ML20040A370
| ML20040A370 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System |
| Issue date: | 01/07/1974 |
| From: | Stello V US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201200819 | |
| Download: ML20040A370 (4) | |
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UNITED STATcS
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t ATOMIC ENERGY COMMISSION l
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E}l JAff 7 1374 Docket flo.: 50-460 R. C, DeYoung, Assistant Director, For Light Uater Reactors, Group 1 f
WASHIllGTON PUBLIC POWER SUPPLY SYSTEM 110. 1 Plant flame:
!!PPSS-1 i
Licensing Stage:
CP Docket ilo. :
50-460 i
Pesponsible Branch LWR Project Branch 1-1 chd Project Manager:
Tom Cox Technical Review Branch l
Involved:
Core Performance Branch Requested Completion Date:
12/28/73 Description of Review:
Round One Questions The attachment contains the round one questions to section 4.2.1, Fuel Mechanical Design, for the WPPSS-1 SER.
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/Y ictor Stello, /, Assistant Director for Reactor Safety Directorate of Licensing cc w/
Attachment:
S. Hanauer J. Hendrie I
A. Giambusso W. Ik:'onald A. Schwencer T. Cox D. Ross D. Ilouston L. Rubenstein L. Reading j
CPB Reading L:RS Administrative Assistant S. Varga l
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8201200819 810403 r
4 ATTAClif1EllT puEST10ris Off WPPSS 4.2.1 Fuel l'echanical Design _
4.2.1.1 - The 11 ark C fuel assembly is a new fuel design. We understand inat the conservative design philosophy employed in the flark B design is used for the Mark C.
In addition, lower fuel temperatures are expected in the new design due to lower linear heat rates.
Provide a table of comparison between the 11 ark B and C designs verifying that the structural adequacy and margins of safety are conservative.
4.2.1.2 - Provide additional information in regard to fuel rod design as follows:
a.
A drawing of the fuel rod, similar to Figure 4.2-2, with dimensions.
A drawing of the fuel pellet with dimensions should,also be provided.
b.
The nominal helium fill gas pressure in the fuel rod, and include the upper and lower tolerance limits.
In addition, describe the propressurization process and the inspection procedures for verification, c.
Deflection design specifications and experimental observations for the lower plenum spring.
Is tbure evidence of permanent deflection due to fuel rod and fuel assembly handling? Would gradual deflection of this spring as a function of irradiation be expecad and what is the maximum deflection, both expected and possible?
4.2.1.3 - Provide the following information in regard to fuel rod performance:
a.
The design analyses for Zr-4 irradiation growth and supply supporting data or references.
b.
The power history used to calculate fission gas released.
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c.
Justify use of 425"F as the limit at which "all significant hydrides have had a chance to precipitate
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. 4.2.1.3(cont'd)- under a favorable stress field." Define what is meant by "all significant hydrides."
d.
Limits on specifications of absorbed gases and moisture in fuel rods.
e.
The cleaning procedure applied to internal and external surfaces of cladding just prior to pellet loading.
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3-4.4 Thermal and Hydraulic Design 4.4.2.10 - Provide fuel centerline temperature, volumetric average fuel temperature, and gap conductance as a function of Kw/ft for beginning of life, end of cycle 1, and 55,000 mwd /mtU burnup, i
Provide information as a function of burnup for 100%
i power and nominal dimensions for (a) gap conductance, i
(b) hot gap size, (c) clad I.D.,
(d) gas pressure _and thermal conductivity, (e) volumetric average temperature, and (f) centerline temperature.
State whether the effects of densification are included in these calculations.
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