ML100560283

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Draft Request for Additional Information from Reactor Systems Branch Extended Power Uprate
ML100560283
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 02/25/2010
From: Justin Poole
Plant Licensing Branch III
To: Jim Costedio, Hale S
Point Beach
Poole Justin/DORL/LPL3-1/ 301-415-2048
References
Download: ML100560283 (1)


Text

From:

Poole, Justin Sent:

Thursday, February 25, 2010 10:52 AM To:

'Hale, Steve'; COSTEDIO, JAMES

Subject:

DRAFT - Request for Additional Information RE: EPU Steve By letter to the U.S. Nuclear Regulatory Commission (NRC) dated April 7, 2009 (Agencywide Documents Access and Management System Accession No. ML091250564), FPL Energy Point Beach, LLC, submitted a request to increase each units licensed core power level from 1540 megawatts thermal (MWt) to 1800 MWt reactor core power, and revise the technical specifications to support operation at this increased core thermal power level.

The Reactor System Branch has reviewed the information provided and determined that in order to complete its evaluation, additional information is required. We would like to discuss the questions, in draft form below, with you in a conference call.

This e-mail aims solely to prepare you and others for the proposed conference call. It does not convey a formal NRC staff position, and it does not formally request for additional information.

Justin C. Poole Project Manager NRR/DORL/LPL3-1 U.S. Nuclear Regulatory Commission (301)415-2048 email: Justin.Poole@nrc.gov

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DRAFT SRXB-LTT-1. Licensing Report Section 2.12.1.2.3.2, "EPU Power Ascension Test Plan and Test Plateaus," refers to "transient data gathered during the specified transient tests at low-power" (LR Page 2.12-6, Paragraph 2), and additional discussion refers the reader to Table 2.12-1 and Table 2.12-2 for additional details regarding the proposed EPU test plan. Table 2.12-1, however, does not refer to any transient testing other than data collection. Table 2.12-2, Item 13, by contrast, refers to "the planned load swing tests" that will "dynamically test the FW control system." This item refers the reader back to 2.12.1.2.3; however, the reviewer was unable to locate further discussion of any planned load swing tests. Describe the planned load swing tests in further detail.

SRXB-LTT-2. A modification is planned to the pressurizer heater system that will remove backup heater actuation on a pressurizer high level deviation signal. How are the effects of this modification tested or demonstrated against a transient that challenges the RCS inventory and pressure control?

SRXB-LTT-3. For the operability evaluations justifying exemptions from large transient testing, describe modeling guidelines followed to assure that LOFTRAN analyses were performed in such a manner as to assure that error attributable to the modeling approach has been minimized.

SRXB-LTT-4. Licensing Report section 2.12.1.2.6, "Justification for Exception to Transient Testing," Page 2.12-12, Paragraph 4 (numbered list excluded), indicates that the LOFTRAN results are consistent with experience on several similar Westinghouse-designed, 2-loop nuclear power plants that use the LOFTRAN computer code for analysis of Condition I and II initiating events. Please provide additional information to describe how this conclusion was reached and validated: (1) How was the fact that the results are consistent with other Westinghouse plant models established, and (2) How was the assertion that this comparison justifies exception to large transient testing validated?

DRAFT