ML070520459

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E-mail, Miller, NRR, to Distel, Exelon, Oyster Creek AST
ML070520459
Person / Time
Site: Oyster Creek
Issue date: 02/09/2007
From: Geoffrey Miller
Plant Licensing Branch III-2
To: Distel D
Exelon Corp
References
TAC MC6519
Download: ML070520459 (3)


Text

From:

Ed Miller To:

david.distel@exeloncorp.com Date:

02/09/2007 3:36:25 PM

Subject:

Question from Telecon

Dave, Attached is a write up of the verbal question that Michelle had from the Telecon this morning.

G. Edward Miller Project Manager Division of Operating Reactor Licensing U.S. Nuclear Regulatory Commission (301) 415-2481

Mail Envelope Properties (45CCDB49.EC6 : 9 : 35080)

Subject:

Question from Telecon Creation Date 02/09/2007 3:36:25 PM From:

Ed Miller Created By:

GXM@nrc.gov Recipients Action Date & Time exeloncorp.com Transferred 02/09/2007 3:37:01 PM david.distel (david.distel@exeloncorp.com)

Post Office Delivered Route exeloncorp.com Files Size Date & Time MESSAGE 778 02/09/2007 3:36:24 PM TEXT.htm 558 OC RAI MSIV leakage source_1.wpd 8934 02/09/2007 11:51:37 AM Options Auto Delete:

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Delivered & Opened

RAI - MSIV Leakage Pathway Activity Modeling:

In looking at the responses to RAI Nos. 2 and 5, provided in licensee letters dated January 24 and February 2, 2007, and considering the potential dose impact of assumption made in the dose analysis, the staff has further questions about the modeling of aerosol and iodine removal in the main steam line piping.

With respect to the modeling of the MSIV leakage pathway, Appendix A to RG 1.183 states that the activity available for release via MSIV leakage should be assumed to be that activity determined to be in the drywell for evaluating containment leakage. The guidance intends to give a reasonable proxy for the radionuclide concentration in the steam that is flowing from the reactor vessel and/or from the drywell, depending on the location of the break that is assumed for the LOCA analysis. In the licensees analysis of the MSIV leakage pathway, this guidance has been interpreted such that the flow is modeled from the drywell into the MSIV, and includes the effect of drywell sprays, containment leakage and mixing with the wetwell airspace (when assumed) to reduce the aerosol and iodine concentration in the source volume.

The staffs concern is that this modeling of the source concentration would underestimate the concentration of radionuclides that are in the steam leaking past the MSIVs into the environment and that the spray removal in the drywell would change the aerosol size distribution so that the model for deposition in the main steam lines is not applicable. Please address the appropriateness and conservatism of your of modeling the MSIV leakage activity source in this manner.