LR-N22-0065, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations

Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations

ML22270A326
Person / Time
Site:	Salem
Issue date:	09/27/2022
From:	Montgomery R Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N22-0065
Download: ML22270A326 (78)

Text

10 CFR 50.55a(g)(5)(iii)

September 27, 2022 LR-N22-0065 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Salem Generating Station Unit 2 Renewed Facility Operating License Nos. DPR-75 NRC Docket No. 50-311

Subject:

Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI)

Interval Limited Examinations In accordance with 10 CFR 50.55a, Codes and standards, paragraph (g)(5)(iii), PSEG Nuclear LLC (PSEG) hereby requests NRC approval of the enclosed request for the fourth 10-year ISI interval for the Salem Generating Station Unit 2 which ended on December 31, 2021. The relief request addresses limitations for examinations performed in accordance with the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components, for Class 1 components.

There are no regulatory commitments contained in this letter. Should you have any questions concerning this matter, please contact Brian Thomas at 856-339-2022.

Sincerely, Richard Montgomery Manager - Licensing PSEG Nuclear LLC

Salem Generating Station Unit 2 American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a(g)(5)(iii) Request for Relief Number S2-I4R-211 Montgomer y, Richard Digitally signed by Montgomery, Richard Date: 2022.09.27 15:07:01 -04'00'

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Page 2 cc:

Mr. D. Lew, Administrator, Region I, NRC Mr. J. Kim, Project Manager, NRC NRC Senior Resident Inspector, Salem Ms. A Pfaff, Manager NJBNE PSEG Corporate Commitment Tracking Coordinator Site Commitment Tracking Coordinator

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Page 1 of 76 Salem Generating Station Unit 2 American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a(g)(5)(iii) Request for Relief Number S2-I4R-211

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Page 2 of 76 Salem Generating Station Unit 2 American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number S2-I4R-211, Revision 0 In Accordance with 10 CFR 50.55a(g)(5)(iii)

--Inservice Inspection Impracticality--

1.

ASME Code Component(s) Affected The Salem Generating Station (SGS) Unit 2 Class 1 welds with limited examinations that are included in this request for relief are for the Fourth Ten-Year Inservice Inspection Interval. The content of this request includes the insights gained from guidance provided in Reference 1 and Reference 2 for the following Code Classes, Examination Categories, and Item Numbers apply.

Code Class:

1 Examination Categories:

B-A, B-B, and R-A Item Numbers:

B1.11, B1.12, B1.21, B1.22, B2.12, R1.11, R1.11S and R1.11/16

2.

Applicable Code Edition and Addenda

The Fourth 10-Year Inservice Inspection (ISI) Interval at SGS was based on the ASME Boiler and Pressure Vessel Code Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 2004 Edition, (Reference 3) as modified by 10 CFR 50.55a. The Appendix VIII requirements and use of the Performance Demonstration Initiative (PDI) requirements at SGS were in accordance with the 2001 Edition of Section XI, (Reference 4) for the limited examinations contained in this request as conditioned by 10 CFR 50.55a(b)(2)(xv) and 10 CFR 50.55a(b)(2)(xxiv).

The SGS Unit 2 Fourth 10-Year ISI Interval ended on December 31, 2021.

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3.

Applicable Code Requirements Exam Cat.

Item No.

Class 1 Weld Examination Coverage Requirements B-A B1.11 To include essentially 100% of the Reactor Vessel Circumferential Shell Welds B-A B1.12 To include essentially 100% of the Reactor Vessel Longitudinal Shell Welds B-A B1.21 To include essentially 100% of the Reactor Vessel Circumferential Head Welds B-A B1.22 To include essentially 100% of the Reactor Vessel Meridional Head Welds B-B B2.12 To include essentially 100% of the Pressurizer Shell-to-Head Longitudinal Welds Exam Cat.

Item No.

Class 1 Piping Welds / Risk-Informed Inservice Inspection Program Coverage Requirements R-A R1.11 To include essentially 100% of the examination location potentially subject to thermal fatigue.

R-A R1.11S To include essentially 100% of the examination location potentially subject to thermal fatigue.

R-A R1.11/16 To include essentially 100% of the examination location potentially subject to thermal fatigue and intergranular stress corrosion cracking.

As previously defined in 10 CFR 50.55a(g)(6)(ii)(A)(2), now removed, and as stated in ASME Code Case N-460 (Reference 5) as approved in Regulatory Guide 1.147, Revision 19 (Reference 6), essentially 100% equates to more than 90% of the examination volume or required surface area of each weld where the reduction in coverage is due to interference by another component or part geometry. Code Case N-460 was invoked for the required coverage associated with the welds in this request.

Limited Class 1 Welds/Risked-Informed Inservice Inspection Programs Class 1 piping welds selected for examination during the fourth interval under the Risk-Informed Inservice Inspection (RI-ISI) Programs used at SGS were examined during the first and second period in accordance with EPRI Topical Report TR-112657, Rev. B-A methodology (Reference

7) which was supplemented by ASME Code Case N-578-1 (Reference 8) and included the piping weld (elements) selected for examination under Category R-A. The use of these documents for SGS was based on a request for alternative S2-I4R-131 (Reference 9). During the fourth interval, third period the implementation of the RI-ISI Program was based on Code Case N-716-1 (Reference 10) as approved in Regulatory Guide 1.147.

RI-ISI Program Limited Examination Evaluations When limited piping weld examination are identified under EPRI TR-112657 Rev. B-A supplemented by Code Case N-578-1 RI-ISI Programs, an evaluation is performed per Note 3 of Table 1 of Code Case N-578-1. Since Salem Unit 2 implemented Code Case N-716-1 in the third period, an evaluation required by Note 3 of Table 1 of Code Case N-716-1 for all limited examinations in the RI-ISI Program for the entire fourth interval is provided below. Table 1 Note

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Page 4 of 76 3 of Code Case N-578-1 and Table 1 Note 3 of Code Case N-716-1 are similar and states in part.When the required examination volume or area cannot be examined due to interference by another component or part geometry, limited examination shall be evaluated for acceptability.

Acceptance of limited examinations or volumes shall not invalidate the results of the change-in-risk evaluation. Salem Unit 2 has evaluated all of the limited examinations for the fourth interval.

Evaluation of RI-ISI Limited Examinations N-716-1, Table 1 Note 3 requires when the required examination volume or area cannot be examined due to interference by another component or part geometry, limited examinations shall be evaluated for acceptability. Acceptance of limited examinations or volumes shall not invalidate the results of the change-in-risk evaluation. Areas with acceptable limited examination and their bases, shall be documented.

PSEG has reviewed each instance of limited coverage and took the appropriate steps (e.g.,

relief requests) consistent with its impact on the basis of the N-716-1 application. This is done using the delta risk values. N-716-1 change in risk acceptance criteria for each system is 1E-7 Core Damage Frequency (CDF) and 1E-8 Large Early Release Frequency (LERF) and the total increase should be less than 1E-6 (CDF) and 1E-7 (LERF). The With POD Credit column is the official result that must meet these criteria (Note: POD - probability of detection).

Below is a summary of the cumulative effect of the limited examinations.

