B-M-2)

B12.50 Valve Body, Exceeding B-M-2 Visual, VT-3 3 1 33.3%(1)(2) 0 0 0 0 Gr. 4 NPS 4 (DN 100) (B-M-2)

B12.50 Valve Body, Exceeding B-M-2 Visual, VT-3 6 1 16.6%(1)(2) 0 0 0 0 Gr. 5 NPS 4 (DN 100) (B-M-2)

B12.50 Valve Body, Exceeding B-M-2 Visual, VT-3 3 1 33.3%(1)(2) 0 0 0 0 Gr. 6 NPS 4 (DN 100) (B-M-2)

B12.50 Valve Body, Exceeding B-M-2 Visual, VT-3 3 1 33.3%(1)(2) 0 0 0 0 Gr. 7 NPS 4 (DN 100) (B-M-2)

B12.50 Valve Body, Exceeding B-M-2 Visual, VT-3 3 1 33.3%(1)(2) 0 0 0 0 Gr. 8 NPS 4 (DN 100) (B-M-2)

Category Total 30 8 0 0 0 0 Cumulative Percentage 0 0% 0% 0%

Note 1: Examinations are limited to at least one valve within each group of valves that are of the same size, constructural design, and manufacturing method and that perform similar functions in the system. STP valves are grouped into 8 groups and one valve per group is required, if Notes for Cat. B-M-2 disassembled.

Note 2: Examination is required only when a valve is disassembled for maintenance or repair.

B-N-1 Reactor Vessel Interior Reactor Vessel, Vessel 100% each B-N-1 B13.10 Visual, VT-3 1 3(1)(2) 3 1 1 1 Interior (B-N-1) period Category Total 1 3(1) 3 1 1 1

Page 90 of 188 Appendix A Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 1, Interval 4 Number Number to Required to be Number to Number to be Number of Examination Examined or be Item Examined be Examined Examined in Category Description Exam Method Components in Percentage Scheduled Examined in Number During in First Second Item No. Required During the Third Interval Period Period Interval Period Cumulative Percentage(3) 3 100% 100% 100%

Note 1: Examination of this item number is required each period. Therefore the number required during the interval is three times the total number of components. This is also reflected in the category total.

Notes for Cat B-N-1 Note 2: Areas to be examined shall include the spaces above and below the reactor core that are made accessible for examination by removal of components during normal refueling outages.

Note 3: Cumulative Percentages are provided for information only and are calculated for each period.

B-N-2 Welded Core Support Structures and Interior Attachments to Reactor Vessels Reactor Vessel (PWR)

Interior Attachments B-N-2 B13.60 Visual, VT-3 6 6 100% 6 0 6 0 Beyond Beltline Region (B-N-2)

Reactor Vessel (PWR)

Interior Attachments B-N-2 B13.60 Beyond Beltline Region (B- Visual, VT-3 2 2 100% 2 0 2 0 N-2) BMI Penetrations 1 and 46 Category Total 8 8 100% 8 0 8 0 Cumulative Percentage(1) 0% 100% 100%

Notes for Cat. B-N-2 Note 1: Cumulative Percentage is provided for information only as these items can be deferred to the end of the interval.

B-N-3 Removable Core Support Structures Reactor Vessel (PWR)

B-N-3 B13.70 Core Support Structure Visual, VT-3 36 36 100% 36 0 36 0 (B-N-3)(1)

Category Total 36 36 100% 36 0 36 0

Page 91 of 188 Appendix A Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 1, Interval 4 Number Number to Required to be Number to Number to be Number of Examination Examined or be Item Examined be Examined Examined in Category Description Exam Method Components in Percentage Scheduled Examined in Number During in First Second Item No. Required During the Third Interval Period Period Interval Period Cumulative Percentage(2) 0% 100% 100%

Note 1: The structure shall be removed from the reactor vessel for examination.

Notes for Cat. B-N-3 Note 2: Cumulative Percentage is provided for information only as these items can be deferred to the end of the interval.

B-O Pressure Retaining Welds in Control Rod Drive and Instrument Nozzle Housings Reactor Vessel (PWR)

Volumetric or B-O B14.20 Welds in Control Rod Drive 48(1) 12 25%(2) 12(3) 0 0 12 surface (CRD) Housings Reactor Vessel (PWR) 10% of Welds in IN-Core Volumetric or B-O B14.21 7(4) 1 peripheral ICI 1(4) 0 0 1 Instrumentation Nozzle Surface Housings (ICI) Housing >NPS 2 Category Total 31 13 13 0 0 13 Cumulative Percentage 0% 0% 100%

Note 1: There are 24 peripheral CRDs each with two welds. 10% of 24 peripheral CRDHs is 3.

Note 2: Code Case N-825 will be used for an alternative.

Notes for Cat. B-O Note 3: STP has chosen to examine a total of six CRD Housing welds to equal the combined length of 10% of the CRD housing welds.

Note 4: There are 4 peripheral CET and 3 IDD each with one welds. 10% or one IDD is schedule for examination.

C-A Pressure Retaining Welds in Pressure Vessels Pressure Vessels Shell C-A C1.10 Volumetric(5) 8 2 25%(1)(2) 2 0 2 0 Circumferential Welds Pressure Vessels Head C-A C1.20 Volumetric(5) 4 1 25%(1)(3) 1 1 0 0 Circumferential Welds Pressure Vessels C-A C1.30 Volumetric (5) 4 1 25%(1)(4) 1 0 0 1 Tubesheet-to-Shell Weld

Page 92 of 188 Appendix A Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 1, Interval 4 Number Number to Required to be Number to Number to be Number of Examination Examined or be Item Examined be Examined Examined in Category Description Exam Method Components in Percentage Scheduled Examined in Number During in First Second Item No. Required During the Third Interval Period Period Interval Period Category Total 16 4 4 1 2 1 Cumulative Percentage 25% 75% 100%

Notes for Cat. C-A Note 1: In the case of multiple vessels of similar design, size, and service, the required examinations may be limited to one vessel or distributed among the vessels and includes essentially 100% of the weld length. (Ref. Table IWC-2500-1, Examination Category C-A, Notes 3 & 4).

Note 2: There are two circumferential welds on each Steam Generator (Barrel B to Transition Cone and Transition Cone to Barrel H); therefore 2 of 8 welds are selected for examination. Implementation of Code Case N-716-1 evaluated the Shutdown Heat Exchangers as Low Safety Significant (LSS) therefore no examinations are required.

Note 3: There is one Top Head weld (Barrel J to Head) on each Steam Generator; therefore 1 of 4 welds is selected for examination.

Note 4: There is one tubesheet-to-shell weld on each steam generator. One tubesheet-to-shell weld on one of the steam generators is selected for examination. Implementation of Code Case N-716-1 evaluated the Shutdown Heat Exchangers Low Safety Significant (LSS) therefore no examinations are required.

Note 5: For welds in vessels with nominal wall thickness of 0.2 in. (5 mm) or less, a surface examination may be applied in lieu of a volumetric examination. [Ref. Table IWC-2500-1, Examination Category C-A, Note (2)].

C-B Pressure Retaining Nozzle Welds in Vessels Nozzles Without Reinforcing Plate in Vessels > 1/2 in. (13 mm) Surface and C-B C2.21 8 2 25%(1)(2) 2 0 1 1 Nominal Thickness Nozzle- volumetric to-Shell (Nozzle to Head or Nozzle to Nozzle) Weld Nozzles Without Reinforcing Plate in C-B C2.22 Vessels > 1/2 in. (13 mm) Volumetric 4 1 25%(1)(3) 1 0 1 0 Nominal Thickness Nozzle Inside Radius Section Category Total 12 3 3 0 2 1

Page 93 of 188 Appendix A Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 1, Interval 4 Number Number to Required to be Number to Number to be Number of Examination Examined or be Item Examined be Examined Examined in Category Description Exam Method Components in Percentage Scheduled Examined in Number During in First Second Item No. Required During the Third Interval Period Period Interval Period Cumulative Percentage 0% 66%(4) 100%

Notes for Cat. C-B Note 1: In case of multiple vessels of similar design, size, and service, the required examinations may be limited to one vessel or distributed among the vessels. [Ref. Table IWC-2500-1, Examination Category C-B, Note (2)].

Note 2: There is one Feedwater nozzle and one Auxiliary Feedwater nozzle on each Steam Generator. Therefore, only one Feedwater and one Auxiliary Feedwater nozzle of one Steam Generator is required to be examined, which equals the required examination of 2 of 8 nozzles or 25%. Implementation of Code Case N-716-1 evaluated the Shutdown RHR Heat Exchangers Low Safety Significant (LSS) therefore no examinations are required.

Note 3: There is one Feedwater nozzle inner radius on each Steam Generator; therefore, 1 of 4 inner radii is required to be examined or 25%.

Note 4: After implementation of Code Case N-716-1 which does not require any examinations of the Boron Injection Tanks, Containment Spray, Regenerative Heat Exchangers, and Residual Heat Removal Heat Exchangers, there are only two nozzles in each item number requiring examination. Per IWC-2411(a) If there are less than three items or welds to be examined in Examination Category, the items or welds may be examined in any two periods, or in any one period if there is only one item or weld, in lieu of the percentage requirements of Table IWC-2411-

1. Since only two nozzles are required to be examined (this includes both the nozzle-to-vessel weld and the inner radius section) one is scheduled in the second period and the other is scheduled in the third period.

Note 5: Pending RR-ENG-4-01 C-C Welded Attachments for Vessels, Piping, Pumps, and Valves Pressure Vessels Welded C-C C3.10 Surface 13 2(1) 15.3% 2(4) 1 0 1 Attachments C-C C3.20 Piping Welded Attachments Surface 22 3 10% 3(2)(4) 0 1 2 C-C C3.30 Pump Welded Attachments Surface 9 1 11.1% 1(3)(4) 0 1 0 Category Total 44 5 6 1 2 3 Cumulative Percentage 16.6% 50% 100%

Page 94 of 188 Appendix A Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 1, Interval 4 Number Number to Required to be Number to Number to be Number of Examination Examined or be Item Examined be Examined Examined in Category Description Exam Method Components in Percentage Scheduled Examined in Number During in First Second Item No. Required During the Third Interval Period Period Interval Period Notes for Cat. C-C Note 1: 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. [Ref. Table IWC-2500-1, Examination Category C-C, Note (6)].

Note 2: For piping, pumps, and valves, a sample of 10% of the welded attachments were selected to be examined. [Ref. Table IWC-2500-1 Examination Category C-C, Note (7)].

Note 3: For pumps, a sample of 10% of the welded attachments associated with the component supports selected for examination under IWF-2510 shall be examined. [Ref. Table IWC-2500-1 Examination Category C-C, Note (7)]. There are three RHR Pumps with three welded attachments each; one welded attachment is selected for examination.

Note 4: 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. [Ref. Table IWC-2500-1, Examination Category C-C, Note (5)].

D-A Welded Attachments for Vessels, Piping, Pumps, and Valves Vessel Welded D-A D1.10 Visual, VT-1 5 3 50% 3(1)(2) 1 1 1 Attachments (1)(2)

D-A D1.20 Piping Welded Attachments Visual, VT-1 6 1 10% 1 0 0 1 Category Total 11 4 4 1 1 2 Cumulative Percentage 25% 50% 100%

Notes for Cat. D-A Note 1: Selected samples of welded attachments shall be examined each inspection interval. 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, 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. For welded attachments of piping, pumps, and valves, a 10% sample shall be selected for examination. This percentage sample shall be proportional to the total number of nonexempt welded attachments connected to the piping, pumps and valves in each system subject to examination. [Ref. Table IWD-2500-1, Category D-A, Note (6)].

Note 2: 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. [Ref. Table IWD-2500-1, Examination Category D-A, Note (5)].

F-A Supports

Page 95 of 188 Appendix A Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 1, Interval 4 Number Number to Required to be Number to Number to be Number of Examination Examined or be Item Examined be Examined Examined in Category Description Exam Method Components in Percentage Scheduled Examined in Number During in First Second Item No. Required During the Third Interval Period Period Interval Period Class 1 Piping Supports - (1)

F-A F1.10A Visual, VT-3 1 1 1 0 0 1 One Directional Class 1 Piping Supports - (1)

F-A F1.10B Visual, VT-3 68 17 19 6 7 6 Multi-Directional Class 1 Piping Supports - (1)

F-A F1.10C Visual, VT-3 77 20 20 9 5 6 Thermal Movement Category F-A, Item F1.10 Total 146 38 40(2) 15 12 13 Class 2 Piping Supports - (1)

F-A F1.20A Visual, VT-3 15 3 4 1 0 3 One Directional Class 2 Piping Supports - (1)

F-A F1.20B Visual, VT-3 352 53 55 19 16 20 Multi-Directional Class 2 Piping Supports - (1)

F-A F1.20C Visual, VT-3 361 55 59 15 16 28 Thermal Movement Category F-A, Item F1.20 Total 728 111 1182) 35 32 51 Class 3 Piping Supports - (1)

F-A F1.30A Visual, VT-3 11 2 3 2 0 1 One Directional Class 3 Piping Supports - (1)

F-A F1.30B Visual, VT-3 441 45 47 19 18 10 Multi-Directional Class 3 Piping Supports - (1)

F-A F1.30C Visual, VT-3 461 47 50 16 15 19 Thermal Movement Category F-A, Item F1.30 Total 913 94 100(2) 37 33 30 Supports other than Piping F-A F1.40 Supports (Class 1,2,3, and Visual, VT-3 225 84 37.3% 84 27 27 30 MC) - Equipment Supports Category F-A, Item F1.40 Total 225 84 84(3) 27 27 30 Category Total 2012 327 342(2) 114 104 124 Cumulative Percentage 33.3% 63.7% 100%

Page 96 of 188 Appendix A Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 1, Interval 4 Number Number to Required to be Number to Number to be Number of Examination Examined or be Item Examined be Examined Examined in Category Description Exam Method Components in Percentage Scheduled Examined in Number During in First Second Item No. Required During the Third Interval Period Period Interval Period Notes for Cat. F-A Note 1: The total percentage sample shall 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. [Ref. Table IWF-2500-1, Examination Category F-A, Note (4)].

Note 2: Based on proration by system, type, and function, and engineering judgement, the number of supports scheduled exceeds the number of supports required.

Note 3: 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. [Ref. Table IWF-2500-1, Examination Category F-A, Note (5)].

R-A Risk Informed Piping Welds - Code Case N-716-1 Welds Subject to Thermal R-A R1.11 Volumetric 174 47 27% 47 14 17 16 Fatigue Volumetric 4 0 0% 0 0 0 0 Socket Welds Subject to R-A R1.11S Thermal Fatigue Visual, VT-2 4 0 0% 0 0 0 0 Welds Subject to Thermal R-A R1.11/16 Volumetric 6 2 33.3% 2 1 1 0 Fatigue and IGSCC Welds not Subject to a R-A R1.20 Volumetric 576 32 5.5% 32 8 10 14 Damage Mechanism Welds not Subject to a R-A R1.20S Visual, VT-2 32 0(2) 0% 0 0 0 0 Damage Mechanism Category Total 792 81 81 23 28 30 Cumulative Percentage 28.3% 62.9% 100%

Notes for Cat. R-A Note 1: STP has initiated Risk-Informed ISI (RI-ISI) contained in ASME Code Case N-716-1, approved in Regulatory Guide 1.147 Revision 19 and listed in Table 2.2-1.

Note 2: These welds are identified for information only; the welds are governed by Code Case N-770 and scheduled as such. These welds are examined every refueling outage and therefore not counted in the cumulative percentage.

N-722 Code Case N-722-1 PWR Class 1 Components Containing Alloy 600/82/182(1)

Page 97 of 188 Appendix A Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 1, Interval 4 Number Number to Required to be Number to Number to be Number of Examination Examined or be Item Examined be Examined Examined in Category Description Exam Method Components in Percentage Scheduled Examined in Number During in First Second Item No. Required During the Third Interval Period Period Interval Period Every Other RPV bottom-mounted N-722 B15.80 Visual, VE 58 58 Refueling 58 58 58 58 instrument penetrations Outage Category Total 58 58 58 58 58 58 Notes for Cat. Note 1: Frequency of examination, examination method, and personnel qualifications are in accordance with Code Case N-722-1, Table 1 as required N-722 by 10 CFR 50.55a(g)(6)(ii(E)).

N-729 Code Case N-729-6 PWR Reactor Vessel Upper Head (RVUH)(1)

Every Third RFO or 5 Head with nozzles and calendar years N-729 B4.30 partial penetration welds of Visual, VE 68 68 68(2) 68 0 68 whichever is PWSCC-resistant material less Nozzles and partial Once per Two penetration welds of Volumetric N-729 B4.40 64 64 Inspection 64(2) 0 0 64 PWSCC-resistant materials &/or Surface Intervals in head Category Total 132 132 132 68 0 132 Notes for Cat. Note 1: These examinations are in accordance with Code Case N-729-6, Table 1 as required by 10 CFR 50.55a(g)(6)(ii)(D).

N-729 Note 2: Code Case N-729-6, Table 1 which requires all nozzles to be examined not to exceed two intervals (20 nominally calendar years). Based on the replacement of the RPVCH in 2009, the volumetric examination would be required in 1RE28 (Spring 2029).

Code Case N-770-5 Class 1 PWR Pressure Retaining Dissimilar Metal Piping and Vessel Nozzle Butt Welds N-770 Containing Alloy 82/182(1)

Volumetric Uncracked butt weld every N-770 Item D mitigated with stress Volumetric 8 8 100% 0 8 0 inspection improvement interval(1)

Page 98 of 188 Appendix A Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 1, Interval 4 Number Number to Required to be Number to Number to be Number of Examination Examined or be Item Examined be Examined Examined in Category Description Exam Method Components in Percentage Scheduled Examined in Number During in First Second Item No. Required During the Third Interval Period Period Interval Period Cracked butt weld Volumetric reinforced by full structural every N-770 Item F-1 Volumetric 12 4 33% 0 0 4 weld overlay of Alloy inspection 52/152 material interval(1)

Category Total 20 12 0 8 4 Note 1: Frequency of examination, examination method, and personnel qualifications are in accordance with Code Case N-770-5, Table 1 as required by 10 CFR 50.55a.

Notes for Cat.

Note 2: An ultrasonic examination from either the ID or the OD in accordance with the requirements of Appendix VIII shall be acceptable in lieu of the N-770 Visual, VE.

RG 1.14 Reactor Coolant Pump Flywheel Integrity Volumetric/

RCPFW RG 1.14 RCP Flywheels 5 5 100% 5 0 0 5 Surface Category Total 5 5 100% 5(1) 0 0 5 Notes for RG 1.14 Note 1: Inservice inspection of each operating (4) reactor coolant pump flywheels shall be performed once every ISI ten year interval. There is a spare RCP Flywheel.

EPRI TR-Break Exclusion Zone (BEZ) 1006937 R-A R1.20 Feedwater 18-inch Volumetric 36 4 11.1% 4 2 2 0 R-A R1.20 Main Steam 30-inch Volumetric 36 4 11.1% 4 2 2 0 R-A R1.20 Main Steam 16-inch Volumetric 9 1 11.1% 1 0 0 1 R-A R1.20 Main Steam 6-inch Volumetric 20 2 10% 2 0 0 2

Page 99 of 188 Appendix A Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 1, Interval 4 Number Number to Required to be Number to Number to be Number of Examination Examined or be Item Examined be Examined Examined in Category Description Exam Method Components in Percentage Scheduled Examined in Number During in First Second Item No. Required During the Third Interval Period Period Interval Period Category Total 101 11 11 4 4 3 Notes for None EPRI TR-1006937 MRP-146 Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines Circumferential Welds in Non-Isolable RCS Branch R-A R1.11 Lines Susceptible to Volumetric(1) 3 3 Every RFO(2) 3 6 6 6 Thermal Fatigue (Pipe-Elbow)

Circumferential Welds in Non-Isolable RCS Branch R-A R1.20S Lines Susceptible to Volumetric(1) 3 3 Every RFO(2) 3 6 6 6 Thermal Fatigue (Drain Line, Elbow-Pipe)

Category Total 6 6(1) 6 12 12 12 Note 1: Volumetric examinations shall be performed as determined through the fatigue management program.

Notes for MRP-146 Note 2: Initial examination was completed in 1RE15.

MRP-192 Assessment of RHR Mixing Tee Thermal Fatigue in PWR Plants (1)

R-A R0.00 RHR Mixing Tee Volumetric 1 1 1 1 0 0 Category Total 1 1 1 1 0 0 Notes for MRP-192 Note 1: Volumetric examinations shall be performed as determined through the fatigue management program.

Page 100 of 188 Appendix A Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 1, Interval 4 Number Number to Required to be Number to Number to be Number of Examination Examined or be Item Examined be Examined Examined in Category Description Exam Method Components in Percentage Scheduled Examined in Number During in First Second Item No. Required During the Third Interval Period Period Interval Period NSAL-06-8 Pressurizer Heaters Sleeves Bare Metal Once per MRP-VT PRZ Pressurizer Heaters Sleeves 1(1) 1 1 0 0 1 Visual(1) interval Category Total 1 1 1 0 0 1 Notes for NSAL-06-8 Note 1: Bare Metal Visual of first row exposed heaters and accessible portion of heaters on outer 2 rows. There is one record to identify all Pressurizer Heater Sleeves.

Page 101 of 188 APPENDIX B INSERVICE INSPECTION

SUMMARY

TABLE - COMPONENT SUPPORTS, STEAM GENERATOR TUBING, SYSTEM PRESSURE TESTING, AND WELD INSPECTIONS - UNIT 2, INTERVAL 4

Page 102 of 188 Appendix B Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 2, Interval 4 Number Number to Number to Number to Required to be Number of Examination Examined or be be be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined Number During Item No. Required During the in First Second in Third Interval Interval Period Period Period B-A Pressure Retaining Welds in Reactor Vessel Reactor Vessel B-A B1.11 Circumferential Shell Volumetric 3 3 100% 3 0 0 3 Welds Reactor Vessel B-A B1.12 Volumetric 9 9 100% 9 0 0 9 Longitudinal Shell Welds Reactor Vessel B-A B1.21 Circumferential Head Volumetric 1 1 100% 1 0 0 1 Welds Reactor Vessel Meridional B-A B1.22 Volumetric 4 4 100% 4 0 0 4 Head Welds Reactor Vessel Shell-to-B-A B1.30 Volumetric 1 1 100% 1 0 0 1 Flange Weld Category Total 18 18(1) 18 0 0 18 Cumulative Percentage 0% 0% 100%

Note 1: Examination Category B-A weld examinations were deferred under RR-ENG-3-14 to December 15, 2028 (ML18177A425). STP has elected to Notes for Cat. B-A perform the examinations in 2RE25 which is scheduled in the Spring of 2027.

B-B Pressure Retaining Welds in Vessels Other Than Reactor Vessels Pressurizer Shell-to-Head B-B B2.11 Volumetric 2 2 100% 2 1 0 1 Welds Circumferential Pressurizer Shell-to-Head B-B B2.12 Volumetric 2 2 100% 2 1 0 1 Welds Longitudinal

Page 103 of 188 Appendix B Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 2, Interval 4 Number Number to Number to Number to Required to be Number of Examination Examined or be be be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined Number During Item No. Required During the in First Second in Third Interval Interval Period Period Period Steam Generators (Primary B-B B2.40 Side) Tubesheet-to-Head Volumetric 4 1 25%(1) 1 0 1 0 Weld Category Total 8 5 5 2 1 2 Cumulative Percentage 40% 60% 100%

Note 1: The examination may be limited to one vessel among the group of vessels performing a similar function. [Ref. Table IWB- 2500-1, Notes for Cat. B-B Examination Category B-B, Note (1)].

B-D Full Penetration Welded Nozzles in Vessels Reactor Vessel Nozzle-to-B-D B3.90 Volumetric 8 8(1) 100% 8 0 0 8 Vessel Welds Reactor Vessel Nozzle Visual, B-D B3.100 8 8(1) 100% 8 0 0 8 Inside Radius Section VT-1(2)

Pressurizer Nozzle-to-B-D B3.110 Volumetric 6 6 100% 6 3 1 2 Vessel Welds(3)

Category Total 22 22 22 3 1 18 Cumulative Percentage(4) 13.6% 18.18% 100%

Note 1: Examination Category B-D weld examinations were deferred under RR-ENG-3-14 to December 15, 2028 (ML18177A425). STP has elected to perform the examinations in 2RE25 which is scheduled in the Spring of 2027.

Note 2: Visual, VT-1 Examination as allowed by Code Case N-648-2 with the NRC condition In lieu of a UT examination, licensees may perform Notes for Cat. B-D a VT-1 examination in accordance with the code of record for the Inservice Inspection Program utilizing the allowable flaw length criteria of Table IWB-3512-1 with limiting assumptions on the flaw aspect ratio.

Note 3: Deferral of examination to the end of interval is not permissible.

Note 4: Cumulative Percentage is provided for information as some of these items may be deferred to the end of the interval.

B-G-1 Pressure Retaining Bolting, Greater Than 2 in. (50 mm) in Diameter

Page 104 of 188 Appendix B Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 2, Interval 4 Number Number to Number to Number to Required to be Number of Examination Examined or be be be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined Number During Item No. Required During the in First Second in Third Interval Interval Period Period Period Reactor Vessel Closure B-G-1 B6.10 Visual, VT-1 36 36 100% 36 0 0 36 Head Nuts Reactor Vessel Closure B-G-1 B6.20 Volumetric(2) 36(3) 36 100%(1) 36 0 0 36 Studs Reactor Vessel Threads in B-G-1 B6.40 Volumetric 36 36 100%(4) 36 0 0 36 Flange Reactor Vessel Closure B-G-1 B6.50 Visual, VT-1 36(5) 36 100% 36 0 0 36 Washers Reactor Vessel Closure B-G-1 B6.50 Volumetric(7) 36 36 100% 36 0 0 36 Bushings B-G-1 B6.180 Pump Bolts and Studs Volumetric(2) 4(8) 1 25%(1)(9) 1 0 0 1 Pumps Flange Surface B-G-1 B6.190 when connection Visual, VT-1 4(6) 1 25%(10) 0 0 0 0 disassembled Category Total 152 146 145 0 0 145 Cumulative Percentage(11) 0% 0% 100%

Page 105 of 188 Appendix B Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 2, Interval 4 Number Number to Number to Number to Required to be Number of Examination Examined or be be be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined Number During Item No. Required During the in First Second in Third Interval Interval Period Period Period Note 1: Bolting may be examined in place under tension, when the connection is disassembled or when the bolting is removed.

Note 2: When bolts or studs are removed for examination, surface examination meeting the acceptance standards of IWB-3515 may be substituted for volumetric examination. [Ref. Table IWB-2500-1, Examination Category B-G-1, Note (7)].

Note 3: There is one spare RPV stud included in the total population but not scheduled.

Note 4: If STP decides to implement Code Case N-864, there would be no examination required.

Notes for Cat.B-G-1 Note 5: There are 36 Closure Washers and 36 Bushings. The Bushings are not required to be examined unless the bolting is removed.

Note 6: Not required unless the connection is disassembled.

Note 7: An Ultrasonic Examination (UT) of the RPV Roto-Lok flange inserts (bushings) in conjunction with the required UT on the RPV Threads in Flange will be performed per Request for Alternative RR-ENG-4-02.

Note 8: Each RCP Bolting (24 ea.) is represented as one record in the database.

Note 9: Volumetric examination of bolting of heat exchangers, pumps, or valves may be conducted on one heat exchanger, one pump, or one valve among a group of heat exchangers, pumps, or valves that are similar in design, type, and function. In addition, when the component to be examined contains a group of bolted connections of similar design and size, such as flanged connections, the examination may be conducted on one bolted connection among the group. [Ref. Table IWB-2500-1, Examination Category B-G-1, Note (3)].

Note 10: Visual examination of bolting for heat exchangers, pumps, and 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. [Ref. Table IWB-2500-1, Examination Category B-G-1, Note (4)].

Note 11: Cumulative Percentage is provided for information as some of these items are not required to be examined unless they are disassembled, and others can be deferred to the end of the interval.

B-G-2 Pressure Retaining Bolting, 2 in. (50 mm) and Less in Diameter Pressurizer Bolts, Studs, B-G-2 B7.20 Visual, VT-1 1 1 100%(1) 0(2) 0 0 0 and Nuts Steam Generators Bolts, B-G-2 B7.30 Visual, VT-1 8 2 25%(1) 0(2) 0 0 0 Studs, and Nuts B7.50 Piping Bolts, Studs, and B-G-2 Visual, VT-1 3 1(3) 33.3%(1) 0 0 0 0 GR.1 Nuts B7.50 Piping Bolts, Studs, and B-G-2 Visual, VT-1 4 1(3) 25%(1) 0 0 0 0 GR.2 Nuts

Page 106 of 188 Appendix B Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 2, Interval 4 Number Number to Number to Number to Required to be Number of Examination Examined or be be be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined Number During Item No. Required During the in First Second in Third Interval Interval Period Period Period Pumps Bolts, Studs, and B-G-2 B7.60 Visual, VT-1 4 1 25%(1) 0(2) 0 0 0 Nuts B7.70 Valves Bolts, Studs, and B-G-2 Visual, VT-1 3 1 33.3%(1) 0(2)(4) 0 0 0 GR. 1 Nuts B7.70 Valves Bolts, Studs, and B-G-2 Visual, VT-1 6 1 16.6%(1) 0(2)(4) 0 0 0 GR. 2 Nuts B7.70 Valves Bolts, Studs, and B-G-2 Visual, VT-1 3 1 33.3%(1) 0(2)(4) 0 0 0 GR. 3 Nuts B7.70 Valves Bolts, Studs, and B-G-2 Visual, VT-1 3 1 33.3%(1) 0(2)(4) 0 0 0 GR. 4 Nuts B7.70 Valves Bolts, Studs, and B-G-2 Visual, VT-1 6 1 16.6%(1) 0(2)(4) 0 0 0 GR. 5 Nuts B7.70 Valves Bolts, Studs, and B-G-2 Visual, VT-1 3 1 33.3%(1) 0(2)(4) 0 0 0 GR. 6 Nuts B7.70 Valves Bolts, Studs, and B-G-2 Visual, VT-1 3 1 33.3%(1) 0(2)(4) 0 0 0 GR. 7 Nuts B7.70 Valves Bolts, Studs, and B-G-2 Visual, VT-1 3 1 33.3%(1) 0(2)(4) 0 0 0 GR. 8 Nuts Category Total 50 14(1) 0 0 0 0 Cumulative Percentage 0 0% 0% 0%

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

Note 2: For components other than piping, examination of bolting is required only when the component is examined under Examination Category B-A, B-B, B-L-2, or B-M-2. Examination of bolted connection is required only once during the interval. [Ref. Table IWB-2500-1, Notes for Cat.B-G-2 Examination Category B-G-2, Note (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. [Ref. Table IWB-2500-1, Examination Category B-G-2, Note (3)].

Note 4: Only one valve of each group of valves is required as outlined in B-M-2.

Page 107 of 188 Appendix B Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 2, Interval 4 Number Number to Number to Number to Required to be Number of Examination Examined or be be be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined Number During Item No. Required During the in First Second in Third Interval Interval Period Period Period B-K Welded Attachments for Vessels, Piping, Pumps, and Valves Pressure Vessels Welded B-K B10.10 Surface 9(3) 1 11%(1)(2) 1 1 0 0 Attachments Category Total 1 1 0 0 Cumulative Percentage 100% 100% 100%

Note 1: 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 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. The Pressurizer Skirt is selected.

Note 2: There are nine welded attachments on the Pressurizer.

Notes for Cat. B-K Note 3: 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. [Ref. Table IWB-2500-1, Examination Category B-K, Note (6)].

B-L-2 Pump Casings Pump Casing B-L-2 B12.20 Visual, VT-3 4 1 25%(1)(2) 0 0 0 0 (B-L-2)

Category Total 4 1 0 0 0 0 Cumulative Percentage 0 0% 0% 0%

Note 1: Examinations are limited to at least one pump in each group of pumps performing similar functions in the system.

Notes for Cat. B-L-2 Note 2: Examination is required only when a pump is disassembled for maintenance or repair.

