ML14141A052
| ML14141A052 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 03/05/2014 |
| From: | Siva Lingam Plant Licensing Branch II |
| To: | Arent G, Bryan R Tennessee Valley Authority |
| Lingam S | |
| References | |
| Download: ML14141A052 (4) | |
Text
From:
Lingam, Siva Sent:
To:
Wednesday, March 05, 2014 2:18 PM garent@tva.gov; rhbryan@tva.gov Cc:
Subject:
Attachments:
Quichocho, Jessie; Poole, Justin; Dion, Jeanne; Kaizer, Joshua; Clifford, Paul Watts Bar, Unit 2 Appendix HH Open Item 61 Regarding PAD Code Information Required by NRC.Ol.docx Per our conference call on February 27, 2014, and to resolve 01-61, we need the information as spelled out in the attached document. if something looks strange in terms of our request, please give us a call for clarification/correction. Thank you.
Siva P. Lingam U.S. Nuclear Regulatory Commission Project Manager (NRR/DORL/LPL2-2)
Brunswick Steam Electric Plant Robinson Steam Electric Plant Location: 08-05; Mail Stop: 08-G9a Telephone: 301-415-1564; Fax: 301-415-1222 E-mail address: siva.lingam@nrc.gov 1
- 1. The NRC staff intends to run FRAPCON-3.4 benchmark calculations of the fuel rod design. Provide the following inputs for FRAPCON 3.4.
A. Rod Power History, KW/ft as a function of GWd/MTU
- 1. Bounding thermal-mechanical operating envelope for both fuel types (i.e.,
U02 and IFBA)
- 2. Discuss any application of rod power uncertainties
- 3. Include power histories for different pellet designs for both fuel types B. Axial Power Distribution (Fz at each axial node)
- 1. Include AXPDs for different axial blanket configurations.
C. Fuel Rod Design Specifications and Manufacturing Tolerances At a minimum, this should include those variables identified in the following table.
Rod Size Units Outer Diameter
?
in Inner Diameter
?
in Pellet Diameter
?
in Stack Length
?
in Plenum Length
?
in Sprina Dimensions spring outer diameter
?
in spring wire diameter
?
in number of spring turns
?
Pellet Shape Pellet Height
?
in Central Hole Radius
?
in Dish Radius
?
in Dish Depth
?
in Pellet lsotoplcs Fuel U-235 Enrichment
? o;o U02 or MOX?
Reactor grade or weapons reactor grade grade 0/M ratio
?
Gadolinia content
?
wt fraction water in pellet
?
ppm nitrogen in pellet
?
ppm percent IFBA rods in core
?
o;o Boron-1 0 enrichment in Zr82
?
atom%
Zr82 layer thickness
?
mm Density of Zr82
?
% T.D.
Pellet Fabrication pellet density
?
o;o open porosity
?
0/o pellet surface roughness
?
microns exp_ected density increase
?
g/cm3 sintering temperature
?
OF Claddina Fabrication Cladding type
?
Zirc-2, Zirc-4, Zirlo, M5 Recommend 0 for RXA and 0.5 Cladding cold work
?
for CWSR Cladding surface roughness
?
microns cladding texture factor
?
Hydrogen in cladding
?
ppm Rod Fill Conditions Fill gas pressure
?
psi Fill Gas
?
Reactor Condutions Type of plant PWR PWR, BWR, HWR rod pitch
?
in Constant thickness or time crud model
?
dependent initial crud thickness
?
mils rate of crud accumulation
?
mils/hr CRUD Thermal conductivity If needed
- 2. For the following inputs from the above table, please provide tolerance values.
A. Cladding Outer Diameter B. Cladding Inner Diameter C. Cladding Surface Roughness D. Pellet Diameter E. Pellet Density F. Pellet re-sinter Density G. Pellet Roughness H. Pellet Dish Diameter I.
Pellet Dish Depth J. Rod Fill Pressure K. Rod Plenum Length
- 3. For the AOO overpower (Fz vs. time) used in the clad strain calculation L. Provide the input used (power vs. time)
M. Provide the predicted strain for both fuel types
- 4. Provide the predicted power to melt limit (kw/ft) vs. Burnup for both fuel types
- 5. Provide the following for the Rod Internal Pressure case for both fuel types A. BOL Void VV B. EOL Hot VV C. EOL RIP D. EOL FGR (% release and moles of Gas)