This Request identifies five Unit 2 Class 1 piping welds with limited examination coverage (90% or less). Welds (3-CV-1241-13, 3-CV-1241-14, 3-CV-1231-16, 2-CV-1275-44, 10-SJ-1211-16) are addressed below, by system.

o Chemical and Volume Control (CVC) (Welds 3-CV-1241-13, 3-CV-1241-14, 3-CV-1231-16, and 2-CV-1275-44)

To conservatively quantify the effect on delta risk for the CV welds, the delta risk is adjusted by not crediting the CVC welds with limited examination coverage. The below table provides the delta risk with the four CVC welds credited and with the four CVC welds not credited. The columns under heading Examined are the delta risk with the weld included, the columns under heading Not Examined is the adjusted delta risk after removing the welds. As can be seen, the change is negligible and well below the acceptable limits of 1E-07 for CDF and 1E-08 for LERF. Therefore, a limited examination of the CVC welds is acceptable. Note that welds 3-CV-1241-13 and 3-CV-1231-16 had been previously accepted with limited examination coverage of 50% under the previous RI-ISI Program based on Request for Alternative S2-I3R-132 as approved by the NRC in the third 10-year ISI Interval (Reference 11).

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Page 5 of 76 CVC CDF Impact LERF Impact Source of Delta Risk w/ POD w/ POD Examined

-8.58E-09

-8.58E-10 Latest interval periodic update required by N-716-1, Section 7 Not Examined

-2.82-09

-2.82E-10 Adjusted delta risk using the periodic update delta risk o Safety Injection (SJ) (Welds 10-SJ-1211-16)

To conservatively quantify the effect on delta risk for the one SJ weld, the delta risk is adjusted by not crediting the one SJ weld with limited examination coverage. The below table provides the delta risk with the one SJ weld credited and with the one SJ weld not credited. The columns under heading Examined are the delta risk with the one SJ weld included, the columns under heading Not Examined is the adjusted delta risk after removing the one SJ weld. As can be seen, the change is negligible and well below the acceptable limits of 1E-07 for CDF and 1E-08 for LERF. Therefore, a limited examination of the one SJ weld is acceptable.

SJ CDF Impact LERF Impact Source of Delta Risk w/ POD w/ POD Examined

-3.29E-09

-3.29E-10 Latest interval periodic update required by N-716, Section 7 Not Examined

-3.29E-08

-3.29E-09 Adjusted delta risk using the periodic update delta risk Cumulative Effect to Delta Risk for the Four CV Weld and the one SJ Welds The impact of the limited examination on the delta risk for the individual system is addressed above. The cumulative effect on the total delta risk is provided below. The columns under heading Examined are the delta risk with the five welds included, the columns under heading Not Examined is the adjusted delta risk after removing the five welds. As can be seen, the change is negligible and well below the acceptable limits of 1E-06 for CDF and 1E-07 for LERF. Therefore, a limited examination of the four CVC Welds and one SJ Weld is acceptable.

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Page 6 of 76 CVC SJ CDF Impact LERF Impact Source of Delta Risk w/ POD w/ POD Examined

-5.12E-08

-5.12E-09 Latest interval periodic update required by N-716, Section 7 Not Examined

-4.54E-08

-4.54E-09 Adjusted delta risk using the periodic update delta risk

4.

Impracticality of Compliance The Construction permit for SGS Unit 2 was issued on September 25, 1968 and falls under the provisions of 10 CFR 50.55a(g)(1), which were applied to components (including supports) that must meet the requirements of paragraphs (g)(4) and (g)(5) to the extent practical.

Components that are part of the reactor coolant pressure boundary and their supports must meet the requirements applicable to components that are classified as ASME Code Class 1.

Other safety-related pressure vessels, piping, pumps and valves, and their supports must meet the requirements applicable to components that are classified as ASME Code Class 2 or Class

3. Therefore, although the design of the plants has provided access for examinations to the extent practical, component design configurations resulting in examination limitations such as those from support interference, geometric configurations of welds and materials such as fittings or valve bodies made of cast stainless steel may not allow the full required examination volume or surface area coverage with the latest techniques available. A typical example of such a condition is a valve-to-pipe weld where essentially 100% of the code required volume cannot be examined from the valve side of the weld and where a plant modification would be needed to provide this coverage. Details of examination restrictions and reductions in required examination coverage are provided in Attachment 1.

When examined, the welds listed in Attachment 1 of this request did not receive the required code volume or surface area coverage due to their component design configurations or interference. These conditions resulted in scanning or surface area access limitations that prohibited obtaining essentially 100% examination coverage of the required examination volumes or surface areas, but when this situation occurred 100% coverage of the accessible volumes or surface areas of each weld was obtained.

5.

Burden Caused by Compliance Burden Caused by Compliance To comply with the code required examination volumes or surface areas for obtaining essentially 100% coverage for the welds listed in this request for relief, the welds and their associated components would have to be physically modified and/or disassembled beyond their current design. Overall, components and fittings associated with the welds listed in this request are constructed of standard design items and materials meeting typical national standards that specify required configurations and dimensions. To replace these items with items of alternate configurations or materials to enhance examination coverage would require unique redesign

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Page 7 of 76 and fabrication. Because these items are in the Class 1 boundaries and for the Class 1 items that form a part of the reactor coolant pressure boundary, their redesign and fabrication would be an extensive effort based on the limitations that exist.

For the Class 1, Examination Category B-A, Lower Shell to Lower Head Circumferential Weld, Item B1.11 (2-RPV-10442) limitations were caused by support lug obstruction.

For the Class 1, Examination Category B-A Upper Shell @ 180°, Longitudinal Weld, Item B1.12 (2-RPV-1442B) limitations were caused by the Outlet Nozzle Boss obstruction.

For Class 1, Examination Category B-A, Lower Shell @ 60°, 180°, and 300°, Longitudinal Welds, Item B1.12 (2-RPV-3442A, 2-RPV-3442B, and 2-RPV-3442C) limitations were caused by support lug obstructions.

For Class 1, Examination Category B-A, Lower Head Disc to Peel Segments Circumferential Weld, Item B1.21 (2-RPV-3443) limitations were caused by incore instrumentation nozzle obstruction.

For Class 1 Examination Category B-A, Meridional Weld @ 30°, 90°, 150°, 210°, 270°, and 330° Lower Head Welds Item B1.22 (2-RPV-1443C, 2-RPV-1443D, 2-RPV-1443E, 2-RPV-1443F, 2-RPV-1443A, and 2-RPV-1443B) limitations were caused by incore instrumentation nozzle obstructions.

For the Class 1, Examination Category B-B, Pressurizer Longitudinal Weld Shell D, Item No.:

B2.12 (2-PZR-LONG D) limitations were caused by permanent vessel support ring.

For the Class 1 piping welds examined per the RI-ISI Programs the limitations listed in this request are typically limited by their design configurations. The configurations of these welds only allow UT examination coverage from one side of the weld or limited coverage from a specific area or areas of one side of the weld and thus they would also require a design modification or replacement to obtain the required examination coverage.

Overall, it is not possible to obtain UT interrogation of greater than 90% of the required code examination volume or surface areas for the welds in this request without extensive weld or component design modifications. Examinations have been performed to the maximum extent possible and radiography is impractical due to the amount of work being performed in the areas on a 24-hour basis when the welds are available for examination. Using radiography would result in numerous work-related stoppages and increased exposure due to the shutdown and startup of other work in the areas. Water may need to be drained from systems or components where radiography is performed, which increases the radiation dose rates over a much broader area than the weld being examined. There is significant impracticality associated with the performance of weld or area modifications or the use of radiography in order to increase the examination coverage.

The UT examination techniques used for welds in this request for relief were reviewed to determine if additional coverage could be achieved by improving those techniques. None could be identified and the examinations have been performed to the maximum extent possible.

