ML102090683
| ML102090683 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 07/28/2010 |
| From: | Geoffrey Miller Plant Licensing Branch 1 |
| To: | Chernoff H Plant Licensing Branch 1 |
| Miller G, NRR/DORL/LPL1-2, 415-2481 | |
| References | |
| TAC ME3623 | |
| Download: ML102090683 (3) | |
Text
July 28, 2010 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:
G. Edward Miller, Project Manager /ra/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
SEABROOK STATION, UNIT NO. 1 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST FOR ALTERNATE DEPTH SIZING QUALIFICATION (TAC NO. ME3623)
The attached draft request for additional information (RAI) was provided via electronic transmission on July 28, 2010 to Mr. Michael OKeefe, at NextEra Energy Seabrook, LLC (NextEra). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call with NextEra in order to clarify the licensees relief request dated March 25, 2010 (Agencywide Documents Access and Management System Accession No. ML100890436), regarding use of an alternate depth sizing qualification. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow NextEra to evaluate and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.
Docket Nos. 50-443
Enclosure:
As stated
- Via E-mail LPL1-2/PM CPNB/BC NAME GEMiller TLupold*
DATE 7/28/10 7/28/10
Enclosure DRAFT REQUEST FOR ADDITIONAL INFORMATION SEABROOK STATION, UNIT NO. 1 LICENSE AMENDMENT REQUEST OPERATIONS MANAGER QUALIFICATION REQUIREMENTS DOCKET NO. 50-443 By letter dated March 25, 2010 (Agencywide Document Access and Management System Accession No. ML100890436), NextEra Energy Seabrook, LLC requested approval to use an alternate depth sizing qualification for volumetric examinations of the reactor pressure vessel nozzle-to-safe end dissimilar metal welds from the inside surface for the Seabrook Station, Unit No. 1. To complete its review, the Nuclear Regulatory Commission Staff needs the following information:
- 1. The submittal states that as an alternative to the required RMS error stated in paragraph 3.3(c) of Code Case N-695, NextEra will add the difference between the required RMS error of 0.125 inch and the actual RMS error value achieved by our chosen inspection vendor, up to a maximum achieved value of 0.224-inches, to the flaw depth as determined during flaw sizing. Please discuss the acceptance criteria that will be applied in the event that an indication is detected that requires depth sizing, considering that the ASME Code 2007 Edition with 2009 Addenda no longer permits the use of IWB-3514 for PWRs with nickel alloy welds that are susceptible to PWSCC for planar, surface-connected flaws that are in contact with the reactor coolant environment during normal operation. Additionally, MPR-139, Section 7, Evaluation Methodologies, specifies that any flaw attributed to PWSCC, regardless of depth, will be evaluated even if it meets the IWB-3500 requirements.
- 2. Please provide an item number for the welds included in this submittal.