ML11361A481
| ML11361A481 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/08/2011 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| Download: ML11361A481 (3) | |
Text
1 Davis-BesseNPEm Resource From:
CuadradoDeJesus, Samuel Sent:
Friday, July 08, 2011 11:21 AM To:
custerc@firstenergycorp.com
Subject:
RE: FW: Davis Besse Question Yes its going to be a long teleconference. Ill send you the order in which well proceed. Well start with the easier ones first.
From: custerc@firstenergycorp.com [1]
Sent: Friday, July 08, 2011 9:29 AM To: CuadradoDeJesus, Samuel Cc: lhinkle@firstenergycorp.com; kmnesser@firstenergycorp.com; dorts@firstenergycorp.com; dckosloff@firstenergycorp.com; almcallister@firstenergycorp.com
Subject:
Re: FW: Davis Besse Question Sam, We can discuss this issue also on the Tuesday afternoon telecom. As this telecom may be lengthy in nature, please give me a list of the order in which you would like to proceed. This will minimize the time your reviewers and the DB site subject matter experts will be tied up with the call.
Cliff Custer FENOC Project Manager License Renewal Work: (724) 682-7139 BPR: (412) 305-4981 From: "CuadradoDeJesus, Samuel" <Samuel.CuadradoDeJesus@nrc.gov>
To: "custerc@firstenergycorp.com" <custerc@firstenergycorp.com>, "'dorts@firstenergycorp.com'" <dorts@firstenergycorp.com>
Date: 07/07/2011 04:31 PM
Subject:
FW: Davis Besse Question Another issue well like to discuss in a Teleconference. There are many issues to be discussed next week and Ill try to schedule only two meetings to address all of them. I know Tuesday and Wednesday are good for you so Ill send a meeting requests soon.
From: Hunt, Christopher Sent: Thursday, July 07, 2011 1:08 PM To: CuadradoDeJesus, Samuel Cc: Karwoski, Kenneth; Obodoako, Aloysius; Murphy, Emmett
Subject:
Davis Besse Question Sam, Our question is as follows:
During a public meeting on February 18, 2011, industry Steam Generator Task Force representatives indicated that primary side fouling of steam generator tubes is not an issue in the United States (refer to the meeting summary in ADAMS under accession number ML110670317). In the applicants license renewal application, reduction of heat transfer of the steam generator tubes in a borated reactor coolant environment is addressed as an aging mechanism.
Has there been any information gained by the industry since the February 18, 2011 meeting that would suggest that
2 primary side loss of heat transfer has become an issue? If there is additional information, please provide it. If not, discuss your plans to withdraw the aging management review line item that deals with reduction in heat transfer of nickel alloy tubing and sleeves in a borated reactor coolant environment.
Respectfully, Christopher Hunt DCI/CSGB Office Phone: 415-1652 M/S: O-9H06
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Hearing Identifier:
Davis_BesseLicenseRenewal_Saf_NonPublic Email Number:
2876 Mail Envelope Properties (Samuel.CuadradoDeJesus@nrc.gov20110708112000)
Subject:
RE: FW: Davis Besse Question Sent Date:
7/8/2011 11:20:31 AM Received Date:
7/8/2011 11:20:00 AM From:
CuadradoDeJesus, Samuel Created By:
Samuel.CuadradoDeJesus@nrc.gov Recipients:
"custerc@firstenergycorp.com" <custerc@firstenergycorp.com>
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