View source for RA-23-0001, Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI

{{Adams
| number = ML23033A037
| issue date = 02/02/2023
| title = Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI
| author name = Ellis K
| author affiliation = Duke Energy Carolinas, LLC, Duke Energy Progress, LLC
| addressee name = 
| addressee affiliation = NRC/NRR, NRC/Document Control Desk
| docket = 05000261, 05000269, 05000270, 05000287, 05000324, 05000325, 05000369, 05000370, 05000400, 05000413, 05000414
| license number = DPR-071, DPR-062, NPF-035, NPF-052, NPF-063, NPF-009, NPF-017, DPR-038, DPR-047, DPR-055, DPR-023
| contact person = 
| case reference number = RA-23-0001
| document type = Letter type:RA, Request for Code Relief or Alternative
| page count = 1
}}

=Text=
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Eil~Mi:y~iess ENERGY@                                                                           l)JJre Enelgy 13.225 tta,en; FenyRd., tl>G011E fu!l"..mille, 1\C 20076 643-951-1329 i<e\iJI,. sM,;e-e11&#xa3;NYCOm Serial: RA-23-0001                                                                   10 CFR 50.55a February 2, 2023 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Docket Nos. 50-325, 50-324 / Renewed License Nos. DPR-71 And DPR-62 Catawba Nuclear Station, Unit Nos. 1 and 2 Docket Nos. 50-413, 50-414 / Renewed License Nos. NPF-35 and NPF-52 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400 / Renewed License No. NPF-63 McGuire Nuclear Station, Unit Nos. 1 and 2 Docket Nos. 50-369, 50-370 / Renewed License Nos. NPF-9 and NPF-17 Oconee Nuclear Station, Unit Nos. 1, 2, and 3 Docket Nos. 50-269, 50-270, and 50-287 / Renewed License Nos. DPR-38, DPR-47, and DPR-55 H. B. Robinson Steam Electric Plant, Unit No. 2 Docket No. 50-261 / Renewed License No. DPR-23

==SUBJECT:==
Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI

==REFERENCES:==
: 1. NRC Regulatory Issue Summary 2004-12, Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI, dated July 28, 2004.
In accordance with 10 CFR 50.55a, Codes and Standards, paragraph (g)(4)(iv), and the guidance provided in the referenced document, Duke Energy Carolinas, LLC and Duke Energy Progress, LLC (hereafter referred to collectively as Duke Energy) request U.S Nuclear Regulatory Commission (NRC) approval to use a specific provision of a later edition of the American Society of Mechanical (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI, for the units identified above. Specifically, Duke Energy is seeking approval to use Paragraph IWA-6230 of the 2019 edition of the ASME Code, Section XI which provides 120 days to submit inservice inspection (ISI) summary reports to the NRC. The request is provided as the Attachment to this submittal.

RA-23-0001 Page 2 Duke Energy requests approval of this request by May 1, 2023 to support post-outage work for the Spring, 2023 plant outages. There are no regulatory commitments in this letter.
If you have additional questions, please contact Ryan Treadway, Director - Nuclear Fleet Licensing, at (980) 373-5873.
Kevin Ellis General Manager, Nuclear Regulatory Affairs, Policy & Emergency Preparedness

==Attachment:==
Proposed Use of Subsequent ASME Code Edition and Addenda In Accordance with 10 CFR 50.55a(g)(4)(iv) cc:
L. Dudes, Regional Administrator USNRC Region II G. Smith, USN RC Senior Resident Inspector - BNP D. Rivard, USNRC Senior Resident Inspector- CNS P. Boguszewski, USNRC Senior Resident Inspector- HNP C. Safouri USNRC Senior Resident Inspector- MNS J. Nadel, USNRC Senior Resident Inspector - ONS J. Zeiler, USNRC Senior Resident Inspector- RNP L. Haeg, USNRC NRR Project Manager for BNP and RNP M. Mahoney, USNRC NRR Project Manager for HNP J. Klos, USNRC NRR Project Manager for MNS S. Williams, USNRC NRR Project Manager for CNS and ONS

RA-23-0001 Attachment Proposed Use of Subsequent ASME Code Edition and Addenda In Accordance with 10 CFR 50.55a(g)(4)(iv)

Proposed Use of Subsequent ASME Code Edition and Addenda In Accordance with 10 CFR 50.55a(g)(4)(iv)
Page 1 1.0     ASME CODE COMPONENTS AFFECTED:
All pressure-retaining components described in the ASME Boiler and Pressure Vessel Code, Section XI, 2019 Edition, Article IWA-6230, Owners Activity Report, paragraph (b).
2.0     APPLICABLE CODE EDITION AND ADDENDA:
The applicable Edition and Addenda of the ASME Code, Section XI is identified in Table 1.
Table 1 ISI         ASME Section XI          Interval Start Plant/Unit(s)                                 Code                             Interval End Date1 Interval       Edition/Addenda               Date Brunswick Steam Electric              2007 Edition, Through 2008 Plant Units 1 and 2            Fifth  Addendum                        05/11/2018       05/10/2028 Catawba Nuclear Station               2007 Edition, Through 2008                   12/06/2024 (Unit 1)
Units 1 and 2                Fourth Addendum                          08/19/2015   02/24/2026 (Unit 2)
H.B. Robinson Steam Electric Plant Unit 2         Sixth   2017 Edition                    02/20/2023       02/19/2033 2007 Edition, Through 2008 McGuire Nuclear Unit 1         Fifth  Addendum                        12/01/2021       11/30/2031 2007 Edition, Through 2008 McGuire Nuclear Unit 2       Fourth   Addendum                        07/15/2014       02/29/2024 Oconee Nuclear Station                2007 Edition, Through 2008 Units 1, 2, and 3              Fifth  Addendum                        07/15/2014       07/15/2024 Shearon Harris Nuclear                2007 Edition, Through 2008 Power Plant Unit 1           Fourth Addendum                          09/09/2017       09/08/2027 Note 1: Date listed is the planned interval end date. In accordance with IWA-2430(c)(1), this end date may be extended or shortened as necessary.
3.0     PROPOSED SUBSEQUENT CODE EDITION AND ADDENDA:
Duke Energy proposes to utilize portions of the ASME Section XI, 2019 Edition in lieu of the 2007 Edition up to and including the 2008 Addenda and 2017 Edition. Specifically, Duke Energy proposes to utilize IWA-6230(b) which provides an extension of the 90 calendar-day submittal requirement of the Owners Activity Report to 120 calendar-days following completion of a refueling outage.

Proposed Use of Subsequent ASME Code Edition and Addenda In Accordance with 10 CFR 50.55a(g)(4)(iv)
Page 2 4.0 RELATED REQUIREMENTS:
10 CFR 50.55a(g)(4)(iv) 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. "
10 CFR 50.55a(b)(2) incorporates by reference Section XI, Division 1, of the ASME B&PV Code 2019 Edition as approved in Reference 2. Duke Energy is requesting use of IWA-6230(b) of the 2019 Edition of ASME Section XI to utilize an extension of the 90 calendar-day submittal requirement of the Owners Activity Report to 120 calendar-days. There are no related requirements or applicable conditions associated with this subparagraph, IWA-6230(b).
5.0 DURATION OF PROPOSED ALTERNATIVE:
This alternative is proposed for the remainder of the current inservice inspection intervals listed in Table 1.

==6.0 PRECEDENTS==
None.

==7.0 REFERENCES==
: 1. NRC Regulatory Issue Summary 2004-12, "Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI," dated July 28, 2004.
: 2. Federal Register, 87 FR 65128, dated October 27, 2022.}}