ML110200692

Transmitting Draft Requests for Additional Information (Snpb) EPU Review

ML110200692
Person / Time
Site:	Point Beach
Issue date:	01/20/2011
From:	Beltz T Plant Licensing Branch III
To:	Hale S Nextera Energy
beltz T, NRR/DORL/LPL3-1, 301-415-3049
References
TAC ME1044, TAC ME1045
Download: ML110200692 (1)

Text

ADAMS Accession No.: ML110200692 From:

Beltz, Terry Sent:

Thursday, January 20, 2011 5:37 PM To:

'Steve.Hale@nexteraenergy.com' Cc:

'liz.abbott@fpl.com'; 'Costedio, James'; 'Flentje, Fritzie'; 'Hanneman, Harv'

Subject:

Point Beach Nuclear Plant, Units 1 and 2 - Request for Additional Information (SNPB) re: EPU Review (TAC Nos. ME1044 and ME1045)

Dear Mr. Hale:

The U.S. Nuclear Regulatory Commission (NRC) staff in the Nuclear Performance and Code Review Branch of the Office of Nuclear Reactor Regulation is reviewing the Extended Power Uprate (EPU) license amendment request (LAR 261) for Units 1 and 2 of the Point Beach Nuclear Plant. The staff determined that additional information is required to continue its review.

Specifically, as a result of the desk audit performed on January 20, 2011, the NRC staff discussed information related to its review and determined the need for the following information:

1. Please describe the models and method utilized to compute the boric acid concentration in the sump following sump re-circulation that is used as a boric acid source during the recirculation mode of injection.

Describe how the vapor source to the containment from the reactor coolant system is computed, the resultant condensation, and hence the boric acid content of the sump.

If 100% of the vapor source to the containment is assumed, then provide the basis and justification for this assumption.

If appropriate, please reference relevant containment transient data for the condensation efficiency of the containment sprays and CAR fans.

Please identify the uncertainty applied to the computation of the sump boric acid concentration and its basis.

2. Please also list all of the major conservatisms and margins inherent in the methods utilized to determine the boric acid build-up in the vessel and the timing for precipitation.

3. Please also describe the interfacial drag correlation used in the WCOBRA/TRAC code to determine the vapor content in the inner vessel, which determines the liquid content and mixing volume for establishing the timing for precipitation.

What is the vapor velocity in the core at 14.7 psia at the time of precipitation?

The NRC staff can discuss these ite formal issuance.

The sole purpose of this e-mail an proposed conference call or meet formal NRC staff position, and do Please don't hesitate to contact me Sincerely, Terry A. Beltz, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-3049 Terry.Beltz@nrc.gov ems with your staff in a conference call, if required nd its attachment is to prepare you and others ting. This e-mail and its attachment do not co o not formally request additional information.

if you have any questions or concerns.

d, prior to s for a onvey a