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=Text=
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{{#Wiki_filter:1 NRR-PMDAPEm Resource From:Chawla, Mahesh Sent: Tuesday, August 08, 2017 2:57 PM To:Davis, J.Michael (J.Michael.Davis@nexteraenergy.com);
{{#Wiki_filter:NRR-PMDAPEm Resource From:                             Chawla, Mahesh Sent:                             Tuesday, August 08, 2017 2:57 PM To:                               Davis, J.Michael (J.Michael.Davis@nexteraenergy.com);
laura.swenzinski@nexteraenergy.com; Catron , Steve (Steve.Catron@fpl.com); Kilby, Gary  
laura.swenzinski@nexteraenergy.com; Catron, Steve (Steve.Catron@fpl.com); Kilby, Gary


==Subject:==
==Subject:==
Request for Additional Inform ation - Duane Arnold Energy Center - Relief Request No.
Request for Additional Information - Duane Arnold Energy Center - Relief Request No.
RR Alternative Requirements for Nozzle Inner Radius and Nozzle-To-Shell Welds -
RR Alternative Requirements for Nozzle Inner Radius and Nozzle-To-Shell Welds -
CAC No. MF9374 By letter dated March 7, 2017 (Agencywide Docu ments Access and Management System (ADAMS) Accession No. ML17069A172), NextEra Energy Duane Arnold, LLC (the licensee) submitted the fifth inservice inspection (ISI) interval program plan for D uane Arnold Energy Center (DAEC) for the U.S. Nuclear Regulatory Commission (NRC) review and approval. The program plan contains several relief requests from certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, requirements. Among them, Relief Request No. 3 proposed to use an alternative based on ASME Code Case N-702, "Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds," for inspection of reactor pressure vessel (RPV) nozzle inner radius and nozzle-to-shell welds at DAEC.  
CAC No. MF9374 By letter dated March 7, 2017 (Agencywide Documents Access and Management System (ADAMS)
 
Accession No. ML17069A172), NextEra Energy Duane Arnold, LLC (the licensee) submitted the fifth inservice inspection (ISI) interval program plan for Duane Arnold Energy Center (DAEC) for the U.S. Nuclear Regulatory Commission (NRC) review and approval. The program plan contains several relief requests from certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, requirements. Among them, Relief Request No. 3 proposed to use an alternative based on ASME Code Case N-702, Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds, for inspection of reactor pressure vessel (RPV) nozzle inner radius and nozzle-to-shell welds at DAEC.
The NRC staff has reviewed the submittal and determined that the additional information below is needed to complete the review of Relief Request No. 3.
The NRC staff has reviewed the submittal and determined that the additional information below is needed to complete the review of Relief Request No. 3.
RAI-1  In Relief Request No. 3, the licensee proposed an alternative based on ASME Code Case N-702 for the RPV nozzle inspection during the fifth ISI interval.
This Code Case was conditionally approved in Regulatory Guide (RG) 1.147, Revision 17, "Inservice Inspection Code Case Acceptability, Section XI, Division 1," dated August 2014, requiring the applicants to address the evaluation criteria in the safety evaluation (SE) for BWRVIP-108, "Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Inner Radii" (ADAMS Accession No. ML073600374) or BWRVIP-241, "Probabilistic Fracture Mechanics [PFM] Evaluation for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii" (ADAMS Accession No. ML13071A240). Both reports are for 40 years of operation
On April 26, 2017, the SE for BWRVIP-241, Appendix A (ADAMS Accession No. ML17114A096) for the period of extended operation was issued, which extends the application of BWRVIP-108 and BWRVIP-241, and, therefore, ASME Code Case N-702, from 40 years to 60 years.
Relief Request No. 3 used the evaluation criteria from the SE for BWRVIP-108, but did not explain why the evaluation criteria for 40 years can be used beyond 40 years during the fifth ISI interval. Please provide justification. Licensees have been using plant-specific PFM analysis for this purpose. However, since the issuance of the SE for BWRVIP-241, Appendix A, one could also justify using ASME Code Case N-702 for the entire period of extended operation by referencing BWRVIP-241, Appendix A, and addressing the required demonstrations under A.3 and A.4 of this Appendix.