Therefore, SGS Unit 2 has determined that obtaining essentially 100% coverage is not feasible and is impractical without adding additional burden consisting of significant redesign work, increased radiation exposure, and/or potential damage to the plant or the component itself.

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6.

Proposed Alternative and Basis for Use Proposed Alternative

1) Periodic system pressure tests and VT-2 visual examinations will continue to be performed in accordance with ASME Section Xl, Examination Category B-P, for Class 1 pressure retaining welds and items each refueling outage of Section XI Table IWB-2500-

1.

2) Conduct required UT examinations to the maximum extent possible as required by ASME Section XI or the RI-ISI Programs.

Basis for Use 10 CFR 50.55a(g)(4) recognizes that throughout the service life of a nuclear power facility, components which are classified as ASME Code Class 1, Class 2 and Class 3 must meet the requirements set forth in the ASME Code to the extent practical within the limitations of design, geometry and materials of construction of the welds and items described in Attachment 1.

When a component is found to have conditions, which limit the required examination volume or surface area, PSEG is required to submit this information to the enforcement and regulatory authorities having jurisdiction at the plant site. This request for relief has been written to address areas where these types of conditions exist and where the required amount of coverage was reduced below the minimum acceptable. SGS Unit 2 has performed the weld examinations listed in this request to the maximum extent possible for each of the welds identified with limitations in Attachment 1.

The Class 1 Examination Category B-A, Reactor Vessel Welds, Examination Category B-B, Pressurizer Longitudinal Weld Shell D, and the Class 1 Risk-Informed Piping Welds within the scope of this request are all located inside the containment. Even though their examination did not meet the essentially 100% code required volume coverage requirement, there is instrumentation in place to assure that early detection of any Reactor Coolant System (RCS) pressure boundary leakage is identified. This is accomplished by the leakage detection instrumentation inside the containment where the RCS leakage detection instrumentation is required to be operable. The instrumentation consists of monitoring of containment floor drain sump level to determine flow rate, containment cooler condensate flow rate increases, and airborne gaseous radioactivity increases. These instruments are used to quantify any unidentified leakage from the RCS and to meet the SGS Technical Specifications Surveillance Requirements that have a Limiting Condition for Operation (LCO) in 3.4.7.2 stating that RCS Operational Leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE,

b.

1 GPM UNIDENTIFIED LEAKAGE,

c.

150 gallons per day primary-to-secondary leakage through any one steam generator,

d.

10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System Based upon the extent of the required UT examination volume achieved for each of the welds within this request for relief, and coupled with applicable leakage monitoring, and required system pressure tests with VT-2 visual examinations, no further action can be taken by SGS Unit 2 at this time to improve these examinations without applying impractical options.

Therefore, the proposed alternative in this request for relief will provide assurance of an acceptable level of quality and safety by providing reasonable assurance of structural integrity.

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7.

Duration of Proposed Alternative This request for relief is for Salem Unit 2, Fourth 10-Year ISI Interval, which began on November 27, 2013 and ended on December 31, 2021.

8.

Precedents Note: Industry requests for relief due to impracticality associated with limited weld examinations are common and are filed by all licensees. Some of the more recent NRC approvals of requested relief that are aligned with Reference 1 are:

1) Millstone Power Station, Unit No. 2 - Relief Requests for Limited Coverage Examinations Performed in the Fourth 10-Year Inservice Inspection Interval (EPID L-2020-LLR-0024, EPID L-2020-LLR-0025, and EPID L-2020-LLR-0026) dated December 10, 2020 (Accession No. ML20312A001).

2) Millstone Power Station, Unit No. 3 - Relief Request for Limited Coverage Examinations Performed in the Third 10-Year Inservice Inspection Interval (EPID L-2020-LLR-0027 through EPID L-2020-LLR-0032) dated December 10, 2020 (Accession No. ML20312A002).

3) Perry Nuclear Power Plant, Unit No. 1 - Relief Request IR-062 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval (EPID L-2020-LLR-0067) dated September 18, 2020 (Accession No. ML20252A026).

4) Nine Mile Point Nuclear Station, Unit 2 - Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (EPID-L-2019-LLR-0099) dated June 2, 2020 (Accession No. ML20141L053).

5) Beaver Valley Power Station, Unit 2 - Relief Request 2-TYP-3-B3.110-1, 2-TYP C2.21-1, 2-TYP-3-C1.30-1, and 2-TYP-3-RA-1 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval (EPID L-2019-LLR-0082) dated April 28, 2020 (Accession No. ML20080J789)

6) Peach Bottom Atomic Power Station, Units 2 and 3 - Issuance of Relief Request RE:

Limited Examination Coverage During Fourth 10-Year Inservice Inspection Interval (EPID L-2019-LLR-0103) dated April 14, 2020 (Accession No. ML20097D644).

7) Beaver Valley Power Station, Unit No. 1 - Relief Requests 1-TYP-4-C2.21-1 and 1-TYP-4-RA-1 Regarding Weld Examination Coverage for the Fourth Inservice Inspection Interval (EPID L-2019-LLR-0083) dated March 26, 2020 (Accession No. ML20079F816).

8) Grand Gulf Nuclear Station, Unit 1 - Relief Request GG-ISI-023, Examination Coverage of Class 1 Piping and Vessel Welds (EPID L-2018-LLR-0197) dated October 11, 2019 (Accession No. ML19266A586).

9) Joseph M. Farley Nuclear Plant, Units 1 and 2 - RE: Relief From Impractical American Society of Mechanical Engineers Code Requirements (FNP-ISI-RR-02) (EPID L-2018-LLR-0195) dated August 8, 2019 (Accession No. ML19213A194).

10) Hope Creek Nuclear Generating Station - Issuance of Relief Request No. HC-I3R-08, Revision 0, RE: Relief from the Requirements of the ASME Code (EPID L-2018-LLR-0124) dated July 11, 2019 (Accession No. ML19136A026).

11) James A FitzPatrick Nuclear Power Plant - Issuance of Relief Request I4R-22 RE:

Relief from the Requirements of the ASME Code (EPID L-2018-LLR-0103) dated June 21, 2019 (Accession No. ML19135A444).

12) Monticello Nuclear Generating Plant - Request for Relief for Coverage of Nozzle-to-Vessel Weld Examinations (EPID L-2018-LLR-0072) dated June 12, 2019 (Accession No. ML19148A694).

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13) LaSalle County Station, Units 1 and 2 - Relief Request I3R-15, Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME Code),Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components associated with the Third 10-Year Inservice Inspection Interval (EPID-L-2018-LLR-0123) dated May 20, 2019 (Accession No. ML19121A317).

14) Watts Bar Nuclear Plant, Unit 1 - Relief Request 1-ISI-21 from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (EPID L-2018-LLR-0090) dated April 12, 2019 (Accession No. ML19071A009).

15) Surry Power Station Unit No. 2 - Relief Requests Regarding Examination Coverage for Pressurizer Nozzle Inner Radius Sections and Certain Stainless Steel Piping Welds (S2-I5-LMT-C01 and S2-I5-OLMT-P01) (EPID No. L-2018-LLR-0091) dated March 15, 2019 (Accession No. Ml19043A824).

16) Surry Power Station Unit No. 1 - Relief Requests Regarding Examination Coverage for Pressurizer Nozzle Inner Radius Section and Certain Stainless Steel Piping Welds (S1-I5-LMT-C01 and S1-I5-LMT-P01) (EPID L-2018-LLR-0041) dated February 28, 2019 (Accession No. ML18331A060).

