ML101060326
| ML101060326 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/26/2009 |
| From: | Robert Kuntz License Renewal Projects Branch 2 |
| To: | Maurice Heath Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2010-0116 | |
| Download: ML101060326 (4) | |
Text
Ths Kuntz, Robert
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From:
Sent:
To:
Subject:
Attachments:
Kuntz, Robert V'U' Monday, October 26, 2009 2:48 PM Heath, Mike DRAFT Request for information.
Containment Delamination RAIl.doc
- Mike, Attached is a DRAFT request for information realted to the recent operating experience at CR-3 related to the CR-3 LRA. If you would like clarification on the attached please let me know and we will schedule a teleconference.
Robert Kuntz Sr. Project Manager NRR/ADRO/DLR/RPB2 (301) 415-3733 robert.kuntz@nrc.gov I
Mr. Jon Franke, Vice President Crystal River Nuclear Plant (NA1 B)
ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE
--A*
CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING\\PLANT, LICENSE RENEWAL APPLICATION (TAC NO. ME0274p)
Dear Mr. Franke:
By letter dated December 16, 2008, Florida Power Corporation submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating license Crystal River Unit 3 Nuclear Generating Plant (CR-3),for review by the U.S. Nuclear Regulatory Commission (NRC or the staff).
By letter dated October 13, 2009 FloriaPower Corporation indicated that a root cause is currently in progress related to the discovery of a gap in the concrete of the outer radius of the containment structure, and that it would evaluate the need to revise any of the technical responses to the NRC request for additional information (RAI). Enclosed is an RAI related to this recent discovery and how it may affect the aging management of the structure. The response to this req uestayibe dependent on results of the root cause analysis. Therefore, a response to this letter irquested bJanuary 15, 2010. If you have any questions, please contact me at 301-45,3 733 or by e9tail robert.kuntz(anrc.qov.
Robert F. Kuntz, Sr. Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosure:
As stated cc w/encl: See next page
(OFFICE PM:RPB2:DLR LA:DLR BC:RPB2:DLR PM:RPB2:DLR NAME RKuntz DWrona RKuntz DATE
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A L REQUEST FOR ADDITIONAL INFORMATION LICENSE RENEWAL APPLICATION FOR CRYSTAL RIVER UNIT 3 DOCKET NO: 50-302 (TAC NO. ME0274)
RAI B.2.25-4
Background:
In order to perform a scheduled steam generator replacement, 10 vertical and 17 horizontal containment pre-stressing tendons were de-tensioned in preparation for hydro-demolition of a containment section.
Issue:
During hydro-demolition of the containment concrete, a crack was identified in the concrete near the horizontal tendons, approximately nine inches from the Outer surface of the containment, on all four sides of the temporary opening. In addition, duhnng hydro-demolition water leaked out of the containment concrete at several pa1es some distance away from the edge of the temporary opening.
Request:
- 1. Explain how the recent pat-specific operating experience will be incorporated into the ASME SectionX
- ,SubsectionIWL and Subsection IWE AMPs, and whether a plant-specific program is necessar tlo manage aging of the containment. Include the containment concrete, pre-,stre~ssing tendos,\\and the containment liner plate in the discussion.
- 2. Identify andexpl=an any changes to the license renewal application based on the recent specific li ENCLOSURE