B-M-2 Valve Bodies

Page 108 of 188 Appendix B Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 2, Interval 4 Number Number to Number to Number to Required to be Number of Examination Examined or be be be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined Number During Item No. Required During the in First Second in Third Interval Interval Period Period Period B12.50 Valve Body, Exceeding B-M-2 Visual, VT-3 3 1 33.3%(1)(2) 0 0 0 0 Gr. 1 NPS 4 (DN 100) (B-M-2)

B12.50 Valve Body, Exceeding B-M-2 Visual, VT-3 6 1 16.6%(1)(2) 0 0 0 0 Gr. 2 NPS 4 (DN 100) (B-M-2)

B12.50 Valve Body, Exceeding B-M-2 Visual, VT-3 3 1 33.3%(1)(2) 0 0 0 0 Gr. 3 NPS 4 (DN 100) (B-M-2)

B12.50 Valve Body, Exceeding B-M-2 Visual, VT-3 3 1 33.3%(1)(2) 0 0 0 0 Gr. 4 NPS 4 (DN 100) (B-M-2)

B12.50 Valve Body, Exceeding B-M-2 Visual, VT-3 6 1 16.6%(1)(2) 0 0 0 0 Gr. 5 NPS 4 (DN 100) (B-M-2)

B12.50 Valve Body, Exceeding B-M-2 Visual, VT-3 3 1 33.3%(1)(2) 0 0 0 0 Gr. 6 NPS 4 (DN 100) (B-M-2)

B12.50 Valve Body, Exceeding B-M-2 Visual, VT-3 3 1 33.3%(1)(2) 0 0 0 0 Gr. 7 NPS 4 (DN 100) (B-M-2)

B12.50 Valve Body, Exceeding B-M-2 Visual, VT-3 3 1 33.3%(1)(2) 0 0 0 0 Gr. 8 NPS 4 (DN 100) (B-M-2)

Category Total 30 8 0 0 0 0 Cumulative Percentage 0 0% 0% 0%

Note 1: Examinations are limited to at least one valve within each group of valves that are of the same size, constructural design, and manufacturing method and that perform similar functions in the system. STP valves are grouped into 4 groups and one valve per group is required, if Notes for Cat. B-M-2 disassembled.

Note 2: Examination is required only when a valve is disassembled for maintenance or repair.

B-N-1 Reactor Vessel Interior Reactor Vessel, Vessel 100% each B-N-1 B13.10 Visual, VT-3 1 3(1)(2) 3 1 1 1 Interior (B-N-1) period Category Total 1 3(1) 3 1 1 1

Page 109 of 188 Appendix B Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 2, Interval 4 Number Number to Number to Number to Required to be Number of Examination Examined or be be be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined Number During Item No. Required During the in First Second in Third Interval Interval Period Period Period Cumulative Percentage(3) 3 100% 100% 100%

Note 1: Examination of this item number is required each period. Therefore the number required during the interval is three times the total number of components. This is also reflected in the category total.

Notes for Cat B-N-1 Note 2: Areas to be examined shall include the spaces above and below the reactor core that are made accessible for examination by removal of components during normal refueling outages.

Note 3: Cumulative Percentages are provided for information only and are calculated for each period.

B-N-2 Welded Core Support Structures and Interior Attachments to Reactor Vessels Reactor Vessel (PWR)

Interior Attachments B-N-2 B13.60 Visual, VT-3 6 6 100% 6 0 0 6 Beyond Beltline Region (B-N-2)

Category Total 6 6 100% 6 0 0 6 Cumulative Percentage(1) 0% 0% 100%

Notes for Cat. B-N-2 Note 1: Cumulative Percentage is provided for information only as these items can be deferred to the end of the interval.

B-N-3 Removable Core Support Structures Reactor Vessel (PWR)

B-N-3 B13.70 Core Support Structure Visual, VT-3 34 34 100% 34 0 0 34 (B-N-3)(1)

Category Total 34 34 100% 34 0 0 34 Cumulative Percentage(2) 0% 0% 100%

Note 1: The structure shall be removed from the reactor vessel for examination.

Notes for Cat. B-N-3 Note 2: Cumulative Percentage is provided for information only as these items can be deferred to the end of the interval.

Page 110 of 188 Appendix B Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 2, Interval 4 Number Number to Number to Number to Required to be Number of Examination Examined or be be be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined Number During Item No. Required During the in First Second in Third Interval Interval Period Period Period B-O Pressure Retaining Welds in Control Rod Drive and Instrument Nozzle Housings Reactor Vessel (PWR)

Volumetric or B-O B14.20 Welds in Control Rod Drive 48(1) 12 25%(2) 12(3) 0 0 12 surface (CRD) Housings Reactor Vessel (PWR) 10% of Welds in IN-Core Volumetric or B-O B14.21 7(4) 1 peripheral ICI 1(4) 0 0 1 Instrumentation Nozzle Surface Housings (ICI) Housing >NPS 2 Category Total 31 5 13 0 0 13 Cumulative Percentage 0% 0% 100%

Note 1: There are 24 peripheral CRDs each with two welds. 10% of 24 peripheral CRDHs is 3.

Note 2: Code Case N-825 will be used for an alternative.

Notes for Cat. B-O Note 3: STP has chosen to examine a total of six CRD Housing welds to equal the combined length of 10% of the CRD housing welds.

Note 4: There are 4 peripheral CET and 3 IDD each with one welds. 10% or one IDD is schedule for examination.

C-A Pressure Retaining Welds in Pressure Vessels Pressure Vessels Shell C-A C1.10 Volumetric(5) 8 2 25%(1)(2) 2 0 2 0 Circumferential Welds Pressure Vessels Head C-A C1.20 Volumetric(5) 4 1 25%(1)(3) 1 1 0 0 Circumferential Welds Pressure Vessels C-A C1.30 Volumetric (5) 4 1 25%(1)(4) 1 0 0 1 Tubesheet-to-Shell Weld Category Total 16 4 4 1 2 1 Cumulative Percentage 25% 75% 100%

Page 111 of 188 Appendix B Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 2, Interval 4 Number Number to Number to Number to Required to be Number of Examination Examined or be be be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined Number During Item No. Required During the in First Second in Third Interval Interval Period Period Period Note 1: In the case of multiple vessels of similar design, size, and service, the required examinations may be limited to one vessel or distributed among the vessels and includes essentially 100% of the weld length. (Ref. Table IWC-2500-1, Examination Category C-A, Notes 3 & 4).

Note 2: There are two circumferential welds on each Steam Generator (Barrel B to Transition Cone and Transition Cone to Barrel H); therefore 2 of 8 welds are selected for examination. Implementation of Code Case N-716-1 evaluated the Shutdown Heat Exchangers as Low Safety Significant (LSS) therefore no examinations are required.

Note 3: There is one Top Head weld (Barrel J to Head) on each Steam Generator; therefore 1 of 4 welds is selected for examination.

Notes for Cat. C-A Note 4: There is one tubesheet-to-shell weld on each steam generator. One tubesheet-to-shell weld on one of the steam generators is selected for examination. Implementation of Code Case N-716-1 evaluated the Shutdown Heat Exchangers Low Safety Significant (LSS) therefore no examinations are required.

Note 5: For welds in vessels with nominal wall thickness of 0.2 in. (5 mm) or less, a surface examination may be applied in lieu of a volumetric examination. [Ref. Table IWC-2500-1, Examination Category C-A, Note (2)].

C-B Pressure Retaining Nozzle Welds in Vessels Nozzles Without Reinforcing Plate in Vessels > 1/2 in. (13 mm) Surface and C-B C2.21 8 2 25%(1)(2) 2 1 1 0 Nominal Thickness Nozzle- volumetric to-Shell (Nozzle to Head or Nozzle to Nozzle) Weld Nozzles Without Reinforcing Plate in C-B C2.22 Vessels > 1/2 in. (13 mm) Volumetric 4 1 25%(1)(3) 1 1 0 0 Nominal Thickness Nozzle Inside Radius Section Category Total 12 3 3 2 1 0 Cumulative Percentage 50% 100%(4) 100%

Page 112 of 188 Appendix B Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 2, Interval 4 Number Number to Number to Number to Required to be Number of Examination Examined or be be be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined Number During Item No. Required During the in First Second in Third Interval Interval Period Period Period Notes for Cat. C-B Note 1: In case of multiple vessels of similar design, size, and service, the required examinations may be limited to one vessel or distributed among the vessels. [Ref. Table IWC-2500-1, Examination Category C-B, Note (2)].

Note 2: There is one Feedwater nozzle and one Auxiliary Feedwater nozzle on each Steam Generator. Therefore, only one Feedwater and one Auxiliary Feedwater nozzle of one Steam Generator is required to be examined, which equals the required examination of 2 of 8 nozzles or 25%. Implementation of Code Case N-716-1 evaluated the Shutdown RHR Heat Exchangers Low Safety Significant (LSS) therefore no examinations are required.

Note 3: There is one Feedwater nozzle inner radius and one Main Steam nozzle inner radius on each Steam Generator; therefore, 2 of 8 inner radii are required to be examined or 25%.

Note 4: After implementation of Code Case N-716-1 which does not require any examinations of the Boron Injection Tanks, Containment Spray, Regenerative Heat Exchangers, and Residual Heat Removal Heat Exchangers, there are only two nozzles in each item number requiring examination. Per IWC-2411(a) If there are less than three items or welds to be examined in Examination Category, the items or welds may be examined in any two periods, or in any one period if there is only one item or weld, in lieu of the percentage requirements of Table IWC-2411-1. Since only two nozzles are required to be examined (this includes both the nozzle-to-vessel weld and the inner radius section) one is scheduled in the first period and the other is scheduled in the second period.

Note 5: Pending RR-ENG-4-01 C-C Welded Attachments for Vessels, Piping, Pumps, and Valves Pressure Vessels Welded C-C C3.10 Surface 13 2(1) 15.3% 1(4) 1 0 1 Attachments (2)(4)

C-C C3.20 Piping Welded Attachments Surface 21 3 10% 3 1 1 1 C-C C3.30 Pump Welded Attachments Surface 9 1 11.1% 1(3)(4) 0 0 1 Category Total 43 5 5 2 1 2 Cumulative Percentage 40% 60% 100%

Page 113 of 188 Appendix B Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 2, Interval 4 Number Number to Number to Number to Required to be Number of Examination Examined or be be be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined Number During Item No. Required During the in First Second in Third Interval Interval Period Period Period Notes for Cat. C-C Note 1: 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. [Ref. Table IWC-2500-1, Examination Category C-C, Note (6)].

Note 2: 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. [Ref. Table IWC-2500-1 Examination Category C-C, Note (7)].

Note 3: For pumps, a sample of 10% of the welded attachments associated with the component supports selected for examination under IWF-2510 shall be examined. [Ref. Table IWC-2500-1 Examination Category C-C, Note (7)]. There are three RHR Pumps with three welded attachments each, one welded attachment is selected for examination.

Note 4: 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. [Ref. Table IWC-2500-1, Examination Category C-C, Note (5)].

D-A Welded Attachments for Vessels, Piping, Pumps, and Valves Vessel Welded D-A D1.10 Visual, VT-1 2 2 100% 2(1)(2) 1 1 0 Attachments D-A D1.20 Piping Welded Attachments Visual, VT-1 7 1 10% 1(1)(2) 0 0 1 Category Total 8 3 3 1 1 1 Cumulative Percentage 33.3% 66.6% 100%

Notes for Cat. D-A Note 1: Selected samples of welded attachments shall be examined each inspection interval. 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, 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. For welded attachments of piping, pumps, and valves, a 10% sample shall be selected for examination. This percentage sample shall be proportional to the total number of nonexempt welded attachments connected to the piping, pumps and valves in each system subject to examination. [Ref. Table IWD-2500-1, Category D-A, Note (6)].

Note 2: 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. [Ref. Table IWD-2500-1, Examination Category D-A, Note (5)].

F-A Supports

Page 114 of 188 Appendix B Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 2, Interval 4 Number Number to Number to Number to Required to be Number of Examination Examined or be be be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined Number During Item No. Required During the in First Second in Third Interval Interval Period Period Period Class 1 Piping Supports - (1)

F-A F1.10A Visual, VT-3 1 1 1 0 0 1 One Directional Class 1 Piping Supports - (1)

F-A F1.10B Visual, VT-3 68 17 19 6 5 8 Multi-Directional Class 1 Piping Supports - (1)

F-A F1.10C Visual, VT-3 75 19 21 6 8 7 Thermal Movement Category F-A, Item F1.10 Total 144 37 41(2) 12 13 16 Class 2 Piping Supports - (1)

F-A F1.20A Visual, VT-3 7 2 2 1 0 1 One Directional Class 2 Piping Supports - (1)

F-A F1.20B Visual, VT-3 346 52 55 18 18 19 Multi-Directional Class 2 Piping Supports - (1)

F-A F1.20C Visual, VT-3 375 57 62 19 15 28 Thermal Movement Category F-A, Item F1.20 Total 728 111 119(2) 38 33 48 Class 3 Piping Supports - (1)

F-A F1.30A Visual, VT-3 10 1 2 2 0 0 One Directional Class 3 Piping Supports - (1)

F-A F1.30B Visual, VT-3 458 46 48 18 11 19 Multi-Directional Class 3 Piping Supports - (1)

F-A F1.30C Visual, VT-3 479 48 52 14 13 26 Thermal Movement Category F-A, Item F1.30 Total 947 95 103(2) 34 24 45 Supports other than Piping F-A F1.40 Supports (Class 1,2,3, and Visual, VT-3 225 84 37.3% 84 26 29 29 MC) - Equipment Supports Category F-A, Item F1.40 Total 225 84 84(3) 26 29 29 Category Total 2044 327 347(2) 110 99 138 Cumulative Percentage 31.7% 60.2% 100%

Page 115 of 188 Appendix B Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 2, Interval 4 Number Number to Number to Number to Required to be Number of Examination Examined or be be be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined Number During Item No. Required During the in First Second in Third Interval Interval Period Period Period Note 1: The total percentage sample shall 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. [Ref. Table IWF-2500-1, Examination Category F-A, Note (4)].

Notes for Cat. F-A Note 2: Based on proration by system, type, and function, and engineering judgement, the number of supports scheduled exceeds the number of supports required.

Note 3: 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. [Ref. Table IWF-2500-1, Examination Category F-A, Note (5)].

R-A Risk Informed Piping Welds - Code Case N-716-1 Welds Subject to Thermal R-A R1.11 Volumetric 177 45 25.4% 45 22 11 12 Fatigue Welds Subject to Thermal R-A R1.11/16 Volumetric 6 2 33.3% 2 0 0 2 Fatigue and IGSCC Welds not Subject to a R-A R1.20 Volumetric 596 36 6% 36 7 14 15 Damage Mechanism Welds not Subject to a R-A R1.20S Visual, VT-2 31 0(3) 0% 0 0 0 0 Damage Mechanism Category Total 810 83 83 29 25 29 Cumulative Percentage 34.9% 65% 100%

Note 1: STP has initiated Risk-Informed ISI (RI-ISI) contained in ASME Code Case N-716-1, approved in Regulatory Guide 1.147 Revision 18 and listed in Table 2.2-1.

Note 2: These welds are identified for information only; the welds are governed by Code Case N-770 and scheduled as such. These welds are Notes for Cat. R-A examined every refueling outage and therefore not counted in the cumulative percentage.

N-722 Code Case N-722-1 PWR Class 1 Components Containing Alloy 600/82/182(1)

Every Other RPV bottom-mounted N-722 B15.80 Visual, VE(2) 58 58 Refueling 58 58 58 58 instrument penetrations Outage

Page 116 of 188 Appendix B Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 2, Interval 4 Number Number to Number to Number to Required to be Number of Examination Examined or be be be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined Number During Item No. Required During the in First Second in Third Interval Interval Period Period Period Category Total 58 58 58 58 58 58 Notes for Cat. Note 1: Frequency of examination, examination method, and personnel qualifications are in accordance with Code Case N-722-1, Table 1 as N-722 required by 10 CFR 50.55a(g)(6)(ii(E)).

N-729 Code Case N-729-6 PWR Reactor Vessel Upper Head (RVUH)(1)

Every Third RFO or 5 Head with nozzles and calendar years N-729 B4.30 partial penetration welds of Visual, VE 68 68 68 0 68 68 whichever is PWSCC-resistant material less Nozzles and partial Once per Two penetration welds of Volumetric N-729 B4.40 64 64 Inspection 64(2) 0 0 0 PWSCC-resistant materials &/or Surface Intervals in head Category Total 132 132 132 64 68 68 Notes for Cat. Note 1: These examinations are in accordance with Code Case N-729-6, Table 1 as required by 10 CFR 50.55a(g)(6)(ii)(D).

N-729 Note 2: Not to exceed two Inspection Intervals (normally 20 calendar years). The RPVCH was replaced in April 2010 and therefore is not required to be volumetrically examined in the 4th Interval.

Code Case N-770-5 Class 1 PWR Pressure Retaining Dissimilar Metal Piping and Vessel Nozzle Butt Welds N-770 Containing Alloy 82/182(1)

Every 2nd Uncracked butt weld Inspection N-770 Item D mitigated with stress Volumetric(2) 8 8 100% 0 8 0 Period not to improvement exceed 7yrs.(1)

Page 117 of 188 Appendix B Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 2, Interval 4 Number Number to Number to Number to Required to be Number of Examination Examined or be be be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined Number During Item No. Required During the in First Second in Third Interval Interval Period Period Period Cracked butt weld Volumetric reinforced by full structural every N-770 Item F-1 Volumetric 12 4 33% 0 0 4 weld overlay of Alloy inspection 52/152 material interval(1)

Category Total 20 12 0 8 4 Note 1: Frequency of examination, examination method, and personnel qualifications are in accordance with Code Case N-770-5, Table 1 as Notes for Cat.

required by 10 CFR 50.55a(g)(6)(ii)(F).

N-770 Note 2: An ultrasonic examination from either the ID or the OD in accordance with the requirements of Appendix VIII shall be acceptable in lieu of the Visual, VE.

RG 1.14 Reactor Coolant Pump Flywheel Integrity Volumetric/

RG1.14 RCPFW RCP Flywheels 5 5 100% 5 0 0 5 Surface Category Total 5 5 100% 5(1) 0 0 5 Notes for RG 1.14 Note 1: Inservice inspection of each operating (4) reactor coolant pump flywheels shall be performed once every ISI ten year interval. There is a spare RCP Flywheel.

EPRI TR-Break Exclusion Zone (BEZ) 1006937 R-A R1.20 Feedwater 18-inch Volumetric 38 4 Each Interval 4 2 0 2 R-A R1.20 Main Steam 30-inch Volumetric 36 4 Each Interval 4 0 3 1 R-A R1.20 Main Steam 16-inch Volumetric 9 1 Each Interval 1 1 0 0 R-A R1.20 Main Steam 6-inch Volumetric 20 2 Each Interval 2 1 0 1

Page 118 of 188 Appendix B Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 2, Interval 4 Number Number to Number to Number to Required to be Number of Examination Examined or be be be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined Number During Item No. Required During the in First Second in Third Interval Interval Period Period Period Category Total 103 11 11 4 3 4 Notes for None EPRI TR-1006937 MRP-146 Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines Circumferential Welds in Non-Isolable RCS Branch R-A R1.11 Lines Susceptible to Volumetric(1) 4 4 Every RFO(2) 4 8 8 8 Thermal Fatigue (Pipe-Elbow)

Circumferential Welds in Non-Isolable RCS Branch R-A R1.20S Lines Susceptible to Volumetric(1) 2 2 Every RFO(2) 2 2 2 2 Thermal Fatigue (Drain Line, Elbow-Pipe)

Category Total 6 6(1) 6 10 10 10 Note 1: Volumetric examinations shall be performed as determined through the fatigue management program.

Notes for MRP-146 Note 2: Initial examination was completed in 2RE14.

MRP-192 Assessment of RHR Mixing Tee Thermal Fatigue in PWR Plants (1)

MRP-UT MRP-192 RHR Mixing Tee Volumetric 1 1 1 1 0 0 Category Total 1 1 1 1 0 0

Page 119 of 188 Appendix B Inservice Inspection Summary Table - Component Supports, Steam Generator Tubing, System Pressure Testing, and Weld Inspections - Unit 2, Interval 4 Number Number to Number to Number to Required to be Number of Examination Examined or be be be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined Number During Item No. Required During the in First Second in Third Interval Interval Period Period Period Notes for MRP-192 Note 1: Volumetric examinations shall be performed as determined through the fatigue management program LRC-42 RPV Stud Insert #30 Visual, Once per B-G-1 B6.10 RPV Stud Insert #30 1 1 1 0 0 1 VT-1(1) interval Category Total 1 1 1 0 0 1 Notes for LRC-42 Note 1: Remote Visual, VT-1 concurrent with the Volumetric, UT Examination.

NSAL-06-8 Pressurizer Heaters Sleeves Bare Metal Once per MRP-VT PRZ Pressurizer Heaters Sleeves 1(1) 1 1 0 0 1 Visual(1) interval Category Total 1 1 1 0 0 1 Notes for NSAL 06-8 Note 1: Bare Metal Visual of first row exposed heaters and accessible portion of heaters on outer 2 rows. There is one record to identify all Pressurizer Heater Sleeves.

Page 120 of 188 APPENDIX C INSERVICE INSPECTION

SUMMARY

TABLE - CONTAINMENT METAL LINER - UNIT 1, INTERVAL 4

Page 121 of 188 Appendix C Inservice Inspection Summary Table - Containment Metal Liner - Unit 1, Interval 4 Number Number to Number to Required to be Number to Number of Examination Examined or be be Item Examined be Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Number During in Third Item No. Required During the in First Second Interval Period Interval Period Period E-A Containment Surfaces(1)

General 100% per E-A E1.11 Accessible Surface Area 9 9 9 9 9 9 Visual period Wetted Surfaces of 100% per E-A E1.12 Visual, VT-3 0 0 0 0 0 0 Submerged Areas Interval General 100% per E-A E1.30 Moisture Barriers(2) 3 3 3 3 3 3 Visual period Category Total 12 12(1)

Cumulative Percentage 0% 100% 100%

Note 1: Examination shall include all accessible interior and exterior surfaces of Class MC components, parts, and appurtenances and metallic shell and penetration liners of Class CC components. The following items shall be examined:

a. Integral attachments and structures that are parts of reinforcing structure, such as stiffening rings, manhole frames, and reinforcement around openings.
b. Surfaces of attachment welds between structural attachments and pressure retaining boundary or reinforcing structure, except for nonstructural or temporary attachments as defined in NE-4435 and minor permanent attachments as defined in CC-4543.4.
c. Surfaces of containment structural and pressure boundary welds, including longitudinal welds (Category A), circumferential Notes for Cat. E-A welds (Category B), flange welds (Category C), and nozzle-to-shell welds (Category D) as defined in NE-3351 for Class MC and CC-3840 for Class CC and surfaces of Flued Head and Bellows Seal Circumferential Welds joined to the Penetration.
d. Pressure-retaining bolted connections including bolts, studs, nuts, bushings, washers, and threads in base material and flange ligaments between fastener holes. Bolted connections need not be disassembled for performance of examinations.

Note 2: Examination shall include moisture barrier materials intended to prevent intrusion of moisture against inaccessible areas of the pressure retaining metal containment shell or liner at concrete-to-metal interfaces and at metal-to-metal interfaces which are not seal-welded.

Containment moisture barrier materials include caulking, flashing, and other sealants used for this application.

10 CFR 50.55a(b)(2) Leak-Chase Channels (ix)(K)(1)

Once per E-A E1.32 Leak Chase Channels Visual(2) 163 163 163 55 56 52 period Category Total 163 163 163 55 56 52

Page 122 of 188 Appendix C Inservice Inspection Summary Table - Containment Metal Liner - Unit 1, Interval 4 Number Number to Number to Required to be Number to Number of Examination Examined or be be Item Examined be Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Number During in Third Item No. Required During the in First Second Interval Period Interval Period Period Notes for 10 CFR Note 1: 10 CFR 50.55a requires the implementation of the 2017 Edition for Leak Chase Channel Systems [ref. 10 CFR 50.55a(b)(2)(ix)(K)].

Note 2: General Visual of cover plate of the Leak Chase Channel System. Caps of stub tubes extending to or above the concrete floor interface may be inspected provided the configuration of the cap functions as a moisture barrier. Leak chase channel system closures need not be disassembled for performance of examinations if the moisture barrier material is clearly visible without disassembly, or coatings are intact.

E-C Containment Surfaces Requiring Augmented Examination(1) 100% per E-C E4.11 Visible Surface Visual, VT-1 0 0 0 0 0 0 period Surface Area Grid, 100% per E-C E4.12 Minimum Wall Thickness UT Thickness 0 0 0 0 0 0 period Location Category Total 0 0 Cumulative Percentage 0% 0% 0%

Notes for Cat. E-C Note 1: There are no Augmented areas identified by STP at this time.

E-G Pressure Retaining Bolting(1) 100% per E-G E8.10 Bolted Connections Visual, VT-1 123 123 123 0 0 123 interval Category Total 123 123 Cumulative Percentage 0% 0% 100%

Note 1: Examination may be performed with the connection assembled and bolting in place under tension, provided the connection is not Notes for Cat. E-G disassembled during the interval. If the bolted connection is disassembled for any reason during the interval, the examination shall be performed with the connection disassembled.

Page 123 of 188 APPENDIX D INSERVICE INSPECTION

SUMMARY

TABLE - CONTAINMENT METAL LINER - UNIT 2, INTERVAL 4

Page 124 of 188 Appendix D Inservice Inspection Summary Table - Containment Metal Liner - Unit 2, Interval 4 Number Number to Number to Required to be Number of Examination Examined or be be Number to be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined in Number During Item No. Required During the in First Second Third Period Interval Interval Period Period E-A Containment Surfaces(1)

General 100% per E-A E1.11 Accessible Surface Area 9 9 9 9 9 9 Visual period Wetted Surfaces of 100% per E-A E1.12 Visual, VT-3 0 0 0 0 0 0 Submerged Areas Interval General 100% per E-A E1.30 Moisture Barriers(2) 3 3 3 3 3 3 Visual period Category Total 12 12(1)

Cumulative Percentage 0% 100% 100%

Note 1: Examination shall include all accessible interior and exterior surfaces of Class MC components, parts, and appurtenances and metallic shell and penetration liners of Class CC components. The following items shall be examined:

e. Integral attachments and structures that are parts of reinforcing structure, such as stiffening rings, manhole frames, and reinforcement around openings.
f. Surfaces of attachment welds between structural attachments and pressure retaining boundary or reinforcing structure, except for nonstructural or temporary attachments as defined in NE-4435 and minor permanent attachments as defined in CC-4543.4.
g. Surfaces of containment structural and pressure boundary welds, including longitudinal welds (Category A), circumferential Notes for Cat. E-A welds (Category B), flange welds (Category C), and nozzle-to-shell welds (Category D) as defined in NE-3351 for Class MC and CC-3840 for Class CC and surfaces of Flued Head and Bellows Seal Circumferential Welds joined to the Penetration.
h. Pressure-retaining bolted connections including bolts, studs, nuts, bushings, washers, and threads in base material and flange ligaments between fastener holes. Bolted connections need not be disassembled for performance of examinations.

Note 2: Examination shall include moisture barrier materials intended to prevent intrusion of moisture against inaccessible areas of the pressure retaining metal containment shell or liner at concrete-to-metal interfaces and at metal-to-metal interfaces which are not seal-welded.

Containment moisture barrier materials include caulking, flashing, and other sealants used for this application.

10 CFR 50.55a(b)(2) Leak-Chase Channels (ix)(K)(1)

Once per E-A E1.32 Leak Chase Channels Visual(2) 163 163 163 55 56 52 period Category Total 163 163 163 55 56 52

Page 125 of 188 Appendix D Inservice Inspection Summary Table - Containment Metal Liner - Unit 2, Interval 4 Number Number to Number to Required to be Number of Examination Examined or be be Number to be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined Examined in Examined in Number During Item No. Required During the in First Second Third Period Interval Interval Period Period Notes for 10 CFR Note 1: 10 CFR 50.55a requires the implementation of the 2017 Edition for Leak Chase Channel Systems [ref. 10 CFR 50.55a(b)(2)(ix)(K)].

Note 2: General Visual of cover plate of the Leak Chase Channel System. Caps of stub tubes extending to or above the concrete floor interface may be inspected provided the configuration of the cap functions as a moisture barrier. Leak chase channel system closures need not be disassembled for performance of examinations if the moisture barrier material is clearly visible without disassembly, or coatings are intact.

E-C Containment Surfaces Requiring Augmented Examination(1) 100% per E-C E4.11 Visible Surface Visual, VT-1 0 0 0 0 0 0 period Surface Area Grid, 100% per E-C E4.12 Minimum Wall Thickness UT Thickness 0 0 0 0 0 0 period Location Category Total 0 0 Cumulative Percentage 0% 0% 0%

Notes for Cat. E-C Note 1: There are no Augmented areas identified by STP at this time.

E-G Pressure Retaining Bolting(1) 100% per E-G E8.10 Bolted Connections Visual, VT-1 123 123 123 0 0 123 interval Category Total 123 123 Cumulative Percentage 0% 0% 100%

Note 1: Examination may be performed with the connection assembled and bolting in place under tension, provided the connection is not Notes for Cat. E-G disassembled during the interval. If the bolted connection is disassembled for any reason during the interval, the examination shall be performed with the connection disassembled.

Page 126 of 188 APPENDIX E INSERVICE INSPECTION

SUMMARY

TABLE - CONCRETE CONTAINMENT - UNIT 1, INTERVAL 4

Page 127 of 188 Appendix E Inservice Inspection Summary Table - Concrete Containment - Unit 1, Interval 4 Number Required to be Number of Examination Examined or Number to be Number to be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined in Examined in Number During Item No. Required During the First Period Third Period Interval Interval L-A Concrete Surfaces 1, 3, 5, and 10 General L-A L1.11 Accessible Surface Area(1) 1 1 yrs. and every 5 1 0 1 Visual(2) yrs. thereafter Detailed 100% per L-A L1.12 Suspect Areas 0 0 0 0 0 Visual(3) Interval Inaccessible Below-Grade L-A L1.13 IWL-2512(c)(5) 1 1 IWL-2512(c)(6) 1 1 1 Areas(4)

Category Total 2 2 Cumulative Percentage 0% 100%

Note 1: Includes concrete surfaces at tendon anchorage areas not selected by IWL-2521 or exempted by IWL-1220(a).

Note 2: Reference IWL-2310(a) for General Visual exam requirements. IWA-2300 for Personnel Qualification requirements.

Note 3: Reference IWL-2310(b) for Detailed Visual exam requirements. IWA-2300 for Personnel Qualification requirements.

Notes for Cat. E-A Note 4: Concrete surfaces exposed to foundation soil, backfill, or ground water.

Note 5: Method of examination as defines by the Responsible Engineer, based on IWL-2512(b) evaluation.

Note 6: Reference IWL-2512(c) for requirements of a condition-monitoring program.

L-B Unbonded Post Tensioning System 1, 3, 5, and 10 Tendon Force L-B L2.10 Tendon 229 6 yrs. and every 5 6 0 6 Measurements(1) yrs. thereafter(8) 1, 3, 5, and 10 Sample Exam L-B L2.20 Wire or Strand 42,594 2 yrs. and every 5 2 0 2 and Test(2) yrs. thereafter(8) 1, 3, 5, and 10 Anchor Hardware and Detailed L-B L2.30 229 10 yrs. and every 5 10 6 4 Surrounding Concrete Visual(3)(4)(5) yrs. thereafter(8) 1, 3, 5, and 10 Corrosion Protection Sampling L-B L2.40 229 10 yrs. and every 5 10 6 4 Medium Testing(6) yrs. thereafter(8)

Page 128 of 188 Appendix E Inservice Inspection Summary Table - Concrete Containment - Unit 1, Interval 4 Number Required to be Number of Examination Examined or Number to be Number to be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined in Examined in Number During Item No. Required During the First Period Third Period Interval Interval 1, 3, 5, and 10 Sampling L-B L2.50 Free Water 229 10 yrs. and every 5 10 6 4 Testing(7) yrs. thereafter(8)

Category Total 38 38 18 20 Cumulative Percentage 47% 100%

Note 1: Reference IWL-2522 for Tendon Force and Elongation Measurement requirements.

Note 2: Reference IWL-2523 for Tendon Wire and Strand Sample Examination and Testing requirements.

Note 3: Relief Request RR-ENG-IWL-01 will be used as authorized for selection of these parts for examination.

Note 4: Reference IWL-2524 for Examination of Tendon Anchorage Areas.

Notes for Cat. L-B Note 5: Reference IWL-2310(b) for Detailed Visual Exam requirements. IWA_2300 for Personnel Qualification requirements.

Note 6: Reference IWL-2525 for Examination of Corrosion Protection Medium requirements.

Note 7: Reference IWL-2525 for Free Water requirements.

Note 8: Reference IWL-2421 for frequency of examination for sites with multiple plants may be applied.