17) Salem Nuclear Generating Station, Unit No. 1 - Issuance of Relief Request No. S1-I4R-210 Re: Fourth Inservice Inspection Interval Limited Examinations (EPID L-2021-LLR-0085), dated May 24, 2022 (ADAMS Accession No. ML22130A791).

9. References

1.

NRC presentation Coverage Relief Requests, Industry/NRC NDE Technical Information Exchange Public Meeting January 13-15, 2015, (ADAMS Accession No.:

ML15013A266).

2.

NRC presentation Coverage Relief Request Update, 2020 Industry/NRC NDE Technical Information Exchange Public Meeting. (ADAMS Accession No.:

ML20009E155)

3.

ASME Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 2004 Edition.

4.

ASME Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, Appendix VIII, Performance Demonstration for Ultrasonic Examination Systems, 2001 Edition.

5.

ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 WeldsSection XI, Division 1.

6.

NRC Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 19, Dated October 2019. (ADAMS Accession No.:

ML19128A244)

7.

EPRI Topical Report TR-112657 Rev. B-A, Revised Risk-Informed Inservice Inspection Evaluation Procedure, Dated: December 1999, (ADAMS Accession No.:

ML013470102)

8.

ASME Code Case N-578-1, Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B Section XI, Division 1.

9.

NRC SER, Salem Generating Station, Unit No. 2 - Safety Evaluation of Relief Request No. S2-I4R-131 Regarding the Fourth 10-Year Inservice Inspection Interval (TAC NO. ME2442), dated June 23, 2014 (ADAMS Accession No. ML14153A146)

10.

ASME Code Case N-716-1, Alternative Classification and Examination Requirements,Section XI, Division 1.

11.

NRC SER, Salem Nuclear Generating Station, Unit No. 2 - Relief from the Requirements of the ASME Code (TAC NO. MF4591), dated July 28, 2015 (ADAMS Accession No. ML15195A495).

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12.

PSEG Letter to NRC, Inservice Inspection (ISI) Program Plan, Fourth Ten-Year Interval, dated November 11, 2013 (ADAMS Accession No.ML13316B177)

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Page 12 of 76 Salem Generating Station Unit 2 American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number S2-I4R-211, Revision 0 In Accordance with 10 CFR 50.55a(g)(5)(iii)

--Inservice Inspection Impracticality--

Introduction This attachment contains figures and tables as applicable that are used to depict the limitations and calculations used for obtained coverage, materials and product forms, with ultrasonic examination angles and wave modes used, any limited surface examinations and the examination results for the welds associated with this request for relief, including any applicable previous examination history used. The following Table 1 for SGS Unit 2 identifies the welds within the scope of this request and summarizes the extent of examination coverage achieved for each weld.

Many of the welds listed were examined with different approved procedures and techniques during the span of the Third 10-Year ISI Interval and therefore not all the coverage calculations used are identical, but they are based on the actual NDE data reports that were provided for the examinations completed.

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Page 13 of 76 TABLE 1 - Unit 2 SGS WELDS WITH LIMITED EXAMINATIONS Seq. Number

/ Weld Identification Number

Class, Category and Item No.

Weld Description Material 1 and Product Form Material 2 and Product Form Pipe Size and/or Thickness Examination Code Coverage Obtained2 Examination Limitations and Results Normal Operating Conditions (Pressure/Temperature)

Applicable Tables and Figures 1.01 2-RPV-10442 (W13) 1 B-A B1.11 Lower Shell to Lower Head Circ.

Weld SA-533 Gr. B SA-533 Gr. B 8.63 -

5.31 75.8%

Exam was limited due to the close proximity of the Support Lugs 2235 psig 575°F Tables 1.01-1, 1.01-2 and 1.01-3 Figures 1.01-1, 1.01-2 and 1.01-3 1.02 2-RPV-1442B (W02) 1 B-A B1.12 Upper Shell

@ 180°,

Long. Weld SA-533 Gr. B SA-533 Gr. B 10.75 72.2%

Exam was limited due to Outlet Nozzle Boss Obstruction 2235 psig 575°F Tables 1.02-1, 1.02-2 and 1.02-3 Figures 1.02-1, and 1.02-2 1.03 2-RPV-3442A (W11) 1 B-A B1.12 Lower Shell

@ 60° Long.

Weld SA-533 Gr. B SA-533 Gr. B 8.63 83.6%

Exam was limited due to Support Lug Obstruction 2235 psig 575°F Tables 1.03-1 and 1.03-2 Figures 1.03-1, and 1.03-2 1.04 2-RPV-3442B (W09) 1 B-A B1.12 Lower Shell

@ 180° Long.

Weld SA-533 Gr. B SA-533 Gr. B 8.63 83.6%

Exam was limited due to Support Lug Obstruction 2235 psig 575°F Tables 1.04-1, 1.04-2 and 1.04-3 Figures 1.04-1 and 1.04-2 1.05 2-RPV-3442C (W10) 1 B-A B1.12 Lower Shell

@ 300° Long.

weld SA-533 Gr. B SA-533 Gr. B 8.63 83.6%

Exam was limited due to Support Lug Obstruction 2235 psig 575°F Tables 1.05-1, 1.05-2 and 1.05-3 Figures 1.05-1 and 1.05-2 1.06 2-RPV-3443 (W14) 1 B-A B1.21 Lower Head Disc to Peel Segments Circ. Weld SA-533 Gr. B SA-533 Gr. B 5.31 27.9%

Exam was limited due to incore instrumentation nozzle obstruction 2235 psig 575°F Tables 1.06-1 and 1.06-2 Figures 1.06-1 and 1.06-2 1.07 2-RPV-1443C (W31) 1 B-A B1.22 Meridional Weld @ 30° Lower Head Weld SA-533 Gr. B SA-533 Gr. B 5.31 80.7%

Exam was limited due to incore instrumentation nozzle obstruction 2235 psig 575°F Tables 1.07-1 and 1.07-2 Figures 1.07-1 and 1.07-2 1.08 2-RPV-1443D (W32) 1 B-A B1.22 Meridional Weld @ 90° Lower Head Weld SA-533 Gr. B SA-533 Gr. B 5.31 87.9%

Exam was limited due to incore instrumentation nozzle obstruction 2235 psig 575°F Tables 1.08-1 and 1.08-2 Figures 1.08-1 and 1.08-2 1.09 2-RPV-1443E (W33) 1 B-A B1.22 Meridional Weld @ 150° Lower Head Weld SA-533 Gr. B SA-533 Gr. B 5.31 77.2%

Exam was limited due to incore instrumentation nozzle obstruction 2235 psig 575°F Tables 1.09-1 and 1.09-2 Figures 1.09-1 and 1.09-2

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Page 14 of 76 TABLE 1 - Unit 2 SGS WELDS WITH LIMITED EXAMINATIONS Seq. Number

/ Weld Identification Number

Class, Category and Item No.

