ML122550438
| ML122550438 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/11/2012 |
| From: | Boska J Plant Licensing Branch II |
| To: | Alter K Duke Energy Carolinas |
| Boska J, NRR, DORL, 301-415-2901 | |
| References | |
| TAC ME8435 | |
| Download: ML122550438 (1) | |
Text
From:
Boska, John Sent:
Tuesday, September 11, 2012 3:08 PM To:
Alter, Kent R Cc:
'Gray, Corey A'; Meixell, Bob
Subject:
Oconee Unit 2, NRC Request for Additional Information on Steam Generator Tube Inspection Report, ME8435 Importance:
High By letter dated February 29, 2011Property "Letter" (as page type) with input value "05000259/LER-1980-009, Has Been CancelledUnable to interpret the "February 29, 2011" input value as valid date or time component with "Month 2 in year 2011 did not have 29 days in this calendar model." being reported." contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process. (Agencywide Documents Access and Management System Accession No. ML12066A243), Duke Energy Carolinas, LLC (the licensee), submitted the results of the steam generator tube inspections done in 2011 for Oconee Nuclear Station, Unit 2 (ONS 2). The report was submitted in accordance with Technical Specification (TS) 5.6.8.
The NRC staff has reviewed the information submitted by the licensee, and determined that the following information is required to complete our evaluation. The questions are found below. On September 10, 2012, the Duke staff indicated that a response to this request for additional information would be provided within 45 days of the date of this email.
REQUEST FOR ADDITIONAL INFORMATION:
- 1. Please clarify the results of your steam generator tube plug inspections.
- 2. Please clarify which tubes were plugged.
- 3. Please provide the effective full power years that the steam generators have operated for the last several outages.
- 4. In your condition monitoring assessment, you assess structural integrity against a limit associated with burst at three times the normal operating differential pressure. Please confirm that this limit is more limiting than the limit associated with a large break loss of coolant accident for both single and multiple sided wear indications.
John Boska Oconee Project Manager, NRR/DORL U.S. Nuclear Regulatory Commission 301-415-2901 email: john.boska@nrc.gov