Page 129 of 188 APPENDIX F INSERVICE INSPECTION

SUMMARY

TABLE - CONCRETE CONTAINMENT - UNIT 2, INTERVAL 4

Page 130 of 188 Appendix F Inservice Inspection Summary Table - Concrete Containment - Unit 2, Interval 4 Number Required to be Number of Examination Examined or Number to be Number to be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined in Examined in Number During Item No. Required During the First Period Third Period Interval Interval L-A Concrete Surfaces 1, 3, 5, and 10 General L-A L1.11 Accessible Surface Area(1) 1 1 yrs. and every 5 1 0 1 Visual(2) yrs. thereafter Detailed 100% per L-A L1.12 Suspect Areas 0 0 0 0 0 Visual(3) Interval Inaccessible Below-Grade L-A L1.13 IWL-2512(c)(5) 1 1 IWL-2512(c)(6) 1 1 1 Areas(4)

Category Total 2 2 Cumulative Percentage 0% 100%

Note 1: Includes concrete surfaces at tendon anchorage areas not selected by IWL-2521 or exempted by IWL-1220(a).

Note 2: Reference IWL-2310(a) for General Visual exam requirements. IWA-2300 for Personnel Qualification requirements.

Note 3: Reference IWL-2310(b) for Detailed Visual exam requirements. IWA-2300 for Personnel Qualification requirements.

Notes for Cat. E-A Note 4: Concrete surfaces exposed to foundation soil, backfill, or ground water.

Note 5: Method of examination as defines by the Responsible Engineer, based on IWL-2512(b) evaluation.

Note 6: Reference IWL-2512(c) for requirements of a condition-monitoring program.

L-B Unbonded Post Tensioning System 1, 3, 5, and 10 Tendon Force L-B L2.10 Tendon 229 6 yrs. and every 5 6 6 0 Measurements(1) yrs. thereafter(8) 1, 3, 5, and 10 Sample Exam L-B L2.20 Wire or Strand 42,594 2 yrs. and every 5 2 2 0 and Test(2) yrs. thereafter(8) 1, 3, 5, and 10 Anchor Hardware and Detailed L-B L2.30 229 10 yrs. and every 5 10 6 4 Surrounding Concrete Visual(3)(4)(5) yrs. thereafter(8) 1, 3, 5, and 10 Corrosion Protection Sampling L-B L2.40 229 10 yrs. and every 5 10 6 4 Medium Testing(6) yrs. thereafter(8)

Page 131 of 188 Appendix F Inservice Inspection Summary Table - Concrete Containment - Unit 2, Interval 4 Number Required to be Number of Examination Examined or Number to be Number to be Item Examined Category Description Exam Method Components in Percentage Scheduled Examined in Examined in Number During Item No. Required During the First Period Third Period Interval Interval 1, 3, 5, and 10 Sampling L-B L2.50 Free Water 229 10 yrs. and every 5 10 6 4 Testing(7) yrs. thereafter(8)

Category Total 38 38 26 12 Cumulative Percentage 68% 100%

Note 1: Reference IWL-2522 for Tendon Force and Elongation Measurement requirements.

Note 2: Reference IWL-2523 for Tendon Wire and Strand Sample Examination and Testing requirements.

Note 3: Relief Request RR-ENG-IWL-01 will be used as authorized for selection of these parts for examination.

Note 4: Reference IWL-2524 for Examination of Tendon Anchorage Areas.

Notes for Cat. L-B Note 5: Reference IWL-2310(b) for Detailed Visual Exam requirements. IWA_2300 for Personnel Qualification requirements.

Note 6: Reference IWL-2525 for Examination of Corrosion Protection Medium requirements.

Note 7: Reference IWL-2525 for Free Water requirements.

Note 8: Reference IWL-2421 for frequency of examination for sites with multiple plants may be applied.

Page 132 of 188 APPENDIX G APPENDIX VIII IMPLEMENTATION PLAN

Page 133 of 188 APPENDIX VIII IMPLEMENTATION PLAN 1.0 Purpose 1.1. The purpose of this program plan is to establish administrative controls for the implementation of the supplements to ASME Section XI Code Mandatory Appendix VIII (Performance Demonstration for Ultrasonic Examination Systems).

2.0 Basis and ASME Code References for Section XI Code Mandatory Appendix VIII.

2.1. This Plan is developed in accordance with the requirements of 10CFR50.55a, 83 FR 2526) which became effective on January 18, 2018.

2.2. As required by 10CFR50.55a the South Texas Project (STP) will implement Mandatory Appendix VIII of the 2013 Edition of the ASME Section XI Code with the following conditions:

(b) (2) (xviii) (D) NDE personnel certification: Fourth provision. The use of Appendix VII, Table VII-4110-1 and Appendix VIII, Subarticle VIII-2200 of the 2011 Addenda and 2013 Edition of Section XI of the ASME BPV Code is prohibited. When using ASME BPV Code,Section XI editions and addenda later than the 2010 Edition, licensees and applicants must use the prerequisites for ultrasonic examination personnel certifications in Appendix VII, Table VII-4110-1 and Appendix VIII, Subarticle VIII-2200 in the 2010 Edition.

2.3. At any time during the Fourth Interval the provisions of 10 CFR 50.55a(g)(4)(ii) may be used. STP may elect to use Appendix VIII from the latest Edition of ASME Section XI listed in 10 CFR 50.55a(a) as approved by the NRC with corresponding conditions. If this provision is used, it must also include Appendix I. NRC approval is not required.

2.4. Applicable Code Cases are provided in Table 4.1.1.

2.5. 10CFR50.55a conditions are provided in 2.2 and Table 4.4 of this Program Plan.

3.0 Definitions 3.1. NONDESTRUCTIVE EXAMINATION (NDE) - An examination by the visual, surface, or volumetric method.

3.2. PERFORMANCE DEMONSTRATION ADMINISTRATOR (PDA) - the administrator of the PDI program. The EPRI NDE Center is the PDA for the program

Page 134 of 188 3.3. PERFORMANCE DEMONSTRATION INITIATIVE (PDI) - an organization comprised of all U.S. nuclear utilities that was formed to provide an efficient, cost-effective, and technically sound implementation of Appendix VIII performance demonstration requirements. PDI is responsible for preparing the test protocol, providing the NRC/Code interface, and providing technical, financial, and administrative oversight.

Under the guidance of PDI and in compliance with the EPRI Quality Program and Procedure Manual, the PDA collects and disperses supplemental funding, provides technical and legal support, and administers the plan provided by PDI. This includes specimen design, sample fabrication, qualification testing, and maintaining registries. The PDA also performs other support activities such as participation in NUPIC and EPRI internal QA audits, coordinating Authorized Nuclear Inservice Inspector involvement in the PDI program, and maintaining generic procedures for manual ultrasonic examinations.

3.4. PDI PROGRAM - an industry initiative administered by the EPRI NDE Center 3.5. PERFORMANCE DEMONSTRATION QUALIFICATION

SUMMARY

(PDQS) -

the paperwork provided by the PDA (EPRI NDE Center) documenting that an individual or an ultrasonic procedure has been qualified in accordance with the PDI Program.

3.6. ULTRASONIC EXAMINATION (UT) - A volumetric NDE method for the purpose of verifying the absence of unacceptable discontinuities throughout the volume of material.

4.0 General Requirements 4.1. Mandatory Appendix VIII provides requirements for performance demonstration for ultrasonic examination procedures, equipment and personnel used to detect and size flaws.

The Mandatory Appendix VIII requirements SHALL be implemented by qualified applicable ultrasonic examination procedures, equipment, and personnel through PDI, the additional requirements of the 0PEP10-ZA- 0002 (Inservice Inspection Ultrasonic Non Destructive Examination Written Practice) for certification of ultrasonic examination personnel to Mandatory Appendix VII requirements, and the individual ultrasonic examination procedures 4.2. The Supplements of Mandatory Appendix VIII apply ONLY to ultrasonic examinations (not including thickness measurements). Reference Section 6.0 for PDI compliance with Mandatory Appendix VIII supplements.

4.3. Welds and/or components NOT addressed by Mandatory Appendix VIII supplements SHALL be examined in accordance with Appendix I of the 2013 Edition of the Code, unless otherwise noted.

4.4. In accordance with Mandatory Appendix I-2600, Components to which Mandatory Appendix VIII is not applicable, examination procedures, personnel, and equipment qualified in accordance with Mandatory Appendix VIII may be applied, provided such components, materials, sizes, and shapes are within the scope of the qualified examination procedure. When this provision is used, examination coverage shall be in accordance with I-3000 and no other requirements of I-1000 or I-2000 apply.

Page 135 of 188 4.5. STP will use personnel and techniques that have been qualified to the PDI Program. STP will utilize the EPRI PDI Program for the personnel qualification for the applicable supplements. The Performance Demonstration Qualification Summary (PDQS) will be used to verify qualification. The PDQS will become part of the NDE personnel certification paperwork. The entire certification/qualification paperwork will be retained as a lifetime record.

4.6. STP will utilize ultrasonic procedures equivalent to the Qualified Generic PDI procedures (utilizing the same essential variables as described in Paragraph VIII-3130 of Mandatory Appendix VIII of the 2013 Edition). The equipment to be used will be included in the NDE procedure used to qualify the NDE personnel. Examination coverage will be provided in the examination procedures.

4.7. Vendor procedures and personnel certifications SHALL be reviewed (i.e., PDQS) to ensure compliance with the requirements of Mandatory Appendix VIII.

4.8. Prior to the start of the examination process, an initial review is performed to ensure that the examination personnel and equipment meet Mandatory Appendix VIII requirements.

4.9. Augmented examinations will be performed by qualified Mandatory Appendix VIII examination personnel for the components being examined.

5.0 Ultrasonic Evaluations 5.1. Personnel performing NDE evaluations and reviews, other than the examiner, are to be knowledgeable of Mandatory Appendix VIII requirements but need NOT be specifically qualified for the examination supplement being evaluated. Mandatory Appendix VIII examination results can only be changed or over-ruled by a qualified individual.

5.2. Acceptance standards for ultrasonic examinations SHALL be in accordance with the applicable Edition and Addenda of ASME Section XI identified in the ISI Program Plan.

5.3. Indications are classified as either geometrical (including metallurgical) or flaws per Mandatory Appendix III. The STP position is that all reflectors SHALL be evaluated, regardless of amplitude, to the extent necessary to determine shape, identity and location.

6.0 Support Documents 6.1. Attachment A, PDI Cross Reference to Mandatory Appendix VIII Supplements 6.2 Attachment B, Examination References 6.3 Attachment C, PDI Procedures 6.4 EPRI Technical Report 3002010307, Nondestructive Evaluation Guide for Compliance of Class 1, 2, 3, IWF, and Common Augmented Inservice Inspection Requirements

Page 136 of 188 Appendix VIII Appendix VIII Supplement Number Supplement Description EPRI Qualified PDI Generic Procedure Remarks Evaluating Electronic The PDI Program does 1 Characteristics of not support this Ultrasonic Systems activity.

PDI-UT-2 (PDI Generic Procedure for the Ultrasonic Examination of Austenitic Pipe Welds)

PDI-UT-3 (PDI Generic Procedure for Ultrasonic Through Wall Sizing in Pipe Welds) Welds containing clad EPRI-PIPE-MPA-1 (Procedure for Manual Phased Array are excluded.

Ultrasonic Examination of Austenitic and Ferritic Pipe Reference Code Case Welds) N-696-1, based on Qualification Reg. Guide 1.147, EPRI-PIPE-TWS-MPA-1(Procedure for Manual Phased 2 requirements for wrought Rev. 18, relief is Array Ultrasonic Through Wall Sizing In Pipe Welds)

Austenitic Piping Welds required.

EPRI-PA-1 (Procedure for Automated Phased Array Ultrasonic Flaw Detection and Length Sizing in Austenitic and Ferritic Piping Welds)

EPRI-SPA-1 (Procedure for Automated Single Phased-Array Probe Ultrasonic Flaw Detection and Length Sizing in Ferritic and Austenitic Piping Welds)

Page 137 of 188 Appendix VIII Appendix VIII Supplement Number Supplement Description EPRI Qualified PDI Generic Procedure Remarks PDI-UT-1 (PDI Generic Procedure for the Ultrasonic Examination of Ferritic Pipe Welds)

PDI-UT-3 (PDI Generic Procedure for Ultrasonic Through Wall Sizing in Pipe Welds)

EPRI-PIPE-MPA-1 (Procedure for Manual Phased Array Ultrasonic Examination of Austenitic and Ferritic Pipe Welds) Reference Code Case Qualification N-696-1, based on EPRI-PIPE-TWS-MPA-1(Procedure for Manual Phased 3 Requirements for Ferritic Reg. Guide 1.147, Array Ultrasonic Through Wall Sizing In Pipe Welds)

Piping Welds Rev. 18, relief is EPRI-PA-1 (Procedure for Automated Phased Array required.

Ultrasonic Flaw Detection and Length Sizing in Austenitic and Ferritic Piping Welds)

EPRI-SPA-1 (Procedure for Automated Single Phased-Array Probe Ultrasonic Flaw Detection and Length Sizing in Ferritic and Austenitic Piping Welds)

PDI-UT-6 (PDI Generic Procedure for the Ultrasonic Examination of RPV Welds)

Qualification PDI-UT-7 (Generic Procedure for Through Wall and Length requirements for the Clad Sizing of Ultrasonic Indications in RPV Welds)

/ Base Metal Interface of PDI-UT-12 (Procedure for Manual Phased Array Ultrasonic RPV (applies to inner Examination of Reactor Pressure Vessel Welds) 4 15% of Clad vessels and EPRI-RPV-PA-1 (Procedure for Manual Phased Array may be applied to the Ultrasonic Examination of Reactor Pressure Vessel Welds) inner 15% of unclad vessels in accordance with VIII-S6-1, Note 1.)

Note: EPRI does not maintain generic procedures for RPV encoded examination.

Page 138 of 188 Appendix VIII Appendix VIII Supplement Number Supplement Description EPRI Qualified PDI Generic Procedure Remarks PDI-UT-11 (PDI Generic Procedure for the Ultrasonic Detection and Sizing of RPV Nozzle-to-Shell Welds and Nozzle-to-Inner Radius)

Qualification PDI-UT-13 (Procedure for Manual Phased Array Ultrasonic requirements for Nozzle Examination of Reactor Pressure Vessel Nozzle to Shell Reference Code Case 5 Welds and Nozzle Inner Radius Regions)

Examination From the N-613-2 Outside Surface Note: EPRI does not maintain generic procedures for RPV nozzle and inner radius encoded examination.

PDI-UT-6 (PDI Generic Procedure for the Ultrasonic Examination of RPV Welds)

PDI-UT-7 (Generic Procedure for Through Wall and Length Qualification Sizing of Ultrasonic Indications in RPV Welds) requirements for RPV welds other than Clad / PDI-UT-12 (Procedure for Manual Phased Array Ultrasonic Base Metal Interface Examination of Reactor Pressure Vessel Welds) 6 (applies to unclad ferritic EPRI-RPV-PA-1 (Procedure for Manual Phased Array components and the outer Ultrasonic Examination of Reactor Pressure Vessel Welds) 85% of clad ferritic components)

Note: EPRI does not maintain generic procedures for RPV encoded examination.

Qualification requirements for Nozzle EPRI does not maintain a generic procedure for Supplement 7

Examination from the 7.

inside surface

Page 139 of 188 Appendix VIII Appendix VIII Supplement Number Supplement Description EPRI Qualified PDI Generic Procedure Remarks PDI-UT-4 (PDI Generic Procedure For The Ultrasonic Qualification Examination Of Studs And Bolts From The Bore) Reference Code Case 8 requirements for Bolts N-845 in lieu of and Studs PDI-UT-5 (PDI Generic Procedure for Straight Beam Supplement 8.

Ultrasonic Examination Of Studs And Bolts)

None PDI Qualification is in Qualification the course of requirements for Cast preparation. The 9

Austenitic Piping Welds Requirements of (In course of preparation) Appendix III are applicable.

PDI-UT-10, (PDI Generic Procedure For The Ultrasonic Examination Of Dissimilar Metal Piping Welds)

EPRI-DMW-PA-1 (Procedure for Manual Phased Array Reference Code Case Qualification Ultrasonic Examination of Dissimilar Metal Welds) N-695-1 and N-696-1, requirements for 10 but Relief is required Dissimilar Metal Piping EPRI-ENC-DMW-PA-1 (Procedure for Encoded Phased based on RG 1.147, Welds Array Ultrasonic Examination of Dissimilar Metal Piping Rev 18.

Welds)

PDI-UT-8 (PDI Generic Procedure For The Ultrasonic Qualification Examination Of Weld Overlay Similar and Dissimilar Metal requirements for full Welds)

Reference Code Case 11 structural overlaid EPRI-WOL-PA-1 (Procedure for Manual Phased Array N-653-1 wrought austenitic piping Welds Ultrasonic Examination of Weld Overlaid Similar and Dissimilar Metal Welds)

Page 140 of 188 Appendix VIII Appendix VIII Supplement Number Supplement Description EPRI Qualified PDI Generic Procedure Remarks Coordinated implementation of 12 selected aspects of Supplements 2 and 3 Deleted in the 2006 13 Addenda Coordinated implementation of PDI is based on Code selected aspects of Case N-696-1 which 14 Supplements 10, 2, and 3 based on Reg. Guide for piping examinations 1.147, Rev. 18 performed from the requires relief.

inside surface

Page 141 of 188 ATTACHMENT B (Appendix G)

EXAMINATION REFERENCES ASME CODE EXAM. REFERENCES COMPONENT RPV Shell and Head Welds (Excluding Flange 2013 Edition, Appendix VIII; Sup. 4 and/or 6 Welds)

RPV Vessel-to Flange and Head-to-Flange Welds 2013 Edition, Appendix I (I-2110(b))

RPV Nozzle Welds and Nozzle Inside Radius 2013 Edition, Appendix VIII; Sup. 5 Section Examined from the Outside Surface RPV Nozzle Welds and Nozzle Inside Radius 2013 Edition, Appendix VIII; Sup. 7 Section Examined from the Bore and Inside Surface Pressurizer and Steam Generator Shell Welds 2013 Edition, Appendix I (I-2120)

Pressurizer and Steam Generator Nozzle Welds and 2013 Edition, Appendix I (I-2400)

Nozzle Inside Radius Section Other Vessels with Thickness 2 Inches 2013 Edition, Appendix I (I-2200)

Austenitic Piping Welds 2013 Edition, Appendix VIII; Sup. 2 Ferritic Piping Welds 2013 Edition, Appendix VIII; Sup. 3 Dissimilar Metal Piping Welds 2013 Edition, Appendix VIII; Sup. 10 Weld Overlays 2013 Edition, Appendix VIII; Sup. 11 Bolts and Studs 2013 Edition, Appendix VIII; Sup. 8 2013 Edition, Appendix VIII; Sup. 9 Cast Austenitic Piping Welds (in course of preparation)

Notes:

1.0 Augmented piping weld examinations will also be typically performed per the applicable Code Appendix VIII Supplement.

Page 142 of 188 ATTACHMENT C (Appendix G)

PDI PROCEDURES PROCEDURE NUMBER PROCEDURE TITLE PDI-UT-1 PDI Generic Procedure for the Ultrasonic Examination of Ferritic Pipe Welds PDI-UT-2 PDI Generic Procedure for the Ultrasonic Examination of Austenitic Pipe Welds PDI-UT-3 PDI Generic Procedure for the Ultrasonic Through Wall Sizing PDI-UT-4 PDI Generic Procedure for the Ultrasonic Examination of Studs and Bolts from the Bore PDI-UT-5 PDI Generic Procedure for Straight Beam Ultrasonic Examination of Studs and Bolts PDI-UT-6 PDI Generic Procedure for the Ultrasonic Examination of RPV Welds PDI-UT-7 PDI Generic Procedure for Through Wall and Length Sizing of Ultrasonic Indications in RPV Welds PDI-UT-8 PDI Generic Procedure for the Ultrasonic Examination of Weld Overlay Similar and Dissimilar Welds PDI-UT-10 PDI Generic Procedure for the Ultrasonic Examination of Dissimilar Metal Piping Welds PDI-UT-11 PDI Generic Procedure for the Ultrasonic Detection and Sizing of RPV Nozzle-to-Shell Welds and Nozzle-to-Inner Radius PDI-UT-12 Procedure for Manual Phased Array Ultrasonic Examination of Reactor Vessel Welds PDI-UT-13 Procedure for Manual Phased Array Ultrasonic Examination of Reactor Pressure Vessel Nozzle to Shell Welds and Nozzle Inner Radius Regions

Page 143 of 188 EPRI-RPV-PA-1 Generic Procedure Manual Phased Array Ultrasonic Examination of Reactor Pressure Vessel Welds EPRI-PIPE-MPA-1 Procedure for Manual Phased Array Ultrasonic Examination of Austenitic and Ferritic Pipe Welds EPRI-PIPE-TWS- EPRI-PIPE-TWS-MPA-1Procedure for Manual Phased Array MPA-1 Ultrasonic Through Wall Sizing In Pipe Welds Procedure for Automated Phased Array Ultrasonic Flaw Detection EPRI-PA-1 and Length Sizing in Austenitic and Ferritic Piping Welds Procedure for Automated Single Phased-Array Probe Ultrasonic EPRI-SPA-1 Flaw Detection and Length Sizing in Ferritic and Austenitic Piping Welds Procedure for Manual Phased Arras Ultrasonic Examination of EPRI-DMW-PA-1 Dissimilar Metal Welds Procedure for Encoded Phased Array Ultrasonic Examination of EPRI-ENC-DMW-PA- Dissimilar Metal Piping Welds 1

Procedure for Manual Phased Array Ultrasonic Examination of EPRI-WOL-PA-1 Weld Overlaid Similar and Dissimilar Metal Welds

Page 144 of 188 APPENDIX H BMI COMMITMENT IMPLEMENTATION PLAN & HISTORICAL DATA

Page 145 of 188 BMI IMPLEMENTATION PLAN & HISTORICAL DATA 1.0 Documentation of BMI NDE Historical Commitments COMMENTARY: The most likely cause of the nozzle cracks and leakage in Unit 1 BMI penetrations #1 and #46 is manufacturing defects and subsequent crack initiation which is limited to those two penetrations. However, since PWSCC and low cycle fatigue cannot be completely eliminated as possible causes, the possibility of future nozzle defects and leakage cannot be eliminated either. Therefore, the objective of future inspections is to validate that the nozzle defects and leakage are limited to Unit 1 nozzles #1 and #46. Because the cracks were tight and the leakage was small and slow to develop, short-term inspections are not expected to provide meaningful results. Consequently, the inspection plan is a longer-term plan designed to detect potential flaws after some reasonable period of time has passed in which leakage might develop. If shorter-term defects and leakage should develop, the routine boric acid walkdowns have demonstrated that small leaks can be detected well before defects become structurally significant.

1.1 Unit 1: Bare Metal Visual (BMV) Examinations of Repaired/Replaced BMI Penetrations (Ref. CR-03-11746-05) 1.1.1 STP Response to RAI on RR-ENG-2-32 (NOC-AE-03001559): STPNOC will perform successive inspections on repaired/replaced BMI penetration nozzles, weld pads, and J-groove welds that establish a new pressure boundary.

Repaired/replaced BMI nozzles, weld pads, and J-groove welds will receive a bare metal visual examination each refueling outage in accordance with the STP Boric Acid Walkdown procedure.

Page 146 of 188 1.1.2 NRC Letter to STP on SIT Review and Staff Evaluation of BMI Leakage Investigation and Repair, July 31, 2003: (AE-NOC-03001093)First, STPNOC will continue to perform 100 percent bare metal visual examinations of the STP, Unit 1 and 2 RPV bottom heads as part of the STPNOC BACC inspection program in a manner consistent with how the inspections were conducted for STP Unit 1 in April 2003. This is not a change for either unit, only a continuation of the licensees established program of performing such inspections during unit refueling outages and during unit forced outages if the unit has been in operation for more than three months and the forced outage is scheduled to be 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or greater in duration.

The STPNOC BACC inspection program was demonstrated to be effective with regard to finding very small deposits around STP, Unit 1, BMI penetrations 1 and

46. The licensee has concluded that its established program will be effective at finding evidence of future leakage, if any were to occur, prior to the development of degradation which significantly affects the structural integrity of either units RPV. The licensee has determined that this conclusion is valid for both the STP, Units 1 and 2, penetrations which maintain the original nozzle/J-groove weld configuration, as well as for the two repaired penetrations on the STP, Unit 1, RPV bottom head.

1.2 Unit 1: Enhanced Visual Examination (EVT) of Boat Sample Cavities at BMI Penetrations 1 and 46 at Next RPV ISI Examinations (Ref. CR-03-11746-06, -07)

COMMENTARY: The enhanced visual will be performed in conjunction with the UT re-examination of the 58 Unit 1 guide tube penetrations. The specific purpose of examining the boat sample excavations on penetrations #1 and #46 is to inspect for stress corrosion cracking of the thermally cut surface.

Video documentation of a baseline inspection, which was performed in July 2003, is documented in the NDE records package transmitted to RMS under FSUG no. T0403 with record date of 7/18/03.

1.2.1 STP Response to RAI on RR-ENG-2-35 (NOC-AE-03001560): ISI examinations of reactor vessel interior attachment welds below the core belt region will be performed in conjunction with the examinations of the vessel shell and bottom head welds when the internals and core barrel are removed. The next ISI VT-3 visual examination of the repaired BMI J-groove welds will be augmented with an enhanced visual examination of the boat sample cavities.

1.2.2 NRC letter to STP authorizing RR-ENG-2-35, August 1, 2003: (AE-NOC-03001095) the next ISI VT-3 visual examination of the repaired BMI J-groove welds will be augmented with an enhanced visual examination of the cut surfaces.

Page 147 of 188 1.2.3 NRC Letter to STP authorizing RR-ENG-2-35, August 1, 2003: (AE-NOC-03001095) At the next inspection of the reactor vessel attachment welds, the licensee will perform an enhanced VT-1 examination (defined as the ability to discern a 0.5 mil wire against a neutral gray background) of the EDM surfaces to inspect for potential cracking related to the EDM process.

1.3 Unit 1: Volumetric NDE and EVT of All BMI Penetrations at Next RPV ISI Examinations (Ref. CR-03-11746-06, -07)

COMMENTARY: The intent of this commitment is to re-examine the 58 Unit 1 BMI guide tube penetrations using the same procedures and techniques in order to compare results with the inspections performed in the summer of 2003. The hypothesis is that the five cracks found in penetrations #1 and #46 resulted from manufacturing defects, not PWSCC. Therefore, recurrence of cracking in other tubes is not expected. There were no cracks in a number of tubes, which showed regions of discontinuities. These discontinuities could be weld defects such as porosity, inclusions, or lack of fusion and may be potential future crack initiation sites.

1.3.1 Supplement to STP Commitment to Investigate and Repair BMI Penetration Indications (NOC-AE-03001567): Perform volumetric and enhanced visual examinations of the Unit 1 penetrations at the next in-service inspection of the Unit 1 reactor pressure vessel.

1.3.2 NRC Letter to STP on SIT Review and Staff Evaluation of BMI Leakage Investigation and Repair, July 31, 2003: Second, STPNOC has committed to perform volumetric and enhanced visual examinations of the STP, Unit 1, penetrations at the next in-service inspection of the RPV, which is currently planned for 2008 or 2009. Although redesigned tooling may be used for the inspections, it is the NRC staffs understanding that this reflects the licensees commitment to perform inspections equivalent to those identified as NDE activities (1) and (2). These inspections were demonstrated to be effective at finding and characterizing crack-like indications in the Inconel Alloy 600 nozzle material of BMI penetrations 1 and 46 [References 11 and 12].

1.3.2.1 NDE Activities (1) and (2) of Section 3.0 of the July 31, 2003 NRC letter:

(1) Ultrasonic testing (UT) of all 58 STP, Unit 1, BMI nozzles from the nozzle ID using axial, circumferential, and zero degree probes to inspect the nozzle wall material for evidence of degradation,

Page 148 of 188 (2) Enhanced visual testing (EVT-1, defined, in part, by the ability to discern a 0.5 mil wire on a neutral gray background) of the J-groove weld surfaces of all 58 STP, Unit 1, BMI penetrations for evidence of cracking, 1.4 Unit 1: UT of One Repaired BMI Penetration for Wastage of Bore During 1RE13 and 1RE15 Refueling Outages (Ref. CR-03-11746-06, -07)

COMMENTARY: The half-nozzle repair leaves a small gap between the two nozzle halves which results in the carbon steel pressure vessel being exposed to borated primary water. Corrosion of the carbon steel has been determined to be acceptable in this configuration, however, some concerns remain that excessive corrosion could still occur. The purpose of this inspection is to search for the unlikely possibility of vessel wastage resulting from such excessive corrosion. Since this is a slow, time-dependent process, the inspections will occur in 1RE13 and 1RE15 on one repaired nozzle location. Baseline phased array inspections, performed in July 2003, are documented in STP NDE records as UT Exam-2003-0025 for penetration no. 1 and UT Exam-2003-0026 for penetration no. 46.

1.4.1 Supplement to STP Commitment to Investigate and Repair BMI Penetration Indications (NOC-AE-03001567): Perform ultrasonic examinations of the reactor pressure vessel base metal around the repaired penetrations at future selected Unit 1 refueling outages to confirm there are no indications of pressure vessel wastage from RCS water in the gap area of the repaired penetrations. The details of these examinations will be described in ASME Code relief requests for the repairs. (See 1.4.2 below) 1.4.2 STP Response to RAI on RR-ENG-2-32 (NOC-AE-03001563): STP Nuclear Operating Company (STPNOC) performed UT examination of the reactor vessel bottom head (RVBH) BMI bore hole areas of Penetrations 1 and 46 as a baseline for future wastage monitoring. STPNOC will perform UT examinations of the RVBH base material around one of these two BMI penetrations for the next two alternate refueling outages (i.e., 1RE13 and 1RE15) to confirm there is no indication of RVBH base material wastage from RCS water in the annulus region of the repaired penetration. The results of the UT examination will be applicable to both repaired penetrations because both penetrations have the same design configuration, materials, and operating environment. If any indication of wastage is detected by these UT examinations, the corrosion monitoring will be extended to the other repaired penetration during that outage.

Page 149 of 188 1.4.3 NRC Letter to STP on SIT Review and Staff Evaluation of BMI Leakage Investigation and Repair, July 31, 2003: Third, STPNOC has committed to perform ultrasonic examinations of the RPV base material around one of the two repaired BMI penetrations for the next two alternate refueling outages (i.e., 1RE13 and 1RE15) to confirm that there are no indications of RPV low-alloy steel wastage from RCS water in the annulus area of the repaired penetrations [References 11 and 12]. It is the NRC staffs understanding that this reflects the licensees commitment to perform an inspection of either STP, Unit 1, BMI penetration 1 or 46 in 1RE13 and 1RE15 equivalent to those identified as NDE activity (5) in Section 3.0 above.

1.4.3.1 NDE Activity (5) of Section 3.0 of the July 31, 2003 NRC letter: (5)

Phased-array UT from the outside surface of the RPV bottom head to inspect penetrations 1 and 46 for evidence of low-alloy steel base material corrosion due to exposure to borated RCS water.

1.5 Unit 2: Volumetric NDE of All BMI Penetrations at Next Refueling Outage When Core Barrel Is Removed (Ref. CR-03-11746-06, -07) 1.5.1 Supplement to STP Commitment to Investigate and Repair BMI Penetration Indications (NOC-AE-03001567): Examine Unit 2 penetrations with a volumetric NDE method at the next Unit 2 refueling outage where the core barrel is planned to be removed.

1.5.1.1 NRC Letter to STP - Summary of HQ, Region IV and STP Teleconference of July 10, 2003 (TAC No. MB8435), August 8, 2003 (ST-AE-NOC-03001104) Unit 2 visual examination has shown no problems. The licensee completed the Unit 2 penetration UT examination in 2005.

1.5.1.2 Revised commitment to inspect STP Unit 2 BMI Penetrations (NOC-AE-05001880 dated May 5, 2005): Volumetric examination of the Unit 2 BMI Penetrations has been rescheduled for the Unit 2 10-year Inservice Inspection (Reactor Vessel) currently scheduled for Spring 2010.

