RA-23-0001, Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI: Difference between revisions

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{{#Wiki_filter:Ke viTIM. Ellis Ge.m,ral ~iagtr Nldearfi'eglllalolyAf~ P:alcy&
{{#Wiki_filter:10 CFR 50.55a Serial: RA-23-0001 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  
( ~ DUKE ENERGY@ Eil~Mi:y~iess
 
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 a nd 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 a nd 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:==
==SUBJECT:==
Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI
Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI  


==REFERENCES:==
==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.
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.
( ~ DUKE ENERGY@
KeviTIM. Ellis Ge.m,ral ~iagtr Nldearfi'eglllalolyAf~ P:alcy&
Eil~Mi:y~iess 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


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.
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.
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  
Kevin Ellis General Manager, Nuclear Regulatory Affairs, Policy & Emergency Preparedness  


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


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


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)
Proposed Use of Subsequent ASME Code Edition and Addenda In Accordance with 10 CFR 50.55a(g)(4)(iv)
Page 1
Page 1 1.0 ASME CODE COMPONENTS AFFECTED:
 
2.0 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).
1.0 ASME CODE COMPONENTS AFFECTED:
APPLICABLE CODE EDITION AND ADDENDA:
 
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.
The applicable Edition and Addenda of the ASME Code, Section XI is identified in Table 1.
 
Table 1 Plant/Unit(s)
Table 1
ISI Interval ASME Section XI Code Edition/Addenda Interval Start Date Interval End Date1 Brunswick Steam Electric Plant Units 1 and 2 Fifth 2007 Edition, Through 2008 Addendum 05/11/2018 05/10/2028 Catawba Nuclear Station Units 1 and 2 Fourth 2007 Edition, Through 2008 Addendum 08/19/2015 12/06/2024 (Unit 1) 02/24/2026 (Unit 2)
 
H.B. Robinson Steam Electric Plant Unit 2 Sixth 2017 Edition 02/20/2023 02/19/2033 McGuire Nuclear Unit 1 Fifth 2007 Edition, Through 2008 Addendum 12/01/2021 11/30/2031 McGuire Nuclear Unit 2 Fourth 2007 Edition, Through 2008 Addendum 07/15/2014 02/29/2024 Oconee Nuclear Station Units 1, 2, and 3 Fifth 2007 Edition, Through 2008 Addendum 07/15/2014 07/15/2024 Shearon Harris Nuclear Power Plant Unit 1 Fourth 2007 Edition, Through 2008 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.
Plant/Unit(s) ISI ASMECode Section XI Interval Start Interval Edition/Addenda Date Interval End Date1
 
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)
Electric PlantH.B. Robinson Steam 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:
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.


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)
Proposed Use of Subsequent ASME Code Edition and Addenda In Accordance with 10 CFR 50.55a(g)(4)(iv)
Page 2
Page 2 4.0 RELATED REQUIREMENTS:
 
10 CFR 50.55a(g)(4)(iv) states:  
4.0 RELATED REQUIREMENTS:
"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(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).
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:
5.0 DURATION OF PROPOSED ALTERNATIVE:
 
This alternative is proposed for the remainder of the current inservice inspection intervals listed in Table 1.  
This alternative is proposed for the remainder of the current inservice inspection intervals listed in Table 1.


==6.0 PRECEDENTS==
==6.0 PRECEDENTS==
None.
None.  


==7.0 REFERENCES==
==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.
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.}}
2.
Federal Register, 87 FR 65128, dated October 27, 2022.}}

Latest revision as of 10:37, 27 November 2024

Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code,Section XI
ML23033A037
Person / Time
Site: Oconee, Mcguire, Catawba, Harris, Brunswick, Robinson, McGuire  Duke Energy icon.png
Issue date: 02/02/2023
From: Ellis K
Duke Energy Carolinas, Duke Energy Progress
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
RA-23-0001
Download: ML23033A037 (1)


Text

10 CFR 50.55a Serial: RA-23-0001 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.

( ~ DUKE ENERGY@

KeviTIM. Ellis Ge.m,ral ~iagtr Nldearfi'eglllalolyAf~ P:alcy&

Eil~Mi:y~iess 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£NYCOm

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, USN RC Senior Resident Inspector - CNS P. Boguszewski, USNRC Senior Resident Inspector-HNP C. Safouri USNRC Senior Resident Inspector-MNS J. Nadel, USN RC Senior Resident Inspector - ONS J. Zeiler, USN RC Senior Resident Inspector - RNP L. Haeg, USNRC NRR Project Manager for BNP and RNP M. Mahoney, USN RC 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:

2.0 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).

APPLICABLE CODE EDITION AND ADDENDA:

The applicable Edition and Addenda of the ASME Code,Section XI is identified in Table 1.

Table 1 Plant/Unit(s)

ISI Interval ASME Section XI Code Edition/Addenda Interval Start Date Interval End Date1 Brunswick Steam Electric Plant Units 1 and 2 Fifth 2007 Edition, Through 2008 Addendum 05/11/2018 05/10/2028 Catawba Nuclear Station Units 1 and 2 Fourth 2007 Edition, Through 2008 Addendum 08/19/2015 12/06/2024 (Unit 1) 02/24/2026 (Unit 2)

H.B. Robinson Steam Electric Plant Unit 2 Sixth 2017 Edition 02/20/2023 02/19/2033 McGuire Nuclear Unit 1 Fifth 2007 Edition, Through 2008 Addendum 12/01/2021 11/30/2031 McGuire Nuclear Unit 2 Fourth 2007 Edition, Through 2008 Addendum 07/15/2014 02/29/2024 Oconee Nuclear Station Units 1, 2, and 3 Fifth 2007 Edition, Through 2008 Addendum 07/15/2014 07/15/2024 Shearon Harris Nuclear Power Plant Unit 1 Fourth 2007 Edition, Through 2008 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.