Please arrange a teleconference with the NRC staff to discuss this request. Thanks Mahesh Chawla 2Project Manager Phone: 301-415-8371
===RAI-1===
In Relief Request No. 3, the licensee proposed an alternative based on ASME Code Case N-702 for the RPV nozzle inspection during the fifth ISI interval.
This Code Case was conditionally approved in Regulatory Guide (RG) 1.147, Revision 17, Inservice Inspection Code Case Acceptability, Section XI, Division 1, dated August 2014, requiring the applicants to address the evaluation criteria in the safety evaluation (SE) for BWRVIP-108, Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Inner Radii (ADAMS Accession No. ML073600374) or BWRVIP-241, Probabilistic Fracture Mechanics [PFM]
Evaluation for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii (ADAMS Accession No. ML13071A240). Both reports are for 40 years of operation On April 26, 2017, the SE for BWRVIP-241, Appendix A (ADAMS Accession No. ML17114A096) for the period of extended operation was issued, which extends the application of BWRVIP-108 and BWRVIP-241, and, therefore, ASME Code Case N-702, from 40 years to 60 years.
Relief Request No. 3 used the evaluation criteria from the SE for BWRVIP-108, but did not explain why the evaluation criteria for 40 years can be used beyond 40 years during the fifth ISI interval. Please provide justification. Licensees have been using plant-specific PFM analysis for this purpose. However, since the issuance of the SE for BWRVIP-241, Appendix A, one could also justify using ASME Code Case N-702 for the entire period of extended operation by referencing BWRVIP-241, Appendix A, and addressing the required demonstrations under A.3 and A.4 of this Appendix.
Please arrange a teleconference with the NRC staff to discuss this request. Thanks Mahesh Chawla 1


Fax: 301-415-1222 mahesh.chawla@nrc.gov  
Project Manager Phone: 301-415-8371 Fax: 301-415-1222 mahesh.chawla@nrc.gov 2


Hearing Identifier: NRR_PMDA Email Number: 3647   Mail Envelope Properties   (Mahesh.Chawla@nrc.gov20170808145600)
Hearing Identifier:     NRR_PMDA Email Number:           3647 Mail Envelope Properties     (Mahesh.Chawla@nrc.gov20170808145600)


==Subject:==
==Subject:==
Request for Additional Information - Duane Arnold Energy Center - Relief Request No. RR Alternative Requirements for Nozzle Inner Radius and Nozzle-To-Shell Welds - CAC No. MF9374 Sent Date:   8/8/2017 2:56:55 PM Received Date: 8/8/2017 2:56:00 PM From:   Chawla, Mahesh Created By:   Mahesh.Chawla@nrc.gov  
Request for Additional Information - Duane Arnold Energy Center - Relief Request No. RR Alternative Requirements for Nozzle Inner Radius and Nozzle-To-Shell Welds -
 
CAC No. MF9374 Sent Date:             8/8/2017 2:56:55 PM Received Date:         8/8/2017 2:56:00 PM From:                   Chawla, Mahesh Created By:             Mahesh.Chawla@nrc.gov Recipients:
Recipients:     "Davis, J.Michael (J.Michael.Davis@nexteraenergy.com)" <J.Michael.Davis@nexteraenergy.com> Tracking Status: None "laura.swenzinski@nexteraenergy.com" <laura.swenzinski@nexteraenergy.com> Tracking Status: None "Catron, Steve (Steve.Catron@fpl.com)" <Steve.Catron@fpl.com> Tracking Status: None "Kilby, Gary" <Gary.Kilby@fpl.com>
"Davis, J.Michael (J.Michael.Davis@nexteraenergy.com)" <J.Michael.Davis@nexteraenergy.com>
Tracking Status: None Post Office:     Files     Size     Date & Time MESSAGE   2871     8/8/2017 2:56:00 PM
Tracking Status: None "laura.swenzinski@nexteraenergy.com" <laura.swenzinski@nexteraenergy.com>
 
Tracking Status: None "Catron, Steve (Steve.Catron@fpl.com)" <Steve.Catron@fpl.com>
Options Priority:     Standard   Return Notification:   No   Reply Requested:   No   Sensitivity:     Normal Expiration Date:     Recipients Received:}}
Tracking Status: None "Kilby, Gary" <Gary.Kilby@fpl.com>
Tracking Status: None Post Office:
Files                           Size                       Date & Time MESSAGE                         2871                       8/8/2017 2:56:00 PM Options Priority:                       Standard Return Notification:           No Reply Requested:               No Sensitivity:                   Normal Expiration Date:
Recipients Received:}}