1.5.2 NRC Letter to STP on SIT Review and Staff Evaluation of BMI Leakage Investigation and Repair, July 31, 2003: Finally, STPNOC has committed to perform volumetric inspections of all STP, Unit 2, BMI penetrations at the next refueling outage when the core barrel is planned to be removed. According to the licensee this is currently planned for refueling outage 2RE11 in 2005. Although redesigned tooling may be used for the inspections, it is the NRC staffs understanding that this reflects the licensees commitment to perform inspections equivalent to those identified as NDE activity (1). (See 1.5.1.2 above)

Page 150 of 188 1.5.2.1 NDE Activity (1) of Section 3.0 of the July 31, 2003 NRC letter: (1)

Ultrasonic testing (UT) of all 58 STP, Unit 1, BMI nozzles from the nozzle ID using axial, circumferential, and zero degree probes to inspect the nozzle wall material for evidence of degradation 2.0 Description of NDE Commitments 2.1 Unit 1: Bare Metal Visual (BMV) Examination of Repaired/Replaced BMI Penetrations Each Refueling Outage

  • Commitment is to inspect new welds and materials of repaired/replaced penetrations (i.e., Nos.1 & 46) that are pressure-retaining
  • Repaired/replaced BMI nozzles, weld pads, and J-groove welds will receive BMV exam each refueling outage
  • EVT will be performed in conjunction with VT-3 on original J-groove weld per Examination Category B-N-2, Item B13.60
  • B-N-2 welds beyond core belt region are only required to be inspected when made accessible by core barrel removal
  • EVT of boat sample cavities will be performed in conjunction with next RPV ISI exams 2.3 Unit 1: Volumetric NDE and EVT of All BMI Penetrations at Next RPV ISI Examinations 2.3.1 NRC Letter to STP - Summary of HQ, Region IV and STP Teleconference of July 10, 2003 (TAC No. MB8435), August 8, 2003 (ST-AE-NOC-03001104) As part of its post-repair monitoring program, the licensee will commit to do penetration ultrasonic testing (UT) inspections again at the end of the Unit 1 current inservice inspection interval, sometime in 2008 or 2009. (See 1.4.2 above)

Page 151 of 188 2.3.2 Supplement to STP Commitment to Investigate and Repair BMI Penetration Indications (NOC-AE-03001567): Perform ultrasonic examinations of the reactor pressure vessel base metal around the repaired penetrations at future selected Unit 1 refueling outages to confirm there are no indications of pressure vessel wastage from RCS water in the gap area of the repaired penetrations. The details of these examinations will be described in ASME Code relief requests for the repairs. (See 1.4.2 above)

  • Repeat volumetric NDE (UT) of nozzle base material from nozzle ID and EVT of internal (i.e., wetted) J-groove weld surfaces of all penetrations
  • Perform NDE and EVT at next RPV ISI exam when core barrel is removed
  • Completed 1RE15 (Fall 2009) 2.4 Unit 1: UT of One Repaired BMI Penetration for Wastage of Bore during 1RE13 and 1RE15 Refueling Outages
  • Perform phased array UT from Outside Surface of RVBH
  • Select either Penetration No. 1 or No. 46 as sample based on access, UT coverage, etc.
  • Performed UT during refueling outage 1RE13 (Fall 2006) and during refueling outage 1RE15 (Fall 2009)
  • No wastage was detected in sampled penetration 2.5 Unit 2: Volumetric NDE of All BMI Penetrations at Next Refueling Outage when Core Barrel is removed
  • Volumetric NDE of penetrations will repeat the UT exams of nozzle material from nozzle ID as performed in Unit 1 during 1RE11
  • Performed examination during 2RE14 (Fall 2010) NO wastage was detected.

2.6 10 CFR 50.55a(g)(6)(ii)(E)(1) that became effective July 21, 2011, requires that the STP Inservice Inspection program SHALL be augmented by implementing Code Case N-722-1 Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials. Code Case N-722-1 includes inspection requirements for BMI penetrations. STP has implemented Code Case N-722-1 starting with outages 1RE15 &

2RE14. Future inspections of BMI penetrations will be performed in accordance with code case N-722-1.

Page 152 of 188 APPENDIX I ALLOY 600 IMPLEMENTATION PLAN & HISTORICAL DATA

Page 153 of 188 ALLOY 600 IMPLEMENTATION PLAN & HISORTICAL DATA 1.0 Commitments 1.1 Materials-related industry organizations have provided guidance and support for effective RCS materials management and also have the authority by NEI 03-08 to impose industry requirements when deemed necessary. Industry RCS materials actions are designated under NEI 03-08 protocol as one of the following implementation categories:

  • Good Practice,
  • Needed, or
  • Mandatory STP (and the industry) has committed to implement NEI 03-08, Needed and Mandatory actions, and will be tracked in accordance with STP procedure for Licensing Commitment Management and Administration (0PGP05-ZN-0002).

1.2 Materials Reliability Program (MRP): MRP-126 Generic Guidance for Alloy 600 Management requires an Alloy 600 Management Plan to define the processes used to maintain the integrity and operability of each Alloy 600/82/182 component for the remaining life of the plant. This requirement is implemented under the NEI 03-08 protocol in STP procedure 0PGP04-ZE-0006 (Alloy 600 Materials Management Program).

0PGP04-ZE-0006 establishes short and long term guidance for mitigation, inspection (type and frequency), repair, and replacement of all Alloy 600 base material and Alloy 82/182 weld metal locations.

1.3 NRC Order EA-03-009 Revision 1, dated February 20, 2004 established required inspections of Reactor Pressure vessel Heads and associated penetration nozzles at Pressurized Water Reactors. This Order was effectively immediately and established the criteria for determining the susceptibility category and applicable inspection methods and frequency. Currently, the order applies to heads fabricated with Alloy 600 or 690 materials.

50.55a(g)(6)(ii)(D)(1) states that once Code Case N-729-1 is implemented the First Revised NRC Order EA-03-009 no longer applies and SHALL be withdrawn. Code Case N-729-1 has been implemented at STP (CR: 09-10162).

Page 154 of 188 1.4 The following MRP letters have been issued with needed or mandatory requirements and have been implemented at STP as required under the NEI 03-08 protocol (unless otherwise noted):

1.4.1 MRP letter 2004-05, dated April 2, 2004 This letter categorized the recommendations of MRP letter 2003-039 as Needed and is applicable to Alloy 82/182 butt welds with the same implementation schedule as MRP 2003-039.

MRP letter 2003-039, dated January 20, 2004 recommended that a bare metal VT be performed on all Alloy 600/82/182 pressure boundary locations that operate at a temperature greater than or equal to 350-deg F in the primary system within the next 2 refueling outages (unless it was performed during the most recent refueling outage).

1.4.2 MRP letter 2005-014, dated September 12, 2005 This letter mandated Section 1.2, Section 5, and Section 6 of MRP-139 Primary System Piping Butt Weld Inspection and Evaluation Guideline. After visual examinations required by MRP 2004-05 are completed, the visual examinations will be performed per the requirements of MRP-139.

MRP-139 identifies butt weld locations susceptible to primary water stress corrosion cracking (PWSCC) and describes approaches for inspection, re-inspection, mitigation, and flaw evaluation. The first inspections required by this guideline will be implemented in a phased approach over several years as outlined in Section 1.2. Section 5 addresses the examination requirements for the applicable welds and Section 6 provides the requirements for categorization the examination schedules applicable to each category.

1.4.3 MRP letter 2007-038, dated November 1, 2007 This letter provided interim guidance to MRP-139 for volumetric examination of butt welds <4 diameter as Mandatory in accordance with NEI 03-08 protocol. By 12-31-2010, Alloy 82/182 butt welds that are greater than or equal to 2 NPS but less than 4 NPS, not explicitly included in implementation items 2 or 3 of MRP-139, Section 1.2, and are either exposed to temperatures equivalent to the hot leg or serve an ECCS function, will be volumetrically inspected per this guideline.

There are no Alloy 82/182 butt welds at STP covered by this interim guidance.

Page 155 of 188 1.4.4 MRP letter 2007-039, dated November 1st, 2007.

This letter provides interim guidance to MRP-139 for bare metal visual examination for dissimilar metal welds 600/82/182 for piping 1 but less than 4 as Mandatory in accordance with NEI 03-08 protocol. For those locations 1 NPS and <4 NPS within the scope of this document but without an explicit requirement for volumetric examination, the initial MRP-139 visual exam SHALL be performed no later than the first refueling outage which begins after July 1, 2008. Subsequent BMV exams SHALL follow the schedule as specified in MRP Table 6-2.

This letter increases the original scope within MRP-139 for bare metal visual examination to include the 2 butt welds on RV Head vent line at the first elbow above the head. The vent line for the replacement RV heads installed in 2009 for Unit 1 and 2010 for Unit 2 are fabricated with Alloy 690/52/152 material and will not be covered by MRP-139.

1.4.5 MRP letter 2009-031, dated June 8, 2009.

This letter provides guidance on Reconciliation of BMV Requirements with Code Case N-722-1 (Mandatory Element). The letter states that performance of bare metal visual exams in accordance with the requirements of Code Case N-722-1 is an acceptable alternative to the visual examination requirements contained in MRP-139, rev. 1. Code Case N-722-1 has been implemented at STP.

1.5 STP Response dated July 27, 2004 to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors (NOC-AE-04001762).

STP committed to perform a bare metal visual inspection of each of the upper pressurizer head (steam space) nozzle to safe end weld locations every refueling outage.

STPNOC will continue to perform these inspections until one of the following conditions justify a change.

  • Regulatory or industry guidance changes,
  • STP takes measures to mitigate the effects of PWSCC at these locations, or
  • STP acquires sufficient acceptable history to propose a revised inspection and/or frequency.

STP has completed a structural weld overlay to mitigate the effects of PWSCC at these locations. Additionally, per MRP-139, rev. 0 [effective date July 14, 2005] Primary System Piping Butt Weld Inspection and Evaluation Guideline, these locations have been reclassified to an examination extent and schedule Category B based on MRP-139 table 6-1. The use of current ASME Code Examination Program is considered appropriate for Category B welds.

Page 156 of 188 1.6 MRP-139 rev. 1 [effective date December 2008, clarified the examination extent and schedule category classifications of MRP-139 table 6-1. The clarification revised the examination extent and schedule category from B to F and the frequency has changed to once in the next 5 years following the weld overlay activities. PSI examination of the pressurizer mitigation was performed in April 2008 for Unit 1 and April 2007 for Unit 2. A PDI examination of the pressurizer mitigation was performed in October 2009 for Unit 1 and April 2010 for Unit 2, no indications were found on either of the PDI examinations. The PDI examinations will continue within the existing Code examination program requirements.

1.7 10 CFR 50.55a(g)(6)(ii)(E)(1) that became effective July 21, 2011, requires that the STP Inservice Inspection program SHALL be augmented by implementing Code Case N-722-1 Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials. STP has implemented Code Case N-722-1. MRP-139 has been superseded by Code Case N-722-1.

1.8 10 CFR 50.55a(g)(6)(ii)(F)(1) that became effective July 21, 2011, requires that the STP Inservice Inspection program SHALL be augmented by implementing Code Case N-770-2 Examination Requirements for class 1 piping and nozzle dissimilar-metal butt welds. STP has implemented Code Case N-770-2. MRP-139 has been superseded by Code Case N-770-5.

1.9 A description of the STP Bottom Mounted Instruments (BMI) penetrations commitment plan for nondestructive examinations is included in Appendix H.

2.0 Applicable STP Program Procedures PROCEDURE PROCEDURE TITLE NUMBER 0PGP04-ZE-0006 Alloy 600 Material Management Program 0PGP04-ZA-0013 Reactor Coolant System Materials Management Program 0PSP11-RC-0015 ASME Section XI Inservice Inspection (Surveillance) 0PEP10-ZA-0054 ASME Section XI VE Visual Examinations

Page 157 of 188 APPENDIX J THERMAL FATIGUE IMPLEMENTATION PLAN

Page 158 of 188 THERMAL FATIGUE IMPLEMENTATION PLAN 1.0 Commitments 1.1 Materials-related industry organizations have provided guidance and support for effective RCS materials management and also have the authority by NEI 03-08 to impose industry requirements when deemed necessary. Industry RCS materials actions are designated under NEI 03-08 protocol as one of the following implementation categories:

  • Good Practice,
  • Needed, or
  • Mandatory STP (and the industry) has committed to implement NEI 03-08, rev. 1 (April 2007), Needed and Mandatory actions, and will be tracked in accordance with STP procedure for Licensing Commitment Management and Administration (0PGP05-ZN-0002).

1.2 Materials Reliability Program (MRP): EPRI MRP-146 Rev. 1 Materials Reliability Program Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines is a multi-tasked effort to provide screening, evaluation, monitoring, inspection, operations, maintenance, and modification guidance to enable utilities to avoid thermal fatigue cracking due to valve in-leakage or turbulence/swirl penetration effects in affected lines.

Materials Reliability Program (MRP): EPRI MRP-146S Materials Reliability Program Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines Supplemental Guidance provides additional screening criteria and tools for determining recommended inspection frequencies for normally stagnant non-isolable reactor coolant system branch lines that have been identified as having the potential for thermal fatigue cracking based on the first level of screening required in MRP-146 Rev. 1.

These requirements are implemented under the NEI 03-08 protocol in STP procedure Reactor Coolant System Materials Management Program (0PGP04-ZA-0013).

This procedure establishes Thermal Fatigue Management for short and long term guidance for mitigation, inspection (type and frequency), repair, and replacement of all potential thermal fatigue cracking locations.

Page 159 of 188 1.3 Based on the criteria established in MRP-146, STP completed a Thermal Fatigue screening and evaluation of Unit 1 & 2 in February 2007. The screened-in locations were inspected during 1RE15 (September 2009) & 2RE14 (April 2010) using the requirements of EPRI PWRMRP-23 NDE Technology for Detection of Thermal Fatigue Damage in Piping. No indications were detected during the inspection activities. Inspection frequency is based on the requirements of MRP-146 Rev. 1.

STP has implemented the requirements of MRP-146 Rev. 1 in early 2012.

1.4 STP has implemented the requirements of MRP-192 Rev. 2 Assessment of RHR Mixing Tee Thermal Fatigue in PWR Plants. An evaluation based on MRP-192 has determined that the RHR mixing tees at STP are susceptible to thermal fatigue.

The Unit 1 & 2 mixing tees are scheduled for inspection in September 2010 using the inspection requirements of PWRMRP-23 STP has implemented the requirements of MRP-192 Rev. 2 in early 2012.

Applicable STP Program Procedures PROCEDURE PROCEDURE TITLE NUMBER 0PGP04-ZA-0013 Reactor Coolant System Materials Management Program 0PSP11-RC-0015 ASME Section XI Inservice Inspection (Surveillance)

Page 160 of 188 APPENDIX K INTERVAL OUTAGE SCHEDULES

Page 161 of 188 Component Support, Repair/Replacement, Steam Generator Tubing, System Pressure Testing, and Weld - Unit 1 Interval Period Dates Outage Dates Remarks 2 1 9/25/00 - 9/24/03 1RE10 10/3 -10/24/01 1RE11 3/26 - 4/20/03 2 9/25/03 - 9/24/07 1RE12 3/9 - 4/16/05 1RE13 10/1 - 11/4/06 3 9/25/07 - 9/24/10 1RE14 3/29 - 4/27/08 1RE15 09/30 - 11/18/09 3 1 9/25/10 - 9/24/13 1RE16 4/2 - 5/08/11 1RE17 10/20 - 11/29/12 2 9/25/13 - 9/24/17 1RE18 3/15 - 5/12/14 1RE19 10/3 - 10/29/15 1RE20 4/1 - 4/23/17 3 9/25/17 - 9/24/20 1RE21 10/6 - 10/31/18 1RE22 3/29 - 4/28/20 4 1 9/25/20 - 9/24/23 1RE23 Fall 2021 1RE24 Spring 2023 2 9/25/23 - 9/24/26 1RE25 Fall 2024 1RE26 Spring 2026 3 9/25/26 - 9/8/29 1RE27 Fall 2027 1RE28 Spring 2029 Component Support, Repair/Replacement, Steam Generator Tubing, System Pressure Testing, and Weld - Unit 2 Interval Period Dates Outage Dates Remarks 2 1 10/19/00 - 10/18/03 2RE08 3/7 - 4/2/01 2RE09 10/2 - 12/6/02 2 10/19/03 - 10/18/07 2RE10 3/31 - 4/27/04 2RE11 10/2 - 10/31/05 2RE12 3/25 - 4/28/07 3 10/19/07 - 10/18/10 2RE13 10/04 - 11/04/08 2RE14 3/27 - 5/2/10 3 1 10/19/10 - 10/18/13 2RE15 10/29 - 11/22/11 2RE16 11/16 - 12/14/13 2 1019/13 - 10/18/16 2RE17 4/4 - 4/29/15 2RE18 10/1 - 10/27/16 3 10/19/16 - 10/18/20 2RE19 3/31 - 4/24/18 2RE20 10/5 - 10/27/19 4 1 9/25/20 - 9/24/23 2RE21 Spring 2021

Page 162 of 188 Component Support, Repair/Replacement, Steam Generator Tubing, System Pressure Testing, and Weld - Unit 2 Interval Period Dates Outage Dates Remarks 2RE22 Fall 2022 2 9/25/23 - 9/24/26 2RE23 Spring 2024 2RE24 Fall 2025 3 9/25/26 - 9/8/29 2RE25 Spring 2027 2RE26 Fall 2028

Page 163 of 188 Containment Metal Liner (IWE) - Unit 1 Interval Period Dates Outage Dates Remarks 1 1 9/9/98 - 9/8/01 1RE08 3/27 - 4/28/99 1RE09 3/1 - 5/15/00 2 9/9/01 - 9/8/05 1RE10 10/3 - 10/24/01 1RE11 3/26 - 4/20/03 1RE12 3/9 - 4/16/05 3 9/9/05 - 9/8/09 1RE13 10/1 - 11/4/06 1RE14 4/29 - 4/27/08 1RE15 9/30-11/18/09 2 1 9/9/09 - 9/8/13 1RE16 4/3 - 4/27/11 1RE17 10/20 - 11/19/12 2 9/9/13 - 9/8/16 1RE18 3/15 - 5/12/14 1RE19 10/3 - 10/29/15 3 9/9/16 - 9/8/19 1RE20 4/1 - 4/23/17 1RE21 10/6 - 10/31/18 4 1 9/9/19 - 9/8/22 1RE22 Spring 2020 1RE23 Fall 2021 2 9/9/22 - 9/8/26 1RE24 Spring 2023 1RE25 Fall 2024 1RE26 Spring 2026 3 9/9/26 - 9/8/29 1RE27 Fall 2027 1RE28 Spring 2029

Page 164 of 188 Containment Metal Liner (IWE) - Unit 2 Interval Period Dates Outage Dates Remarks 1 1 9/9/98 - 9/8/01 2RE06 10/3 -10/24/98 2RE07 10/13 - 11/9/99 2RE08 3/7 - 4/2/01 2 9/9/01 - 9/8/05 2RE09 10/2 - 12/6/02 2RE10 3/31 - 4/27/04 3 9/9/05 - 9/8/09 2RE11 10/2 - 10/31/05 2RE12 3/25 - 4/28/07 2RE13 10/4 - 11/4/08 2 1 9/9/09 - 9/8/13 2RE14 3/27 - 5/2/10 2RE15 10/29-11/22/11 2RE16 11/16 - 12/14/13 2 9/9/13 - 9/8/16 2RE17 4/4 - 4/29/15 2RE18 10/1 - 10/27/16 3 9/9/16 - 9/8/19 2RE19 3/31 - 4/24/18 2RE20 10/5 - 10/27/19 4 1 9/9/19 - 9/8/22 2RE20 Fall 2019 2RE21 Spring 2021 2 9/9/22 - 9/8/26 2RE22 Fall 2022 2RE23 Spring 2024 2RE24 Fall 2025 3 9/9/26 - 9/8/29 2RE25 Spring 2027 2RE26 Fall 2028

Page 165 of 188 APPENDIX L EXAMINATION VOLUME FIGURES

Page 166 of 188 Risk Informed ISI Examination Volume For Thermal Fatigue Stress Corrosion Cracking No Specific Degradation Mechanism Identified (Reference Code Case N-716-1(2013 IWB-2500 Figures))

Weld buttering (where applicable) 2 T max 2 T max 2T max T

C D 1/3 T C 1/3 T F Exam Volume E

1/2 in C-D-E-F 1/2 in Piping Butt Weld (When Counterbore is Present within 2T of Weld Fusion Line)

Weld buttering (where applicable) 1/2 in 1/2 in 1/2 in T

C D 1/3 T C 1/3 T F Exam Volume E C-D-E-F Piping Butt Weld (When Counterbore is Not Present)

Figure D-1

Page 167 of 188 T

B 1/2T Surface Exam Area B-E Exam Volume A-B-C-D C

1/2T r

Circumferential Weld A

D E Corner radius of taper Cladding Flange Reactor Vessel Head to Flange (Reference ASME Figure IWB-2500-5)

Figure D-2

Page 168 of 188 Cladding T2 Shell G F 1/2T2 Exam Volume E-F-G-H Circumferential Weld H 1/2T3 E

T3 Head Class 1 Vessel Shell Circumferential Weld Joints (Reference ASME Figure IWB-2500-1a)

Figure D-3

Page 169 of 188 Cladding Nozzle Tn 1/2Ts 1/2Ts A

N O B C D Exam Volume Shell M-N-O-P Ri Ri-1/2 in Ts or Head P

M H G F E Exam Volume A-B-C-D-E-F-G-H Class 1 Nozzle in Shell or Head (Reference ASME Figure IWB-2500-7(b))

Figure D-4

Page 170 of 188 Pressure Retaining Component Ts 1/2 in 1/2 in B C A D Ts Surface Exam 1/2 in 1/2 in Surface Exam Area A-B Area C-D A B C D IWB Boundary IWC Boundary Support Lug Integral Attachment Welds (Reference ASME Figures IWB-2500-15 [A-B-C-D]

and IWC-2500-5(a) [A-B-C-D] )

Figure D-5

Page 171of188 Vessel Surface Exam Reinforcing Area A-B Pad A Nozzle Exam Volume C-D-E-F RHR HX Nozzle to Vessel Weld (Reference ASME Figure IWC-2500-4)

Figure D-6

Page 172 of 188 A

RHR HX 1/2 in 1/2 in Surface Exam B Area A-B Support Skirt Class 2 RHR HX Support Skirt Weld (Reference ASME Figure IWC-2500-5(c))

Figure D-7

Page 173 of 188 Flange/RSG Head D A 1/2 in Exam Volume A-B-C-D*

1/2 in C

B Shell/RSG Barrel

  • The angle beam examination for reflectors transverse to the weld shall be performed on the weld crown in two directions along the weld. (Reference ASME Section XI, Appendix III, III-4430)

Class 2 Vessel Shell/RSG Barrel to Flange/RSG Head (Reference ASME Figure IWC-2500-1)

Figure D-8

Page 174 of 188 Pump Casing or Flange B

C 1/2 in measured along surface 1/2 in Exam Surface C-D Exam Surface A-B 1/2 in D 1/2 in A

Pump Casing Note: Surface examination may be performed from either inside or outside surface of component.

Class 2 Pump Casing Welds (Reference ASME Figure IWC-2500-8)

Figure D-9

Page 175 of 188 Vessel Cladding Shell s

s C e B l S

Longitudinal Weld 1/2T h e

l D l Exam Volume A-B-C-D 1/2T A

T Class 1 Vessel Shell Longitudinal Weld Joints (Reference ASME Figure IWB-2500-2)

Figure D-10

Page 176 of 188 Setup Blocks 4 @90 Cladding degree apart P

M Primary Nozzle rimary Nozzle 1/2 in O

N Exam Volume M-N-O-P Class 1 RSG Primary Nozzle Inner Radius (Reference ASME Figure IWB-2500-7(d) &

Code Case N-593)

Figure D-11

Page 177 of 188 6 in Exam Surface A-B A

r=2 in 1/2 in B

AF/FW RSG Nozzle Shell G

4.71 in D C 45 1.62 in @ 6 and 12 deg oclock 0.43 @ 3 and 9 r=2 in oclock E 1/4 in F H

Exam Greater of r or 1/2 in Volume C-D-E-F Exam Volume G-H Class 2 Aux. Feedwater/Feedwater Nozzle to RSG (Reference ASME Figure IWC-2500-4(a))

Figure D-12

Page 178 of 188 EX.lllllfATIIJI ~ !A+<-O+f+!l-n t

  • PI l£lD nucoss ~ llE.ISm evun lllll.llES ll.lllllHS 1lllcas5 Reference UTI-063 Figure 1 PRZ Support Skirt Weld Figure D-13

Page 179 of 188 Risk Informed ISi Examination Volume Reference Figure D-1 for Examination Coverage Reference the following drawing and table for scan volume coverage from the Outside Diameter ONLY 38°L&T (48" ID Impingement Angle) 34°L Circumrrential Scan Limits 45°L

/ ...(56" ID Impingement Angle)

        • ..--38°L&T t ~ ,:/ (49 " ID Impingement Angle) f' )'...-- *45°L (56" ID Impingement Angle)

B utter ~

.. ~

Code Exam Volume .' \ Stainless Steel Sare End Class 1 RSG Nozzle to Safe End (Hot Leg)

Figure D-14 Page 1 of 2

Page 180 of 188 0o Transducer Transducer S/N Scan Direction/Location o

0 Panametrics 1.0, 1.0 Interference Scan/Weld and MHz Both Sides. Maintained 80% BR during scanning Shear Wave Angle Transducer Scan Sensitivity Scan Direction/Location S/N 38o Shear Scanned at reference due Axial - Safe End Side Only to adequate ID roll Longitudinal Wave Angle Transducer Scan Sensitivity Scan Direction/Location S/N 45oRL 68.4 dB Axial - Safe End Side Only 60oRL 70.8 dB Axial - Safe End Side Only 38oRL 67.2 dB Axial - Safe End Side Only 34oRL 78.8 dB Circumferential - Safe End Side Only 34oRL 79.6 dB Circumferential - Safe End Side Only 45oRL 74.0 dB Circumferential - Safe End Side Only Comments: 1. All axial scans were performed from the safe end side only due to the nozzle to safe end configuration. Circumferential scans were performed on the weld and both sides in both directions.

2. Reference EPRI Technical Justification for the Acceptance of Ultrasonic Demonstration Results on Beaver Valleys Steam Generator Nozzle-to-safe-end Dissimilar Metal Weld Mockup # IR-2005-85.

Class 1 RSG Nozzle to Safe End (Hot Leg)

Figure D-14 Page 2 of 2

Page 181 of 188 Shell E

H 1/2T Cladding Circumferential Weld Exam Volume E-F-G-H 1/2T G

F T

Head Class 1 RSG Channel Head to Tubeplate (Reference ASME Figure IWB-2500-6b)

Figure D-15

Page 182 of 188 1/2in.

D A Shell-to-head circumferential weld C B Exam. vol.

1/2in. A-B-C-D Class 2 RHX Shell to Head Circ. Weld (Reference ASME Figure IWC-2500-1)

Figure D-16

Page 183 of 188 Tubesheet G H F E 1/2 in. 1/2 in.

Exam. vol. E-F-G-H Class 2 RSG Tubesheet to Shell Circ. Weld (Reference ASME Figure IWC-2500-2)

Figure D-17

Page 184 of 188 Note 1

T 25% T

  • PSI EXAMINATION VOLUME Note 1

T 25% T ISI EXAMINATION VOLUME Note 1: The width of the required inspection volume shall include the original pipe weld crown plus a minimum of 0.50 from each weld toe. If the weld crown width or location of the weld with respect to the overlay position is unknown, the examination shall be performed across the entire overlay surface.

Weld Overlaid Examination Volume Figure D-18

Page 185of188 RCS Pipe

- UT or RT Base Metal for Length I ~ 1" Past Toe of Weld 00062r4 Unit 2- Socket welds IR CS Piipe UT or RT !Elbow IB ase Metal--.J ooos;,3 Unit 1- Bends - Inspect 16" of bend outside radius Examination volume for Line No.
2"-RC-1418-BBl , 2"-RC-1121-BBl , 2"-RC-1220-BBl , 2"-RC-2418-BBl ,

2"-RC-2121-BB 1, 2"RC-2220-BB 1 Figure D-19 (Reference MRP-146 Rev. 1)

Page 186of188

/ UT or RT Weld RCS Pipe

\___ UT or RT Base Metal at Bottom of Pipe and Any Horizontal Pipe Welds Within 5 Diameters of Nozzle*

(but not beyond the valve)

  • Maximum inspection extent of pipe bottom and any welds , including pipe-to-valve welds, may be reduced based on analysis. If cracking is observed within the inspection zone, additional inspection is required out to 20 diameters (but not beyond the valve) to establish the extent of condition .

00064r5 Examination volume for Line No. 4"-RC-1126-BBl , 4"-RC-1323-BBl , 4"-RC-2126-BBl , 4"-RC-2323-BBl Examination volume shall be a Yz" wide zone at the bottom of the piping within 20" of pipe-to-nozzle weld.

Piping welds shall also meet the requirements of Exam volume figure D-1 Figure D-20 (Reference MRP-146 Rev. 1)

Page 187of188 THERMAL FATIGUE EXAMINATION VOLUME RCS Pipe l!JT or RT \!IJela Examination volume for Line No. 4"-RC-2126-BBl Shaded area of vertical pipe at weld Examination to include base metal and 2.5" pass toe of weld Figure D-21

Page 188of188 THERMAL FATIGUE EXAMINATION VOLUME ht 11 *ct r h c mixing tee dm n trcam ' cld plu IJ buU and am-wl'ld Within

-I internal pipe dfamctcn from tl1c down *1.ream weld.

Down tr am Weltl i

~old RllR H r I fixing cc Outl t F'Jo t

Hot By[Jll Flow Examination volume for Line No. 8" RH-1106-KB2, 8" RH-2106-KB2 (RHR mixing tee) should include the mixing tee downstream weld plus all butt and seam-welds within at least four internal pipe diameters downstream from the mixing tee downstream weld. All piping welds included within the 4D inspection volume shall meet the requirements of Exam volume figure D-1.

It is not necessary that 100 percent of the recommended examination volumes be inspected. If full examination is not possible due to obstructions (permanent or nonremovable), weld crowns, etc. , inspections that cover the accessible examination volume are adequate to detect the presence of thermal fatigue cracking.

Figure D-22 (Reference MRP-192 Rev. 2)

NOC-AE-21003806 Attachment 2 Attachment 2 Inservice Testing Program for STP Units 1 and 2 Snubber Inservice Test Plan

South Texas Project Electric Generating Station Revision 1 P.O. Box 289 March 8,2021 Wadswoith, TX 77483 STI:35134967 SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION INSERVICE TESTING PROGRAM UNIT 1 AND 2 SNUBBER INSERVICE TEST PLAN FOURTH TEN-YEAR INTERVAL SOUTH TEXAS PROJECT UNITS 1 AND 2 DOCKET NOS. STN 50-498, STN 50-499 FACILITY OPERATING LICENSE NOS, NPF-76/80 COMMERCIAL OPERATING DATES Unit 1:8/25/1988 Unit 2: 6/19/1989 FOURTH TEN-YEAR INTERVAL DATES 9/25/2020 THROUGH 9/24/2030 Approved by: 03/6Q/Z^

Kellie Harris Date 1ST Sqis^ber Program Engineej Approved by:

^{'\ ^L "layt$ Date fSyffervisor, Testing^Kfgrams Engineering Approved by: <) "^{

Chandler Date Strategic Engineering Manager Revision 1

REVISION 1

SUMMARY

SHEET SECTION EFFECTIVE CHANGE PAGE(S) 1.1 1

  • In the third paragraph, update from "third" to "fourth" 1ST 10-year interval
  • In the third paragraph, update to fourth interval dates: "September 25,2020 and ends on September 24,2030"
  • In the fifth paragraph, update from "third" to "fourth" 10-year interval
  • In the fifth paragraph, update from "2004 Edition" to "2012 Edition" 2.1 2
  • In the first paragraph, add, "or in mitigating the consequences of an accident." Should now read, "The scope of the Snubber 1ST Program includes those Snubbers that are required to perform a specific function in shutting down the reactor to a safe shutdown condition, in maintaining the safe shutdown condition, in mitigating the consequences of an accident, or to ensure the integrity of the reactor coolant pressure boundary."

