ML101060331

Email from A. Sheikh, NRR to B. Lehman, NRR Et Al., CR3 Containment Crack

ML101060331
Person / Time
Site:	Crystal River
Issue date:	10/08/2009
From:	Sheikh A Division of License Renewal
To:	Ashar H, Rajender Auluck, Bryce Lehman Office of Nuclear Reactor Regulation
References
FOIA/PA-2010-0116
Download: ML101060331 (2)

Text

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From: Sheikh, Abdul Sent: Thursday, October 08, 2009 11:20 AM To: Lehman, Bryce; Auluck, Rajender; Ashar, Hansraj Cc: Kuntz, Robert

Subject:

RE: CR3 Containment Crack Please wait for a day or two. I understand that Hans is attending a meeting with the NRC chairman right now.

In addition, I understand there are other events taking place.

From: Lehman, Bryce 1 *Q*

Sent: Thursday, October 08, 2009 10:18 AM To: Auluck, Rajender; Sheikh, Abdul; Ashar, Hansraj Cc: Kuntz, Robert

Subject:

CR3 Containment Crack Gentlemen, I have attached an existing CR-3 AMR RAI which has not yet been issued. I added a subpart to the question (in red) that attempts to address the recent operating experience. Please let me know if you think this should be added to the RAI before it is sent out, or if we should wait and issue an entire RAI focused on the crack issue.

Thanks, Bryce Lehman 0-11F10 (301) 415-1626 Brvce.LehmanO.nrc.aov 1

Draft RAI 3.5.2.2.1.4-1 (BF77, B. Lehman, Draft RAI 3.5.2.2.1.4-1)

Background

GALL Report item Il.A2-9 states that corrosion is not significant for inaccessible areas of steel containments (embedded containment steel shell or liner) if the four conditions are satisfied.

One of the conditions is the concrete is monitored to ensure that it is free of penetrating cracks that provide a path for water seepage to the surface of the containment shell or liner.

Issue:

LRA Section 3.5.2.2.1.4 does not discuss whether or not the concrete is monitored for penetrating cracks.

Request:

1. Explain if the concrete is monitored for penetrating cracks, and if so which program monitors the program.

2. Discuss plant specific operating experience with cracks in the concrete covering the inaccessible areas of the containment liner. Address the recent crack discovered during hydro-demolition associated with the steam generator replacement.

3. If no program exists to monitor the concrete, please provide the further evaluation of this aging effect, as recommended by the GALL Report and SRP-LR Section 3.5.2.2.1.4.