Revision as of 23:27, 29 October 2019

Request for Additional Information - Duane Arnold Energy Center - Relief Request No. RR-03 - Alternative Requirements for Nozzle Inner Radius and Nozzle-To-Shell Welds - CAC No. MF9374
ML17220A333
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 08/08/2017
From: Mahesh Chawla
Plant Licensing Branch III
To: Catron S, Jennifer Davis, Kilby G, Swenzinski L
Florida Power & Light Co, NextEra Energy Duane Arnold
References
MF9374
Download: ML17220A333 (3)
v • d • e


Text

NRR-PMDAPEm Resource From: Chawla, Mahesh Sent: Tuesday, August 08, 2017 2:57 PM To: Davis, J.Michael (J.Michael.Davis@nexteraenergy.com);

laura.swenzinski@nexteraenergy.com; Catron, Steve (Steve.Catron@fpl.com); Kilby, Gary

Subject:

Request for Additional Information - Duane Arnold Energy Center - Relief Request No.

RR Alternative Requirements for Nozzle Inner Radius and Nozzle-To-Shell Welds -

CAC No. MF9374 By letter dated March 7, 2017 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML17069A172), NextEra Energy Duane Arnold, LLC (the licensee) submitted the fifth inservice inspection (ISI) interval program plan for Duane Arnold Energy Center (DAEC) for the U.S. Nuclear Regulatory Commission (NRC) review and approval. The program plan contains several relief requests from certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, requirements. Among them, Relief Request No. 3 proposed to use an alternative based on ASME Code Case N-702, Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds, for inspection of reactor pressure vessel (RPV) nozzle inner radius and nozzle-to-shell welds at DAEC.

The NRC staff has reviewed the submittal and determined that the additional information below is needed to complete the review of Relief Request No. 3.

RAI-1

In Relief Request No. 3, the licensee proposed an alternative based on ASME Code Case N-702 for the RPV nozzle inspection during the fifth ISI interval.

This Code Case was conditionally approved in Regulatory Guide (RG) 1.147, Revision 17, Inservice Inspection Code Case Acceptability,Section XI, Division 1, dated August 2014, requiring the applicants to address the evaluation criteria in the safety evaluation (SE) for BWRVIP-108, Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Inner Radii (ADAMS Accession No. ML073600374) or BWRVIP-241, Probabilistic Fracture Mechanics [PFM]

Evaluation for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii (ADAMS Accession No. ML13071A240). Both reports are for 40 years of operation On April 26, 2017, the SE for BWRVIP-241, Appendix A (ADAMS Accession No. ML17114A096) for the period of extended operation was issued, which extends the application of BWRVIP-108 and BWRVIP-241, and, therefore, ASME Code Case N-702, from 40 years to 60 years.

Relief Request No. 3 used the evaluation criteria from the SE for BWRVIP-108, but did not explain why the evaluation criteria for 40 years can be used beyond 40 years during the fifth ISI interval. Please provide justification. Licensees have been using plant-specific PFM analysis for this purpose. However, since the issuance of the SE for BWRVIP-241, Appendix A, one could also justify using ASME Code Case N-702 for the entire period of extended operation by referencing BWRVIP-241, Appendix A, and addressing the required demonstrations under A.3 and A.4 of this Appendix.

Please arrange a teleconference with the NRC staff to discuss this request. Thanks Mahesh Chawla 1

Project Manager Phone: 301-415-8371 Fax: 301-415-1222 mahesh.chawla@nrc.gov 2

Hearing Identifier: NRR_PMDA Email Number: 3647 Mail Envelope Properties (Mahesh.Chawla@nrc.gov20170808145600)

Subject:

Request for Additional Information - Duane Arnold Energy Center - Relief Request No. RR Alternative Requirements for Nozzle Inner Radius and Nozzle-To-Shell Welds -

CAC No. MF9374 Sent Date: 8/8/2017 2:56:55 PM Received Date: 8/8/2017 2:56:00 PM From: Chawla, Mahesh Created By: Mahesh.Chawla@nrc.gov Recipients:

"Davis, J.Michael (J.Michael.Davis@nexteraenergy.com)" <J.Michael.Davis@nexteraenergy.com>

Tracking Status: None "laura.swenzinski@nexteraenergy.com" <laura.swenzinski@nexteraenergy.com>

Tracking Status: None "Catron, Steve (Steve.Catron@fpl.com)" <Steve.Catron@fpl.com>

Tracking Status: None "Kilby, Gary" <Gary.Kilby@fpl.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 2871 8/8/2017 2:56:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

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