2.3 3

  • For information in the Snubber Database, add bullet for "Accessible/Inaccessible" 4.3.2 15
  • At the end of the third paragraph, add, "... (see attachment 3 for additional details)"

Table 3 16

  • Update 10CFR50,55a(b)(3)(v) to reflect 10CFR50.55a effective 05/03/2020 Section 5.0 19
  • At the end of the third paragraph, add, " ,., (see attachment 4 for additional details)"

Revision 1 1

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Inservice Test Plan SECTION EFFECTIVE CHANGE PAGE(S)

Table 7 19

  • Add the following OM Code Interpretations: 09-01 and 09-04 Section 6.0 19
  • In the third paragraph, update from "ITS program" to "1ST program" Attachments 1
  • Add column for "Accessible/Inaccessible" and 2
  • Add OM Code Interpretations 09-01 and 09-04 Revision 1 11

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Inservice Test Plan TABLE OF CONTENTS SECTION DESCRIPTION PAGE 1,0 INTRODUCTION 1 1.1 Overview 1 1.2 Program Test Plan 1 2.0 SCOPE 2 2.1 Overview 2 2.2 Code Classification 2 2,3 Snubber 1ST Listing 3 2.4 Implementing Processes [Acceptance Criteria / 3 Test or Examination Methods / Frequency or Schedule 2.5 Applicable Documents [P&IDs / Procedures] 4 3.0 METHOD OF EVALUATING SNUBBERS 13 4.0 ALTERNATIVE REQUIREMENTS TO OM CODE 14 4.1 Code Cases 14 4.2 10CFR50.55a Requirements - Code Cases 14 4.3 Code Case Adoption 15 4.4 Relief Requests 17 4.5 50.5 5 a Limitations, Modifications and 18 Clarifications Revision 1 Ill

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Inservice Test Plan TABLE OF CONTENTS SECTION DESCRIPTION PAGE 5.0 INTERPRETATIONS TO THE OM CODE 19 6.0 PROGRAM IMPLEMENTATION 19 7.0 PROGRAM CONFIGURATION CONTROL 20 8.0 TEST PLAN ATTACHMENTS 20 Unit 1 Snubber 1ST Listing Unit 2 Snubber 1ST Listing Snubber Code Cases - Information Only Snubber Interpretation - Information Only Revision 1 IV

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Inservice Test Plan

1.0 INTRODUCTION

1.1 Overview 10CFR50.55a and the South Texas Project (STP) Technical Requirements Manual invoke inservice testing (1ST) of Snubbers per ASME OM Code (Code of Operation and Maintenance of Nuclear Power Plants). Part 50.55a establishes the requirements that each nuclear power plant must develop and implement an inservice inspection and testing program. Inservice tests are used to verify operational readiness of Snubbers whose function is required for safety. The tests conducted during successive 120-month intervals must comply with the requirements of the latest edition and addenda of the OM Code that is in effect 12 months prior to the start of the interval.

Title 10, Part 50.55a of the Code of Federal Regulations invoke, by reference, the requirement for insendce inspection (ISI) of Snubbers per Section XI of the ASME Boiler and Pressure Vessel Code.

STP begins its fourth 1ST 10-year interval of commercial plant operation for Unit 1 & 2 on September 25, 2020 and ends on September 24, 2030.

The Snubber Inservice Test Plan was developed in accordance with the requirements of 10CFR50.55a. Code of Federal Regulations, Codes and Standards.

The edition and addenda of the ASME OM Code for the Snubber 1ST Program for the fourth 10-year interval is the 2012 Edition, Subsections ISTA & ISTD [the Code].

1.2 Program Test Plan Since the period of time that the requirement for inservice testing was first incorporated into the Code of Federal Regulations; the NRC, ASME, and the nuclear industry have provided additional interpretations to the Code requirements. These interpretations have been documented through various mechanisms such as 10CFR50.55a Final Rules, Code Cases, Code Interpretations, generic letters, program review meetings, site inspections, and others. It is the intent of the Program Plan to:

  • ; Establish a set criteria and philosophy for determining the Snubber Testing Scope,
  • Evaluate each plant Snubber in a consistent manner to identify which Snubbers SHOULD be included in the testing program and to identify the extent,
  • Identify Alternative requirements to the Code,
  • Identify implementation processes of testing required for each snubber and implementing documents.

Revision 1 Page 1 of 20

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Inservice Test Plan 2.0 SCOPE 2.1 Overview The scope of the Snubber 1ST Program includes those Snubbers that are required to perform a specific function in shutting down the reactor to a safe shutdown condition, in maintaining the safe shutdown condition, in mitigating the consequences of an accident, or to ensure the integrity of the reactor coolant pressure boundary.

This program was developed to encompass system safety requirements defined in 10 CFR 50 as well as Snubber functions required in response to the abnormal operational transients and accidents defined in the UFSAR. The program is not limited to the postulated accidents ofUFSAR Chapter 15. The UFSAR, Technical Specifications, and related design basis documents are the primary references used to determine which Snubbers are required to perform specific functions related to the spectrum of postulated accidents.

The only snubbers excluded from this program are those installed on nonsafety-related systems, and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.

2.2 Code Classification The quality group classification system for water, steam, and radioactive waste containing components important to the safety ofwater-cooled nuclear power plants is established by NRC Regulatory Guide 1.26, in conjunction with 10CFR50.55a. Regulatory Guide 1.26, "Quality Group Classification and Standards", defines the Quality Group Classification System consisting of four Quality Groups, A through D. Quality Group A is defined as "Reactor Coolant Pressure Boundary" (Class 1) by 10CFR50.2. The definitions of Groups B, C, and D (Class 2, Class 3 and non-classed, respectively) are provided by Regulatory Guide 1.26.

Revision 1 Page 2 of 20

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Inservice Test Plan 2.3 Snubber 1ST Listing The.Snubber 1ST Listing was previously known as the Snubber Index prior to invoking ASME OM Code, The Snubber 1ST Listing is maintained as the Snubber Database, which is an electronic database containing component test and inspection history, acceptance criteria, and references.

The Snubber Database is used to identify snubbers to be tested in accordance with the requirements of the Code. The Snubber Database contains, as a minimum, the following information about each Snubber;

  • Snubber identification (Snubber TPNS number, model/size, and serial number)
  • Applicable plant system
  • ASME Code class (same as Quality Group Classifications in R.G. 1.26)
  • TRM/NSR
  • Accessible/Inaccessible
  • Test or examination method
  • Test and examination history Reference Attachment 1 (Unit 1 Snubber 1ST Listing) & Attachment 2 (Unit 2 Snubber 1ST Listing) for a listing of snubbers tested and examined in accordance with this plan.

The listing provides basic information about the scoped snubbers.

2,4 Implementing Processes Program inservice tests required by the Code SHALL be implemented using the Surveillance Test Program process. The Surveillance Test Program provides acceptance criteria for the tests and examinations. As a result of the performed tests, any identified corrective actions and subsequent retests SHALL be made per the requirements of the Code and the ASME Section XI Repair/Replacement Program.

In conjunction with the Surveillance Test Program process, other STP site documents detail Code requirements and implementation processes [test or examination methods and frequency or schedule].

The Condition Reporting (CR) process at STP provides a method to document material deficiencies and engineering evaluations required to comply with the Code. Work orders initiated by the CR process will be used to implement corrective maintenance on snubbers identified for Inservice Testing and will allow for recording and tracking component history.

Revision 1 Page 3 of 20

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Inservice Test Plan 2.5 Applicable Documents The details of the Snubber 1ST Program referenced in this Test Plan are contained in documents that are available at STP. These documents include, but are not limited to, piping and instrumentation. diagrams, piping isometric drawings, component support drawings, and procedures that support implementation of the Snubber 1ST program.

2.5.1 Piping and Instrumentation Diagrams (P&IDS)

This section provides a listing of the various piping and instrumentation diagrams applicable to the Snubber 1ST Program, Table 1 provides a listing of the piping systems containing Class 1, 2, or 3 snubbers, and applicable Instmmentation Diagrams (P&ID's) for these Class 1, 2, and 3 piping systems. Table 1 is arranged in alphabetical system abbreviation.

Revision 1 Page 4 of 20

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Insemce Test Plan Table 1 Piping and Instnunentation Diagrams System System Drawing Sheet Abbr. Designation Number No. Drawing Title AF Auxiliary Feedwater 5S141F00024 1 Auxiliary Feedwater 5S141F00024 2 Auxiliary Feedwater 5S142F00024 1 Auxiliary Feedwater 5S142F00024 2 Auxiliary Feedwater 5S199F00020#1 Condensate Storage System (Note 1) 5S199F00020#2 Condensate Storage System (Note 1)

AP Post Accident Sampling 5Z549Z47501#1 Post Accident Sampling System 5Z549Z47501#2 Post Accident Sampling System 5Z169Z00046#1 Containment Hydrogen Momtormg System (Note 2) 5Z169Z00046#2 Contamment Hydrogen Monitoring System (Note 2)

BA Breathing Air 5Q129F05044#1 Low Pressure Breathing Air System (Note 3) 5Q129F05044#2 Low Pressure Breathing Air System (Note 3) ec Component Cooling 5R209F05017#1 Component Coolitig Water System 5R209F05017#2 Component Cooling Water System 5R209F05018#1 Component Cooling Water System 5R209F05018#2 Component Cooling Water System 5R209F05019#1 Component Cooling Water System 5R209F05019#2 Component Cooling Water System 5R209F05020#1 Component Cooling Water System Revision 1 Page 5 of 20

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Inservice Test Plan Table 1 (Cont'd.)

Piping and Instrumentation Diagrams System System Drawing Sheet Abbr. Designation Number No. Drawing Title 5R209F05020#2 Component Cooling Water System 5R209F05021#1 Component Cooling Water System 5R209F05021#2 Component Cooling Water System CH Essential Chilled Water 5VU9V10001#1 Essential Chilled Water System 5V119V10001#2 Essential Chilled Water System 3V119V10002#1 Essential Chilled Water System 3V119V10002#2 Essential Chilled Water System 3V119V10003#1 Essential Chilled Water System 3V119V10003#2 Essential Chilled Water System 3V119V10004#1 Essential Chilled Water System 3V119V10004#2 Essential Chilled Water System CM Containment Hydrogen 5Z169Z00046#1 Containment Hydrogen Monitoring System Monitoring 5Z169Z00046#2 Containment Hydrogen Monitoring System cs Containment Spray 5N109F05037#1 Containment Spray System 5N109F05037#2 Containment Spray System 5N129F05013#1 Safety Injection System (Note 4) 5N129F05013#2 Safety Injection System (Note 4) 5N129F05014#1 Safety Injection System (Note 4)

Revision 1 Page 6 of 20

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Inservice Test Plan Table 1 (Cont'd.)

Piping and Instrumentation Diagrams System System Drawing Sheet Abbr. Designation Number No. Drawing Title 5N129F05014#2 Safety Injection System (Note 4) 5N129F05015#1 Safety Injection System (Note 4) 5N129F05015#2 Safety Injection System (Note 4) cv Chemical and Volume 5R179F05005#1 Chemical & Volume Control System Control 5R179F05005#2 Chemical & Volume Control System 5R179F05006#1 Chemical & Volume Control System 5R179F05006#2 Chemical & Volume Control System 5R179F05007#1 Chemical & Volume Control System 5R179F05007#2 Chemical & Volume Control System 5R179F05008#1 Chem & Vol Control Sys BTRS Sub Sys 5R179F05008#2 Chem & Vol Control Sys BTRS Sub Sys 5R179F05009#1 Chemical & Volume Control System 5R179P05009#2 Chemical & Volume Control System DI Standby Diesel Generator 5Q159F22543#1 Diesel Air Intake & Exhaust Systems Combustion Air Intake 5Q159F22543#2 Diesel Air Intake & Exhaust Systems DO Standby Diesel Generator 5Q159F00045#1 1 Sdby Gen Fuel Oil Stor & Trans System Fuel Oil 5Q159F00045#1 2 Sdby Gen Fuel Oil Star & Trans System Revision 1 Page 7 of 20

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Insendce Test Plan Table 1 (Cont'd.)

Piping and Instrumentation Diagrams System System Drawing Sheet Abbr. Designation Number No. Drawing Title 5Q159F00045#2 1 Sdby Gen Fuel Oil Stor & Trans System 5Q159F00045#2 2 Sdby Gen Fuel Oil Stor & Trans System DW Demineratized Water 5S199F05034#1 Demin Water Dist Sys RCB FHB & MEAB (Note 3) 5S199F05034#2 Dernin Water Dist Sys RCB FHB & MEAB (Note 3)

DX Standby Diesel Generator 5Q159F22543#1 Diesel Air Intake & Exhaust Systems Combustion Gas Exhaust 5Q159F22543#2 Diesel Air Intake & Exhaust Systems ED Radioactive Vents and 5Q069F05030#1 Radioactive Vents And Drains System (Note 3)

Drains 5Q069F05030#2 Radioactive Vents And Drains System (Note 3)

EW Essential Cooling Water 5Q159F22541#1 Standby Diesel Gen Sys Cooling Water (Note 5) 5Q159F22541#2 Standby Diesel Gen Sys Cooling Water (Note 5) 5R289F05038#1 1 Essential Cooling Water System - TRN 1A 5R289F05038#1 2 Essential Cooling Water System - TRN 1B 5R289F05038#1 3 Essential Cooling Water System - TRN 1C 5R289F05038#2 1 Essential Cooling Water System - TRN 2A 5R289F05038#2 2 Essential Cooling Water System - TRN 2B 5R289F05038#2 3 Essential Cooling Water System - TRN 2C 5R289F05039#1 Essential Cooling Water System Revision 1 Page 8 of 20

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Inservice Test Plan Table 1 (Cont'd.)

Piping and Instrumentation Diagrams System System Drawing Sheet Abbr. Designation Number No. Drawing Title 5R289F05039#2 Essential Cooling Water System PC Spent Fuel Pool Cooling 5R219F05028#1 Spent Fuel Pool Cooling & Cleanup Sys 5R219F05028#2 Spent Fuel Pool Cooling & Cleanup Sys 5R219F05029#1 Spent Fuel Pool Cooling & Cleanup Sys 5R219F05029#2 Spent Fuel Pool Cooling & Cleanup Sys pp Fire Protection 5Q279F05047#1 FH,TVC, Contjmt Bldg Fire Protection Sys CNote 3) 5Q279F05047#2 FH,rVC, Contmnt Bldg Fire Protection Sys (Note 3)

FW Feedwater 5S139F00062#1 Feedwater System 5S139F00062#2 Feedwater System 5S139F00063#1 Feedwater System 5S139F00063#2 Feedwater System HC Containment Building 5V149V00018#1 Containment Bldg. HVAC System Noimal Purge (Note 3)

HVAC 5V149V00018#2 Containment Bldg. HVAC System Nonnal Purge (Note 3) 5V149V00019#1 Containment Bldg. HVAC System Supplementary Purge (Note 3) 5V149V00019#2 Contamment Bldg. HVAC System Supplementary Purge (Note 3)

IA Instrument Air 5Q119F05040#1 Fuel Hndlng Bldg & RCB Inst Air System (Note 3) 5Q119F05040#2 Fuel Hndlng Bldg & RCB Inst Air System (Note 3)

IL Integrated Leak Test 5C560F05058 Containment Leak Rate Test Pressurization System (Note 3L Revision 1 Page 9 of 20

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Inservice Test Plan Table 1 (Cont'd.)

Piping and Instrumentation Diagrams System System Drawing Sheet Abbr. Designation Number No. Drawing Title JW Standby Diesel Generator 5Q159F22540#1 Standby Diesel Generator Sys Jacket Water Jacket Water 5Q159F22540#2 Standby Diesel Generator Sys Jacket Water LU Standby Diesel Generator 5Q159F22542#1 Standby Diesel Generator Sys Lube Oil Lube Oil 5Q159F22542#2 Standby Diesel Generator Sys Lube Oil MS Main Steam 5S109F00016#1 Main Steam System 5S109F00016#2 Main Steam System 5S141F00024 1 Auxiliary Feedwater (Note 6) 5S141F00024 2 Auxiliary Feedwater (Note 6) 5S142F00024 1 Auxiliary Feedwater (Note 6) 5S142F00024 2 Auxiliary Feedwater (Note 6)

PO Reactor Coolant Pump Oil 5R379F05042#1 Reactor C/P Oil Changing System (Note 3)

Change-Out 5R379F05042#2 Reactor C/P Oil Changing System CNote 3)

PS Primary Sampling 5Z329Z00045#1 Primary Sampling System 5Z329Z00045#2 Primary Sampling System RA Radiation Monitoring 5V149V00017#1 HVAC React. CnbnntBldg. Sys. Composite (Note 7) 5V149V00017#2 HVAC React. Cntmnt Bldg. Sys. Composite (Note 7)

RC Reactor Coolaat 5R149F05001#1 RCS Primary Coolant Loop Revision 1 Page 10 of 20

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Insendce Test Plan Table 1 (Cont'd.)

Piping and Instrumentation Diagrams System System Drawing Sheet Abbr. Designation Number No. Drawing Title 5R149F05001#2 RCS Primary Coolaat Loop 5R149F05003#1 RCS Pressurizer 5R149F05003#2 RCS Pressurizer 5R149F05004#1 RCS Pressurizer Relief Tank 5R149F05004#2 RCS Pressurizer Relief Tank RD Reactor Coolant System 5R349F05046#1 RCS Vacuum Degassing System (Note 3)

Degassing 5R349F05046#2 RCS Vacuum Degassing System (Note 3)

RH Residual Heat Removal 5R169F20000#1 Residual Heat Removal System 5R169F20000#2 Residual Heat Removal System RM Reactor Makeup Water 5R279F05033#1 Reactor Makeup Water System 5R279F05033#2 Reactor Makeup Water System SA Station Air 5Q109F05041#1 FHB & RCB Service Air System (Note 3) 5Q109F05041#2 PHB & RCB Service Air System (Note 3)

SB Steam Generator Blowdo-wn 5S209F20001#1 Steam Generator Blowdowa System 5S209F20001#2 Steam Generator Blowdown System SD Standby Diesel Generator 5Q159F22546#1 Standby Diesel Starting Air System Starting Air 5Q159F22546#2 Standby Diesel Starting Air System SI Safety Injection 5N129F05013#1 Safety Injection System Revision 1 Page 11 of 20

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Liservice Test Plan Table 1 (Cont'd.)

Piping and Instrumentation Diagrams System System Drawing Sheet Abbr. Designation Number No. Drawing Title 5N129F05013#2 Safety Injection System 5N129F05014#1 Safety Injection System 5N129F05014#2 Safety Injection System 5N129F05015#1 Safety Injection System 5N129F05015#2 Safety Injection System 5N129F05016#1 Safety Injection System 5N129F05016#2 Safety Injection System SL Steam Generator Sludge 5S209F05057#1 Stm Gen Sludge Lancing & Chem Cleaiung Sys Lancing (Note 3) 5S209F05057#2 Stm Gen Sludge Lancing & Chem Cleaning Sys (Note 3)

WL Liquid Waste Processing 5R309F05022#1 Liquid Waste Processing System (Note 3) 5R309F05022#2 Liquid Waste Processing System (Note 3)

Notes: 1. Includes AF piping.

2. Includes AP piping.
3. Class 2 containment penetration piping and isolation valves only.
4. Includes CS piping.
5. Includes EW piping.
6. Includes MS piping.
7. Includes RA piping; Class 2 containment penetration piping and isolation valves only.

Revision 1 Page 12 of 20

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Inservice Test Plan 2.5.2 Procedures Table 2 lists applicable Snubber 1ST Program procedures.

Table 2 Snubber Program Procedures PROCEDURE PROCEDURE TITLE NUMBER OPGP03-ZE-0009 Snubber Testing Program OPSP11-SN-0001 Mechanical Snubber Visual Examination (surveillance procedure)

OPSP11-SN-0002 Hydraulic Snubber Visual Inspection (surveillance procedure)

OPSP11-SN-0003 Mechanical Snubbers Functional Test (surveillance procedure)

OPSP11-SN-0004 Hydraulic Snubber Functional Test (surveillance procedure)

OPSP11-SN-0005 Snubber Service Life Review and Reevaluation (surveillance procedure) 3.0 METHOD OF EVALUATING SNUBBERS The Master Equipment Database and system design basis documents were reviewed to determine which systems include snubbers that encompass system safety requirements defined in 10 CFR 50 as well as snubbers required in response to the abnormal operational transients and accidents defined in the UFSAR. This review was not limited to the postulated accidents ofUFSAR Chapter 15.

Each system was reviewed in the following manner; The P&ID for each system was reviewed to identify the system boundaries for each class of snubbers that are subject to a specific function in shutting down a reactor to the safe shutdown condition, maintaining the safe shutdown condition, or in mitigating the consequences of an accident.

Each snubber was reviewed for design and installation arrangement for allowances for adequate access and clearances for conduct of tests.

The Snubber 1ST Listing was developed from the above review activities.

Revision 1 Page 13 of 20

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Inservice Test Plan 4.0 ALTERNATIVE REQUIREMENTS TO OM CODE This section lists the alternative requirements to the Code for specific portions of the Snubber 1ST Program. The alternative requirements identified meet the rules for alternative requirements that are defined in the Code.

4.1 Code Cases Code Cases to be used during a preservice or inservice test examinations SHALL be identified in the Test Plan [ISTA 3130(a)].

Code Cases SHALL be applicable to the edition and addenda specified in the Test Plan[ISTA-3130(b)].

Code Cases SHALL be in effect at the time the test plan is filed [ISTA-3130(c)].

Code Cases issued subsequent to filing the Test Plan MAY be proposed for use in amendments to the Test Plan [ISTA-3130(d)],

Superseded Code Cases approved for use MAY continue to be used [ISTA-3140].

Code Cases approved for use MAY be used after annulment for the duration of the Test Plan [ISTA-3150].

Endorsement of Regulatory Guide 1.192 "Operation and Maintenance Code Case Acceptability, ASME OM Code", does NOT commit the STP to all code cases listed therein, but rather allows for selection of applicable code cases. The purpose of this endorsement is to identify all code cases that could potentially be incorporated into this 1ST Program Plan.

4,2 1 OCFR50.55a Requirements - Code Cases 10CFR50.55a(b)(6) addresses the application of Code Cases and states the following criteria:

Licensees MAY apply the ASME Operation and Maintenance Nuclear Power Plants Code cases listed in Regulatory Guide 1.192 without prior NRC approval subject to the following:

When a licensee initially applies a listed Code case, the licensee SHALL apply the most recent version of that Code case.

Revision 1 Page 14 of 20

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Inservice Test Plan If a licensee has previously applied a Code case and a later version of the Code case is incorporated, the licensee MAY continue to apply, to the end of the current 120-month interval, the previous version of the Code case as authorized or MAY apply the later version of the Code case, including any NRC-specified conditions placed on its use Application of an annulled Code case is prohibited unless a licensee previously applied the listed Code case prior to it being listed as annulled in Regulatory Guide 1.192. If a licensee has applied a listed Code case that is later listed as annulled in Regulatory Guide 1.192, the licensee MAY continue to apply the Code case to the end of the current 120-month interval.

4,3 Code Case Adoption; 4.3.1 Adoption of Code Cases Accepted for Generic Use in Regulatory Guide 1.192 Code cases that are designated "Acceptable" or "Conditionally Acceptable" for generic use in Regulatory Guide 1.192 (latest revision) have been adopted for use by listing them in Table 3. All conditions or limitations delineated in Regulatory Guide 1.192 for applicable code cases will apply.

4.3.2 Adoption of Code Cases Not Accepted for Generic Use in Regulatory Guide 1.192 via Submittal of Relief Requests Adoption of code cases that have been approved by the ASME Board of Nuclear Codes and Standards, but that have NOT been accepted for generic use in Regulatory Guide 1.192, MAY be submitted in the form of a relief request in accordance with 1 OCFR5 0.55 a(a)(3). Once approved, these relief requests will be available for use by STP. The Relief Request is approved for use until the end of the 10-year interval in which it was approved.

Table 4 lists those code cases for which relief requests have been submitted. In addition to the requirements stated in the code cases, criteria MAY be stipulated in the relief request OR MAY be agreed upon through subsequent correspondence with the NRC. STP will implement these additional requirements as applicable (see attachment 3 for additional details).

Revision 1 Page 15 of 20

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Inservice Test Plan Table 3 Adopted Code Cases Approved in Regulatory Guide 1.192 Code Affected Case Code Case Title Program Number Area OMN-13, Requirements for Extending Snubber Inservice Visual Snubber visual exams Revision 2 Examination Interval at LWR Power Plants Table 4 Code Cases Submitted Through Relief Requests Code (1) Relief Request No. Affected Case Code Case Title (2) Correspondence No. Program Number (3) Relief Request Date Area NONE (1)

(2)

^L Revision 1 Page 16 of 20

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Inservice Test Plan 4.4 Relief Requests Relief from the requirements of the OM Code SHALL be requested where full compliance with the Code will not be achieved. Relief requests are submitted to the NRC for approval pursuant to the requirements of 10 CFR 50,5 5 a, Table 5 provides a listing of additional relief requests, not associated with a code case, that have been written in accordance with 10CPR50.55a(a)(3) when specific inservice testing requirements are considered impractical. If other examination requirements are determined to be impractical during the course of the interval, relief requests SHALL be submitted in accordance with 10CFR50.55a.

Table 5 Relief Requests Not Associated With a Code Case (1) Relief Request No. Affected Relief Request Subject (2) Correspondence No. Program (3) Relief Request Date Area NONE (1)

(2)

OL Revision 1 Page 17 of 20

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Inservice Test Plan 4.5 50.5 5 a Limitations, Modifications and Clarifications Certain paragraphs in 10CFR50,55a list the limitations, modifications, and/or clarifications to the implementation requirements of the Code. The paragraphs in 10CFR50,55a applicable to STP are listed in Table 6.

TABLE 6 CODE OF FEDERAL REGULATIONS 10CFRSO.SSa LIMITATIONS 10CFRSO.SSa Paragraphs Limitations, Modifications, and Clarifications 10CFR50,55a(b)(3)(v) Subsection ISTD. Article IWF-5000, "Inservice Inspection Requirements for Snubbers," of the ASME BPV Code,Section XI, must be used when performing inservice inspection examinations and tests of snubbers at nuclear power plants, except as conditioned in paragraphs (b)(3)(v)(A) and (B) of this section.

(A) Snubbers: First provision. Licensees may use Subsection ISTD, Preservlce and Inservlce Examination and Testing of Dynamic Restraints (Snubbers) in Llght-Water Reactor Power Plants," ASME OM Code, 1995 Edition through the latest edition and addenda incorporated by reference in paragraph (a)(l)(iv) of this section, in place of the requirements for snubbers in the editions and addenda up to the 2005 Addenda of the ASME BPV Code,Section XI, IWF-5200(a) and (b) and IWF-5300(a) and (b), by making appropriate changes to their technical specifications or licensee-controlled documents. Preservice and inservice examinations must be performed using the VT-3 visual examination method described in IWA-2213.

(B) Snubbers: Second provision. Licensees must comply with the provisions for examining and testing snubbers in Subsection ISTD of the ASME OM Code and make appropriate changes to their technical specifications or licensee-controlled documents when using the 2006 Addenda and later editions and addenda of Section XI of the ASME BPV Code.

Revision 1 Page 18 of 20

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Inservice Test Plan 5.0 INTERPRETATIONS TO THE OM CODE This section lists interpretations to the Code for specific portions of the Snubber 1ST Program.

Code interpretations provide clarification to the intent of Code requirements. Although the NRC agrees with most interpretations, some are inconsistent with NRC requirements. NRC requirements SHALL be met. Interpretations serve to support the users understanding of Code requirements. Many interpretations address specific circumstances. Therefore, the context of the interpretation must be thoroughly understood prior to its application at STP.

Code interpretations applicable to Snubber 1ST Program are listed in Table 7 (see attachment 4 for additional detail),

TABLE 7 OM CODE INTERPRETATIONS Interpretation Interpretation Description / Subject Application No. Impact 04-10 ASME Code-1998 through OMb-2000 Snubber testing 09-01 ASME OM Code -1998 Edition through 2005 Snubber testing Addenda, Subsection ISTD 09-04 ASME OM Code: 1998 Edition Through 2004 Snubber testing Edition up to and Including ASME OM Code 2006) 6.0 PROGRAM IMPLEMENTATION The Snubber Testing Program procedure (OPGP03-ZE-0009) details program implementation based on the Code and alternate requirements of the Code.

Snubber program inservice tests required by the Code SHALL be implemented using the Surveillance Test Program. The snubber surveillance test program SHALL be used to identify the test method for verifying operational readiness of the snubber, to identify the frequency of the required tests, to establish plant conditions for performing tests, and to document the results of snubber testmg. The surveillance tests act as the record of testing required by the Code.

Reference Table 2 for a listing of the applicable snubber 1ST program implementing procedures.

Revision 1 Page 19 of 20

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION Unit 1 and 2 Snubber Inservice Test Plan 7.0 PROGRAM CONFIGURATION CONTROL As a minimum the program will be reviewed and revised as necessary for compliance with the -

Code in effect as referenced by 10CFR50.55a 12 months prior to the end of the fourth 120-month interval of commercial operation. Additionally, the scope of the program is subject to revision due to changes in system design, changes in design that affect the snubber safety function, or revisions to the applicable code requirements through Alternate Requirements to the Code. In order to accommodate these changes STP reserves the right to submit program revisions that will enhance or improve the program at any time within the effective interval.

