ML20336A160

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

ML20336A160
Person / Time
Site:	Monticello
Issue date:	12/09/2020
From:	Nancy Salgado Plant Licensing Branch III
To:	Conboy T Northern States Power Company, Minnesota
Kuntz R, NRR/DORL/LPLIII, 415-3733
References
EPID L-2020-LLR-0151
Download: ML20336A160 (6)

Text

December 9, 2020 Mr. Thomas A. Conboy Site Vice President Northern States Power Company - Minnesota Monticello Nuclear Generating Plant 2807 West County Road 75 Monticello, MN 55362

SUBJECT:

MONTICELLO GENERATING PLANT - 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-0151)

Dear Mr. Conboy:

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 (BPV) Code,Section XI, for Monticello Nuclear Generating Plant (Monticello). This action is in response to your request dated November 30, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20335A340).

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 (NSPM or licensee), proposed to use subparagraph IWA-4540(b) of the 2017 Edition of the ASME BPV 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 BPV Code,Section XI, for Monticello, for the duration of the fifth inservice inspection interval that started on September 1, 2012, and ends on May 31, 2022. All other ASME BPV 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.

T. Conboy 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 Nancy L. Nancy L. Salgado Date: 2020.12.09 Salgado 08:45:29 -05'00' Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263 cc: Listserv

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST RR-018 - REQUEST TO USE A PROVISION OF A LATER EDITION OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE NORTHERN STATE POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263

1.0 INTRODUCTION

By letter dated November 30, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20335A340), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (NSPM or licensee), submitted proposal No. 1RR-018 to use a portion of a later edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME Code) for Monticello Nuclear Generating Plant (Monticello).

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 Code,Section XI, instead of the corresponding subparagraph from the current Code of Record.

The time period applicable for the use of the requested subsequent ASME Code edition and addenda is the fifth inservice inspection (ISI) interval.

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 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 ISI Code of Record for the current 10-year ISI interval at Monticello, is the ASME Code,Section XI, 2007 Edition, through the 2008 Addenda.

Enclosure

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 Code,Section XI.

2.5 Duration of the Use of the Later Code Edition and Addenda The duration of this request is for the fifth interval that started on September 1, 2012, and ends on May 31, 2022.

3.0 REGULATORY EVALUATION

The licensee is proposing to use a section of a later edition and addenda of the ASME Code,Section XI, in accordance with 10 CFR 50.55a(g)(4)(iv), 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 or Commission) staff to approve the use of subsequent ASME 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 Code,Section XI, and the NRC staff has the regulatory authority to approve the later edition and addenda of the ASME 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 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 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 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 request dated November 30, 2020, constitutes a request to the Commission for approval to use a subsequent edition/addendum of the ASME 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 Code,Section XI, is acceptable. The NRC staff approves the use of subparagraph IWA-4540(b) of the 2017 Edition of the ASME Code,Section XI, at Monticello, for the remainder of the fifth ISI interval.

All other ASME 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: Robert Kuntz, NRR Date: December 9, 2020

ML20336A160 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DNRL/NPHP/BC NAME RKuntz SRohrer MMittchell DATE 12/1/20 12/1/20 12/3/20 OFFICE NRR/DORL/LPL3/BC NAME NSalgado DATE 12/9/20