ML092160597

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Update on Status of 11/18/08 Request for Additional Information & Additional Testing Pursuant to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
ML092160597
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 07/28/2009
From: Brandi Hamilton
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GL-04-002
Download: ML092160597 (2)


Text

Duke BRUCE H HAMILTON Ener Vice President PcEWIry McGuire Nuclear Station Duke Energy Corporation MG01 VP / 12700 Hagers Ferry Road Huntersville, NC 28078 704-875-5333 704-875-4809 fax bhhamilton@duke-energy. corn July 28, 2009 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001

Subject:

Duke Energy Carolinas, LLC (Duke)

McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 Update on the Status of the November 18, 2008 Request for Additional Information (RAI) and Additional Testing for McGuire Units 1 and 2 Pursuant to NRC Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors" Pursuant to the November 18, 2008 RAI letter from the Nuclear Regulatory Commission (NRC) and the February 16, 2009 response from Duke, Duke is providing an update on its RAI response plan and confirmatory conventional debris head loss testing (subsequently referred to herein as "testing") progress.

Since February 2009, McGuire has continued to make progress on development of responses to the RAI questions using insights from teleconferences with the NRC. A teleconference was held on May 20, 2009 to discuss testing protocols.

A second teleconference was held on June 17, 2009 to discuss chemical effects.

The testing at Wyle Laboratories was completed on June 25, 2009. This testing incorporated the guidance of the document titled "NRC Staff Review Guidance Regarding Generic Letter 2004-02 Closure in the Area of Strainer Head Loss and Vortexing" dated March 2008, as well as, lessons learned from earlier testing and inputs from the NRC. The results from this testing are being finalized and will be incorporated into the RAI responses presently under development.

This testing modeled the current bounding fiber insulation configuration, assuming a 7D jacketed fiber Zone of Influence (ZOI) value as reported in the GL 2004-02 supplemental responses dated February 28, 2008 and April 30, 2008.

McGuire recognizes that some regulatory uncertainty remains in invoking the wWW. duke-energy. comr

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U. S. Nuclear Regulatory Commission July 28, 2009 Page 2 findings of WCAP-16710-P, "Jet Impingement Testing to Determine the ZOI of Min-K and NUKON Insulation for Wolf Creek and Callaway Nuclear Operating Plants." McGuire continues to participate with the industry in resolving these regulatory uncertainties. The RAI questions concerning this issue and others will be discussed with the NRC as described below.

On June 23, 2009, the NRC conducted a public meeting to provide the status and path forward on Generic Safety Issue (GSI) 191. Duke will follow the process of conducting telecoms with the NRC, as discussed in the June 2 3 rd meeting, prior to submitting the responses to the RAIs. Duke is currently working with the NRC Project Manager to plan these series of telecoms, including a follow-up to the June 17, 2009 teleconference associated with the subject of chemical effects.

Questions regarding this update should be directed to P. T. Vu at (980) 875-4302.

Very truly yours, Bruce H. Hamilton xc:

L. A. Reyes Regional Administrator, Region II U. S. Nuclear Regulatory Commission 61 Forsyth Street,. S.W., Suite 23T85 Atlanta, GA 30303-8931 J. H. Thompson (addressee only)

NRC Project Manager (MNS & CNS)

U. S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 08G9A Rockville, MD 20852-2738 J. B. Brady NRC Senior Resident Inspector McGuire Nuclear Station