8.0 TEST PLAN ATTACHMENTS Attachment 1, Unit 1 Snubber 1ST Listing Attachment 2, Unit 2 Snubber 1ST Listing Attachment 3, Code Cases - Information Only Attachment 4, Interpretations - Information Only Revision 1 Page 20 of 20

ATTACHMENT 1 Unit 1 Snubber 1ST Listing Revision 1

Mdtpns Tagtpns / Model No Qc Route / Elev Hang Dwg Iso Dwg Pipe Dwg Accessible/

Snubber Level Location Inaccessible 2C111XSN0001A HYD- 2 RCB SGA-NE 58 400290- 400290- 0957- I 1300KIP 00010XX 00010XX 0100008WN 2C111XSN0001B HYD- 2 RCB SGB- 58 400290- 400290- 0957- I 1300KIP N/E 00010XX 00010XX 0100008WN 2C111XSN0001C HYD- 2 RCB SGC- 58 400290- 400290- 0957- I 1300KIP N/E 00010XX 00010XX 0100008WN 2C111XSN0001D HYD- 2 RCB SGD- 58 400290- 400290- 0957- I 1300KIP N/E 00010XX 00010XX 0100008WN 2C111XSN0002A HYD- 2 RCB SGA- 58 400290- 400290- 0957- I 1300KIP NAV 00010XX 0001 OXX 0100008WN 2C111XSN0002B HYD- 2 RCB SGB- 58 400290- 400290- 0957- I 1300KIP NAV 00010XX 00010XX 0100008WN 2C111XSN0002C HYD- 2 RCB SGC- 58 400290- 400290-- 0957- I 1300KIP NAV 00010XX 00010XX 0100008WN 2C111XSN0002D HYD- 2 RCB SGD- 58 400290- 400290- 0957- I 1300KIP NAV 00010XX 00010XX 0100008WN 2C111XSN0003A HYD- 2 RCB SGA- 58 400290- 400290- 0957- I 1300KIP s/w 00010XX 00010XX 0100008WN 2C111XSN0003B HYD- 2 RCB SGB- 58 400290- 400290- 0957- I 1300KIP SAV 00010XX 00010XX 0100008WN 2C111XSN0003C HYD- 2 RCB SGC- 58 400290- 400290- 0957- I 1300KCP s/w 00010XX 00010XX 0100008WN 2C111XSN0003D HYD- 2 RCB SGD- 58 400290- 400290- 0957- I 1300KIP s/w 00010XX 00010XX 0100008WN 2C111XSN0004A HYD- 2 RCB SGA- 58 400290- 400290- 0957- I 1300KIP S/E 00010XX 00010XX 0100008WN 2C111XSN0004B HYD- 2 RCB SGB- 58 400290- 400290- 0957- I 1300KIP S/E 00010XX 0001 OXX 0100008WN Revision 1

2C111XSN0004C HYD- 2 RCB SGC- 58 400290- 400290- 0957- I 1300KIP S/E 00010XX 00010XX 0100008WN 2C111XSN0004D HYD- 2 RCB SGD- 58 400290- 400290- 0957- I 1300KIP S/E 0001 OXX 00010XX 0100008WN AF1006HL5003 AD5501 2 RCB 19 AF9006HL5003 2C369PAF402- F00024 I SGAD>52' 02 AF1006HL5015 AD5501 2 RCB 19 AF9006HL5015 2C369PAF402- F00024 I SGAD>52' 02 AF1006HL5018 AD5501 2 RCBOMB 19 AF9006HL5018 2C369PAF402- F00024 I

>19' 02 AF1006HL5035N AD5501 2 RCB 19 AF9006HL5035 2C369PAF402- F00024 I SGAD>68' 02 AF1006HL5035S AD5501 2 RCB 19 AF9006HL5035 2C369PAF402- F00024 I SGAD>68' 02 AF1008HL5028 AD5501 2 RCB 19 AF9008HL5028 2C369PAF402- F00024 I SGAD>68' 02 AF1008HL5029 AD5501 2 RCB 19 AF9008HL5029 2C369PAF402- F00024 I SGAD>68' 02 AF1008HL5030 AD5501 2 RCBOMB 19 AF9008HL5030 2C369PAF402- F00024 I

>19' 02 AF1008HL5041N AD5501 2 RCB 19 AF9008HL5041 2C369PAF402- F00024 I SGAD>68' 02 AF1008HL5041S AD5501 2 RCB 19 AF9008HL5041 2C369PAF402- F00024 I SGAD>68' 02 AF1010HL5002L AD5501 2 RCBOMB 19 AF9010HL5002 2C369PAF402- F00024 I

>19' 01 AF1010HL5002U AD5501 2 RCBOMB 19 AF9010HL5002 2C369PAF402- F00024 I

>19' 01 AF1010HL5007E AD5501 2 RCB 19 AF9010HL5007 2C369PAF402- F00024 I SGBC>52' 01 AF1010HL5007W AD5501 2 RCB 19 AF9010HL5007 2C369PAF402- F00024 I SGBC>52' 01 AF1010HL5008L AD5501 2 RCB 19 AF9010HL5008 2C369PAF402- F00024 I SGB068' 01 Revision 1

AF1010HL5008U AD5501 2 RCB 19 AF9010HL5008 2C369PAF402- F00024 I SGB068' 01 AF1010HL5009 AD1601 2 RCB 19 AF9010HL5009 2C369PAF402- F00024 I SGBC>68' 01 AF1010HL5017 AD5501 2 RCB 19 AF9010HL5017 2C369PAF402- F00024 I SGB068' 01 AF1010HL5018 AD1601 2 RCB 19 AF9010HL5018 2C369PAF402- F00024 I SGB068' 01 AF1010HL5020 AD1601 2 RCB 19 AF9010HL5020 2C369PAF402- F00024 I SGB068' 01 AF1010HL5026 AD1601 2 RCB 19 AF9010HL5026 2C369PAF402- F00024 I SGB019' 01 AF1010HL5035 AD1601 2 RCB 19 AF9010HL5035 2C369PAF402- F00024 I SGBC>68' 01 AF1012HL5014E AD1601 2 RCB 19 AF9012HL5014 2C369PAF402- F00024 I SGB068' 01 AF1012HL5014W AD1601 2 RCB 19 AF9012HL5014 2C369PAF402- F00024 I SGB068' 01 AF1012HL5017 AD5501 2 RCB 19 AF9012HL5017 2C369PAF402- F00024 I SGBC>68' 01 AF1012HL5018 AD1601 2 RCB 19 AF9012HL5018 2C369PAF402- F00024 I SGB068' 01 AP1012HL5020 AD1601 2 RCB 19 AF9012HL5020 2C369PAF402- F00024 I SGB068' 01 AF1012HL5024 AD5501 2 RCBOMB 19 AF9012HL5024 2C369PAF402- F00024 I

>19' 01 AF1012HL5027 AD5501 2 RCBOMB 19 AF9012HL5027 2C369PAF402- F00024 I

>19' 01 AF1012HL5038L AD5501 2 RCB 19 AF9012HL5038 2C369PAF402- F00024 I SGB068' 01 AF1012HL5038U AD5501 2 RCB 19 AF9012HL5038 2C369PAF402- F00024 I SGB068' 01 AF1054HL5004N AD151 3 WC D 34 AF9054HL5004 5G369PAF602- F00024 A 10 Revision 1

AF1054HL5004S AD151 3 WCD 34 AF9054HL5004 5G369PAF602- F00024 A 10 AF1061HL5001 AD1601 2 RCB 19 AF9061HL5001 2C369PAF402- F00024 I SGAD>52' 02 AF1061HL5002 AD1601 2 RCB 19 AF9061HL5002 2C369PAF402- F00024 I SGAD>68' 02 AF1062HL5011 AD1601 2 RCB 19 AF9062HL5011 2C369PAF402- F00024 I SGAD>68' 02 AF1062HL5012 AD1601 2 RCB 19 AF9062HL5012 2C369PAF402- F00024 I SGAD>68' 02 AF1062HL5015 AD1601 2 RCB 19 AF9062HL5015 2C369PAF402- F00024 I SGAD>52' 02 AF1063HL5002 AD1601 2 RCB 19 AF9063HL5002 2C369PAF402- F00024 I SGBC>68' 01 AF1063HL5003 AD151 2 RCB 19 AF9063HL5003 2C369PAF402- F00024 I SGBC>68' 01 AF1063HL5005 AD1601 2 RCB 19 AF9063HL5005 2C369PAF402- F00024 I SGB068' 01 AF1063HL5006 AD1601 2 RCB 19 AF9063HL5006 2C369PAF402- F00024 I SGB068' 01 AF1064HL5004 AD1601 2 RCB 19 AF9064HL5004 2C369PAF402- F00024 I SGB052' 01 AP1003HF5001 AD41 2 MABRM108 29 AP1003HF5001 5M369PAP287- Z47501 A A01 CC1105HL5004 AD5501 3 RCBRHR 37 CC9105HL5004 4C369PCC407- F05017 I HX1A 08 CC1105HL5009 AD5501 3 RCBOMB 52 CC9105HL5009 4C369PCC407- F05017 I

>52' 08 CC1109HL5001N AD501 3 MABRM 27 CC9109HL5001 5M361PCC207- F05017 A 106A 07 CC1109HL5001S AD501 3 MABRM 27 CC9109HL5001 5M361PCC207- F05017 A 106A 07 CC1110HL5001 AD1601 3 MABRM 27 CC9110HL5001 5M361PCC207- F05017 A 106A 07 Revision 1

CC1136HL5002 AD501 7 MABRM64 10 CC9136HL5002 5M361PCC207- F05017 A 07 CC1205HL5007L AD501 3 RCBOMB 52 CC9205HL5007 4C369PCC407- F05018 I

>52' 07 CC1205HL5007U AD501 3 RCBOMB 52 CC9205HL5007 4C369PCC407- F05018 I

>52' 07 CC1206HL5008 AD501 3 RCBOMB 52 CC9206HL5008 4C369PCC407- F05018 I

>52' 10 CC1209HL5002 AD1601 3 MABRM216 41 CC9209HL5002 5M369PCC207- F05018 A 11 CC1209HL5003 AD1601 3 MABRM216 41 CC9209HL5003 5M369PCC207- F05018 A 11 CC1210HL5001 AD1601 3 MABRM 27 CC9210HL5001 5M369PCC207- F05018 A 106A 22 CC1215SS0002 AD501 3 RCB 0MB >- -11 CC9215SS0002 3C369PCC407- F05018 I 11 16 CC1220SS0002L AD501 3 MABRM64 10 CC9220SS0002 5M369PCC207- F05018 A 11 CC1220SS0002U AD501 3 MABRM64 10 CC9220SS0002 5M369PCC207- F05018 A 11 CC1309SS0002 AD1601 3 MABRM216 41 CC9309SS0002 5M361PCC207- F05019 A 01 CC1309SS0003L AD1601 3 MABRM216 41 CC9309SS0003 5M361PCC207- F05019 A 01 CC1309SS0003U AD1601 3 MABRM216 41 CC9309SS0003 5M361PCC207- F05019 A 01 CC1311SS0001 AD1601 3 MABRM216 41 CC9311SS0001 5M369PCC207- F05019 A 08 CC1320HL5001 AD1601 3 MABRM216 41 CC9320HL5001 5M361PCC207- F05019 A 01 CC1425HL5016 AD151 3 FHBRM208 30 CC9425HL5016 5M361PCC207- F05020 A 01 CC1613SS0003 AD151 7 RCBOMB 37 CC9613SS0003 5C369PCC407- F05021 I

>37' 03 Revision 1

CV1002HL5002 AD71 2 RCB 19 CV9002HL5002 4C369PCV417- F05005 I SGB052' 04 CV1002HL5003 AD71 2 RCB 19 CV9002HL5003 4C369PCV417- F05005 I SGB019' 04 CV1002HL5004 AD71 2 RCB 19 CV9002HL5004 4C369PCV417- F05005 I SGB019' 04 CV1002HL5007 AD151 2 RCB 19 CV9002HL5007 4C369PCV417- F05005 I SGB019' 04 CV1002HL5008 AD71 2 RCB 19 CV9002HL5008 4C369PCV417- F05005 I SGB037' 04 CV1002HL5009 AD151 2 RCB 19 CV9002HL5009 4C369PCV417- F05005 I SGBC>37' 04 CV1002HL5010 AD151 2 RCB 19 CV9002HL5010 4C369PCV417- F05005 I SGB019' 04 CV1002HL5012 AD71 2 RCB 19 CV9002HL5012 4C369PCV417- F05005 I SGB037' 04 CV1002HL5019 AD151 2 RCB 19 CV9002HL5019 4C369PCV417- F05005 I SGB019' 04 CV1002HL5020 AD151 2 RCB 19 CV9002HL5020 4C369PCV417- F05005 I SGB019' 04 CV1002HL5021 AD501 2 RCB 19 CV9002HL5021 4C369PCV417- F05005 I SGBC>19' 04 CV1003HF5003 AD151 2 RCB RON 37 CV1003HF5003 5C369PCV417- F05005 I HX A09 CV1003HL5003N AD151 2 RCB RGN 37 CV2003HL5003 4C369PCV417- F05005 I HX 04 CV1003HL5003S AD151 2 RCB RON 37 CV1003HL5003 4C369PCV417- F05005 I HX 04 CV1004HF5001 AD41 2 RCB RON 37 CV1004HF5001 5C369PCV417- F05005 I HX A09 CV1005HF5001 AD41 2 RCB RON 37 CV1005HF5001 5C369PCV417- F05005 I HX A09 CV1006HL5037L AD151 2 MABRM108 29 CV9006HL5037 4M369PCV217- A 04 Revision 1

CV1006HL5037U AD151 2 MABRM108 29 CV9006HL5037 4M369PCV217- A 04 CV1011HL5009 AD71 2 MABRM49 10 CV9011HL5009 4M369PCV217- F05006 A 04 CV1086SS0002 AD71 2 MABRM110 29 CV9086SS0002 2M369PCV217- F05006 A 05 CV1088HL5002 AD41 2 MABRM31 10 CV9088HL5002 4M369PCV217- F05006 A 04 CV1116HL5018 AD71 2 MABRM108 29 CV9116HL5018 2M369PCV217- F05007 A 20 CV1117HF5054 AD41 2 RCB PZR 37 CV1117HF5054 4C369PCV417- F05005 I A02 CV1117HL5005 AD501 2 RCB 19 CV9117HL5005 4C369PCV417- F05005 I SGB037' 02 CV1117SS0006 AD1601 2 RCB 19 CV9117SS0006 4C369PCV417- F05005 I SGB037' 02 CV1121HS5007 AD41 1 RCB PZR 37 CV9121HS5007 4C369PCV417- F05005 I A02 CV1121HS5009 AD151 1 RCB PZR 37 CV9121HS5009 4C369PCV417- F05005 I A02 CV1121HS5010 AD151 1 RCB PZR 37 CV9121HS5010 4C369PCV417- F05005 I A02 FC1009SS0001 AD41 3 FHBRM110 21 FC9009SS0001 4F369PFC530- F05028 A 03 FC1011HL5001 AD1601 2 FHBRM110 21 FC9011HL5001 4F369PFC530- F05028 A 02 FC1012HL5002 AD501 3 FHBRMHO 21 FC9012HL5002 4F369PFC530- F05028 A 02 FW1012HL5002E AD5501 2 RCB 19 FW9012HL5002 2C369PFW433- F00062 I SGAD>37' 01 FW1012HL5002W AD5501 2 RCB 19 FW9012HL5002 2C369PFW433- F00062 I SGAD>37' 01 FW1012HL5003 AD12501 2 RCB 19 FW9012HL5003 2C369PFW433- F00062 I SGAD>37' 01 Revision 1

FW1012HL5005L AD5501 2 RCBOMB 37 FW9012HL5005 2C369PFW433- F00062 I

>37' 01 FW1012HL5005U AD5501 2 RCBOMB 37 FW9012HL5005 2C369PFW433- F00062 I

>37' 01 FW1012HL5011 AD5501 2 RCB 19 FW9012HL5011 2C369PFW433- F00062 I SGAD>19' 01 FW1012HL5016 AD12501 2 RCB 19 FW1012HL5016 2C369PFW433- F00062 I SGAD>37' 01 FW1014HL5001E AD5501 2 RCB FW9014HL5001 2C369PFW433- F00062 I SGBC>37' 01 FW1014HL5001W AD5501 2 RCB FW9014HL5001 2C369PFW433- F00062 I SGB037' 01 FW1014HL5002 AD12501 2 RCB 19 FW9014HL5002 2C369PFW433- F00062 I SGB037' 01 FW1014HL5003L AD5501 2 RCB RON 37 FW9014HL5003 2C369PFW433- F00062 I HX 01 FW1014HL5003U AD5501 2 RCB RON 37 FW9014HL5003 2C369PFW433- F00062 I HX 01 FW1014HL5009 AD12501 2 RCB 19 FW9014HL5009 2C369PFW433- F00062 I SGB037' 01 FW1014HL5012 AD5501 2 RCB 19 FW9014HL5012 2C369PFW433- F00062 I SGBC>19' 01 FW1016HL5003 AD5501 2 RCB RON 37 FW9016HL5003 2C369PFW433- F00062 I HX 11 FW1016HL5004 AD5501 2 RCB 19 FW9016HL5004 2C369PFW433- F00062 I SGB019' 01 FW1016HL5006 AD5501 2 RCB 19 FW9016HL5006 2C369PFW433- F00062 I SGBC>52' 01 FW1016HL5007 AD5501 2 RCB 19 FW9016HL5007 2C369PFW433- F00062 I SGB019' 01 FW1016HL5008 AD5501 2 RCB RON 37 FW9016HL5008 2C369PFW433- F00062 I HX 01 FW1016HL5009 AD12501 2 RCB 19 FW9016HL5009 2C369PFW433- F00062 I SGB037' 01 Revision 1

FW1016HL5010 AD5501 2 RCB 19 FW9016HL5010 2C369PFW433- F00062 I SGB037' 01 FW1016SH0001 AD5501 2 RCB 19 FW9016SH0001 2C369PFW433- F00062 I SGBC>37' 01 FW1016SS0006 AD5501 2 RCB 19 FW9016SS0006 2C369PFW433- F00062 I SGB052' 01 FW1018HL5003 AD5501 2 RCBOMB 37 FW9018HL5003 2C369PFW433- F00062 I

>37' 01 FW1018HL5004 AD5501 2 RCB 19 FW9018HL5004 2C369PFW433- F00062 I SGAD>19' 01 FW1018HL5006L AD5501 2 RCBOMB 37 FW9018HL5006 2C369PFW433- F00062 I

>37' 01 FW1018HL5006U AD5501 2 RCBOMB 37 FW9018HL5006 2C369PFW433- F00062 I

>37' 01 FW1018HL5007N AD5501 2 RCB 19 FW9018HL5007 2C369PFW433- F00062 I SGAD>37' 01 FW1018HL5007S AD5501 2 RCB 19 FW9018HL5007 2C369PFW433- F00062 I SGAD>37' 01 FW1018HL5008 AD12501 2 RCB 19 FW9018HL5008 2C369PFW433- F00062 I SGAD>37' 01 FW1018HL5009 AD12501 2 RCB 19 FW9018HL5009 2C369PFW433- F00062 I SGAD>37' 01 FW1018SS0001 AD5501 2 RCB 19 FW9018SS0001 2C369PFW433- P00062 I SGAD>19' 01 FW1018SS0006 AD5501 2 RCB 19 FW9018SS0006 2C369PFW433- F00062 I SGAD>52' 01 FW1018SS0007 AD12501 2 RCB 19 FW9018SS0007 2C369PFW433- F00062 I SGAD>37' 01 FW1029HL5002E AD1601 2 TVCA 44 FW9029HL5002 2G369PFW633- F00062 A 02 FW1029HL5002W AD1601 2 IVCA 44 FW9029HL5002 2G369PFW633- F00062 A 02 FW1029HL5003 AD1601 2 TVCA 44 FW9029HL5003 2G369PFW633- F00062 A 02 Revision 1

FW1030HL5002E AD1601 2 WC B 44 FW9030HL5002 2G369PFW633- F00062 A 03 FW1030HL5002W AD1601 2 TVCB 44 FW9030HL5002 2G369PFW633- F00062 A 03 FW1030HL5003 AD1601 2 rvcB 44 FW9030HL5003 2G369PFW633- F00062 A 03 FW1031HL5002E AD1601 2 we c 44 FW9031HL5002 2G369PFW633- F00062 A 04 FW1031HL5002W AD1601 2 rvcc 44 FW9031HL5002 2G369PFW633- F00062 A 04 FW1031HL5003 AD1601 2 P/CC 44 FW9031HL5003 2G369PFW633- F00062 A 04 FW1032HL5002E AD1601 2 WCD 44 FW9032HL5002 2G369PFW633- F00062 A 01 FW1032HL5002W AD1601 2 TVCD 44 FW9032HL5002 2G369PFW633- F00062 A 01 FW1032HL5003 AD1601 2 TVCD 44 FW9032HL5003 2G369PFW633- F00063 A 01 FW1117HL5001 AD41 2 we c 34 FW9117HL5001 2G369PFW633- F00063 A 05 FW1117HL5003 AD41 2 we c 34 FW9117HL5003 2G369PFW633- F00063 A 05 FW1117HL5004 AD41 2 rvcc 44 FW9117HL5004 2G369PFW633- F00063 A 05 FW1119HL5001 AD41 2 FVCB 34 FW9119HL5001 2G369PFW633- F00063 A 05 FW1119HL5003 AD41 2 WCB 34 FW9119HL5003 2G369PFW633- F00063 A 05 FW1119HL5004 AD41 2 FVCB 44 FW9119HL5004 2G369PFW633- F00063 A 05 FW1121HL5001 AD41 2 rvcA 34 FW9121HL5001 2G369PFW633- F00063 A 05 FW1121HL5003 AD41 2 TVCA 34 FW9121HL5003 2G369PFW633- F00063 A 05 Revision 1

FW1121HL5004 AD41 2 TVCA 34 FW9121HL5004 2G369PFW633- F00063 A 05 FW1123HL5001 AD41 2 rvcD 34 FW9123HL5001 2G369PFW633- F00063 A 05 FW1123HL5003 AD41 2 TVCD 34 FW9123HL5003 2G369PFW633- F00063 A 05 FW1123HL5004 AD41 2 rvcD 34 FW9123HL5004 2G369PFW633- F00063 A 05 MD1147HF5002 AD71 7 P/CA 44 MD1147HF5002 9G369PMD645- F00055 A A01 MD1148HF5002 AD71 7 IVCB 44 MD1148HF5002 9G369PMD645- F00055 A A01 MD1149HF5002 AD71 7 rvcc 44 MD1149HF5002 9G369PMD645- F00055 A A01 MD1150m?5002 AD41 7 FVCD 44 MD1150HF5002 9G369PMD645- F00055 A A01 MS1001HL5004 AD5501 2 RCBOMB 68 MS9001HL5004 2C369PMS446- F00016 I

>68' 01 MS1001HL5007 AD12501 2 RCB 19 MS9001HL5007 2C369PMS446- F00016 I SGAD>68' 01 MS1001HL5010L AD1601 2 IVCA 51 MS9001HL5010 2G369PMS646- F00016 A 06 MS1001HL5010U AD1601 2 WC A 51 MS9001HL5010 2G369PMS646- F00016 A 06 MS1001HL5011E AD5501 2 WC A 51 MS9001HL5011 2G369PMS646- F00016 A 06 MS1001HL5011W AD5501 2 TVCA 51 MS9001HL5011 2G369PMS646- F00016 A 06 MS1001HL5012L AD1601 2 D/CA 51 MS9001HL5012 2G369PMS646- F00016 A 06 MS1001HL5012U AD1601 2 FVCA 51 MS9001HL5012 2G369PMS646- F00016 A 06 MS1001HL5015 AD5501 2 RCB 19 MS9001HL5015 2C369PMS446- F00016 I SGAD>83' 01 Revision 1

MS1002HL5006 AD5501 2 RCBOMB 68 MS9002HL5006 2C369PMS466- F00016 I

>68' 02 MS1002HL5007 AD12501 2 RCB 19 MS9002HL5007 2C369PMS446- F00016 I SGB068' 02 MS1002HL5010L AD1601 2 FVCB 51 MS9002HL5010 2G369PMS646- F00016 A 07 MS1002HL5010U AD1601 2 T^CB 51 MS9002HL5010 2G369PMS646- F00016 A 07 MS1002HL5011E AD5501 2 WC B 51 MS9002HL5011 2G369PMS646- F00016 A 07 MS1002HL5011W AD5501 2 rvcB 51 MS9002HL5011 2G369PMS646- F00016 A 07 MS1002HL5012L AD1601 2 IVCB 51 MS9002HL5012 2G369PMS646- F00016 A 07 MS1002HL5012U AD1601 2 WC B 51 MS9002HL5012 2G369PMS646- F00016 A 07 MS1002HL5015 AD5501 2 RCB 19 MS9002HL5015 2C369PMS446- F00016 I SGBC>83' 02 MS1002HL5016 AD5501 2 RCB 19 MS9002HL5016 2C369PMS446- F00016 I SGB083' 02 MS1003HL5004 AD5501 2 RCBOMB 68 MS9003HL5004 2C369PMS446- F00016 I

>68' 03 MS1003HL5012 AD12501 2 RCB 19 MS9003HL5012 2C369PMS446- F00016 I SGBC>68' 03 MS1003HL5013 AD5501 2 RCB 19 MS9003HL5013 2C369PMS446- F00016 I SGB083' 03 MS1003HL5014 AD5501 2 RCB 19 MS9003HL5014 2C369PMS446- F00016 I SGB083' 03 MS1003HL5015L AD1601 2 rvcc 51 MS9003HL5015 2G369PMS646- F00016 A 08 MS1003HL5015U AD1601 2 IVCC 51 MS9003HL5015 2G369PMS646- F00016 A 08 MS1003HL5016E AD5501 2 rvcc 51 MS9003HL5016 2G369PMS646- F00016 A 08 Revision 1

MS1003HL5016W AD5501 2 rvcc 51 MS9003HL5016 2G369PMS646- F00016 A 08 MS1003HL5017L AD1601 2 we c 51 MS9003HL5017 2G369PMS646- F00016 A 08 MS1003HL5017U AD1601 2 IVCC 51 MS9003HL5017 2G369PMS646- F00016 A 08 MS1004HL5007 AD5501 2 RCBOMB 68 MS9004HL5007 2C369PMS446- F00016 I

>68' 04 MS1004HL5012 AD12501 2 RCB 19 MS9004HL5012 2C369PMS446- F00016 I SGAD>68' 04 MS1004HL5013 AD12501 2 RCB PZR 37 MS9004HL5013 2C369PMS446- F00016 I 04 MS1004HL5014 AD12501 2 RCB 19 MS9004HL5014 2C369PMS446- F00016 I SGAD>83' 04 MS1004HL5015L AD1601 2 TVCD 51 MS9004HL5015 2G369PMS646- F00016 A 09 MS1004HL5015U AD1601 2 r^CD 51 MS9004HL5015 2G369PMS646- F00016 A 09 MS1004HL5016E AD5501 2 TVCD 51 MS9004HL5016 2G369PMS646- F00016 A 09 MS1004HL5016W AD5501 2 WC D 51 MS9004HL5016 2G369PMS646- F00016 A 09 MS1004HL5017L AD1601 2 FVCD 51 MS9004HL5017 2G369PMS646- F00016 A 09 MS1004HL5017U AD1601 2 WC D 51 MS9004HL5017 2G369PMS646- F00016 A 09 MS1005SS0001N AD5501 7 TGBB 55 MS9005SS0001 7G369PMS846- F00016 A 05 MS1005SS0001S AD5501 7 TGBB 55 MS9005SS0001 7G369PMS846- F00016 A 05 MS1005SS0002E AD5501 7 TGBB 29 MS9005SS0002 7G369PMS846- F00016 A 05 MS1005SS0002W AD5501 7 TGBB 29 MS9005SS0002 7G369PMS846- F00016 A 05 Revision 1

MS1006SS0001N AD5501 7 TGBB 55 MS9006SS0001 7G369PMS846- F00016 A 06 MS1006SS0001S AD5501 7 TGBB 55 MS9006SS0001 7G369PMS846- F00016 A 06 MS1006SS0002E AD5501 7 TGBB 29 MS9006SS0002 7G369PMS846- F00016 A 06 MS1006SS0002W AD5501 7 TGBB 29 MS9006SS0002 7G369PMS846- F00016 A 06 MS1007SS0002E AD5501 7 TGBB 29 MS9007SS0002 7G369PMS846- F00016 A 06 MS1007SS0002W AD5501 7 TGBB 29 MS9007SS0002 7G369PMS846- F00016 A 06 MS1008HL5001 AD5501 7 TGBB 55 MS9008HL5001 7G369PMS846- F00016 A 05 MS1008SS0001E AD5501 7 TGBB 29 MS9008SS0001 7G369PMS846- F00016 A 05 MS1008SS0001W AD5501 7 TGBB 29 MS9008SS0001 7G369PMS846- F00016 A 05 MS1013HL5002E AD5501 7 TGBB 55 MS9013HL5002 7G369PMS846- F00016 A 08 MS1013HL5002W AD5501 7 TGBB 55 MS9013HL5002 7G369PMS846- F00016 A 08 MS1013HL5003 AD5501 7 TGBB 55 MS9013HL5003 7G3G9PMS846- F00016 A 05 MS1013HL5004 AD5501 7 TGBB 55 MS9013HL5004 7G369PMS846- F00016 A 05 MS1013SS0002E AD5501 7 TGBB 55 MS9013SS0002 7G369PMS846- F00016 A 09 MS1013SS0002W AD5501 7 TGBB 55 MS9013SS0002 7G369PMS846- F00016 A 09 MS1051HL5009 AD71 3 WC D 10 MS9051HL5009 4G369PMS646- F00024 A 05 PS1020HF5002 AD41 7 MABRM108 29 PS1020HF5002 5M369PPS285- Z00045 A A01 Revision 1

RC1000SS0001 AD151 1 RCB PZR 37 RC9000SS0001 4C369PRC457- F05003 I 07 RC1003HL5006 AD501 1 RCB PZR 37 RC9003HL5006 1C369PRC457- F05003 I 06 RC1003HL5009 AD501 1 RCB PZR 37 RC9003HL5009 1C369PRC457- F05003 I 06 RC1014HL5001 AD5501 7 RCB PZR 37 RC9014HL5001 7C369PRC457- F05004 I 02 RC1014HL5003E AD5501 7 RCB PZR 37 RC9014HL5003 7C769PRC457- F05004 I 02 RC1014HL5003W AD5501 7 RCB PZR 37 RC9014HL5003 7C369PRC457- F05004 I 02 RC1014HL5005N AD5501 7 RCB PZR 37 RC9014HL5005 7C369PRC457- F05004 I 02 RC1014HL5005S AD5501 7 RCB PZR 37 RC9014HL5005 7C369PRC457- F05004 I 02 RC1014HL5006L AD5501 7 RCB PZR 37 RC9014HL5006 7C369PRC457- F05004 I 02 RC1014HL5006U AD5501 7 RCB PZR 37 RC9014HL5006 7C369PRC457- F05004 I 02 RC1014HL5009 AD501 7 RCB PZR 37 RC9014HL5009 7C369PRC457- F05004 I 02 RC1014HL5012N AD5501 7 RCB PZR 37 RC9014HL5012 7C369PRC457- F05004 I 02 RC1014HL5012S AD5501 7 RCB PZR 37 RC9014HL5012 7C369PRC457- F05004 I 02 RC1014HL5013 AD1601 7 RCB PZR 37 RC9014HL5013 7C369PRC457- F05004 I 02 RC1014HL5015 AD1601 7 RCB PZR 37 RC9014HL5015 7C369PRC457- F05004 I 02 RC1014HL5019N AD5501 7 RCB PZR 19 RC9014HL5019 7C369PRC457- F05004 I 02 RC1014HL5019S AD5501 7 RCB PZR 19 RC9014HL5019 7C369PRC457- F05004 I 02 Revision 1

RC1014HL5026 AD501 7 RCB PZR 19 RC9014HL5026 7C369PRC457- F05004 I 02 RC1014HL5028 AD1601 7 RCB PZR 19 RC9014HL5028 7C369PRC457- F05004 I 02 RC1112HL5002 AD5501 1 RCB 19 RC9112HL5002 4C369PRC457- F05001 I SGAD>19' 09 RC1123HL5013 AD501 1 RCB PZR 37 RC9123HL5013 4C369PRC457- F05001 I 07 RCH25HL5001 AD5501 1 RCB 1MB >- -11 RC9125HL5001 4C369PRC457- F05001 I 11 10 RC1125HL5008 AD1601 1 RCB 1MB >- -11 RC9125HL5008 4C369PRC457- F05001 I 11 10 RC1221HL5001 AD1601 1 RCB 1MB >- -11 RC9221HL5001 4C369PRC457- F05001 I 11 10 RC1221HL5003 AD5501 1 RCB MB >- -11 RC9221HL5003 4C369PRC457- F05001 I 11 10 RC1221HL5004 AD5501 1 RCB 19 RC9221HL5004 4C369PRC457- F05001 I SGBC>19' 10 RC1221HL5005 AD5501 1 RCB 19 RC9221HL5005 4C369PRC457- F05001 I SGB019' 10 RC1221HL5006 AD5501 1 RCB 1MB >- -11 RC9221HL5006 4C369PRC457- F05001 I 11 10 RC1221HL5007 AD5501 1 RCB 1MB >- -11 RC9221HL5007 4C369PRC457- F05001 I 11 10 RC1320HL5002 AD1601 1 RCB 19 RC9320HL5002 4C369PRC457- F05001 I SGB019' 04 RC1320HL5004 AD501 1 RCB 19 RC9320HL5004 4C369PRC457- F05001 I SGB019' 04 RC1422HL5019 AD501 1 RCB 19 RC9422HL5019 1C369PRC457- F05001 I SGAD>52' 06 RH1101HL5001 AD1601 1 RCBVLV -2 RH9101HL5001 4C369PRH459- F20000 I RM 04 RH1101HL5002 AD1601 1 RCBVLV -2 RH9101HL5002 4C369PRH459- F20000 I RM 04 Revision 1

RH1101HL5003 AD1601 1 RCBVLV 19 RH9101HL5003 4C369PRH459- F20000 I RM 04 RH1101HL5006 AD55Q1 1 RCB 19 RH9101HL5006 4C369PRC459- F20000 I SGAD>19' 04 RH1101HL5009 AD1601 1 RCB 19 RH9101HL5009 4C369PRH459- F20000 I SGAD>19' 04 RH1110HL5002 AD501 2 RCB 19 RH9110HL5002 4C369PRH459- F20000 I SGAD>19' 03 RH1201HL5001 AD1601 1 RCBVLV -2 RH9201HL5001 4C369PRH459- F20000 I RM 07 RH1201HL5006 AD5501 1 RCBVLV -2 RH9201HL5006 4C369PRH459- F20000 I RM 07 RH1202SS0002 AD1601 2 RCBVLV -2 RH9202SS0002 4C369PRH459- F20000 I RM 07 RH1203HL5001 AD501 2 RCBVLV 19 RH9203HL5001 2C369PRH459- F20000 I RM 02 RH1204HL5001 AD501 2 RCBVLV 19 RH9204HL5001 2C369PRH459- F20000 I RM 02 RH1211HL5002L AD501 2 RCB 19 RH9211HL5002 4C369PRH459- F20000 I SGBC>19' 07 RH1211HL5002U AD501 2 RCB 19 RH9211HL5002 4C369PRH459- F20000 I SGB019' 07 RH1303HL5007 AD501 2 RCBVLV 19 RH9303HL5007 2C369PRH459- F20000 I RM 05 RH1303HL5009 AD501 2 RCB VLV -2 RH9303HL5009 2C369PRH459- F20000 I RM 05 RH1306SS0001 AD501 2 RCBVLV -2 RH9306SS0001 4C369PRH459- F20000 I RM 06 RH1312HL5002 AD501 2 RCB VLV 19 RH9312HL5002 4C369PRH459- F20000 I RM 01 RH1313HL5003L AD501 2 RCB 19 RH9313HL5003 4C369PRH459- F20000 I SGB019' 06 RH1313HL5003U AD501 2 RCB 19 RH9313HL5003 4C369PRH459- F20000 I SGBC>19' 06 Revision 1

