ML20276A003

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

ML20276A003
Person / Time
Site:	Prairie Island
Issue date:	10/02/2020
From:	Nancy Salgado Plant Licensing Branch III
To:	Sharp S Northern States Power Co
Kuntz R
References
EPID L-2020-LLR-0131
Download: ML20276A003 (6)

Text

October 2, 2020 Mr. Scott Sharp Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota 1717 Wakonade Drive East Welch, MN 55089

SUBJECT:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -

REQUEST TO USE A PROVISION OF A LATER EDITION OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE, SECTION XI (EPID L-2020-LLR-0131)

Dear Mr. Sharp:

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 Boiler and Pressure Vessel Code (ASME Code),Section XI, for Prairie Island Nuclear Generating Plant (Prairie Island), Units 1 and 2. This action is in response to your request dated October 1, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20275A294).

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

the Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (the licensee), proposed to use subparagraphs IWB-3516 and IWB-3519 of the 2017 Edition of the ASME Code,Section XI, in place of the corresponding subparagraph from the Code of Record for the evaluation of welded attachments for pumps.

The NRC staff approves the use of subparagraph IWB-3516 and IWB-3519 of the 2017 Edition of ASME Code,Section XI for the evaluation of welded attachments for pumps for Prairie Island, Units 1 and 2, for the duration of the fifth inservice inspection interval that started on December 21, 2014, and ends on December 20, 2024. All other ASME Code,Section XI, requirements which are not modified by the staffs approval of the licensees request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.

S. Sharp Enclosed is the NRC staffs safety evaluation.

If you have any questions, please contact Robert Kuntz at 301-415-3733 or via e-mail at Robert.Kuntz@nrc.gov.

Sincerely, Digitally signed by Scott P. Scott P. Wall Date: 2020.10.02 Wall 15:01:23 -04'00' Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306

Enclosure:

Safety Evaluation cc: Listserv

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUESTS 1-RR-5-14 AND 2-RR-5-14 REGARDING USE OF SUBSEQUENT EDITIONS AND ADDENDA OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE NORTHERN STATE POWER COMPANY - MINNESOTA CORPORATION - XCEL ENERGY PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306

1.0 INTRODUCTION

By letter dated October 1, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession ML20275A294), Northern States Power Company, a Minnesota Corporation doing business as Xcel Energy (the licensee), requested to use certain portions of later editions and addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for inservice inspection (ISI) of Class 1 pump welded attachments. Requests 1-RR-5-14 and 2-RR-5-14 are for the Prairie Island Nuclear Generating Plant (Prairie Island), Units 1 and 2, respectively.

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

the licensee requested to use the requirements in subparagraphs IWB-3516 and IWB-3519 of the 2017 Edition of the ASME Code,Section XI, subject to conditions in 50.55a(b), for ISI of the welded attachments for pumps, classified as Examination Category B-K, Item No. B10.30 in Table IWB-2500-1 of Section XI.

2.0 REGULATORY EVALUATION

Pursuant to 10 CFR 50.55a(a) and 50.55a(a)(1)(ii), the ASME Code,Section XI, from the 1970 Edition through the 1976 Winter Addenda, and the 1977 Edition through the 2017 Edition have been approved for incorporation by reference, but limited to those provisions identified in paragraph (b)(2) of 50.55a.

Pursuant to 10 CFR 50.55a(g)(4)(iv), 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 50.55a, subject to the conditions listed in paragraph (b) of 50.55a, and subject to U.S. Nuclear Regulatory Commissions (NRC) approval.

Portions of editions or addenda may be used, provided that all related requirements of the respective editions or addenda are met.

Enclosure

Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request and the NRC to approve the use of subsequent editions and addenda of the ASME Code requested by the licensee.

3.0 TECHNICAL EVALUATION

3.1 Component Affected ASME Code Class 1 welded attachments for pumps, classified as Examination Category B-K, Item No. B10.30 in Table IWB-2500-1 of Section XI, are affected.

3.2 Applicable Code Edition and Addenda The Code of Record for the fifth 10-year ISI interval of Prairie Island, Units 1 and 2, is the 2007 Edition and 2008 Addenda of the ASME Code.

3.3 Duration of Request The licensee submitted requests 1-RR-5-14 and 2-RR-5-14 for remainder of the fifth 10-year ISI interval for Prairie Island, Units 1 and 2, respectively, which commenced on December 21, 2014, and is scheduled to end on December 20, 2024.

3.4 Request The licensee requested to use the requirements in the 2017 Edition of the ASME Code,Section XI, subparagraphs IWB-3516 and IWB-3519, which provide evaluation and acceptance standards for flaws detected during examination of the welded attachments for pumps, classified as Examination Category B-K, Item No. B10.30 in Table IWB-2500-1 of Section XI.

3.5 NRC Staff Evaluation The NRC staff has evaluated requests 1-RR-5-14 and 2-RR-5-14 pursuant to 10 CFR 50.55a(g)(4)(iv). The NRC staffs evaluation focused on whether: (1) the subsequent editions and addenda of the ASME Code as requested for use is incorporated by reference in 50.55a(a); (2) the ASME Code requirements subject to the conditions listed in 50.55a(b) are met; (3) a request is submitted for the NRC approval; and (4) all related requirements of the respective editions and addenda are met. The NRC staff finds that if these four criteria are met, the requirements of 10 CFR 50.55a(g)(4)(iv) will also be met.

In evaluating requests 1-RR-5-14 and 2-RR-5-14, the NRC staff confirms that,

1. The 2017 Edition of Section XI to the ASME Code as requested for use, is incorporated by reference in 10 CFR 50.55a and subject to conditions in paragraph (b)(2) of 50.55a.

2. There are no applicable provisions in 10 CFR 50.55a related to subparagraphs IWB-3516 and IWB-3519 which would govern the licensees use of the proposed code provisions.

3. This submittal (i.e., 1-RR-5-14 and 2-RR-5-14) serves as the licensees request for NRC approval to use the 2017 Edition of ASME Code,Section XI, subparagraphs IWB-3516

and IWB-3519 for ISI of the welded attachments for pumps, classified as Examination Category B-K, Item No. B10.30 in Table IWB-2500-1 of Section XI.

4. The licensee has acknowledged that it will comply with all related requirements of the respective editions and addenda.

Therefore, the NRC staff determines that each of the four regulatory requirements for use of certain portions of later editions and addenda of the ASME Code have been met, and that use of the 2017 Edition of the ASME Code,Section XI, subparagraphs IWB-3516 and IWB-3519 for the welded attachments for pumps, classified as Examination Category B-K, Item No. B10.30 in Table IWB-2500-1 of Section XI, is acceptable.

4.0 CONCLUSION

As set forth above, NRC staff concludes 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 approves requests 1-RR-5-14 and 2-RR-5-14 at Prairie Island, Units 1 and 2, for remainder of each units fifth 10-year ISI interval, which commenced on December 21, 2014, and is scheduled to end on December 20, 2024.

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

Principal Contributor: Ali Rezai, NRR Date: October 2, 2020

ML20276A003

• via email OFFICE NRR/DORL/LPL3/PM* NRR/DORL/LPL3/LA* NRR/DNRL/NPHP/BC*

NAME RKuntz SRohrer (JBurkhardt for) MMitchell DATE 10/2/20 10/2/20 10/2/20 OFFICE NRR/DORL/LPL3/BC*

NAME NSalgado (SWall for)

DATE 10/2/20