ML12037A225

E-mail from M. Khanna, NRR to E. Benner, NMSS; FW: Ulpdate: North Anna ISFSI

ML12037A225
Person / Time
Site:	North Anna
Issue date:	08/29/2011
From:	Meena Khanna Office of Nuclear Reactor Regulation
To:	Benner E J Office of Nuclear Material Safety and Safeguards
References
FOIA/PA-2011-0357
Download: ML12037A225 (2)

Text

DE FOIA Resource From: Khanna, Meena .- NJ\Sent: Monday, August 29, 2011 5:07 PM To: Benner, Eric Cc: Li, Yong

Subject:

FW: Update: North Anna ISFSI fyi From: Munday, Joel To: Franke, Mark; Croteau, Rick; Jones, William Sent:Mon Aug 29 16:15:02 2011

Subject:

FW: Update: North Anna ISFSI FYI From: Rivera-Ortiz, Joel \\L.\ \Sent: Monday, August 29, 2011 4:11 PM To: Benner, Eric; Waters, Michael Cc: McCoy, Gerald; Ninh, Son; Munday, Joel; Christensen, Harold; Carrion, Robert

Subject:

Update: North Anna ISFSI Michael/Eric, We had a phone call with the ISFSI points of contact at North Anna to gather information on the current status of the ISFSI. There is not a lot of new information available; here is a summary of our call: ISFSI Pad 1 -The licensee conducted a walk-down on 08/24 and identified the following:

1) There are 27 TN-32 casks. Twenty five of the 27 casks moved as a result of the earthquake; some of them moved up to 4.5 inches.2) No changes in radiological conditions

3) No damage to the pressure monitors in each cask 4) No pressure monitoring system alarms during and after the earthquake

5) No damage to the cables connected to the ground and the casks 6) No crack indications observed in the concrete pad or casks 7) Six casks sets (12 casks total) do not meet the 16ft separation required by design for decay heat loads greater than 27.1 kW. Three of the 12 casks exceeded the 27.1 kW heat load when initially loaded a couple of years ago. The licensee will determine the current decay heat load for each cask.8) No loss of power experienced during or after the earthquake

9) No damage to the ISFSI Diesel Generators

10) More detailed inspections are being performed at the moment, including vendor involvement.

ISFSI Pad 2 (NUHOMS CoC-1030, A0 and Al) -The licensee conducted a walk-down on 08/24 and identified the following:

1) There are 13 horizontal modules on Pad 2. Three out of the 13 modules meet CoC-1030, Amendment 0 and the rest meet Amendment 1.2) No changes in radiological conditions

3) No abnormal indications in thermal performance

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4) Some damage identified around the outlet vents. The licensee determined this had no impact on shielding and structural integrity 5) Some surface cracking indications were noted. The licensee characterized these as "cosmetic" in nature and potentially historical.

The licensee will review past inspection records from Operations to confirm the presence of the cracks prior to the event.6) Some modules showed gaps between them of approximately 1.5" versus the required 1.0" gap.7) No loss of power experienced during or after the earthquake

8) More detailed inspections are being performed at the moment, including vendor involvement.

Additional Notes: 1) The licensee is following RG 1.166, "Pre-Earthquake Planning And Immediate Nuclear Power Plant Operator Post-Earthquake Actions" as a guide to perform their post-event assessment.

2) Determination of the ground acceleration at the ISFSI pad location is still in process.3) An AIT has been officially launched for the event. One of the items in the scope of the AIT Charter is to assess the extent of the damage to the ISFSI.Thanks, JOEL E. RIVERA-ORTIZ, PE Acting Chief, Engineering Branch 3 US Nuclear Regulatory Commission Region II, Division of Reactor Safety, Branch 3 245 Peachtree Center Ave. NE, Suite 1200 Atlanta, GA 30303 Tel. (404) 997-4825 E-Mail: Toel.Rivera-Ortiz(a?)nrc.zov 2