SB1101HL5007 AD1601 2 RCBOMB 19 SB9101HL5007 2C369PSB468- F20001 I

>19' 02 SB1101HL5012 AD501 2 RCB 19 SB9101HL5012 2C369PSB468- F20001 I SGAD>19' 02 SB1101HL5017 AD1601 2 RCBOMB 19 SB9101HL5017 2C369PSB468- F20001 I

>19' 02 SB1101HL5019 AD501 2 H^CA 10 SB9101HL5019 5G369PSB668- F20001 A 03 SB1101HL5020 AD501 2 IVCA 10 SB9101HL5020 5G369PSB668- F20001 A 03 SB1101HL5022 AD501 2 rye A 10 SB9101HL5022 5G369PSB668- F20001 A 03 SB1104HL5001 AD501 7 WC A 10 SB9104HL5001 5G369PSB668- F20001 A 03 SB1104HL5002 AD501 7 WC A 10 SB9104HL5002 5G369PSB668- F20001 A 03 SB1104HL5006 AD501 7 WC A 10 SB9104HL5006 5G369PSB668- F20001 A 03 SB1105HL5001 AD71 7 FVCA 10 SB9105HL5001 5G369PSB668- F20001 A 03 SB1107HF5001 AD41 2 WC A 10 SB1107HF5001 7G369PSB668- F20001 A A01 SB1201HL5004 AD1601 2 RCBOMB 19 SB9201HL5004 2C369PSB468- F20001 I

>19' 02 SB1201HL5010 AD1601 2 RCBOMB 19 SB9201HL5010 2C369PSB468- F20001 I

>19' 02 SB1201HL5013 AD501 2 RCB 19 SB9201HL5013 2C369PSB468- F20001 I SGBC>19' 02 SB1201HL5017 AD501 2 rye B 10 SB9201HL5017 5G369PSB668- F20001 A' 05 SB1201HL5018 AD501 2 TVCB 10 SB9201HL5018 5G369PSB668- 720001 A 05 SB1201HL5020 AD501 2 WC B 10 SB9201HL5020 5G369PSB668- F20001 A 05 Revision 1

SB1202HF5002 AD71 2 RCB 19 SB1202HF5002 2C361PSB468- F20001 I SGB019' A05 SB1204HL5001 AD501 7 WC B 10 SB9204HL5001 5G369PSB668- F20001 A 05 SB1204HL5002 AD501 7 IVCB 10 SB9204HL5002 5G369PSB668- F20001 A 05 SB1205HL5003 AD151 7 IVCB 10 SB9205HL5003 5G369PSB668- F20001 A 05 SB1207HF5001 AD41 7 WC B 10 SB1207HF5001 7G369PSB668- F20001 A A01 SB1250HF5003 AD41 2 RCB 19 SB1250HF5003 2C361PSB468- F20001 I SGB019' A05 SB1274HL5002L AD151 7 WC B 10 SB9274HL5002 5G369PSB668- F20002 A 05 SB1274HL5002U AD151 7 FVCB 10 SB9274HL5002 5G369PSB668- F20002 A 05 SB1301HL5003L AD501 2 RCBOMB 19 SB9301HL5003 2C369PSB468- F20001 I

>19' 02 SB1301HL5003U AD501 2 RCBOMB 19 SB9301HL5003 2C369PSB468- F20001 I

>19' 02 SB1301HL5011L AD501 2 RCB 19 SB9301HL5011 2C369PSB468- F20001 I SGB019' 02 SB1301HL5011U AD501 2 RCB 19 SB9301HL5011 2C369PSB468- F20001 I SGB019' 02 SB1301HL5012N AD151 2 RCB 19 SB9301HL5012 2C369PSB468- F20001 I SGB019' 02 SB1301HL5012S AD151 2 RCB 19 SB9301HL5012 2C369PSB468- F20001 I SGB019' 02 SB1301HL5018 AD501 2 we c 10 SB9301HL5018 5G369PSB668- F20001 A 07 SB1301HL5020 AD501 2 IVCC 10 SB9301HL5020 5G369PSB668- F20001 A 07 SB1301HL5021 AD501 2 we c 10 SB9301HL5021 5G369PSB668- F20001 A 07 Revision 1

SB1302HF5003 AD41 2 RCB 19 SB1302HF5003 2C369PSB468- F20001 I SGB019' A04 SB1303HF5005 AD151 2 RCB 19 SB1303HF5005 2C369PSB468- F20001 I SGB037' A04 SB1304HL5001 AD501 7 P/CC 10 SB9304HL5001 5G369PSB668- F20001 A 07 SB1304HL5002 AD501 7 rvcc 10 SB9304HL5002 5G369PSB668- F20001 A 07 SB1304HL5006 AD501 7 rvcc 10 SB9304HL5006 5G369PSB668- F20001 A 07 SB1350HF5016 AD41 2 RCB 19 SB1350HF5016 2C361PSB468- F20001 I SGB019' A05 SB1401HL5003 AD1601 2 RCBOMB 19 SB9401HL5003 2C369PSB468- F20001 I

>19' 02 SB1401HL5011 AD1601 2 RCBOMB 19 SB9401HL5011 2C369PSB468- F20001 I

>19' 02 SB1401HL5012 AD501 2 RCB 19 SB9401HL5012 2C369PSB468- F20001 I SGAD>19' 02 SB1401HL5016L AD151 2 RCB 19 SB9401HL5016 2C369PSB468- F20001 I SGAD>19' 02 SB1401HL5016U AD151 2 RCB 19 SB9401HL5016 2C369PSB468- P20001 I SGAD>19' 02 SB1401HL5019 AD501 2 RCB 19 SB9401HL5019 2C369PSB468- F20001 I SGAD>19' 02 SB1401HL5020 AD501 2 FVCD 10 SB9401HL5020 5G369PSB668- F20001 A 01 SB1401HL5022 AD501 2 P/CD 10 SB9401HL5022 5G369PSB668- F20001 A 01 SB1401HL5023 AD501 2 rvcD 10 SB9401HL5023 5G369PSB668- F20001 A 01 SB1402HF5002 AD71 2 RCB 19 SB1402HF5002 2C369PSB468- F20001 I SGAD>3T A04 SB1402HF5004 AD71 2 RCB 19 SB1402HF5004 2C369PSB468- F20001 I SGAD>37' A04 Revision 1

SB1403HF5002 AD71 2 RCB 19 SB1403HF5002 2C368PSB468- F20001 I SGAD>19' A04 SB1404HL5001 AD501 7 WC D 10 SB9404HL5001 5G369PSB668- F20001 A 01 SB1404HL5002 AD501 7 WC D 10 SB9404HL5002 5G369PSB668- F20001 A 01 SB1406HL5007 AD41 7 TVCD 10 SB9406HL5007 5G369PSB668- F20001 A 01 SB1407HF5001 AD41 7 P/CD 10 SB1407HF5001 7G369PSB668- F20001 A A01 SB1474HL5002 AD501 7 rvcD 10 SB9474HL5002 5G369PSB668- F20002 A 01 SH101SS0008L AD501 2 FHB HHSI A -29 SI9101SS0008 2F369PSI572- F05013 A 03 SI1101SS0008U AD501 2 FHBHHSIA -29 SI9101SS0008 2F369PSI572- F05013 A 03 SI1107HL5001N AD501 2 RCBOMB 19 SI9107HL5001 4C369PSI472- F05013 I

>19' 01 SI1107HL5001S AD501 2 RCBOMB 19 SI9107HL5001 4C369PSI472- F05013 I

>19' 01 SI1107SS0061 AD501 2 RCBOMB 19 SI9107SS0061 4C369PSI472- F05013 I

>19' 01 SI1108HL5001 AD1601 1 RCB 19 SI9108HL5001 4C369PSI472- F05013 I SGAD>19' 01 SI1108HL5003 AD1601 1 RCB 19 SI9108HL5003 4C369PSI472- F05013 I SGAD>19' 01 SI1112HF5023 AD41 7 RCBOMB 19 SI1112HF5023 5C369PSI472- F05013 I

>19' A07 SI1201HL5010L AD501 2 FHB HHSI B -29 SI9201HL5010 2F369PSI572- F05014 A 04 SI1201HL5010U AD501 2 FHB HHSI B -29 SI9201HL5010 2F369PSI572- F05014 A 04 SI1205HL5022 AD501 2 RCB 1MB >- -11 SI9205HL5022 2C369PSI472- F05014 I 11 02 Revision 1

SI1206HL5008 AD151 2 RCB 1MB >- -11 SI9206HL5008 4C369PSI472- F05014 I 11 05 SI1206HL5012 AD501 2 RCB 1MB >- -11 SI9206HL5012 4C369PSI472- F05014 I 11 05 SI1207SS0001 AD501 2 RCBOMB 19 SI9207SS0001 4C369PSI472- F05014 I

>19' 05 SH208HL5005 AD1601 1 RCB 19 SI9208HL5005 4C369PSI472- F05014 I SGB019' 05 SI1217HL5009 AD1601 2 RCB 0MB >- -2 SI9217HL5009 5C369PSI472- F05016 I 11 03 SI1301SS0005L AD501 2 FHB HHSI C -29 SI9301SS0005 2F369PSI572- F05015 A 06 SI1301SS0005U AD501 2 FHB HHSI C -29 SI9301SS0005 2F369PSI572- F05015 A 06 SI1306HL5012 AD151 2 FHB HHSI C -29 SI9306HL5012 2F369PSI572- F05015 A 05 SI1308HL5001 AD501 1 RCB 1MB >- -11 SI9308HL5001 4C369PSI472- F05015 I 11 07 SI1314HL5007 AD5501 2 RCB 1MB >- -11 SI9314HL5007 5C369PSI472- F05016 I 11 03 SI1315HL5003 AD12501 1 RCB 19 SI9315HL5003 5C369PSI472- F05016 I SGB019' 03 SI1315HL5004 AD5501 1 RCB 19 SI9315HL5004 5C369PSI472- F05016 I SGBC>19' 03 SI1326HL5001 AD501 2 RCB 19 SI9326HL5001 4C369PSI472- F05015 I SGB019' 07 SI1327HL5001 AD1601 2 RCB 19 SI9327HL5001 4C369PSI472- F05015 I SGB019' 07 WL1019HF5001 AD71 7 RCB 1MB >- -11 WL1019HF5001 7G369PWL477- F05022 I 11 A03 WL1284HL5002 AD1601 7 MABRM 10 WL9284HL5002 7M369PWL277- F05026 A 67C 03 WL1284HL5003 AD501 7 MABRM 10 WL9284HL5003 7M369PWL277- F05026 A 53B 03 Revision 1

ATTACHMENT 2 Unit 2 Snubber 1ST Listing Revision 1

Mdtpns Tagtpns / Model No Qc Route / Elev Hang Dwg Iso Dwg Pipe Dwg Accessible/

Snubber Level Location Inaccessible 2C112XSN0001A HYD- 2 RCB SGA- 58 400290- 400290- 0957-0100008WN I 1300KIP N/E 00010XX 0001 OXX 2C112XSN0001B HYD- 2 RCB SGB- 58 400290- 400290- 0957-0100008WN I 1300KIP N/E 00010XX 0001 OXX 2C112XSN0001C HYD- 2 RCB SGC- 58 400290- 400290- 0957-0100008WN I 1300KIP N/E 00010XX 00010XX 2C112XSN0001D HYD- 2 RCB SGD- 58 400290- 400290- 0957-0100008WN I 1300KIP N/E 0001 OXX 00010XX 2C112XSN0002A HYD- 2 RCB SGA- 58 400290- 400290- 0957-0100008WN I 1300IOP NAV 00010XX 00010XX 2C112XSN0002B HYD- 2 RCB SGB- 58 400290- 400290- 0957-0100008WN I 1300KIP NAV 00010XX 00010XX 2C112XSN0002C HYD- 2 RCB SGC- 58 400290- 400290- 0957-0100008WN I 1300KIP NAV 00010XX 00010XX 2C112XSN0002D HYD- 2 RCB SGD- 58 400290- 400290- 0957-0100008WN I 1300KIP NAV 00010XX 00010XX 2C112XSN0003A HYD- 2 RCB SGA- 58 400290- 400290- 0957-0100008WN I 1300KIP SAV 00010XX 00010XX 2C112XSN0003B HYD- 2 RCB SGB- 58 400290- 400290- 0957-0100008WN I 1300KIP SAV 00010XX 00010XX 2C112XSN0003C HYD- 2 RCB SGC- 58 400290- 400290- 0957-0100008WN I 1300KIP s/w 00010XX 00010XX 2C112XSN0003D HYD- 2 RCB SGD- 58 400290- 400290- 0957-0100008WN I 1300KIP s/w 00010XX 00010XX 2C112XSN0004A HYD- 2 RCB SGA- 58 400290- 400290- 0957-0100008WN I 1300KIP S/E 00010XX 00010XX 2C112XSN0004B HYD- 2 RCB SGB- 58 400290- 400290- 0957-0100008WN I 1300KIP S/E 00010XX 00010XX 2C112XSN0004C HYD- 2 RCB SGC- 58 400290- 400290- 0957-0100008WN I 1300KIP S/E 00010XX 0001 OXX 2C112XSN0004D HYD- 2 RCB SGD- 58 400290- 400290- 0957-0100008WN I 1300KIP S/E 00010XX 00010XX Revision 1

AF2006HL5003 AD5501 2 RCB 19 AF9006HL5003 2C369PAF402- F00024 I SGAD>52' 02 AF2006HL5015 AD5501 2 RCB 19 AF9006HL5015 2C369PAF402- F00024 I SGAD>52' 02 AF2006HL5018 AD5501 2 RCBOMB 19 AF9006HL5018 2C369PAF402- F00024 I

>19' 02 AF2006HL5035N AD5501 2 RCB 19 AF9006HL5035 2C369PAF402- F00024 I SGAD>68' 02 AF2006HL5035S AD5501 2 RCB 19 AF9006HL5035 2C369PAF402- F00024 I SGAD>68' 02 AF2008HL5028 AD5501 2 RCB 19 AF9008HL5028 2C369PAF402- F00024 I SGAD>68' 02 AF2008HL5029 AD5501 2 RCB 19 AF9008HL5029 2C369PAF402- F00024 I SGAD>68' 02 AF2008HL5030 AD5501 2 RCBOMB 19 AF9008HL5030 2C369PAF402- F00024 I

>19' 02 AF2008HL5041N AD5501 2 RCB 19 AF9008HL5041 2C369PAF402- F00024 I SGAD>68' 02 AF2008HL5041S AD5501 2 RCB 19 AF9008HL5041 2C369PAF402- F00024 I SGAD>68' 02 AF2010HL5002L AD5501 2 RCBOMB 19 AF9010HL5002 2C369PAF402- F00024 I

>19' 01 AF2010HL5002U AD5501 2 RCBOMB 19 AF9010HL5002 2C369PAF402- F00024 I

>19' 01 AF2010HL5007E AD5501 2 RCB 19 AF9010HL5007 2C369PAF402- F00024 I SGBC>52' 01 AF2010HL5007W AD5501 2 RCB 19 AF9010HL5007 2C369PAF402- F00024 I SGBC>52' 01 AF2010HL5008L AD5501 2 RCB 19 AF9010HL5008 2C369PAF402- F00024 I SGB068' 01 AF2010HL5008U AD5501 2 RCB 19 AF9010HL5008 2C369PAF402- F00024 I SGBC>68' 01 AF2010HL5009 AD1601 2 RCB 19 AF9010HL5009 2C369PAF402- F00024 I SGB068' 01 Revision 1

AF2010HL5017 AD5501 2 RCB 19 AF9010HL5017 2C369PAF402- F00024 I SGB068' 01 AF2010HL5018 AD1601 2 RCB 19 AF9010HL5018 2C369PAF402- F00024 I SGB068' 01 AF2010HL5020 AD1601 2 RCB 19 AF9010HL5020 2C369PAF402- F00024 I SGBC>68' 01 AF2010HL5026 AD1601 2 RCB 19 AF9010HL5026 2C369PAF402- F00024 I SGB019' 01 AF2010HL5035 AD1601 2 RCB 19 AF9010HL5035 2C369PAF402- F00024 I SGB068' 01 AF2012HL5014E AD1601 2 RCB 19 AF9012HL5014 2C369PAF402- F00024 I SGB068' 01 AF2012HL5014W AD1601 2 RCB 19 AF9012HL5014 2C369PAF402- F00024 I SGB068' 01 AF2012HL5017 AD5501 2 RCB 19 AF9012HL5017 2C369PAF402- F00024 I SGB068' 01 AF2012HL5018 AD1601 2 RCB 19 AF9012HL5018 2C369PAF402- F00024 I SGB068' 01 AF2012HL5020 AD1601 2 RCB 19 AF9012HL5020 2C369PAF402- F00024 I SGB068' 01 AF2012HL5024 AD5501 2 RCBOMB 19 AF9012HL5024 2C369PAF402- F00024 I

>19' 01 AF2012HL5027 AD5501 2 RCBOMB 19 AF9012HL5027 2C369PAF402- F00024 I

>19' 01 AF2012HL5038L AD5501 2 RCB 19 AF9012HL5038 2C369PAF402- F00024 I SGB068' 01 AF2012HL5038U AD5501 2 RCB 19 AF9012HL5038 2C369PAF402- F00024 I SGB068' 01 AF2054HL5004N AD151 3 FVCD 34 AF9054HL5004 5G369PAF602- F00024 A 10 AF2054HL5004S AD151 3 FVCD 34 AF9054HL5004 5G369PAF602- F00024 A 10 AF2061HL5001 AD 1601 2 RCB 19 AF9061HL5001 2C369PAF402- F00024 I SGAD>52' 02 Revision 1

AF2061HL5002 AD1601 2 RCB 19 AF9061HL5002 2C369PAF402- F00024 I SGAD>68' 02 AF2062HL5011 AD1601 2 RCB 19 AP9062HL5011 2C369PAF402- F00024 I SGAD>68' 02 AF2062HL5012 AD1601 2 RCB 19 AF9062HL5012 2C369PAF402- F00024 I SGAD>68' 02 AF2062HL5015 AD1601 2 RCB 19 AF9062HL5015 2C369PAF402- F00024 I SGAD>52' 02 AF2063HL5002 AD1601 2 RCB 19 AF9063HL5002 2C369PAF402- F00024 I SGB068' 01 AF2063HL5003 AD151 2 RCB 19 AF9063HL5003 2C369PAF402- F00024 I SGBC>68' 01 AF2063HL5005 AD1601 2 RCB 19 AF9063HL5005 2C369PAF402- F00024 I SGB068' 01 AF2063HL5006 AD1601 2 RCB 19 AF9063HL5006 2C369PAF402- F00024 I SGB068' 01 AF2064HL5004 AD16Q1 2 RCB 19 AF9064HL5004 2C369PAF402- F00024 I SGB052' 01 AP2003HF5001 AD41 2 MABRM 29 AP2003HF5001 5M369PAP287- Z47501 A 108C A01 CC2105HL5004 AD5501 3 RCBRHR 37 CC9105HL5004 4C369PCC407- F05017 I HX2A 08 CC2105HL5009 AD5501 3 RCBOMB 52 CC9105HL5009 4C369PCC407- F05017 I

>52' 08 CC2109HL5001N AD501 3 MABRM 27 CC9109HL5001 5M362PCC207- F05017 A 106A 07 CC2109HL5001S AD501 3 MABRM 27 CC9109HL5001 5M362PCC207- F05017 A 106A 07 CC2110HL5001 AD1601 3 MABRM 27 CC9110HL5001 5M362PCC207- F05017 A 106A 07 CC2136HL5002 AD501 7 MABRM64 10 CC9136HL5002 5M362PCC207- F05017 A 07 CC2205HL5007L AD501 3 RCBOMB 52 CC9205HL5007 5M362PCC207- F05018 I

>52' 07 Revision 1

CC2205HL5007U AD501 3 RCBOMB 52 CC9205HL5007 5M362PCC207- F05018 I

>52' 07 CC2206HL5008 AD501 3 RCBOMB 52 CC9206HL5008 4C369PCC407- F05018 I

>52' 10 CC2209HL5002 AD1601 3 MABRM216 41 CC9209HL5002 5M369PCC207- F05018 A 11 CC2209HL5003 AD1601 3 MABRM216 41 CC9209HL5003 5M369PCC207- F05018 A 11 CC2210HL5001 AD1601 3 MABRM 27 CC9210HL5001 5M369PCC207- F05018 A 106A 22 CC2215SS0002 AD501 3 RCB 0MB >- -11 CC9215SS02 3C369PCC407- F05018 I 11' 16 CC2220SS0002L AD501 3 MABRM64 10 CC9220SS0002 5M369PCC207- F05018 A 11 CC2220SS0002U AD501 3 MABRM64 10 CC9220SS0002 5M369PCC207- F05018 A 11 CC2309SS0002 AD1601 3 MABRM216 41 CC9309SS0002 5M362PCC207- F05019 A 01 CC2309SS0003L AD1601 3 MABRM216 41 CC9309SS0003 5M362PCC207- F05019 A 01 CC2309SS0003U AD1601 3 MABRM216 41 CC9309SS0003 5M362PCC207- F05019 A 01 CC2311SS0001 AD1601 3 MABRM216 41 CC9311SS0001 5M369PCC207- F05019 A 08 CC2320HL5001 AD1601 3 MABRM216 41 CC9320HL5001 5M362PCC207- F05019 A 01 CC2425HL5016 AD151 3 FHB RM 208 30 CC9425HL5016 5F369PCC507- F05020 A 01 CC2613SS0003 AD151 7 RCBOMB 37 CC9613SS0003 5C369PCC407- F05021 I

>37' 03 CV2002HL5002 AD71 2 RCB 19 CV9002HL5002 4C369PCV417- F05005 I SGBC>52' 04 CV2002HL5003 AD71 2 RCB 19 CV9002HL5003 4C369PCV417- F05005 I SGB019' 04 Revision 1

CV2002HL5004 AD71 2 RCB 19 CV9002HL5004 4C369PCV417- F05005 I SGBC>19' 04 CV2002HL5007 AD151 2 RCB 19 CV9002HL5007 4C369PCV417- F05005 I SGB019' 04 CV2002HL5008 AD71 2 RCB 19 CV9002HL5008 4C369PCV417- F05005 I SGBC>37' 04 CV2002HL5009 AD151 2 RCB 19 CV9002HL5009 4C369PCV417- F05005 I SGB037' 04 CV2002HL5010 AD151 2 RCB 19 CV9002HL5010 4C369PCV417- F05005 I SGBC>19' 04 CV2002HL5012 AD71 2 RCB 19 CV9002HL5012 4C369PCV417- F05005 I SGB037' 04 CV2002HL5019 AD151 2 RCB 19 CV9002HL5019 4C369PCV417- F05005 I SGB019' 04 CV2002HL5020 AD151 2 RCB 19 CV9002HL5020 4C369PCV417- F05005 I SGB019' 04 CV2002HL5021 AD501 2 RCB 19 CV9002HL5021 4C369PCV417- F05005 I SGB019' 04 CV2003HF5003 AD151 2 RCB RON 37 CV2003HF5003 5C369PCV417- F05005 I HX A09 CV2003HL5003N AD151 2 RCB RON 37 CV2003HL5003 4C369PCV417- F05005 I HX 04 CV2003HL5003S AD151 2 RCB RON 37 CV2003HL5003 4C369PCV417- F05005 I HX 04 CV2004HF5001 AD41 2 RCB RON 37 CV2004HF5001 5C369PCV417- F05005 I HX A09 CV2005HF5001 AD41 2 RCB RON 37 CV2005HF5001 5C369PCV417- F05005 I HX A09 CV2006HL5037 AD1601 2 MABRM 29 CV9006HL5037 4M369PCV217- F05005 A 108C 04 CV2011HL5009 AD71 2 MABRM49 10 CV9011HL5009 4M369PCV217- F05006 A 04 CV2086SS0002 AD71 2 MABRM110 29 CV9086SS0002 2M369PCV217- F05006 A 05 Revision 1

CV2088HL5002 AD41 2 MABRM31 10 CV9088HL5002 4M369PCV217- F05006 A 04 CV2116HL5018 AD71 2 MABRM 29 CV9116HL5018 2M369PCV217- F05007 A 108C 20 CV2117HF5054 AD41 2 RCB PZR 37 CV2117HF5054 4C369PCV417- F05005 I A02 CV2117HL5005 AD501 2 RCB 19 CV9117HL5005 4C369PCV417- F05005 I SGB037' 02 CV2117SS0006 AD1601 2 RCB 19 CV9117SS0006 4C369PCV417- F05005 I SGB037' 02 CV2121HS5007 AD41 1 RCB PZR 37 CV9121HS5007 4C369PCV417- F05005 I A02 CV2121HS5009 AD151 1 RCB PZR 37 CV9121HS5009 4C369PCV417- F05005 I A02 CV2121HS5010 AD151 1 RCB PZR 37 CV9121HS5010 4C369PCV417- F05005 I A02 FC2009SS0001 AD41 3 FHBRM110 21 FC9009SS0001 4F369PFC530- F05028 A 03 FC2011HL5001 AD1601 2 FHBRM110 21 FC9011HL5001 4F369PFC530- F05028 A 02 FC2012HL5002 AD501 3 FHBRM110 21 FC9012HL5002 4F369PFC530- F05028 A 02 FW2012HL5002E AD5501 2 RCB 19 FW9012HL5002 2C369PFW433- F00062 I SGAD>37' 01 FW2012HL5002W AD5501 2 RCB 19 FW9012HL5002 2C369PFW433- F00062 I SGAD>37' 01 FW2012HL5003 AD12501 2 RCB 19 FW9012HL5003 2C369PFW433- F00062 I SGAD>37' 01 FW2012HL5005L AD5501 2 RCBOMB 37 FW9012HL5005 2C369PFW433- F00062 I

>37' 01 FW2012HL5005U AD5501 2 RCBOMB 37 FW9012HL5005 2C369PFW433- F00062 I

>37' 01 FW2012HL5011 AD5501 2 RCB 19 FW9012HL5011 2C369PFW433- F00062 I SGAD>19' 01 Revision 1

FW2012HL5016 AD12501 2 RCB 19 FW2012HL5016 2C369PFW433- F00062 I SGAD>37' 01 FW2014HL5001E AD5501 2 RCB 19 FW9014HL5001 2C369PFW433- F00062 I SGBC>37' 01 FW2014HL5001W AD5501 2 RCB 19 FW9014HL5001 2C369PFW433- F00062 I SGBC>37' 01 FW2014HL5002 AD12501 2 RCB 19 FW9014HL5002 2C369PFW433- F00062 I SGB037' 01 FW2014HL5003L AD5501 2 RCB RON 37 FW9014HL5003 2C369PFW433- F00062 I HX 01 FW2014HL5003U AD5501 2 RCB RON 37 FW9014HL5003 2C369PFW433- F00062 I HX 01 FW2014HL5009 AD12501 2 RCB 19 FW9014HL5009 2C369PFW433- F00062 I SGBC>37' 01 FW2014HL5012 AD5501 2 RCB 19 FW9014HL5012 2C369PFW433- F00062 I SGB019' 01 FW2016HL5003 AD5501 2 RCB RON 37 FW9016HL5003 2C369PFW433- F00062 I HX 11 FW2016HL5004 AD5501 2 RCB 19 FW9016HL5004 2C369PFW433- F00062 I SGB019' 01 FW2016HL5006 AD5501 2 RCB 19 FW9016HL5006 2C369PFW433- F00062 I SGB052' 01 FW2016HL5007 AD5501 2 RCB 19 FW9016HL5007 2C369PFW433- F00062 I SGB019' 01 FW2016HL5008 AD5501 2 RCB RON 37 FW9016HL5008 2C369PFW433- F00062 I HX 01 FW2016HL5009 AD12501 2 RCB 19 FW9016HL5009 2C369PFW433- F00062 I SGBC>37' 01 FW2016HL5010 AD5501 2 RCB 19 FW9016HL5010 2C369PFW433- F00062 I SGB037' 01 FW2016SH0001 AD5501 2 RCB 19 FW9016SH0001 2C369PFW433- F00062 I SGBC>19" 01 FW2016SS0006 AD5501 2 RCB 19 FW9016SS0006 2C369PFW433- F00062 I SGB052' 01 Revision 1

PW2018HL5003 AD5501 2 RCBOMB 37 FW9018HL5003 2C369PFW433- F00062 I

>3T 01 FW2018HL5004 AD5501 2 RCB 19 FW9018HL5004 2C369PFW433- F00062 I SGAD>19' 01 FW2018HL5006L AD5501 2 RCBOMB 37 FW9018HL5006 2C369PFW433- F00062 I

>37' 01 FW2018HL5006U AD5501 2 RCBOMB 37 FW9018HL5006 2C369PFW433- F00062 I

>37' 01 FW2018HL5007N AD5501 2 RCB 19 FW9018HL5007 2C369PFW433- F00062 I SGAD>37' 01 FW2018HL5007S AD5501 1 RCB 19 FW9018HL5007 2C369PFW433- F00062 I SGAD>37' 01 FW2018HL5008 AD12501 2 RCB 19 FW9018HL5008 2C369PFW433- F00062 I SGAD>37' 01 FW2018HL5009 AD12501 2 RCB 19 FW9018HL5009 2C369PFW433- F00062 I SGAD>37' 01 FW2018SS0001 AD5501 2 RCB 19 FW9018SS0001 2C369PFW433- F00062 I SGAD>19' 01 FW2018SS0006 AD5501 2 RCB 19 FW9018SS0006 2C369PFW433- F00062 I SGAD>52' 01 FW2018SS0007 AD12501 2 RCB 19 FW9018SS0007 2C369PFW433- F00062 I SGAD>37' 01 FW2029HL5002E AD1601 2 WC A 44 FW9029HL5002 2G369PFW633- F00062 A 02 FW2029HL5002W AD1601 2 IVCA 44 FW9029HL5002 2G369PFW633- F00062 A 02 FW2029HL5003 AD1601 2 IVC A 44 FW9029HL5003 2G369PFW633- F00062 A 02 FW2030HL5002E AD1601 2 TVC B 44 FW9030HL5002 2G369PFW633- F00062 A 03 FW2030HL5002W AD1601 2 r^cB 44 FW9030HL5002 2G369PFW633- F00062 A 03 FW2030HL5003 AD1601 2 FVCB 44 FW9030HL5003 2G369PFW633- F00062 A 03 Revision 1

FW2031HL5002E AD1601 2 rvcc 44 FW9031HL5002 2G369PFW633- F00062 A 04 FW2031HL5002W AD1601 2 we c 44 FW9031HL5002 2G369PFW633- F00062 A 04 FW2031HL5003 AD1601 2 IVCC 44 FW9031HL5003 2G369PFW633- F00062 A 04 FW2032HL5002E AD1601 2 rye D 44 FW9032HL5002 2G369PFW633- F00062 A 01 FW2032HL5002W AD1601 2 FVCD 44 FW9032HL5002 2G369PFW633- F00062 A 01 FW2032HL5003 AD1601 2 rv-CD 44 FW9032HL5003 2G369PFW633- F00062 A 01 FW2H7HL5001 AD41 2 we c 34 FW9117HL5001 2G369PFW633- F00063 A 05 FW2117HL5003 AD41 2 rvcc 34 FW9117HL5003 2G369PFW633- F00063 A 05 FW2117HL5004 AD41 2 rvcc 44 FW9117HL5004 2G369PFW633- F00063 A 05 FW2119HL5001 AD41 2 FVCB 34 FW9119HL5001 2G369PFW633- F00063 A 05 FW2H9HL5003 AD41 2 rv-CB 34 FW9119HL5003 2G369PFW633- F00063 A 05 FW2119HL5004 AD41 2 IVCB 44 FW9119HL5004 2G369PFW633- F00063 A 05 FW2121HL5001 AD41 2 WC A 34 FW9121HL5001 2G369PFW633- F00063 A 05 FW2121HL5003 AD41 2 WC A 34 FW9121HL5003 2G369PFW633- F00063 A 05 FW2121HL5004 AD41 2 IVCA 34 FW9121HL5004 2G369PFW633- F00063 A 05 FW2123HL5001 AD41 2 JVC D 34 FW9123HL5001 2G369PFW633- F00063 A 05 FW2123HL5003 AD41 2 r^cD 34 FW9123HL5003 2G369PFW633- F00063 A 05 Revision 1

FW2123HL5004 AD41 2 WC D 34 FW9123HL5004 2G369PFW633- F00063 A 05 MD2147HF5002 AD71 7 TVCA 44 MD2147HF5002 9G369PMD645- F00055 A A01 MD2148HF5002 AD71 7 WC B 44 MD2148HF5002 9G369PMD645- F00055 A A01 MD2149HP5002 AD71 7 rvcc 44 MD2149HF5002 9G369PMD645- F00055 A A01 MD2150HF5002 AD71 7 IVCD 44 MD2150HF5002 9G369PMD645- F00055 A A01 MS2001HL5004 AD5501 2 RCBOMB 68 MS9001HL5004 2C369PMS446- F00016 I

