ML19066A042

NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Relief Request FNP-ISI-RR-03, Version 1.0

ML19066A042
Person / Time
Site:	Farley
Issue date:	03/07/2019
From:	Shawn Williams Plant Licensing Branch II
To:	Coleman J Southern Nuclear Operating Co
References
L-2018-LLR-0196
Download: ML19066A042 (4)

Text

NRR-DMPSPEm Resource From: Williams, Shawn Sent: Thursday, March 7, 2019 5:43 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-03, Version 1.0 (EPID L-2018-LLR-0196)

Attachments: Farley RAI FNP-ISI-RR-03 RAIs.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-03 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 1

Hearing Identifier: NRR_DMPS Email Number: 849 Mail Envelope Properties (BL0PR0901MB31544B15E254E4AB88AADD13904C0)

Subject:

Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Relief Request FNP-ISI-RR-03, Version 1.0 (EPID L-2018-LLR-0196)

Sent Date: 3/7/2019 5:42:40 AM Received Date: 3/7/2019 5:42:42 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 1340 3/7/2019 5:42:42 AM Farley RAI FNP-ISI-RR-03 RAIs.docx 32027 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST NO. FNP-ISI-RR-03 EXAMINATION COVERAGE OF WELDS SOUTHERN NUCLEAR OPERATING COMPANY JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 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, IWC-2500 and Code Case N-716 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-03 proposing the 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 Only the materials of construction for Category B-F Item B5.70 welds were listed in the submittal.

(a) Please discuss the materials of construction (e.g., ASME material specifications) of the other subject welds and adjacent components (nozzles and pipes) in Tables RR-03.1 and RR-03.2 of the relief request.

(b) 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.

RAI No. 2 Discuss any factors or other measures that could ensure or monitor the structural integrity of the subject welds, given that certain volume of the subject welds could not be examined. The other measures may include the reactor coolant system leakage detection systems, routine system leakage tests in accordance with IWA/B-5000 of the ASME Code,Section XI, boric acid monitoring programs, operator walkdowns, and any augmented examinations.

RAI No. 3 The submittal states that no recordable indications were identified during examination of the Category R-A and Category B-F components. Please confirm whether recordable indications were identified in any of the other subject welds.

RAI No. 4 The second paragraph of Applicable Code Requirements states The extent of examination requirement for Examination Category B-J, Item Numbers B9.11 and B9.21, per Table IWB-2500-1, requires a surface and volumetric examination of essentially 100% of the weld length. However, B9.21 only requires a surface examination method. Additionally, there does not seem to be any welds identified as B9.21 in the submittal. Please confirm whether any B9.21 welds were supposed to be included in the submittal.