ML20300A206

Duke Fleet - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI

ML20300A206
Person / Time
Site:	Oconee, Mcguire, Catawba, Harris, Brunswick, Robinson, McGuire
Issue date:	11/09/2020
From:	Undine Shoop NRC/NRR/DORL/LPL2-2
To:	Snider S Duke Energy Nuclear
Hon A
References
EPID L-2020-LLR-0125
Download: ML20300A206 (7)

Text

November 9, 2020 Mr. Steve Snider Vice President Nuclear Engineering Duke Energy 526 South Church Street, EC-07H Charlotte, NC 28202

SUBJECT:

BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2; CATAWBA NUCLEAR STATION, UNITS 1 AND 2; H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT 2; MCGUIRE NUCLEAR STATION, UNITS 1 AND 2; OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3; AND SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - REQUEST TO USE A PROVISION OF A LATER EDITION OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE, SECTION XI (EPID NO. L-2020-LLR-0125)

Dear Mr. Snider:

The U.S. Nuclear Regulatory Commission (NRC) has approved your request to use a provision of a later edition of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, for Brunswick Steam Electric Plant, Units 1 and 2; Catawba Nuclear Station, Units 1 and 2; H. B. Robinson Steam Electric Plant, Unit 2; McGuire Nuclear Station, Units 1 and 2; Oconee Nuclear Station, Units 1, 2, and 3; and Shearon Harris Nuclear Power Plant, Unit. This action is in response to your request RA-20-0262, dated September 16, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20260H325).

Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(4)(iv),

the Duke Energy Carolinas, LLC and Duke Energy Progress, LLC (hereafter referred to collectively as Duke Energy), proposed to use subparagraph IWA-4540(b) of the 2017 Edition of the ASME B&PV Code,Section XI, in place of the of the corresponding subparagraph from the Code of Record.

The NRC staff approves the use of subparagraph IWA-4540(b) of the 2017 Edition of ASME B&PV Code,Section XI, for the Fourth 10-Year Inservice Inspection (ISI) interval for Catawba Nuclear Station, Units 1 and 2, that started on August 19, 2015, and ends on December 6, 2024 (Unit 1) and February 24, 2026 (Unit 2); McGuire Nuclear Station, Units 1 and 2, that started on December 1, 2011 (Unit 1) and July 15, 2014 (Unit 2) and ends on November 30, 2021 (Unit 1) and February 29, 2024 (Unit 2); and Shearon Harris Nuclear Power Plant, Unit 1, that started on September 9, 2017, and ends on September 8, 2027; and the Fifth 10-year ISI interval for Brunswick Steam Electric Plant, Units 1 and 2, that started on May 11, 2018, and ends on May 10, 2028; H. B. Robinson Steam Electric Plant, Unit 2, that started on July 21, 2012, and ends on February 19, 2023; and Oconee Nuclear Station, Units 1, 2, 3, that started on July 15, 2014, and ends on July 15, 2024.

S. Snider All other ASME B&PV Code,Section XI, requirements which are not modified by the NRC staffs approval of the licensees request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.

If you have any questions, please contact the Duke Fleet Project Manager, Andrew Hon at 301-415-8480 or via e-mail at Andrew.Hon@nrc.gov.

Sincerely, Kimberly J. Digitally signed by Kimberly J. Green Date: 2020.11.09 Green 08:59:51 -05'00' Undine S. Shoop, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-261, 50-269, 50-270, 50-287, 50-324, 50-325, 50-369, 50-370, 50-413, 50-414, and 50-400

Enclosure:

Safety Evaluation cc:

Mr. J. Ed Burchfield, Jr. Ms. Kim Maza Site Vice President Site Vice President Oconee Nuclear Station Shearon Harris Nuclear Power Plant Duke Energy Carolinas, LLC Duke Energy Progress, LLC 7800 Rochester Highway 5413 Shearon Harris Road Seneca, SC 29672-0752 Mail Code NHP01 New Hill, NC 27562-9300 Mr. Ernest J. Kapopoulos, Jr.

