ML12052A273
| ML12052A273 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/13/2011 |
| From: | Martin R Office of Nuclear Reactor Regulation |
| To: | Mark Franke, Gregory Kolcum, Gerald Mccoy NRC/RGN-II |
| References | |
| FOIA/PA-2011-0357 | |
| Download: ML12052A273 (1) | |
Text
Boyle, Patrick From:
Martin, Robert Sent:
Tuesday, September 13, 2011 7:59 AM To:
McCoy, Gerald; Kolcum, Gregory; Franke, Mark Cc:
Kulesa, Gloria; Boyle, Patrick; Ulses, Anthony; Parks, Benjamin; Khanna, Meena
Subject:
Reactor Systems North Anna Questions We are preparing questions to send to Dominion. Which of the following Reactor Systems branch questions do you regard as being within Region 11"s scope - either as covered by the AIT or other Regional actions?
Even if within the Region's scope and NRR/Reactor Systems has the Q, how should we proceed with getting the answer? Region II to provide the answer or should we ask it of Dominion anyway?
From: Mendiola, Anthony Sent: Monday, September 12, 2011 3:18 PM To: Martin, Robert
Subject:
FW: North Anna Questions Fyi...
From: Parks, Benjamin Sent: Monday, September 12, 2011 12:56 PM To: Mendiola, Anthony; Miranda, Samuel
Subject:
FW: North Anna Questions These were sent for Tony's consideration. --bp
- 1.
How has the licensee evaluated, inspected, or analyzed the steam generators to ensure SG tube integrity?
What further work is planned in this area?
- 2.
What assurances does the licensee have that system pressure relief capabilities are maintained?
- 3.
How will licensee ensure overall RCS pressure boundary integrity? What have the licensee's observations been so far?
- 4.
How has the licensee inspected, examined, and evaluated the ECCS? How does the licensee know it will still perform as intended? Can it continue to perform its ECCS functions under simultaneous design basis earthquake loading per the ECCS design basis seismic requirements?
- 5.
Were there any complications in residual heat removal following the earthquake? Did all RHR equipment perform as intended?
- 6.
How has the licensee assessed the reactor trip system, including its actuation circuitry and its mechanical components? How will the licensee ensure the RCCAs and the guide tubes retain their required functionality?
Benjamin T. Parks Reactor Systems Branch, NRR O1O-D2 415-6472 1ý