ML031040105
| ML031040105 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/31/2003 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| FOIA/PA-2003-0018, GSI-191 LA-UR-02-0279 | |
| Download: ML031040105 (2) | |
Text
FES 0 4 2002 LA-UR-02-0279 AoPmvedibpubfcreease; distibugonkurnftfed Tile: GSI-191: THE IMPACT OF DEBRIS-INDUCED LOSS OF ECCS RECIRCULATION ON PWR CORE DAMAGE FREQUENCYE Author(s): John L Darby, Venkateswara (DV Rao) Dasari, Bruce Letellier, and Scott G. Ashbaugh, D-1 t Willard Thomas, ARES Mark T. Leonard, ITS Submitfed to: Programmatic Distribution Los Alamos NATIONAL LABORATORY G1 Los Amos National laftrator, an affirmative edai qiappor yempoye. Is kcperated byte UrveWryofCal oriaforthe U.S.
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Question from Public Meeting re Davis Besse [3' Response prepared by NRR Staff Generic Safety Issue (GSI) 191 focused on blockage of the containment sump screens during the recirculation phase of ECCS. Has Davis-Besse adequately addressed GSI-191 with respect to insulation surrounding the reactor vessel pressure head?
A: The potential for ECCS recirculation sump screen dogging has been confirmed to be a generic concern for pressurized-water reactors In a parametric research study performed for the NRC in support of GSI-191. However, the level of detail in this generalized parametric study was not sufficient to allow conclusive findings to be made regarding the susceptibilities of specific plants.
Therefore, although the particular type of Insulation (i.e., reflective metallic) used on Davis-Besse's reactor vessel head is generally shown In the parametric study to be relatively resistant to clogging sump screens, It is currently premature, due to a number of Important plant-specific factors, to speculate as to whether a rupture In Davis-Besse's reactor vessel head would have resulted in sump screen clogging. As part of the NRC's action plan for resoling GSI-191, the NRC is evaluating the need for plant-specific assessments to be performed to conclusively identify the susceptibility to recirculation sump screen dogging for each pressurized-water reactor. The NRC's current GSI-191 action plan is publicly available In the Director's Quarterly Status Report, dated February 7. 2002 (Accession number ML020150515).
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Davis Bessle Oplonion.wpd April 1, 2002