Letter Sequence RAI |
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Initiation
- Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
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2010-08-09
[Table View] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 March 22, 2010 Mr. George H. Gellrich, Vice President Calvert Cliffs Nuclear Power Plant, LLC Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RE: TRANSITION FROM WESTINGHOUSE TO AREVA ADVANCED CE-14 HTP FUEL - CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 (TAC NOS. ME2831 AND ME2832)
Dear Mr. Gellrich:
By letter dated November 23, 2009 (Agencywide Document Access and Management System Accession No. ML093350189), Calvert Cliffs Nuclear Power Plant, LLC submitted a license amendment request for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, to modify the licensing basis and Technical Specifications to allow the use of AREVA Advanced CE-14 HTP fuel.
The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided and has determined that additional information is needed to complete its review. Enclosed is the NRC staff's request for additional information (RAI). As discussed with your staff, we understand that you intend to respond to this RAI within 4 weeks of receipt of this letter.
Please contact me at 301-415-1364 if you have any questions.
Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION TRANSITION TO AREVA FUEL CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-317 AND 50-318 The Nuclear Regulatory Commission staff intends to run FRAPCON-3 benchmark calculations of the AREVA CE-14 HTP fuel rod design. Please provide the following input. Known values were extracted from Table 2-1 of the application dated November 23, 2009.
- 1. Rod Power History, KW/ft as a function of GWd/MTU
- a. Bounding thermal-mechanical operating envelope (e.g., radial falloff curve)
- b. Discuss any application of rod power uncertainties
- c. Include power histories for different pellet designs (U02, Gad).
- 2. Axial Power Distribution (Fz at each axial node)
- a. Include AXPDs for different axial blanket configurations.
- 3. Fuel Rod Design Specifications and Manufacturing Tolerances
- a. Outer Diameter =
0.4400 in., Tolerance j, x
- b. Inside Diameter =
0.4135 in., Tolerance :t x
- c. Pellet Diameter =
0.3805 in., Tolerance y x
- d. Stack Length =
136.70 in., Tolerance j x
- e. Plenum Length
- f.
Pellet Height
- g. Dish Radius
- h. Dish Depth
- i.
Spring Outer Diameter
- j.
Spring Wire Diameter
- k. Number of Spring Turns I.
Maximum U-235 Enrichment (%)
- m. Average U-235 Enrichment (%)
- n. Maximum Gadolinia Content (%)
Enclosure
- 2
- o. Water in Pellet (ppm)
- p. Nitrogen in Pellet (ppm)
- q. Pellet Density (%TO)
- r.
Open Porosity (%)
- s. Pellet Surface Roughness (microns)
- t.
Expected Density Increase (g/cm3)
- u. Sintering Temperature CF)
- v. Cladding Alloy =
M5
- w. Final Thermal Treatment =
RXA
- x. Cladding Surface Roughness (microns)
- y. Cladding Texture Factor
- z. Claddng Hydrogen Content (ppm) aa. Fill Gas Pressure bb. Fill Gas Composition cc. Rate of CRUD Accumulation (mils/hr) dd. CRUD Thermal Conductivity
- 4. Coolant Conditions
- a. Coolant Inlet Temperature (F)
- b. Coolant Mass Flux (lbm/hr-ft2)
- c. Pressure (psia)
ML100710319 OFFICE PM/LPL 1-1 LA:LPL1-1 BC/SRXB BC/LPL1-1 NAME DPickett SLittie GCranston NSalgado DATE 03/22/10 031 151 10 03/22/10 03/221 10
