ML19345E487
| ML19345E487 | |
| Person / Time | |
|---|---|
| Site: | 07002932 |
| Issue date: | 01/14/1981 |
| From: | Ketzlach N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Gary R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| References | |
| NUDOCS 8102040666 | |
| Download: ML19345E487 (4) | |
Text
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-S Texas Utilities Generating Company ATTN: Mr. R. J. Gary Executive Vice President and General Manager 2001 Bryan Tower Dallas, Texas 75201 Gentlemen:
We have completed the initial review of the Texas Utilities Generating.. Company application dated July 10, 1980, for authorization for the receipt, possession, storage, inspection and preparation for transport of special nuclear material required for the operation of the Comanche Peak Steam Electric Station Unit 1.
We find that additional infonnation is needed (see enclosure) to complete our eval uation.
In order to meet your requested date for receipt of the fuel, your responses to our comments should be provided no later than April 3,1981.
If there are any questions concerning this matter, please call me at 301-427-4510.
Sincerely, W
G l
Norman Ketzlach Uranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety
Enclosure:
Conments on Texas Utilities Generating Company License Application for Fuel Storage Only at Unit 1 of the Comanche Peak Steam Electric Station (dated July 10, 1980) 1 8102040$hh
ENCLOSURE F
COMMENTS ON TEXAS UTILITIES GENERATING COMPANY LICENSE APPLICATION FOR FUEL STORAGE ONLY AT UNIT 1 COMANCHE PEAK STEAM ELECTRIC STATION (DATED JULY 10, 1980) 1.
Page 2 Section 1.1:.2 a.
Specify the pellet diameter and fuel rod pitch in an assembly.
b.
Confirm 3.1% 235U is the maximum enrichment in a fuel assembly.
2.
Page 3 a.
Section 1.2.2 (1) Specify the minimum spacings between fuel handling (e.g., carrier unloading, assembly inspection) and fuel assembly storage areas.
(2) Confirm preoperational testing for necessary fuel handling and support systems will be completed prior to receipt of unirradiated fuel.
All equipment should be inspected and tested for safe operation prior to use in fuel handling activities.
b.
Section 1.2.4 Confirm all construction related to fire protection of the fuel handling and storage areas is completed prior to receipt of unirradiated fuel.
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3.
Page 5 a.
Section 2.1.2 (1)
Identify the responsibility for administration controls and for the development and approval requirements to ensure safety for all fuel handling and storage operations.
Specify the approval i
requirements.
(2) Confirm all fuel handling operations will be performed in accord-ance with approved written procedures.
(3) Specify the precautions to be taken to meet ALARA.
b.
Section 2.2 Confirm there will be no'more than one fuel assembly outside the shipping container or storage rack at any one time.
4.
Page 6 a.
Describe the design of the new and spent fuel storage racks.
Include l
sketches in support of the description.
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b.
Provide the results of the nuclear criticality safety analyses, the method of analysis usea, and the assumptions made in the analysis (e.g., degrees of water moderation, dropping of a crane loading on top of the rack).
c.
Confirm all degrees of credible interspersed moderation (e.g., from sprinklers) have been considered in the nuclear criticality safety eval 0ation.
d.
Provide the administrative controls to ensure " checkerboard" loading of new fuel in the spent fuellpool racks. What is to prevent the inadvertent insertion of an assembly in the open storage cells of the array?
Provide justification for the assumption the " checkerboard" array of e.
fuel assemblies has a multiplication factor (k,ff) no greater than that for the array of assemblies in the new fuel storage areas. The edge-to-edge spacing between some. assemblies 16'ther" checkerboard" array are closer than that between those in the new fuel storage racks. C6nsideration should be given to the optimum credible water moderation within and between fuel assemblies.
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