Site Vice President Mr. Tom Ray H. B. Robinson Steam Electric Plant Site Vice President Duke Energy Progress, LLC McGuire Nuclear Station 3581 West Entrance Road, RNPA01 Duke Energy Carolinas, LLC Hartsville, SC 29550 12700 Hagers Ferry Road Huntersville, NC 28078 Mr. John A. Krakuszeski Site Vice President Mr. Robert T. Simril Brunswick Steam Electric Plant Site Vice President Duke Energy Progress, LLC Catawba Nuclear Station 8470 River Rd. SE (M/C BNP001) Duke Energy Carolinas, LLC Southport, NC 28461 Catawba Nuclear Station 4800 Concord Road York, SC 29745 Additional Distribution via Listserv

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST RA-20-0262 - REQUEST TO USE A PROVISION OF A LATER EDITION OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE DUKE ENERGY CAROLINAS, LLC CATAWBA NUCLEAR STATION, UNITS 1 AND 2 MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DUKE ENERGY PROGRESS, LLC BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT 2 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NOS. 50-413, 50-414, 50-369, 50-370, 50-269, 50-270, 50-287, 50-324, 50-325, 50-261, and 50-400

1.0 INTRODUCTION

By letter dated September 16, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20260H325), Duke Energy Carolinas, LLC and Duke Energy Progress, LLC (hereafter referred to collectively as Duke Energy, the licensee) submitted RA 20-0262 to use a portion of a later edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code for Brunswick Steam Electric Plant, Units 1 and 2; Catawba Nuclear Station, Units 1 and 2; H. B. Robinson Steam Electric Plant, Unit 2; McGuire Nuclear Station, Units 1 and 2; Oconee Nuclear Station, Units 1, 2, and 3; and Shearon Harris Nuclear Power Plant, Unit 1.

Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(4)(iv),

the licensee proposed to use subparagraph IWA-4540(b) of the 2017 Edition of the ASME B&PV Code,Section XI, instead of the corresponding subparagraph from the current Code of Record.

Enclosure

The time period applicable for the use of the requested subsequent ASME B&PV Code edition and addenda is the Fourth 10-Year Inservice Inspection (ISI) interval for Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units 1 and 2; and Shearon Harris Nuclear Power Plant, Unit 1; and the Fifth 10-year ISI interval for Brunswick Steam Electric Plant, Units 1 and 2; H.B. Robinson Steam Electric Plant, Unit 2; and Oconee Nuclear Station, Units 1, 2, and 3. The licensee asserts that it meets all related requirements of the 2017 Edition of the ASME B&PV Code,Section XI.

2.0 PROPOSED USE OF SUBSEQUENT CODE EDITION AND ADDENDA 2.1 Component(s) for Which the Subsequent Code Edition is Requested All Class 1, 2, and 3 items located in the ASME B&PV Code,Section XI, boundaries.

2.2 Current Code Requirement Subparagraph IWA-4540(b) provides items that are exempt from pressure testing after repair/replacement activities.

2.3 Current Code Edition and Addenda of Record The Code of Record for the current 10-year ISI interval at the subject plants is ASME Code,Section XI, 2007 Edition with the 2008 Addenda.

2.4 Proposed Subsequent Code Edition and Addenda The proposed subsequent Code edition and addenda to be used is subparagraph IWA-4540(b) of the 2017 Edition of the ASME B&PV Code,Section XI.

2.5 Duration of the Use of the Later Code Edition and Addenda The licensee is requesting approval of this proposed alternative for the remainder of the 10-year ISI intervals, as shown in Table 1 below.

Table 1 Plant/Unit(s) ISI Interval Start Date Current Planned Interval Interval End Date Brunswick Steam Electric Fifth 05/11/2018 05/10/2028 Plant, Units 1 and 2 Catawba Nuclear Station, Fourth 08/19/2015 12/06/2024 (Unit 1)

Units 1 and 2 02/24/2026 (Unit 2)

H. B. Robinson Steam Fifth 07/21/2012 02/19/2023 Electric Plant, Unit 2 McGuire Nuclear Station, Fourth 12/01/2011 (Unit 1) 11/30/2021 (Unit 1)

Units 1 and 2 07/15/2014 (Unit 2) 02/29/2024 (Unit 2)

Oconee Nuclear Station, Fifth 07/15/2014 07/15/2024 Units 1, 2, and 3 Shearon Harris Nuclear Fourth 09/09/2017 09/08/2027 Power Plant, Unit 1

3.0 REGULATORY EVALUATION

The licensee is proposing to use a section of a later edition and addenda of the ASME B&PV Code,Section XI, in accordance with 10 CFR 50.55a(g)(4)(iv), Applicable ISI Code: Use of subsequent Code editions and addenda, which states:

Inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (a) of this section, subject to the conditions listed in paragraph (b) of this section, and subject to Commission approval. Portions of editions or addenda may be used, provided that all related requirements of the respective editions or addenda are met.