>68' 01 MS2001HL5007 AD12501 2 RCB 19 MS9001HL5007 2C369PMS446- F00016 I SGAD>68' 01 MS2001HL5010L AD1601 2 IVCA 51 MS9001HL5010 2G369PMS646- F00016 A 06 MS2001HL5010U AD1601 2 WC A 51 MS9001HL5010 2G369PMS646- F00016 A 06 MS2001HL5011E AD5501 2 WC A 51 MS9001HL50H 2G369PMS646- F00016 A 06 MS2001HL5011W AD5501 2 WC A 51 MS9001HL5011 2G369PMS646- F00016 A 06 MS2001HL5012L AD1601 2 TVCA 51 MS9001HL5012 2G369PMS646- FOOD 16 A 06 MS2001HL5012U AD1601 2 IVCA 51 MS9001HL5012 2G369PMS646- F00016 A 06 MS2001HL5015 AD5501 2 RCB 19 MS9001HL5015 2C369PMS446- F00016 I SGAD>83' 01 MS2002HL5006 AD5501 2 RCBOMB 68 MS9002HL5006 2C369PMS466- F00016 I

>68' 02 MS2002HL5007 AD12501 2 RCB 19 MS9002HL5007 2C369PMS446- F00016 I SGB068' 02 MS2002HL5010L AD1601 2 TVCB 51 MS9002HL5010 2G369PMS646- F00016 A 07 Revision 1

MS2002HL5010U AD1601 2 rvcB 51 MS9002HL5010 2G369PMS646- F00016 A 07 MS2002HL5011E AD5501 2 IVCB 51 MS9002HL5011 2G369PMS646- F00016 A 07 MS2002HL50HW AD5501 2 WCB 51 MS9002HL5011 2G369PMS646- FOOD 16 A 07 MS2002HL5012L AD1601 2 WC B 51 MS9002HL5012 2G369PMS646- F00016 A 07 MS2002HL5012U AD1601 2 r^cB 51 MS9002HL5012 2G369PMS646- F00016 A 07 MS2002HL5015 AD5501 2 RCB 19 MS9002HL5015 2C369PMS446- F00016 I SGBC>83' 02 MS2002HL5016 AD5501 2 RCB 19 MS9002HL5016 2C369PMS446- F00016 I SGB083' 02 MS2003HL5004 AD5501 2 RCBOMB 68 MS9003HL5004 2C369PMS446- F00016 I

>68' 03 MS2003HL5012 AD12501 2 RCB 19 MS9003HL5012 2C369PMS446- F00016 I SGB068' 03 MS2003HL5013 AD5501 2 RCB 19 MS9003HL5013 2C369PMS446- F00016 I SGB083' 03 MS2003HL5014 AD5501 2 RCB 19 MS9003HL5014 2C369PMS446- F00016 I SGB083' 03 MS2003HL5015L AD1601 2 r/cc 51 MS9003HL5015 2G369PMS646- F00016 A 08 MS2003HL5015U AD1601 2 we c 51 MS9003HL5015 2G369PMS646- F00016 A 08 MS2003HL5016E AD5501 2 we c 51 MS9003HL5016 2G369PMS646- F00016 A 08 MS2003HL5016W AD5501 2 TVCC 51 MS9003HL5016 2G369PMS646- F00016 A 08 MS2003HL5017L AD1601 2 rvcc 51 MS9003HL5017 2G369PMS646- F00016 A 08 MS2003HL5017U AD1601 2 rvcc 51 MS9003HL5017 2G369PMS646- F00016 A 08 Revision 1

MS2004HL5007 AD5501 2 RCBOMB 68 MS9004HL5007 2C369PMS446- F00016 I

>68' 04 MS2004HL5012 AD12501 2 RCB 19 MS9004HL5012 2C369PMS446- F00016 I SGAD>68' 04 MS2004HL5013 AD12501 2 RCB PZR 37 MS9004HL5013 2C369PMS446- F00016 I 04 MS2004HL5014 AD12501 2 RCB 19 MS9004HL5014 2C369PMS446- F00016 I SGAD>83' 04 MS2004HL5015L AD1601 2 TVCD 51 MS9004HL5015 2G369PMS646- F00016 A 09 MS2004HL5015U AD1601 2 rvcD 51 MS9004HL5015 2G369PMS646- F00016 A 09 MS2004HL5016E AD5501 2 IVCD 51 MS9004HL5016 2G369PMS646- F00016 A 09 MS2004HL5016W AD5501 2 WC D 51 MS9004HL5016 2G369PMS646- F00016 A 09 MS2004HL5017L AD1601 2 WC D 51 MS9004HL5017 2G369PMS646- F00016 A 09 MS2004HL5017U AD1601 2 FVCD 51 MS9004HL5017 2G369PMS646- F00016 A 09 MS2005SS0001N AD5501 7 TGBB 55 MS9005SS0001 7G369PMS846- F00016 A 05 MS2005SS0001S AD5501 7 TGBB 55 MS9005SS0001 7G369PMS846- F00016 A 05 MS2005SS0002E AD5501 7 TGBB 29 MS9005SS0002 7G369PMS846- F00016 A 05 MS2005SS0002W AD5501 7 TGBB 29 MS9005SS0002 7G369PMS846- F00016 A 05 MS2006SS0001N AD5501 7 TGBB 55 MS9006SS0001 7G369PMS846- F00016 A 06 MS2006SS0001S AD5501 7 TGBB 55 MS9006SS0001 7G369PMS846- F00016 A 06 MS2006SS0002E AD5501 7 TGBB 29 MS9006SS0002 7G369PMS846- F00016 A 06 Revision 1

MS2006SS0002W AD5501 7 TGBB 29 MS9006SS0002 7G369PMS846- F00016 A 06 MS2007SS0002E AD5501 7 TGBB 29 MS9007SS0002 7G369PMS846- F00016 A 06 MS2007SS0002W AD5501 7 TGBB 29 MS9007SS0002 7G369PMS846- F00016 A 06 MS2008HL5001 AD5501 7 TGBB 55 MS9008HL5001 7G369PMS846- F00016 A 05 MS2008SS0001E AD5501 7 TGBB 29 MS9008SS0001 7G369PMS846- F00016 A 05 MS2008SS0001W AD5501 7 TGBB 29 MS9008SS0001 7G369PMS846- F00016 A 05 MS2013HL5002E AD5501 7 TGBB 55 MS9013HL5002 7G369PMS846- F00016 A 08 MS2013HL5002W AD5501 7 TGBB 55 MS9013HL5002 7G369PMS846- F00016 A 08 MS2013HL5003 AD5501 7 TGBB 55 MS9013HL5003 7G3G9PMS846- F00016 A 05 MS2013HL5004 AD5501 7 TGBB 55 MS9013HL5004 7G369PMS846- F00016 A 05 MS2013SS0002E AD5501 7 TGBB 55 MS9013SS0002 7G369PMS846- F00016 A 09 MS2013SS0002W AD5501 7 TGBB 55 MS9013SS0002 7G369PMS846- F00016 A 09 MS2051HL5009 AD71 3 FVCD 10 MS9051HL5009 4G369PMS646- F00024 A 05 PS2020HF5002 AD41 7 MABRM 29 PS2020HF5002 5M369PPS285- Z00045 A 108C A01 RC2000SS0001 AD151 RCB PZR 37 RC2000SS0001 4C369PRC457- F05003 I 07 RC2003HL5006 AD501 1 RCB PZR 37 RC9003HL5006 1C369PRC457- F05003 I 06 RC2003HL5009 AD501 1 RCB PZR 37 RC9003HL5009 1C369PRC457- F05003 I 06 Revision 1

RC2014HL5001 AD5501 7 RCB PZR 37 RC9014HL5001 7C369PRC457- F05004 I 02 RC2014HL5003E AD5501 7 RCB PZR 37 RC9014HL5003 7C769PRC457- F05004 I 02 RC2014HL5003W AD5501 7 RCB PZR 37 RC9014HL5003 7C369PRC457- F05004 I 02 RC2014HL5005N AD5501 7 RCB PZR 37 RC9014HL5005 7C369PRC457- F05004 I 02 RC2014HL5005S AD5501 7 RCB PZR 37 RC9014HL5005 7C369PRC457- F05004 I 02 RC2014HL5006L AD5501 7 RCB PZR 37 RC9014HL5006 7C369PRC457- F05004 I 02 RC2014HL5006U AD5501 7 RCB PZR 37 RC9014HL5006 7C369PRC457- F05004 I 02 RC2014HL5009 AD501 7 RCB PZR 37 RC9014HL5009 7C369PRC457- F05004 I 02 RC2014HL5012N AD5501 7 RCB PZR 37 RC9014HL5012 7C369PRC457- F05004 I 02 RC2014HL5012S AD5501 7 RCBPZR 37 RC9014HL5012 7C369PRC457- F05004 I 02 RC2014HL5013 AD1601 7 RCB PZR 37 RC9014HL5013 7C369PRC457- F05004 I 02 RC2014HL5015 AD1601 7 RCB PZR 37 RC9014HL5015 7C369PRC457- F05004 I 02 RC2014HL5019N AD5501 7 RCB PZR 19 RC9014HL5019 7C369PRC457- F05004 I 02 RC2014HL5019S AD5501 7 RCB PZR 19 RC9014HL5019 7C369PRC457- F05004 I 02 RC2014HL5026 AD501 7 RCB PZR 19 RC9014HL5026 7C369PRC457- F05004 I 02 RC2014HL5028 AD1601 7 RCBPZR 19 RC9014HL5028 7C369PRC457- F05004 I 02 RC2112HL5002 AD5501 1 RCB 19 RC9112HL5002 4C369PRC457- F05001 I SGAD>19' 09 Revision 1

RC2123HL5013 AD501 1 RCB PZR 37 RC9123HL5013 4C369PRC457- F05001 I 07 RC2125HL5001 AD5501 1 RCB 1MB >- -11 RC9125HL5001 4C369PRC457- F05001 I 11' 10 RC2125HL5008 AD1601 1 RCB 1MB >- -11 RC9125HL5008 4C369PRC457- F05001 I ir 10 RC2221HL5001 AD1601 1 RCB 1MB >- -11 RC9221HL5001 4C369PRC457- F05001 I 11' 10 RC2221HL5003 AD5501 1 RCB 1MB >- -11 RC9221HL5003 4C369PRC457- F05001 I ir 10 RC2221HL5004 AD5501 1 RCB 19 RC9221HL5004 4C369PRC457- F05001 I SGBC>19' 10 RC2221HL5005 AD5501 1 RCB 19 RC9221HL5005 4C369PRC457- F05001 I SGB019' 10 RC2221HL5006 AD5501 1 RCB 1MB >- -11 RC9221HL5006 4C369PRC457- F05001 I 11' 10 RC2221HL5007 AD5501 1 RCB 1MB >- -11 RC9221HL5007 4C369PRC457- F05001 I 11' 10 RC2320HL5002 AD1601 1 RCB 19 RC9320HL5002 4C369PRC457- F05001 I SGB019' 04 RC2320HL5004 AD501 1 RCB 19 RC9320HL5004 4C369PRC457- F05001 I SGB019' 04 RC2422HL5019 AD501 1 RCB 19 RC9422HL5019 1C369PRC457- F05001 I SGAD>52' 06 RH2101HL5001 AD1601 1 RCBVLV -2 RH9101HL5001 4C369PRH459- F20000 I RM 04 RH2101HL5002 AD1601 1 RCBVLV -2 RH9101HL5002 4C369PRH459- F20000 I RM 04 RH2101HL5003 AD1601 1 RCBVLV 19 RH9101HL5003 4C369PRH459- F20000 I RM 04 RH2101HL5006 AD5501 1 RCB 19 RH9101HL5006 4C369PRC459- F20000 I SGAD>19' 04 RH2101HL5009 AD1601 1 RCB 19 RH9101HL5009 4C369PRH459- F20000 I SGAD>19' 04 Revision 1

RH2110HL5002 AD501 2 RCB 19 RH9110HL5002 4C369PRH459- F20000 I SGAD>19' 03 RH2201HL5001 AD1601 1 RCBVLV -2 RH9201HL5001 4C369PRH459- F20000 I RM 07 RH2201HL5006 AD5501 1 RCBVLV -2 RH9201HL5006 4C369PRH459- F20000 I RM 07 RH2202SS0002 AD1601 2 RCBVLV -2 RH9202SS0002 4C369PRH459- F20000 I RM 07 RH2203HL5001 AD501 2 RCBVLV 19 RH9203HL5001 2C369PRH459- F20000 I RM 02 RH2204HL5001 AD501 2 RCBVLV 19 RH9204HL5001 2C369PRH459- F20000 I RM 02 RH2211HL5002L AD501 2 RCB 19 RH9211HL5002 4C369PRH459- F20000 I SGB019' 07 RH2211HL5002U AD501 2 RCB 19 RH9211HL5002 4C369PRH459- F20000 I SGB019' 07 RH2303HL5007 AD501 2 RCBVLV 19 RH9303HL5007 2C369PRH459- F20000 I RM 05 RH2303HL5009 AD501 2 RCB VLV -2 RH9303HL5009 2C369PRH459- F20000 I RM 05 RH2306SS0001 AD501 2 RCBVLV -2 RH9306SS0001 4C369PRH459- F20000 I RM 06 RH2312HL5002 AD501 2 RCBVLV 19 RH9312HL5002 4C369PRH459- F20000 I RM 01 RH2313HL5003L AD501 2 RCB 19 RH9313HL5003 4C369PRH459- F20000 I SGB019' 06 RH2313HL5003U AD501 2 RCB 19 RH9313HL5003 4C369PRH459- F20000 I SGB019' 06 SB2101HL5007 AD1601 2 RCBOMB 19 SB9101HL5007 2C369PSB468- F20001 I

>19' 02 SB2101HL5012 AD501 2 RCB 19 SB9101HL5012 2C369PSB468- F20001 I SGAD>19' 02 SB2101HL5017 AD1601 2 RCBOMB 19 SB9101HL5017 2C369PSB468- F20001 I

>19' 02 Revision 1

SB2101HL5019 AD501 2 IVCA 10 SB9101HL5019 5G369PSB668- F20001 A 03 SB2101HL5020 AD501 2 FVCA 10 SB9101HL5020 5G369PSB668- F20001 A 03 SB2101HL5022 AD501 2 rye A 10 SB9101HL5022 5G369PSB668- F20001 A 03 SB2104HL5001 AD501 7 WC A 10 SB9104HL5001 5G369PSB668- F20001 A 03 SB2104HL5002 AD501 7 rvcA 10 SB9104HL5002 5G369PSB668- F20001 A 03 SB2104HL5006 AD501 7 FVCA 10 SB9104HL5006 5G369PSB668- F20001 A 03 SB2105HL5001 AD71 7 IVCA 10 SB9105HL5001 5G369PSB668- F20001 A 03 SB2107HF5001 AD41 2 WC A 10 SB2107HF5001 7G369PSB668- F20001 A A01 SB2201HL5004 AD1601 2 RCBOMB 19 SB9201HL5004 2C369PSB468- F20001 I

>19' 02 SB2201HL5010 AD1601 2 RCBOMB 19 SB9201HL5010 2C369PSB468- F20001 I

>19' 02 SB2201HL5013 AD501 2 RCB 19 SB9201HL5013 2C369PSB468- F20001 I SGBC>19' 02 SB2201HL5017 AD501 2 FVCB 10 SB9201HL5017 5G369PSB668- F20001 A 05 SB2201HL5018 AD501 2 r^CB 10 SB9201HL5018 5G369PSB668- F20001 A 05 SB2201HL5020 AD501 2 IVCB 10 SB9201HL5020 5G369PSB668- F20001 A 05 SB2202HF5002 AD41 2 RCB 19 SB2202HF5002 2C362PSB468- F20001 I SGB019' A05 SB2204HL5001 AD501 7 IVCB 10 SB9204HL5001 5G369PSB668- F20001 A 05 SB2204HL5002 AD501 7 FVCB 10 SB9204HL5002 5G369PSB668- F20001 A 05 Revision 1

SB2205HL5003 AD151 7 FVCB 10 SB9205HL5003 5G369PSB668- F20001 A 05 SB2207HF5001 AD41 7 D/CB 10 SB2207HF5001 7G369PSB668- F20001 A A01 SB2250HF5003 AD41 2 RCB 19 SB2250HF5003 2C362PSB468- F20001 I SGB019' A05 SB2274HL5002L AD151 7 rvcB 10 SB9274HL5002 5G369PSB668- F20002 A 05 SB2274HL5002U AD151 7 WC B 10 SB9274HL5002 5G369PSB668- F20002 A 05 SB2301HL5003L AD501 2 RCBOMB 19 SB9301HL5003 2C369PSB468- F20001 I

>19' 02 SB2301HL5003U AD501 2 RCBOMB 19 SB9301HL5003 2C369PSB468- F20001 I

>19' 02 SB2301HL5011L AD501 2 RCB 19 SB9301HL5011 2C369PSB468- F20001 I SGBC>19' 02 SB2301HL5011U AD501 2 RCB 19 SB9301HL5011 2C369PSB468- F20001 I SGB019' 02 SB2301HL5012N AD151 2 RCB 19 SB9301HL5012 2C369PSB468- F20001 I SGB019' 02 SB2301HL5012S AD151 2 RCB 19 SB9301HL5012 2C369PSB468- F20001 I SGB019' 02 SB2301HL5018 AD501 2 P/CC 10 SB9301HL5018 5G369PSB668- F20001 A 07 SB2301HL5020 AD501 2 IVCC 10 SB9301HL5020 5G369PSB668- F20001 A 07 SB2301HL5021 AD501 2 rvcc 10 SB9301HL5021 5G369PSB668- F20001 A 07 SB2302HF5003 AD151 2 RCB 19 SB2302HF5003 2C369PSB468- F20001 I SGB019' A04 SB2303HF5005 AD151 2 RCB 19 SB2303HF5005 2C369PSB468- F20001 I SGBC>3T A04 SB2304HL5001 AD501 7 we c 10 SB9304HL5001 5G369PSB668- F20001 A 07 Revision 1

SB2304HL5002 AD501 7 rye c 10 SB9304HL5002 5G369PSB668- F20001 A 07 SB2304HL5006 AD501 7 rvcc 10 SB9304HL5006 5G369PSB668- F20001 A 07 SB2350HF5016 AD41 2 RCB 19 SB2350HF5016 2C362PSB468- F20001 I SGBC>19' A05 SB2401HL5003 AD1601 2 RCBOMB 19 SB9401HL5003 2C369PSB468- F20001 I

>19' 02 SB2401HL5011 AD1601 2 RCBOMB 19 SB9401HL5011 2C369PSB468- F20001 I

>19' 02 SB2401HL5012 AD501 2 RCB 19 SB9401HL5012 2C369PSB468- F20001 I SGAD>19' 02 SB2401HL5016L AD151 2 RCB 19 SB9401HL5016 2C369PSB468- F20001 I SGAD>19' 02 SB2401HL5016U AD151 2 RCB 19 SB9401HL5016 2C369PSB468- F20001 I SGAD>19' 02 SB2401HL5019 AD501 2 RCB 19 SB9401HL5019 2C369PSB468- F20001 I SGAD>19' 02 SB2401HL5020 AD501 2 WC D 10 SB9401HL5020 5G369PSB668- F20001 A 01 SB2401HL5022 AD501 2 IVCD 10 SB9401HL5022 5G369PSB668- F20001 A 01 SB2401HL5023 AD501 2 rvcD 10 SB9401HL5023 5G369PSB668- F20001 A 01 SB2402HF5002 AD71 2 RCB 19 SB2402HF5002 2C369PSB468- F20001 I SGAD>37' A04 SB2402HF5004 AD71 2 RCB 19 SB2402HF5004 2C369PSB468- F20001 I SGAD>37' A04 SB2403HF5002 AD151 2 RCB 19 SB2403HF5002 2C368PSB468- F20001 I SGAD>19' A04 SB2404HL5001 AD501 7 FVCD 10 SB9404HL5001 5G369PSB668- F20001 A 01 SB2404HL5002 AD501 7 F/CD 10 SB9404HL5002 5G369PSB668- F20001 A 01 Revision 1

SB2406HL5007 AD41 7 IVCD 10 SB9406HL5007 5G369PSB668- F20001 A 01 SB2407HF5001 AD41 7 TVCD 10 SB2407HF5001 7G369PSB668- F20001 A A01 SB2474HL5002 AD501 7 WC D 10 SB9474HL5002 5G369PSB668- F20002 A 01 SI2101SS0008L AD501 2 FHBHHSIA -29 SI9101SS0008 2F369PSI572- F05013 A 03 SI2101SS0008U AD501 2 FHBHHSIA -29 SI9101SS0008 2F369PSI572- F05013 A 03 SI2107HL5001N AD501 2 RCBOMB 19 SI9107HL5001 4C369PSI472- F05013 I

>19' 01 SI2107HL5001S AD501 2 RCBOMB 19 SI9107HL5001 4C369PSI472- F05013 I

>19' 01 SI2107SS0061 AD501 2 RCBOMB 19 SI9107SS0061 4C369PSI472- F05013 I

>19' 01 SI2108HL5001 AD1601 1 RCB 19 SI9108HL5001 4C369PSI472- F05013 I SGAD>19' 01 SI2108HL5003 AD501 1 RCB 19 SI9108HL5003 4C369PSI472- F05013 I SGAD>19' 01 SI2201HL5010L AD501 2 FHBHHSIB -29 SI9201HL5010 2F369PSI572- F05014 A 04 SI2201HL5010U AD501 2 FHB HHSI B -29 SI9201HL5010 2F369PSI572- F05014 A 04 SI2205HL5022 AD501 2 RCB 1MB >- -11 SI9205HL5022 2C369PSI472- F05014 I 11' 02 SI2206HL5008 AD151 2 RCB 1MB >- -11 SI9206HL5008 4C369PSI472- F05014 I 11' 05 SI2206HL5012 AD501 2 RCB 1MB >- -11 SI9206HL5012 4C369PSI472- F05014 I 11' 05 SI2207SS0001 AD501 2 RCBOMB 19 SI9207SS0001 4C369PSI472- F05014 I

>19' 05 SI2208HL5005 AD1601 1 RCB 19 SI9208HL5005 4C369PSI472- F05014 I SGB019' 05 Revision 1

SI2217HL5009 AD1601 2 RCB 0MB >- -2 SI9217HL5009 5C369PSI472- F05016 I 11' 03 SI2301SS0005L AD501 2 FHB HHSI C -29 SI9301SS0005 2F369PSI572- F05015 A 06 SI2301SS0005U AD501 2 FHB HHSI C -29 SI9301SS0005 2F369PSI572- F05015 A 06 SI2306HL5012 AD151 2 FHB HHSI C -29 SI9306HL5012 2F369PSI572- F05015 A 05 SI2308HL5001 AD501 1 RCB 1MB >- -11 SI9308HL5001 4C369PSI472- F05015 I 11' 07 SI2314HL5007 AD5501 2 RCB 1MB >- -11 SI9314HL5007 5C369PSI472- F05016 I 11' 03 SI2315HL5003 AD12501 1 RCB 19 SI9315HL5003 5C369PSI472- F05016 I SGB019' 03 SI2315HL5004 AD5501 1 RCB 19 SI9315HL5004 5C369PSI472- F05016 I SGBC>19' 03 SI2326HL5001 AD501 2 RCB 19 SI9326HL5001 4C369PSI472- F05015 I SGB019' 07 SI2327HL5001 AD1601 2 RCB 19 SI9327HL5001 4C369PSI472- F05015 I SGBC>19' 07 WL2019HF5001 AD71 7 RCB 1MB >- -11 WL2019HF5001 7G369PWL477- F05022 I ir A03 Revision 1

ATTACHMENT 3 Snubber Code Cases - Information Only Revision 1

Code Case OMN-13, Revision 2 Perfomnance.&ased Requirements For Extending; Snubber tnservice Visual Examination Interval at LWR Power Plants Infjiiiry: With the low rate of problem identification Table I Correlation Table through th>> viiiual examination proceBii, can thi? viiiual 199B Edition Through 1995 Edition and exammation interval allowfe>d in Table ISTD-4252-1 fif iggfi Addenda zoo6 Addenda the OM Code, Subsection ISTD, 1995 Editidn through 2M1 Addenda be extended? (STD 1.13 ISTD.I750 ISTB6 ISW-^MSO iSTO 6-1. 6.?, 6.3. 6.4 IST&-A210, <i220, 4230, <i240 Ri'ply: Yes, provided that the following additional ser-tSTO 6.^.1 ISTD-4251 vice life monitnring rt'quirementB are met. ISTB 6.^.7 IST&.4252 ISTO a IS10.60DO Applicnbiiity: ASME OM Code 1995 Edition thniugh fSTS a.s IST&.&5CO 2011 Addenda. Table (£10 6.5.2-1 Table ISTO-42^2-1 1 APPUCASIUTY This Code Case HitabliHhes sped fic requirements that must be met in order to allow extension of the visual 3 SPECIFIC REQUIREMENTS examination interval beyond the maximum interval 3.1 Examination for Indications of Degradation or allowed in Table ISTD-4252-t for mechnnlcal and Severe Operating Environments hydraulic snubbers. Paragraphs referenced ui this C<ide Case denote the 199ft Edition through the 2011 Addenda. Examinations per para.s. ISTD-4210, ISTD-4220, A correlation table fTable 1} is provided for the 1995 ISTD-4230, and ISTD-4240 shall mclude examination for Edition. This Code Case super.wdes the previously pub- indicationii uf degradatitin and severe operating lushed \'ersi(in. envinmmenbi.

3.2 Examination Prior to Maintenance 01 Testing 2 GENERAL REQUIREMENTS All snubbeni shall be examlnfd in acotirdance with Thu following rEquirfmenbi shall be implementyd in the requirement!, of paras. ISTD-4210, 1STD-4220, order to extend thy visual examination intrrval beyond ISTD-t230, and ISTD-4240 and para. 3.1 of this Codtt the maximum interval allowed in Table ISTD-42S2-1: CtUie prior to conducting any rnaintenance/ sfrtiklng/ or (fl) These requirements an? in addition td the secvictf tciiting, and prior to removal, for any pBason, from their life monitoring requininwnbi in section ISTD-fiOOO. installed location.

(b) The requiremenhi of this Ccidt* Caxo shall b>> implB-mented after the requirementH of paras. ISTD-4251 and 3.3 Monitoring of Resor/oir Fluid Level ISTD-4252 have been satisfied and the previous exami-Fluid li.'vel in hydraulic .wiubber ninwvolrs shall be nation per Table ISTD-4252-1 was performed at a maxi-Hufficicnt to (msure that the snubber is acceptable for mum interval of two fuel cycles.

continued service to the next examinatian interval.

(c) Demoruitrate that the requlrementK of parnii. 3.1 through 3.6 (if this Code Cane have been met for one interval prior to extending the examination interval.

3,4 Review of Operaticmal Readiness Test Data All insen'ice test data acquired since implfe'mentati<in 2.1 Service Life Evaluations (if the requlrementa (if this, Code Case shall be evaluated The data and information gathered under this Code for indications of snubber degradation or iither anoma-Case shall be utilized Id reevaluate service life as lieit. This includes a review of teiit hsces, where available.

described in section ISTD-fiflOO. The resulb, of thiB yvaluatidn shall be UKed (ft) to idyntify anubbera that are subject to pmgressivB 2.2 Testing for This Code Case degradation Snubbers teiited Hpecif'lcally for this Codi* Case shall (b) to identify severe operating envimnmenbi not pre-be dispiwitioned per para. ISTD-65<10. viousily idemtified

Whtire applicable, data gathenid prior to ImpltsmfnEa- W U at any (Imf during an examination Interval the tion of this Code Cass Bhall also be evaluattid, cumulative* number of unacceptable snubbers exceeds the applicable value from Column B in 3.5 Examination During Disassembty Table ISTD-4252-1, the current examination inter val shall Snubbers and snubbcr parts Khall be examined for end, and all remaining examinatinns must be complfted indicatidns of dogradalicm and severe operating envi- within the current fuel cycle. The duration of the subse-ninmtznts during dlsassembly (e.g., during failure walu- quent examinaliiin inlerval shall be reduced in accor-ation, refurbiHhment}. dance with Table ISTD-4252-1, using the examinatitm interval prior to implementing the code case as the base 3.6 Transient Dynamic Event interval. The beginning of the subsequent fuel cycleshall be the starting date for the new examination interval.

The iiervice life evaluatiun required by para. 2.1 of ihis Cnde Casti Bhall include any trarciient dynamic event 3.B Examination Corrective Action and actions taken under para. ISTD-175D. The following actionK shall by taken for imubbers that do not meet examination niquirements:

3.7 Frequency of Examinations W An evaluation shall be ronductcd Id determine (a) All Bnubbeni within the scope of Subsection 1STD the cause of tht; unacceptabiUty.

shall be examined and evaluated per this Code CaKC at ((i) Unacceptable snubberashallbB adjusted, repaired,

]i*ast once every 1ft yr. modified, or replaced.

ATTACHMENT 4 Snubber Interpretations - Information Only Revision 1

Interpretation: 04-10

Subject:

ASME Code-1998 through 0Mb Code-2000 Date Issued: December 12, 2005 Kle: OMI 05-04 Question (I): Reference ISTD-4240 and 4252(d). If a snnbber requires further evaluation or is classified as unacceptable during inservice examination and subsequently satisfies the operational readiness test criteria of ISTD-5210, is the snubber required to be classified as unacceptable for the purpose of determining the subsequent visual examination interval in accordance with Table ISTD-4252-1?

Reply (1); No. Per ISTD-4240, test results that satisfy the operational readiness criteria of ISTD-5210 shall be used to accept the snubber, provided the test demonsh-ates that the unacceptable condition did not affect operational readiness. In such cases, the visual examination requirements of ISTD-4230 are considered to be satisfied.

Question (2): It appears that ISTD-5200 and 5240 are conflicting as to when operational readiness testing can be performed. May inservice operational readiness tests be performed on snubbers at any time during a fuel cycle, normal system operation, or system or plant outages?

Reply (2): No. JSTD-5240 restricts snubber testing from beginning earlier than 60 days before a scheduled refueling outage.

Question (3); It appears that ISTD is silent in relation to subsequent operational readiness testing requirements for a snubber thathas failed operational readiness testmg and, after corrective action/ is installed at a different location than where the failure occurred. Is it a requirement of JSTD-5500 for a snubber that has failed operational readiness testing, then after corrective action and subsequently being installed in a different location, to be retested during the next operational readiness testing campaign?

Reply (3): No.

1-7 Copyright ASME InlemaUonal P.widod DylHS undflracansexvtUtASME Ucenaea'<Sotnh Texas Pmfacl/99548WDO No fepfoductkw or networkfns pafrmlpd wlhoul <canse from IH3 Nol for Rsaata. 01/16/2007 D7:M;19 MST

Interpretation; 09-01

Subject:

Subsection ISTD (ASME OM Code: 1998 Edition through 2005 Addenda)

Date Issued: June 20, 2007 File: OMI 07-118 Question (I): Does Subsection ISTD allow for the substihition of a snubber being removed for mamtenance activities not affecting the snubber, in place of a snubber randomly selected for testing, if the snubber is within the same DTPG?

Reply (1); No; paras. ISTD-5311 and ISTD-5411 do not allow this type of substitution.

Question (2): If the snubber being substituted is NOT within the same DTPG, but its substitution does not make either DTFG fall below the minunum testing requirements (10% or 37 Plan)?

Reply (2); No; paras. ISTD-5311 and ISTD-5411 have specific sample selection criteria for each DTPG and do not allow substitution of snubbers between different DTFGs.

Question (3); If the snubber bemg substituted is NOT within the same DTPG, and its substitution would result in tfie DTPC falling below minimal testmg requirements (10% or 37 Plan)?

Reply (3); No; paras. ISTD-5311 and ISTD-5411 have specific sample selection criteria for each DTPG and do not allow substitution of snubbers between different DTPGs.

Interpretation; 09-04

Subject:

Paragraph ISTD-3220: Test Correction Factors (ASME OM Code: 1998 Edition Through 2004 Edition up to and Indudmg ASME 0Mb Code-2006)

Date Issued: July 25, 2008 Pile: OMI 08-262 Question: Are the requirements of para. ISTD-3220 applicable to hydraulic snubbers only?

Reply: No, they are applicable to all snubbers.

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