ML19056A214
| ML19056A214 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 02/25/2019 |
| From: | Shawn Williams Plant Licensing Branch II |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| L-2018-LLR-0195 | |
| Download: ML19056A214 (4) | |
Text
1 NRR-DMPSPEm Resource From:
Williams, Shawn Sent:
Monday, February 25, 2019 9:41 AM To:
Coleman, Jamie Marquess Cc:
Jackson, Nicole D.
Subject:
Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Relief Request FNP-ISI-RR-02, Version 1.0 (EPID L-2018-LLR-0195)
Attachments:
RAI FNP-ISI-RR-02.docx
Dear Ms. Coleman,
By letter dated November 30, 2018, Southern Nuclear Operating Company (SNC, the licensee) requested relief from IWB-2500 requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, at the Farley Nuclear Plant, Units 1 and 2 (FNP). Pursuant to Title 10 of the Code of Federal Regulations (CFR) 50.55a, paragraph (g)(5)(iii), SNC submitted relief request FNP-ISI-RR-02 proposing the alternate examination coverage of certain welds during the fourth 10-year inservice inspection program interval.
The U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information is needed in order to complete its review. Please respond within 30 days of the date of this e-mail. Please note that the NRC staff's review is continuing and further requests for information may be developed.
If you have any questions, please contact me at 301-415-1009 or Shawn.Williams@nrc.gov.
Sincerely, Shawn A. Williams, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364
Enclosure:
Request for Additional Information cc w/encl: Listserv
Hearing Identifier:
NRR_DMPS Email Number:
815 Mail Envelope Properties (BL0PR0901MB3154956AE1C43FE321410B5D907A0)
Subject:
Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Relief Request FNP-ISI-RR-02, Version 1.0 (EPID L-2018-LLR-0195)
Sent Date:
2/25/2019 9:40:37 AM Received Date:
2/25/2019 9:40:41 AM From:
Williams, Shawn Created By:
Shawn.Williams@nrc.gov Recipients:
"Jackson, Nicole D." <NDJACKSO@southernco.com>
Tracking Status: None "Coleman, Jamie Marquess" <JAMIEMCO@SOUTHERNCO.COM>
Tracking Status: None Post Office:
BL0PR0901MB3154.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 1307 2/25/2019 9:40:41 AM RAI FNP-ISI-RR-02.docx 31073 Options Priority:
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REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST FNP-ISI-RR-02 EXAMINATION COVERAGE OF WELDS JOSEPH M. FARLEY NUCLAR PLANT, UNITS 1 AND 2 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
DOCKET NOS. 50-348 AND 50-364 By letter dated November 30, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No.ML18334A032), Southern Nuclear Operating Company (SNC, the licensee) requested relief from IWB-2500 requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, at the Farley Nuclear Plant, Units 1 and 2 (FNP). Pursuant to Title 10 of the Code of Federal Regulations (CFR) 50.55a, paragraph (g)(5)(iii), SNC submitted relief request FNP-ISI-RR-02, proposing an alternate examination coverage of certain welds during the fourth 10-year inservice inspection program interval.
To complete its review, the Nuclear Regulatory Commission (NRC) staff requests the following additional information.
Request for Additional Information (RAI) No. 1 Discuss the materials of construction (e.g., ASME material specifications) of the subject welds and adjacent components (nozzles and pipes) in Tables RR-02.1 and RR-02.2 of the relief request. If Alloy 82/182 filler metal was used, discuss whether the subject welds have been mitigated to minimize the potential for primary water stress corrosion cracking. If stainless steel filler metal was used, discuss how the examination coverage of the subject welds was calculated and how the examination was conducted because claiming coverage for the volume on the opposite side of the weld centerline (far-side) requires meeting the 10 CFR 50.55a(b)(2)(xv)(A)(2) far-side UT qualifications, which has not been demonstrated in any qualification attempts to date.
RAI No. 2 Discuss other measures that could monitor structural integrity of the subject welds, given that certain volume of the subject welds could not be examined.
RAI No. 3 Section 2 of the relief request states that FNP, Units 1 and 2 examinations were performed in accordance with the requirements of ASME,Section XI, Article 4 of Section V Clarify whether the reference should be the ASME Code,Section V, Article 4.
RAI No. 4 Section 3 of the relief request states that: The extent of examination requirement for Examination Category B-D, Item Number B3.110, per Table IWB-2500-1, requires a volumetric examination of essentially 100% of the weld length The NRC staff understands that Table IWB-2500-1 requires a volumetric examination of 100%, not essentially 100%, coverage of the weld length. The essentially 100% examination coverage is permitted only by ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds,Section XI, Division 1. Please clarify the above examination coverage statement.