ML093140490
| ML093140490 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/10/2009 |
| From: | Justin Poole Plant Licensing Branch III |
| To: | Jim Costedio, Flentje F, Hale S Florida Power & Light Energy Point Beach, Point Beach |
| Poole Justin/DORL/LPL3-1/ 301-415-2048 | |
| References | |
| Download: ML093140490 (4) | |
Text
From:
Poole, Justin Sent:
Tuesday, November 10, 2009 2:15 PM To:
'Hale, Steve'; COSTEDIO, JAMES; 'Flentje, Fritzie'
Subject:
DRAFT RAIs for the SBLOCA model data for EPU Steve By letter to the U.S. Nuclear Regulatory Commission (NRC) dated April 7, 2009, as supplemented by letters dated September 11 and October 9, 2009 (Agencywide Documents Access and Management System Accession Nos. ML091250564, ML092570205, and ML092860098), 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
- 1) Page 2.8.5.6.3-6 of the Point Beach Extended Power Uprate (EPU) Licensing Report (Enclosure 5 to Reference 1) indicates that the small break (SB) loss of coolant accident (LOCA) analysis was performed using the NOTRUMP evaluation model. Please provide a copy of the NOTRUMP analysis report that supports the EPU application.
- 2) For the Point Beach nuclear steam supply system, please provide the following information:
a) Core Rated Thermal Power b) Power uncertainty, %
c) Total Core Peaking Factor, FQ d) Hot channel enthalpy rise factor, FH e) Hot assembly average power factor, P HA
f) Most limiting top and bottom skewed axial power shapes g) Full power loop mass flow rate, lb/sec h) Core mass flow rate, lbs/sec i) Thot, °F j) Tcold, °F k) Safety injection Flow delay time, sec l) High pressure safety injection (HPSI) flow rate (lb/sec) vs reactor coolant system (RCS) pressure (psia) m) HPSI runout flow rate n) Low pressure safety injection flow rate (lb/sec) vs RCS pressure (psia) o) If charging flow is part of the ECCS, provide the flow vs pressure for this pump curve also p) Head flow curves for the ECC pumped injection assuming a severed injection line.
q) Active Core height, ft r) Peak linear heat generation rate, kw/ft
s) Average linear heat generation rate, kw/ft t) No of fuel rods u) No of fuel assemblies v) Fuel rod pellet diameter and inside and outside radius of cladding w) Radiological waste storage tank (RWST) max temperature, °F x) RWST capacity, gallons, and boron concentration y) Accumulator minimum pressure, psia z) Accumulator minimum liquid volume, ft3, and maximum boric acid concentration aa) Volumes and heights of the following regions, each identified separately:
i) Lower plenum ii) Core iii) Upper plenum below the bottom elevation of the hot leg bb) Elevation data:
i) Bottom elevation of suction leg horizontal leg piping ii) Top elevation of cold leg at reactor coolant pump discharge iii) Top elevation of the core (also core height) iv) Bottom elevation of the downcomer cc) Loop friction and geometry pressure losses from the core exit through the steam generators to the inlet nozzle of the reactor vessel dd) Locked rotor reactor coolant pump (RCP) k-factor ee) Mass flow rates, flow areas, k-factors, and coolant temperatures for the pressure losses provided (upper plenum, hot legs, SGs, suction legs, RCPs, and discharge legs).
Please include the reduced SG flow areas due to plugged tubes. Please also provide the loss from each of the intact cold legs through the annulus to a single broken cold leg.
Please also provide the equivalent loop resistance for the broken loop and separately for the intact loop.
ff) Capacity of the condensate storage tank gg) Flushing flow rate at the time of switch to simultaneous injection hh) Capacities and boron concentrations for high concentrate boric acid storage tanks
- 3) Please provide the sump temperature vs. time following recirculation. How does this impact precipitation? Is the boric acid concentration in the vessel below the precipitation limit based on the minimum sump temperature at the time the switch to simultaneous injection is performed? Please explain.
DRAFT