ML13015A501

E-mail January 15, 2013 - Draft RAI Regarding Oyster Creek Nuclear Generating Station RR I5R-01

ML13015A501
Person / Time
Site:	Oyster Creek
Issue date:	01/14/2013
From:	John Lamb Plant Licensing Branch 1
To:	David Helker Exelon Corp
Lamb J NRR/DORL/LPL1-2 301-415-3100
References
Download: ML13015A501 (2)

Text

From: Lamb, John To: "david.helker@exeloncorp.com" Cc: Richard.Gropp@exeloncorp.com; thomas.loomis@exeloncorp.com; Hughey, John; Khanna, Meena; McLellan, Thomas

Subject:

For Your Review - DRAFT RAI - Oyster Creek RR I5R-01 Date: Monday, January 14, 2013 12:24:00 PM Importance: High

Dave, Below, for your review, is a draft RAI regarding Oyster Creek Relief Request I5R-01.

Please review to ensure that the questions are understandable, the regulatory basis is clear, there is no proprietary information contained in the RAI, and to determine if the information was previously docketed. Please also let me know if Exelon wishes a conference call to clarify the questions and how much time Exelon needs to respond to the RAI.

The NRC staff does not have any RAIs for Request for Relief Nos. I5R-02, I5R-05, I5R-06, and I5R-07 in your letter dated August 28, 2012.

Thanks.

John DRAFT RAI By letter dated August 28, 2012, Exelon Generation (the licensee), (Agencywide Documents Access and Management System (ADAMS), Accession No. ML12243A287),

proposed 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 in-service inspection (ISI) of reactor vessel internal (RVI) components.

The NRC staff has reviewed the information the licensee provided in Request for Relief (RR) I5R-01 that supports the proposed relief request and has the following questions:

(1) The NRC staff requests that the licensee identify whether there are any furnace-sensitized stainless steel vessel attachment welds associated with the RVI components in Oyster Creek. It is requested that the licensee provide an explanation regarding the type of inspection program and any additional augmented inspection program that are implemented for any existing furnace-sensitized stainless steel attachment welds in Oyster Creek.

(2) The NRC staff requests that the licensee include the following BWRVIP reports in Section 5.0 of RRI5R- 01 contained in the licensees submittal dated August 28, 2012.

BWRVIP-139, BWR Vessel Internals Project, Steam Dryer Inspection and Flaw Evaluation Guidelines.

(3) The NRC staff requests that the licensee confirm whether NUREG-0619, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking, will be used for the

inspection of feedwater sparger tee welds and feedwater sparger piping brackets. If not, provide alternative methods for inspecting these components.

(4) In Table 1 of the submittal dated August 28, 2012, the licensee did not provide inspection criteria for the shroud support leg weld (H12) which requires inspection per the requirements specified in the staffs SE for the BWRVIP-38 report, BWR Vessel Internal Project, BWR ShroudSupport Inspection and Flaw Evaluation Guidelines. However, the staffs final SE for theBWRVIP-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 NDE 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 H12 will be inspected when the inspection tooling and methodologies permit such an inspection.

(5) The NRC staff requests that the licensee shall include a reference to BWRVIP-25, "BWR Core Plate Inspection and Flaw Evaluation Guidelines," in the row designated as ASME item B13.10 in Table 1 of Page 2 of 32 of the submittal dated August 28, 2012.

(6) Identify the welds that were made with Alloy182 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