Weld Description Material 1 and Product Form Material 2 and Product Form Pipe Size and/or Thickness Examination Code Coverage Obtained2 Examination Limitations and Results Normal Operating Conditions (Pressure/Temperature)

Applicable Tables and Figures 1.10 2-RPV-1443F (W34) 1 B-A B1.22 Meridional Weld @ 210° Lower Head Weld SA-533 Gr. B SA-533 Gr. B 5.31 87.9%

Exam was limited due to incore instrumentation nozzle obstruction 2235 psig 575°F Tables 1.10-1 and 1.10-2 Figures 1.10-1 and 1.10-2 1.11 2-RPV-1443A (W35) 1 B-A B1.22 Meridional Weld @ 270° Lower Head Weld SA-533 Gr. B SA-533 Gr. B 5.31 85.2%

Exam was limited due to incore instrumentation nozzle obstruction 2235 psig 575°F Tables 1.11-1 and 1.11-2 Figures 1.11-1 and 1.11-2 1.12 2-RPV-1443B (W36) 1 B-A B1.22 Meridional Weld @ 330° Lower Head Weld SA-533 Gr. B SA-533 Gr. B 5.31 80.8%

Exam was limited due to incore instrumentation nozzle obstruction 2235 psig 575°F Tables 1.12-1 and 1.12-2 Figures 1.12-1, 1.12-2, 1.12-3, and 1.12-4 1.13 2-PZR-LONG D 1

B-B B2.12 Pressurizer Longitudinal Weld Shell D SA-533 Gr. A SA-533 Gr. A 4.19 75%

Exam was limited due to the permanent support ring (limited to 9.0/12.0) 2235 psig 655°F Figures 1.13-1, 1.13-2, 1.13-3, and 1.13-4 1.14 10-SJ-1211-16 1

R-A R1.11/16 Safety Injection System -

Pipe to Valve (21SJ56)1 A-376 TP-316 A-351 CF8 10 Schedule 160 50%

Exam was limited to a single sided exam due to the configuration of the valve 650 psig 120°F Figures 1.14-1, 1.14-2, 1.14-3, 1.14-4, and 1.14-5 1.15 3-CV-1241-13 1

R-A R1.11 Chemical Volume and Control -

Valve (2CV80) to Elbow1 A-403 WP-316 A-182 F-316 3

Schedule 160 45.5%

Exam was limited to a single side exam due to the configuration of the valve and the elbow intrados.

2520 psig 494°F Figures 1.15-1, 1.15-2, 1.15-3, 1.15-4, and 1.15-5 1.16 3-CV-1241-14 1

R-A R1.11 Chemical Volume and Control -

Elbow to Branch Connection1 A-403 WP-316 A-182 F-316 3

Schedule 160 45.5%

Exam was limited due to the configuration of the branch connection/ID Band and the elbow intrados.

2520 psig 494°F Table 1.16-1, Figures 1.16-1, 1.16-2, 1.16-3, 1.16-4, 1.16-5, 1.16-6, and 1.16-7 1.17 3-CV-1231-16 1

R-A R1.11 Chemical Volume and Control -

Valve (2CV78) to pipe1 A-376 TP-316 A-182 F-316 3

Schedule 160 48.8%

Exam was limited to a single side exam due to the configuration of the valve and proximity of branch connection.

2520 psig 494°F Figures 1.17-1, 1.17-2, 1.17-3, 1.17-4, 1.17-5, and 1.17-6

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Page 15 of 76 TABLE 1 - Unit 2 SGS WELDS WITH LIMITED EXAMINATIONS Seq. Number

/ Weld Identification Number

Class, Category and Item No.

Weld Description Material 1 and Product Form Material 2 and Product Form Pipe Size and/or Thickness Examination Code Coverage Obtained2 Examination Limitations and Results Normal Operating Conditions (Pressure/Temperature)

Applicable Tables and Figures 1.18 2-CV-1275-44 1

R-A R1.11S Chemical Volume and Control - Pipe to Branch Connection (Socket Weld)1 A-376 TP-316 A-182 F-316 2

Schedule 160 35%

Exam was limited due to the upstream valve (2CV76) that limiting the scanning of the 1 of base metal.

2520 psig 494°F Figures 1.18-1, 1.18-2, and 1.18-3 NOTES: 1. Containment RCS Leakage Detection Applies

2. Ultrasonic (UT) Examination, Phased Array UT Examination (PAUT) and Surface Examination by Liquid Penetrant (PT) or Magnetic Particle (MT).

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Page 16 of 76 1.01 Weld 2-RPV-10442, Lower Shell to Lower Head Circumferential Weld Figure 1.01-1 Weld 2-RPV-10442 (Extracted from Reference 12 Dwg. S2-A-01)

This weld was UT examined in Inspection Period 3, during the S2R25 refueling outage in 2021.

The NDE data came from UT Report No.: S2-VE-21-050. The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-1. The corresponding CRV as shown on that Figure is E-F-G-H. This volume was examined with 45°S and 45°L wave transducers. The UT examination was limited by the proximity of the support lug resulting in total UT coverage of 75.8% as described in Tables 1.01-1 and 1.01-2 combined with Figures 1.01-2 and 1.01-3. Weld 2-RPV-10442 (W13) has one recordable indication as described in Table 1.01-3, this indication is classified as a subsurface indication originated during the manufacturing process and was not recorded during previous examinations.

Section XI Appendices and Supplements used for this UT examination were Appendix VIII, Supplements 4 and 6.

Note: No laminations exist on the RPV shell that could interfere with the angle beam examinations performed on this weld.

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Page 17 of 76 Table 1.01-1 Weld 2-RPV-10442 Scan Coverage and Scan Summary Table 1.01-2 Weld 2-RPV-10442 Scan Coverage and Scan Summary

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Page 18 of 76 Figure 1.01-2 Weld 2-RPV-10442 (Examination Location and Coverage Map)

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Page 19 of 76 Figure 1.01-3 Weld 2-RPV-10442 (Examination Location and Coverage Map)

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Page 20 of 76 Table 1.01-3 Weld 2-RPV-10442 Flaw Evaluation Summary Sheet

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Page 21 of 76 1.02 Weld 2-RPV-1442B, Upper Shell @ 180° Longitudinal Weld Figure 1.02-1 Weld 2-RPV-1442B (Extracted from Reference 12 Dwg. S2-A-01)

This weld was UT examined in Inspection Period 3, during the S2R25 refueling outage in 2021.

The NDE data came from UT Report No.: S2-VE-21-058. The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-2. The corresponding CRV as shown on that Figure is A-B-C-D. This volume was examined with 45°S and 45°L wave transducers. The UT examination was limited by the proximity of Outlet Nozzle Boss resulting in total UT coverage of 72.2% as described in Tables 1.02-1 and 1.02-2 combined with Figure 1.02-2. Weld 2-RPV-1442B (W02) has one recordable indication as described in Table 1.02-3, this indication is classified as a slag inclusion from the welding process during fabrication and was not recorded during previous examinations.

Section XI Appendices and Supplements used for this UT examination were Appendix VIII, Supplements 4 and 6.

Note: No laminations exist on the RPV shell that could interfere with the angle beam examinations performed on this weld.

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Page 22 of 76 Table 1.02-1 Weld 2-RPV-1442B Scan Coverage and Scan Summary Table 1.02-2 Weld 2-RPV-1442B Scan Coverage and Scan Summary

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Page 23 of 76 Figure 1.02-2 Weld 2-RPV-1442B (Examination Location and Coverage Map)

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Page 24 of 76 Table 1.02-3 Weld 2-RPV-1442B Flaw Evaluation Summary Sheet

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Page 25 of 76 1.03 Weld 2-RPV-3442A, Lower Shell @ 60° Longitudinal Weld Figure 1.03-1 Weld 2-RPV-3442A (Extracted from Reference 12 Dwg. S2-A-01)

This weld was UT examined in Inspection Period 3, during the S2R25 refueling outage in 2021.

