ML11293A381

Lr - Request for a Teleconference with DB Next Week

ML11293A381
Person / Time
Site:	Davis Besse
Issue date:	09/02/2011
From:	Office of Nuclear Reactor Regulation
To:	Division of License Renewal
References
Download: ML11293A381 (3)

Text

Davis-BesseNPEm Resource From: CuadradoDeJesus, Samuel Sent: Friday, September 02, 2011 3:45 PM To: custerc@firstenergycorp.com Cc: dorts@firstenergycorp.com; Davis-BesseHearingFile Resource

Subject:

Request for a teleconference with DB next week Importance: High Cliff:

Please let me know when can we have a teleconference to discuss the following issues:

LRA Table 3.3.2-14 items missing (8/26/11 Response letter)

On page 4 of 36 of the enclosure, DB stated that all of LRA Table 3.3.2-14 was replaced with the table in the enclosure. However, the original table 3.3.2-14 had 2 sections, the first part was for the fire protection system (rows 1-153) and the second part was for the fire pump diesel engine (rows 154-224). The replacement table in the 8/26/11 letter only has 174 items. I did a line by line comparison, and it appears that all the items from the original fire pump diesel engine section are missing. There was no text in the RAI response discussing why the items would have been deleted.

One Time Inspection EVT-1 (8/26/11 Response letter)

DB states on p 16 of the attachment and on pages 30 and 34 of the enclosure that they are going to manage cracking due to cyclic loading of the stainless steel high-pressure makeup pumps (DB-P37-1 and 2) in the Makeup and Purification System using enhanced visual (VT-1 or equivalent) and/or volumetric (RT or UT) inspections. However, the designation for enhance visual exam is EVT-1. DB used the term EVT-1 correctly in the table on p 35 of the enclosure when revising the detection of aging effects element of the AMP, but used the wrong designation in the commitment and scope program element. It is an important distinction to make, because a VT-1 exam may not be adequate to detect cracking.

RAI 4.1-2 regarding Code Case N-481 (8/17/2011 response letter)

In its response dated Aug 17, 2011, the applicant stated that the fracture toughness of the cast austenitic stainless steel is not time dependent as the analysis used a lower bound fracture toughness of 139 ksiin that bounds the saturated fracture toughness of the Davis-Besse material. The staff concern is that the applicants basis may be predicated on charpy or thermal aging data that are not up to date or conservative when compared to the most recent data for the state of the industry.

It is not clear to the staff whether the assumption that the lower bound fracture toughness of 139 and bounds the saturated fracture toughness of the applicants materials remains valid.

Thanks Samuel Cuadrado de Jesús 1

Project Manager Projects Branch1 Division of License Renewal U.S. Nuclear Regulatory Commission Phone: 301-415-2946 Samuel.CuadradoDeJesus@nrc.gov 2

Hearing Identifier: Davis_BesseLicenseRenewal_Saf_NonPublic Email Number: 1419 Mail Envelope Properties (377CB97DD54F0F4FAAC7E9FD88BCA6D0804F9AA29B)

Subject:

Request for a teleconference with DB next week Sent Date: 9/2/2011 3:45:06 PM Received Date: 9/2/2011 3:45:08 PM From: CuadradoDeJesus, Samuel Created By: Samuel.CuadradoDeJesus@nrc.gov Recipients:

"dorts@firstenergycorp.com" <dorts@firstenergycorp.com>

Tracking Status: None "Davis-BesseHearingFile Resource" <Davis-BesseHearingFile.Resource@nrc.gov>

Tracking Status: None "custerc@firstenergycorp.com" <custerc@firstenergycorp.com>

Tracking Status: None Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 2617 9/2/2011 3:45:08 PM Options Priority: High Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received: