ML13014A570
| ML13014A570 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/05/2013 |
| From: | John Lamb Plant Licensing Branch 1 |
| To: | Pacilio M Exelon Nuclear, Exelon Generation Co |
| Lamb J NRR/DORl/LPL1-2 301-415-3100 | |
| References | |
| TAC ME9490 | |
| Download: ML13014A570 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 5, 2013 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST FOR THE FIFTH 10-YEAR INTERVAL INSERVICE INSPECTION REGARDING RELIEF NO. 15R-01 (TAC NO. ME9490)
Dear Mr. Pacilio:
By letter dated August 28,2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12243A287), Exelon Generation Company, LLC (Exelon),
submitted Relief Request 15R-01 for Oyster Creek Nuclear Generating Station (Oyster Creek).
Relief Request 15R-01 proposes to use BOiling-Water Reactor Vessel and Internals Project guidelines as an alternative to certain requirements of Section XI of the American SOciety of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for the Oyster Creek fifth 10-year inservice inspection (lSI) of reactor vessel internal (RVI) components.
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. The draft questions were sent via email onJanuary14.2013(ADAMSAccessionNo.ML13015A501). to Mr. David Helker of your staff, to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. During a discussion with Mr. Thomas Loomis of your staff on January 31, 2013, it was agreed that you would provide a response 40 days from the date of this letter.
Please note that if you do not respond to this letter by the agreed-upon date or provide an acceptable alternate date in writing, the NRC may reject your request for relief under the provisions of 10 CFR 2.108, "Denial of application for failure to supply information."
M. Pacilio
- 2 If you have any questions regarding this letter, please feel "free to contact me at (301) 415-3100.
. Lamb, Senior Project Manager Pia Licensing Branch 1-2 Divi ion of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-219
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUEST FOR THE FIFTH 10-YEAR INTERVAL INSERVICE INSPECTION FOR RELIEF NO. 15R-01 OYSTER CREEK NUCLEAR GENERATING STATION EXELON GENERATING COMPANY, LLC DOCKET NO. 50-219 By letter dated August 28, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12243A287), Exelon Generation Company, LLC (Exelon),
submitted Relief Request 15R-01 for Oyster Creek Nuclear Generating Station (Oyster Creek).
Relief Request 15R-01 proposes to use BOiling-Water Reactor Vessel and Internals Project (BWRVIP) guidelines as an alternative to certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for the Oyster Creek fifth 10-year inservice inspection (lSI) of reactor vessel internal (RVI) components.
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed below.
REQUEST FOR ADDITIONAL INFORMATION (1)
In Table 1 of the submittal dated August 28,2012, the licensee did not provide inspection criteria for the shroud support leg weld (H 12) which requires inspection per the requirements specified in the staff's safety evaluation (SE) for the BWRVIP-38 report, BWR Vessel Internal Project, BWR Shroud Support Inspection and Flaw Evaluation Guidelines. However, the staff's final SE for the BWRVIP-38 report (ADAMS Accession No. ML003735498) indicates that when inspection tooling and methodologies are developed that allow the welds in the lower plenum to be accessible, the guidelines will state that the licensee will inspect these welds with the appropriate nondestructive examination methods in order to establish a baseline for these welds. Consistent with these requirements, the NRC staff, therefore, requests that the licensee revise Table 1, Page 8 of 32, of the submittal dated August 28, 2012, to include a commitment that the shroud support leg weld H 12 will be inspected when the inspection tooling and methodologies permit such an inspection.
(2)
The NRC staff requests that the licensee include a reference to BWRVIP-25, "BWR Core Plate Inspection and Flaw Evaluation Guidelines," in the row deSignated as ASME Item B 13.10 in Table 1, of Page 2 of 32, of the submittal dated August 28, 2012.
Enclosure
- 2 (3)
The staff requests that the licensee identify the welds that were made with Alloy 182 weld electrode in Oyster Creek RVI components. Since Alloy 182 welds are prone to intergranular stress-corrosion cracking, the licensee is requested to provide the history of inspections and the results of these inspections of these welds, and subsequent examination criteria if cracking was found in these welds.
ML13014A570 Sincerely, IRA!
John G. Lamb, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- via email OFFICE LPL 1-2/PM LPL1-2/LA EVIB/BC LPL1-2/BC LPL 1-2/PM NAME JLamb ABaxter SRosenberg*
MKhanna JLamb DATE 01/31/13 01/29/13 01/14/13 02/04/13 02/05/13