The NDE data came from UT Report No.: S2-VE-21-055. The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-2. The corresponding CRV as shown on that Figure is A-B-C-D. This volume was examined with 45°S and 45°L wave transducers. The UT examination was limited by the proximity of support lug resulting in total UT coverage of 83.6% as described in Tables 1.03-1 and 1.03-2 combined with Figure 1.03-2.

No recordable indications were detected during Weld 2-RPV-3442A (W11) scan.

Section XI Appendices and Supplements used for this UT examination were Appendix VIII, Supplements 4 and 6.

Note: No laminations exist on the RPV shell that could interfere with the angle beam examinations performed on this weld.

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Page 26 of 76 Table 1.03-1 Weld 2-RPV-3442A Scan Coverage and Scan Summary Table 1.03-2 Weld 2-RPV-3442A Scan Coverage and Scan Summary

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Page 27 of 76 Figure 1.03-2 Weld 2-RPV-3442A (Examination Location and Coverage Map)

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Page 28 of 76 1.04 Weld 2-RPV-3442B, Lower Shell @ 180° Longitudinal Weld Figure 1.04-1 Weld 2-RPV-3442B (Extracted from Reference 12 Dwg. S2-A-01)

This weld was UT examined in Inspection Period 3, during the S2R25 refueling outage in 2021.

The NDE data came from UT Report No.: S2-VE-21-056. The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-2. The corresponding CRV as shown on that Figure is A-B-C-D. This volume was examined with 45°S and 45°L wave transducers. The UT examination was limited by the proximity of support lug resulting in total UT coverage of 83.6% as described in Tables 1.04-1 and 1.04-2 combined with Figure 1.04-2.

Weld 2-RPV-3442B (W09) has one recordable indication as described in Table 1.04-3, this indication is classified as a subsurface indication originated during the manufacturing process and was not recorded during previous examinations.

Section XI Appendices and Supplements used for this UT examination were Appendix VIII, Supplements 4 and 6.

Note: No laminations exist on the RPV shell that could interfere with the angle beam examinations performed on this weld.

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Page 29 of 76 Table 1.04-1 Weld 2-RPV-3442B Scan Coverage and Scan Summary Table 1.04-2 Weld 2-RPV-3442B Scan Coverage and Scan Summary

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Page 30 of 76 Figure 1.04-2 Weld 2-RPV-3442B (Examination Location and Coverage Map)

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Page 31 of 76 Table 1.04-3 Weld 2-RPV-3442B Flaw Evaluation Summary Sheet

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Page 32 of 76 1.05 Weld 2-RPV-3442C, Lower Shell @ 300° Longitudinal Weld Figure 1.05-1 Weld 2-RPV-3442C (Extracted from Reference 12 Dwg. S2-A-01)

This weld was UT examined in Inspection Period 3, during the S2R25 refueling outage in 2021.

The NDE data came from UT Report No.: S2-VE-21-057. The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-2. The corresponding CRV as shown on that Figure is A-B-C-D. This volume was examined with 45°S and 45°L wave transducers. The UT examination was limited by the proximity of support lug resulting in total UT coverage of 83.6% as described in Tables 1.05-1 and 1.05-2 combined with Figure 1.05-2.

Weld 2-RPV-3442C (W10) has one recordable indication as described in Table 1.05-3, this indication is classified as a subsurface indication originated during the manufacturing process and was not recorded during previous examinations.

Section XI Appendices and Supplements used for this UT examination were Appendix VIII, Supplements 4 and 6.

Note: No laminations exist on the RPV shell that could interfere with the angle beam examinations performed on this weld.

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Page 33 of 76 Table 1.05-1 Weld 2-RPV-3442C Scan Coverage and Scan Summary Table 1.05-2 Weld 2-RPV-3442C Scan Coverage and Scan Summary

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Page 34 of 76 Figure 1.05-2 Weld 2-RPV-3442C (Examination Location and Coverage Map)

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Page 35 of 76 Table 1.05-3 Weld 2-RPV-3442C Flaw Evaluation Summary Sheet

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Page 36 of 76 1.06 Weld 2-RPV-3443, Lower Head Disc. To Peel Segments Circumferential Weld Figure 1.06-1 Weld 2-RPV-3443 (Extracted from Reference 12 Dwg. S2-A-01)

This weld was UT examined in Inspection Period 3, during the S2R25 refueling outage in 2021.

The NDE data came from UT Report No.: S2-VE-21-057. The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-3. The corresponding CRV as shown on that Figure is A-B-C-D. This volume was examined with 45°S and 45°L wave transducers. The UT examination was limited by the proximity of incore instrumentation nozzle obstruction resulting in total UT coverage of 27.9% as described in Tables 1.06-1 and 1.06-2 combined with Figure 1.06-2. No recordable indications were detected during Weld 2-RPV-3443 (W14) scan.

Section XI Appendices and Supplements used for this UT examination were Appendix VIII, Supplements 4 and 6.

Note: No laminations exist on the RPV shell that could interfere with the angle beam examinations performed on this weld.

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Page 37 of 76 Table 1.06-1 Weld 2-RPV-3443 Scan Coverage and Scan Summary Table 1.06-2 Weld 2-RPV-3443 Scan Coverage and Scan Summary

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Page 38 of 76 Figure 1.06-2 Weld 2-RPV-3443 (Examination Location and Coverage Map)

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Page 39 of 76 1.07 Weld 2-RPV-1443C, Meridional Weld @ 30° Lower Head Weld Figure 1.07-1 Weld 2-RPV-1443C (Extracted from Reference 12 Dwg. S2-A-01)

This weld was UT examined in Inspection Period 3, during the S2R25 refueling outage in 2021.

The NDE data came from UT Report No.: S2-VE-21-063. The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-3. The corresponding CRV as shown on that Figure is E-F-G-H. This volume was examined with 45°S and 45°L wave transducers. The UT examination was limited by the proximity of incore instrumentation nozzle obstruction resulting in total UT coverage of 80.7% as described in Tables 1.07-1 and 1.07-2 combined with Figure 1.07-2. No recordable indications were detected during Weld 2-RPV-1443C (W31) scan.

Section XI Appendices and Supplements used for this UT examination were Appendix VIII, Supplements 4 and 6.

Note: No laminations exist on the RPV shell that could interfere with the angle beam examinations performed on this weld.

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Page 40 of 76 Table 1.07-1 Weld 2-RPV-1443C Scan Coverage and Scan Summary Table 1.07-2 Weld 2-RPV-1443C Scan Coverage and Scan Summary

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Page 41 of 76 Figure 1.07-2 Weld 2-RPV-1443C (Examination Location and Coverage Map)

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Page 42 of 76 1.08 Weld 2-RPV-1443D, Meridional Weld @ 90° Lower Head Weld Figure 1.08-1 Weld 2-RPV-1443D (Extracted from Reference 12 Dwg. S2-A-01)

This weld was UT examined in Inspection Period 3, during the S2R25 refueling outage in 2021.

The NDE data came from UT Report No.: S2-VE-21-064. The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-3. The corresponding CRV as shown on that Figure is E-F-G-H. This volume was examined with 45°S and 45°L wave transducers. The UT examination was limited by the proximity of incore instrumentation nozzle obstruction resulting in total UT coverage of 87.9% as described in Tables 1.08-1 and 1.08-2 combined with Figure 1.08-2. No recordable indications were detected during Weld 2-RPV-1443D (W32) scan.

Section XI Appendices and Supplements used for this UT examination were Appendix VIII, Supplements 4 and 6.

