ML14181B401
| ML14181B401 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/24/2014 |
| From: | Beltz T Plant Licensing Branch III |
| To: | Millen M Point Beach |
| References | |
| MF3304 | |
| Download: ML14181B401 (4) | |
Text
NRR-PMDAPEm Resource From: Beltz, Terry Sent: Tuesday, June 24, 2014 10:49 AM To: Millen, Michael (Michael.Millen@nexteraenergy.com)
Cc: 'Clark, Roger'; 'harv.hanneman@nexteraenergy.com'; Carlson, Robert; Audrain, Margaret
Subject:
Point Beach Nuclear Plant, Unit 2 - Draft Requests for Additional Information (EPNB)
Regarding Relief Request 2-RR-7 (TAC No. MF3304)
Attachments: Point Beach, Unit 2 - Draft RAIs Regarding 2-RR-7 (TAC No. MF3304).docx
Dear Mr. Millen:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated December 27, 2013 (Agencywide Documents Access and Management System Accession No. ML13365A310), NextEra Energy Point Beach, LLC (NextEra) submitted relief request 2-RR-7 for NRC staff review. The request is associated with the re-categorization of four steam generator nozzle to safe-end dissimilar metal welds installed at Unit 2 of the Point Beach Nuclear Plant (PBNP) under the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Code Case N-770-1, with conditions specified in Title 10 of the Code of Federal Regulations, Part 50 (10 CFR 50), paragraph 55a(g)(6)(ii)(F). NextEra states that the proposed alternative categorization for the Unit 2 steam generator nozzle dissimilar metal welds (inlet and outlet) will be a permanent change to the PBNP Inservice Inspection Program for the duration of the extended license.
The NRC staff in the Component Performance, NDE, and Testing Branch of the Office of Nuclear Reactor Regulation has identified areas where additional information is needed to complete its review. The draft requests for additional information (RAI) are provided as an attachment to this e-mail.
You may accept the draft RAIs as formal Requests for Additional Information and provide a response by July 25, 2014. Alternatively, you may request to discuss the contents of this draft RAI with the NRC staff in a conference call, including any change to the proposed response date.
Please let me know if you have any questions or concerns.
Sincerely, TERRY A. BELTZ, SENIOR PROJECT MANAGER U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Mail Stop: O-8D15 1
Hearing Identifier: NRR_PMDA Email Number: 1408 Mail Envelope Properties (Terry.Beltz@nrc.gov20140624104900)
Subject:
Point Beach Nuclear Plant, Unit 2 - Draft Requests for Additional Information (EPNB) Regarding Relief Request 2-RR-7 (TAC No. MF3304)
Sent Date: 6/24/2014 10:49:23 AM Received Date: 6/24/2014 10:49:00 AM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov Recipients:
"'Clark, Roger'" <Roger.Clark@nexteraenergy.com>
Tracking Status: None
"'harv.hanneman@nexteraenergy.com'" <harv.hanneman@nexteraenergy.com>
Tracking Status: None "Carlson, Robert" <Robert.Carlson@nrc.gov>
Tracking Status: None "Audrain, Margaret" <Margaret.Audrain@nrc.gov>
Tracking Status: None "Millen, Michael (Michael.Millen@nexteraenergy.com)" <Michael.Millen@nexteraenergy.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 1792 6/24/2014 10:49:00 AM Point Beach, Unit 2 - Draft RAIs Regarding 2-RR-7 (TAC No. MF3304).docx 34987 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST 2-RR-7 POINT BEACH NUCLEAR PLANT, UNIT 2 NEXTERA ENERGY POINT BEACH, LLC DOCKET NO. 50-301 By letter dated December 27, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML13365A310), NextEra Energy Point Beach, LLC (NextEra) submitted for the U.S. Nuclear Regulatory Commission (NRC) staff review and approval Relief Request 2-RR-7, which requests authorization for re-categorization of primary Steam Generator (SG) nozzle to safe-end welds under the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code (Code), Code Case N-770-1, with conditions specified in Title 10 of the Code of Federal Regulations, Part 50 (10 CFR 50), paragraph 55a(g)(6)(ii)(F), for duration of the extended license at the Point Beach Nuclear Plant (Point Beach), Unit 2.
To complete its review, the NRC staff requests the following additional information:
- 1. On page two of the December 27, 2013, submittal, NextEra states that one of the SG safe-end to inlet nozzle welds will be examined in approximately 2022, but do not mention the examination of the outlet nozzle to safe end welds. Under 10 CFR 50.55a(g)(6)(ii)(F)(5), all hot-leg operating temperature welds in Inspection Items G, H, J, and K must be inspected each interval. A 25-percent sample of Inspection Items G, H, J and K cold-leg operating temperature welds must be inspected whenever the core barrel is removed (unless it has already been inspected within the past 10 years) or 20 years, whichever is less.
Given this requirement, please identify your future inspection plans and, if a proposed alternative is requested, provide justification for the change from the current regulatory requirements.
- 2. Were any indications detected during the pre-inlay installation examination of the Alloy 82/182 weld? If so, discuss whether the indication was removed in its entirety prior to the inlay installation or discuss the flaw size that remained in the alloy 82/182 weld.
Please discuss whether the remaining indication was accepted by the ASME Code,Section XI, Table IWB-3410-1. If not, discuss whether the remaining indication was evaluated in accordance with IWB-3600.
- 3. The industry operating experience of UT of Alloy 82/182 welds in hot leg nozzles and weld overlaid pressurizer nozzles has shown that the conventional UT has missed detecting indications.
Please discuss whether the future inspections of the subject weld(s) at Point Beach, Unit 2, will include the latest industry guidance on UT of Alloy 82/182 welds.
- 4. In the August 12, 2011, Public Meeting Summary (ADAMS Accession Number ML112240818), the NRC staff provided guidance on requesting re-categorization of mitigated welds (see question/answer #24). Several of the topics to be addressed are not included in your submittal.
Please provide the following information with regard to the inlay installed at the SG nozzles, or alternatively provide a technical justification for not doing so:
- a. Repairs performed on the Alloy 82/182 weld prior to the inlay installation and on the inlay during inlay installation and any fillers materials used;
- b. Methods used to identify the dissimilar metal weld fusion zones and the accuracy of the methods used;
- c. Qualifications of the weld procedure specifications, welders and welding operators;
- d. Pre- and post-weld heat treatment or temper bead welding requirements followed;
- e. Design and analysis requirements used, in detail;
- f. Preservice and inservice inspections performed since installation of the inlays/onlays;
- g. ASME Code Editions and Addenda associated with requirements used, where applicable, and figures, as applicable, to assist in describing the information submitted in conjunction with the request for alternative categorization;
- h. Thickness of inlay/onlay;
- i. Flaw evaluation to show adequate thickness against stress corrosion cracking.