Given that 10 CFR 50.55(g)(4)(iv) permits the U.S. Nuclear Regulatory Commission (NRC) staff to approve the use of subsequent ASME B&PV Code edition and addenda, the NRC staff finds that, subject to the following technical evaluation, the licensee may propose to use a section of a later edition and addenda of the ASME B&PV Code,Section XI, and the NRC staff has the regulatory authority to approve the later edition and addenda of the ASME B&PV Code,Section XI.

4.0 NRC TECHNICAL EVALUATION As previously stated in Section 3.0 of this safety evaluation, prior to approving the use of a subsequent edition and addenda of the ASME B&PV Code under 10 CFR 50.55a(g)(4)(iv), the NRC staff must find that (1) the proposed subsequent edition and addenda are incorporated by reference in 10 CFR 50.55a(a); (2) the licensee has identified any conditions listed in 10 CFR 50.55a(b) appropriate to the request and will comply with those conditions; (3) the licensee has requested approval to use the subsequent edition and addenda; and (4) if only portions of edition or addenda are to be used, all related requirements of the respective edition or addenda are met. If these criteria are met, the NRC staff finds the use of the subsequent edition and addenda of the ASME B&PV Code,Section XI, to be acceptable.

4.1 Incorporation by Reference In evaluating the first criterion, 10 CFR 50.55a(a) incorporates by reference the ASME B&PV Code,Section XI, from the 1970 Edition through the 1976 Winter Addenda, and the 1977 Edition through the 2017 Edition. The licensee proposed to use the 2017 Edition, which is included in the list of editions and addenda incorporated by reference in the current edition of 10 CFR 50.55a(a). Therefore, the NRC finds that the first criterion has been satisfied.

4.2 Subject to Conditions Listed in 10 CFR 50.55a(b)

In evaluating the second criterion, the NRC staff finds that 10 CFR 50.55a(b) contains no conditions relevant to this request. Therefore, the NRC staff finds that the second criterion has been satisfied.

4.3 Requesting Commission Approval In evaluating the third criterion, the licensee's request dated September 16, 2020, constitutes a request to the Commission for approval to use a subsequent edition/addendum of the ASME B&PV Code. Therefore, the NRC staff finds that the third criterion has been satisfied.

4.4 All Related Requirements In evaluating the fourth criterion, the NRC staff finds that there are no related requirements relevant to this request. Therefore, the NRC staff finds that the fourth criterion has been satisfied.

4.5 Summary Based on the review above, the NRC staff finds that the licensee has adequately addressed all regulatory requirements set forth in 10 CFR 50.55a(g)(4)(iv).

5.0 CONCLUSION

As set forth above, NRC staff finds that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(4)(iv). Therefore, the NRC staff concludes that the use of subparagraph IWA-4540(b) the 2017 Edition of the ASME B&PV Code,Section XI, is acceptable. The NRC staff approves the use of subparagraph IWA-4540(b) of the 2017 Edition of the ASME B&PV Code,Section XI, for the Fourth 10-year ISI interval for Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units 1 and 2; and Shearon Harris Nuclear Power Plant, Unit 1; and the Fifth 10-year ISI interval for Brunswick Steam Electric Plant, Units 1 and 2; H. B. Robinson Steam Electric Plant, Unit 2; and Oconee Nuclear Station, Units 1, 2, and 3.

All other ASME B&PV Code,Section XI, requirements which are not modified by the NRC staffs approval of the licensees request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.

Principal Contributor: M. Mahoney, NRR Date: November 9, 2020

ML20300A206

• via email OFFICE NRR/DORL/LPL2-2/PM* NRR/DORL/LPL2-2/LA* NRR/DNRL/NPHP/BC*

NAME MMahoney BAbeywickrama MMitchell DATE 10/27/2020 10/26/2020 10/23/2020 OFFICE DORL/LPL2-2/BC*

NAME UShoop (KGreen for)

DATE 11/09/2020