Note: No laminations exist on the RPV shell that could interfere with the angle beam examinations performed on this weld.

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Page 43 of 76 Table 1.08-1 Weld 2-RPV-1443D Scan Coverage and Scan Summary Table 1.08-2 Weld 2-RPV-1443D Scan Coverage and Scan Summary

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Page 44 of 76 Figure 1.08-2 Weld 2-RPV-1443D (Examination Location and Coverage Map)

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Page 45 of 76 1.09 Weld 2-RPV-1443E, Meridional Weld @ 150° Lower Head Weld Figure 1.09-1 Weld 2-RPV-1443E (Extracted from Reference 12 Dwg. S2-A-01)

This weld was UT examined in Inspection Period 3, during the S2R25 refueling outage in 2021.

The NDE data came from UT Report No.: S2-VE-21-065. The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-3. The corresponding CRV as shown on that Figure is E-F-G-H. This volume was examined with 45°S and 45°L wave transducers. The UT examination was limited by the proximity incore instrumentation nozzle obstruction resulting in total UT coverage of 77.2% as described in Tables 1.09-1 and 1.09-2 combined with Figure 1.09-2. No recordable indications were detected during Weld 2-RPV-1443E (W33) scan.

Section XI Appendices and Supplements used for this UT examination were Appendix VIII, Supplements 4 and 6.

Note: No laminations exist on the RPV shell that could interfere with the angle beam examinations performed on this weld.

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Page 46 of 76 Table 1.09-1 Weld 2-RPV-1443E Scan Coverage and Scan Summary Table 1.09-2 Weld 2-RPV-1443E Scan Coverage and Scan Summary

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Page 47 of 76 Figure 1.09-2 Weld 2-RPV-1443E (Examination Location and Coverage Map)

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Page 48 of 76 1.10 Weld 2-RPV-1443F, Meridional Weld @ 210° Lower Head Weld Figure 1.10-1 Weld 2-RPV-1443F (Extracted from Reference 12 Dwg. S2-A-01)

This weld was UT examined in Inspection Period 3, during the S2R25 refueling outage in 2021.

The NDE data came from UT Report No.: S2-VE-21-066. The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-3. The corresponding CRV as shown on that Figure is E-F-G-H. This volume was examined with 45°S and 45°L wave transducers. The UT examination was limited by the proximity incore instrumentation nozzle obstruction resulting in total UT coverage of 87.9% as described in Tables 1.10-1 and 1.10-2 combined with Figure 1.10-2. No recordable indications were detected during Weld 2-RPV-1443F (W34) scan.

Section XI Appendices and Supplements used for this UT examination were Appendix VIII, Supplements 4 and 6.

Note: No laminations exist on the RPV shell that could interfere with the angle beam examinations performed on this weld.

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Page 49 of 76 Table 1.10-1 Weld 2-RPV-1443F Scan Coverage and Scan Summary Table 1.10-2 Weld 2-RPV-1443F Scan Coverage and Scan Summary

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Page 50 of 76 Figure 1.10-2 Weld 2-RPV-1443F (Examination Location and Coverage Map)

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Page 51 of 76 1.11 Weld 2-RPV-1443A, Meridional Weld @ 270° Lower Head Weld Figure 1.11-1 Weld 2-RPV-1443A (Extracted from Reference 12 Dwg. S2-A-01)

This weld was UT examined in Inspection Period 3, during the S2R25 refueling outage in 2021.

The NDE data came from UT Report No.: S2-VE-21-061. The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-3. The corresponding CRV as shown on that Figure is E-F-G-H. This volume was examined with 45°S and 45°L wave transducers. The UT examination was limited by the proximity of incore instrumentation nozzle obstruction resulting in total UT coverage of 85.2% as described in Tables 1.11-1 and 1.11-2 combined with Figure 1.11-2. No recordable indications were detected during Weld 2-RPV-1443A (W35) scan.

Section XI Appendices and Supplements used for this UT examination were Appendix VIII, Supplements 4 and 6.

Note: No laminations exist on the RPV shell that could interfere with the angle beam examinations performed on this weld.

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Page 52 of 76 Table 1.11-1 Weld 2-RPV-1443A Scan Coverage and Scan Summary Table 1.11-2 Weld 2-RPV-1443A Scan Coverage and Scan Summary

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Page 53 of 76 Figure 1.11-2 Weld 2-RPV-1443A (Examination Location and Coverage Map)

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Page 54 of 76 1.12 Weld 2-RPV-1443B, Meridional Weld @ 330° Lower Head Weld Figure 1.12-1 Weld 2-RPV-1443B (Extracted from Reference 12 Dwg. S2-A-01)

This weld was UT examined in Inspection Period 3, during the S2R25 refueling outage in 2021.

The NDE data came from UT Report No.: S2-VE-21-062. The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-3. The corresponding CRV as shown on that Figure is E-F-G-H. This volume was examined with 45°S and 45°L wave transducers. The UT examination was limited by the proximity of incore instrumentation nozzle obstruction resulting in total UT coverage of 80.8% as described in Tables 1.12-1 and 1.12-2 combined with Figure 1.12-2. No recordable indications were detected during Weld 2-RPV-1443B (W36) scan.

Section XI Appendices and Supplements used for this UT examination were Appendix VIII, Supplements 4 and 6.

Note: No laminations exist on the RPV shell that could interfere with the angle beam examinations performed on this weld.

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Page 55 of 76 Table 1.12-1 Weld 2-RPV-1443B Scan Coverage and Scan Summary Table 1.12-2 Weld 2-RPV-1443B Scan Coverage and Scan Summary

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Page 56 of 76 Figure 1.12-2 Weld 2-RPV-1443B (Examination Location and Coverage Map)

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Page 57 of 76 1.13 Weld 2-PZR-LONG D - Longitudinal Weld Shell D Figure 1.13-1 Weld 2-PZR-LONG D (Extracted from Reference 12 DWG S2-A-05)

This weld was UT examined in Inspection Period 1, during the S2R21 refueling outage in 2015.

The NDE data came from UT Report No.: UT-15-028. The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-2. This volume was examined using 0°L, 45°S and 60°S wave transducers. The corresponding CRV as shown on that Figure is A-

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Page 58 of 76 B-C-D. The UT examination was limited to 9.0 / 12.0 due to the permanent support ring resulting in total UT coverage of 75% as described in Figures 1.13-2 through 1.13-4. No recordable indication was detected during this examination.

This examination was performed in accordance with Section XI Appendix I, I-2120 which required Article 4 of Section V, as supplemented by Table I-2000-1.

Note: No laminations exist on the Pressurizer that could interfere with the angle beam examinations performed on this weld.

Figure 1.13-2 Weld 2-PZR-LONG D Scan Coverage and Scan Summary

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Page 59 of 76 Figure 1.13-3 Weld 2-PZR-LONG D (Photo)

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Page 60 of 76 Figure 1.13-4 Weld 2-PZR-LONG D (Photo)

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Page 61 of 76 1.14 Weld 10-SJ-1211 Pipe to Valve (21SJ56)

Figure 1.14-1 Weld 10-SJ-1211-16 (Extracted from Reference 12 DWG S2-A-66)

This weld was UT examined in Inspection Period 3, during the S2R25 refueling outage in 2021.

The NDE data came from UT Report No.: S2-UT-21-030. The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-8(c). The corresponding CRV as shown on that Figure is C-D-E-F. This volume was examined using 45°S, 60°S and 60°L wave transducers. No credit was taken for the 60°L examination. The UT examination was limited to a one-sided examination due to the configuration of the valve resulting in total UT coverage of 50% as described in Figures 1.14-2, through 1.14-4. One recordable indication was detected during this examination using the 60°S wave transducer. The indication was evaluated as root geometry as shown in Figure 1.14-5.

This examination was performed in accordance with Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) in Regulatory Guide 1.147 Rev. 19. The examination satisfied the requirements of Appendix VIII with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

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Page 62 of 76 Figure 1.14-2 Weld 10-SJ-1211-16 (Photo)

Figure 1.14-3 Weld 10-SJ-1211-16 (Contour)

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Page 63 of 76 Figure 1.14-4 Weld 10-SJ-1211-16 (Dimensions)

Figure 1.14-5 Weld 10-SJ-1211-16 (Indication Plot)

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Page 64 of 76 1.15 Weld 3-CV-1241 Valve (2CV80) to Elbow Figure 1.15-1 Weld 3-CV-1241-13 (Extracted from Reference 12 DWG S2-A-12)

This weld was UT examined in Inspection Period 2, during the S2R22 refueling outage in 2017.

The NDE data came from UT Report No.: UT-17-033. The UT Code Required Volume (CRV) was determined based on EPRI TR-112657 Rev. B-A, Figure 4-1. The corresponding CRV as shown on that Figure is A-B-C-D. This volume was examined using 45°S, 60°S and 70°S wave transducers. The UT examination was limited due to the configuration of the valve and the elbow intrados resulting in total UT coverage of 45.5% as described in Figures 1.18-2, through 1.18-5. No recordable indication was detected during this examination. This weld was previously approved for limited examination for the third Interval with a UT coverage of approximately 50% (ML15195A495).

This examination was performed in accordance with Request for Alternative S2-I4R-131 as approved by the Nuclear Regulatory Commission (NRC) on June 23, 2014 (ML14153A146).

The examination satisfied the requirements of Appendix VIII with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

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Page 65 of 76 Figure 1.15-2 Weld 3-CV-1241-13 (Photo)

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Page 66 of 76 Figure 1.15-3 Weld 3-CV-1241-13 (Contour)

Figure 1.15-4 Weld 3-CV-1241-13 (Dimensions)

Figure 1.15-5 Weld 3-CV-1241-13 (Scan Coverage and Scan Summary)

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Page 67 of 76 1.16 Weld 3-CV-1241 Elbow to Branch Connection Figure 1.16-1 Weld 3-CV-1241-14 (Extracted from Reference 12 DWG S2-A-12)

This weld was UT examined in Inspection Period 2, during the S2R22 refueling outage in 2017.

The NDE data came from UT Report No.: UT-17-033. The UT Code Required Volume (CRV) was determined based on EPRI TR-112657 Rev. B-A, Figure 4-1. The corresponding CRV as shown on that Figure is A-B-C-D. This volume was examined using 45°S, 60°S and 70°S wave transducers. The UT examination was limited due to the configuration of the branch connection/

ID Band and the elbow intrados resulting in total UT coverage of 45.5% as described in Figures 1.16-2, through 1.16-7. The thermal fatigue examination obtained 80.25% of the required area of interest.

ISI and Thermal Fatigue examination performed using Procedure 54-ISI-836 with axial scans of 45°, 60°, and 70° and circ. Scans of 46° (3.5 in. dia. contoured wedges) Thermal Fatigue examination also using Procedure 54-UT-613-02 using axial and circ. Scans of 45° (6.625 in.

dia. contoured wedges). Larger contoured wedges used with 54-UT-613-02 allowed better skewing capabilities in order to meet recommended scanning patterns provided by MRP-23 for

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Page 68 of 76 interrogation of thermal fatigue. And as shown in Table 1.16-1, use of these contoured wedges provide better sensitivity when compared to the contoured wedges used for 54-ISI-836. Actual calibration sensitivity was set using the 30-SAM block in order to provide the higher sensitivity.

Table 1.16-1 Weld 3-CV-1241-14 No recordable indication was detected during this examination.

This examination was performed in accordance with Request for Alternative S2-I4R-131 as approved by the Nuclear Regulatory Commission (NRC) on June 23, 2014 (ML14153A146).

The examination satisfied the requirements of Appendix VIII with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

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Page 69 of 76 Figure 1.16-2 Weld 3-CV-1241-14 (Photo)

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Page 70 of 76 Figure 1.16-3 Weld 3-CV-1241-14 (Contour)

Figure 1.16-4 Weld 3-CV-1241-14 (Dimensions)

Figure 1.16-5 Weld 3-CV-1241-14 (Scan Coverage and Scan Summary)

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Page 71 of 76 Figure 1.16-6 Weld 3-CV-1241-14 (Scan Coverage and Scan Summary)

Figure 1.16-7 Weld 3-CV-1241-14 (Scan Coverage and Scan Summary)

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Page 72 of 76 1.17 Weld 3-CV-1231 Valve (2CV78) to Pipe Figure 1.17-1 Weld 3-CV-1231-16 (Extracted from Reference 12 DWG S2-A-13)

This weld was UT examined in Inspection Period 2, during the S2R22 refueling outage in 2017.

The NDE data came from UT Report No.: UT-17-032. The UT Code Required Volume (CRV) was determined based on EPRI TR-112657 Rev. B-A, Figure 4-2. The corresponding CRV as shown on that Figure is A-B-C-D. This volume was examined using 45°S, 60°S and 70°S wave transducers. The UT examination was limited due to the configuration of the valve resulting in total UT coverage of 48.8% as described in Figures 1.17-2, through 1.17-6. No recordable indication was detected during this examination. This weld was previously approved for limited examination for the third Interval with a UT coverage of approximately 50% (ML15195A495).

This examination was performed in accordance with Request for Alternative S2-I4R-131 as approved by the Nuclear Regulatory Commission (NRC) on June 23, 2014 (ML14153A146).

The examination satisfied the requirements of Appendix VIII with qualified personnel,

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Page 73 of 76 procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

Figure 1.17-2 Weld 3-CV-1231-16 (Photo)

Figure 1.17-3 Weld 3-CV-1231-16 (Contour)

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Page 74 of 76 Figure 1.17-4 Weld 3-CV-1231-16 (Dimensions)

Figure 1.17-5 Weld 3-CV-1231-16 (Scan Coverage and Scan Summary)

Figure 1.17-6 Weld 3-CV-1231-16 (Contour of Branch Connection Limitation)

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Page 75 of 76 1.18 Weld 2-CV-1275 Pipe to Branch Connection (Socket Weld)

Figure 1.18-1 Weld 2-CV-1275-44 (Extracted from Reference 12 DWG S2-A-15B)

This weld was UT examined in Inspection Period 3, during the S2R24 refueling outage in 2020.

The NDE data came from UT Report No.: UT-20-012. The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-8(c). This volume was examined using a 45°S wave transducers. The corresponding CRV as shown on that Figure is C-D-E-F. The

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Page 76 of 76 UT examination was limited due to the proximity of valve 2CV76 resulting in total UT coverage of 35% as described in Figures 1.18-2, through 1.18-3. No recordable indication was detected during this examination.

This examination was performed in accordance with Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) in Regulatory Guide 1.147. The examination satisfied the requirements of Appendix VIII with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

Figure 1.18-2 Weld 2-CV-1275-44 (Photo)

Figure 1.18-3 Weld 2-CV-1275-44 (Scan Coverage and Scan Summary)