ML19352A054
| ML19352A054 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf, 07002936  |
| Issue date: | 12/03/1980 |
| From: | Ketzlach N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Dale L MISSISSIPPI POWER & LIGHT CO. |
| References | |
| NUDOCS 8102250684 | |
| Download: ML19352A054 (5) | |
Text
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Distribution:
Docket 50416
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ocket 50-417 Docket 70-2936 FCUP:HK NMSS r/f 70-2936 FCUP r/f FCUF r/f DEC 3 1930 PDR DCS IE HQ (2) 4 b'$r$
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Mississippi Power & Light Company JAN 2 81981 % '-~:
JAMartore ATTH: Mr. L. F. Dale Huclear Project Manager hv.s.eaunmuc, I
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AGWagner, Res. IE P.O. Box 1640 Jackson, Mississippi 39205 s
ON Gentienen:
We have completed the initial review of the Mississippi Power & Light Coapany application dated October 1,1980, for authorization to possess and
. use in-core detectors and for the receipt, possession, storage, inspection and transportation of special nuclear and byproduct material. We find that additional information is needed (see enclosure) to complete our evaluation.
In order to meet your requested date for receipt of the fuel, your responses to the comments are duc no later than January 9,1981.
If there are any questions concerning this matter, please call me.
Sincerely, Original Signed by:
N. Ketzlach Uranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety
Enclosure:
Coments on Mississippi Power & Light Conpany License Application for Fuel Storage Only at Unit 1 of the Grand Gulf Huclear Station (Dated October 1, 1980)
- A :R MAL SEE PREVIOUS YELLOW-FOR CONCURRENCES
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COMMENTS ON MISSISSIPPI POWER & LIGHT COMPANY LICENSE APPLICATION FOR FUEL STORAGE ONLY AT UNIT 1 0F THE GRAND GULF NUCLEAR STATION (DATED OCTOBER 1,1980) 1.
Page 5 Section 1.1.2 Describe the fuel assemblies in sufficient detail so that a nuclear criticality safety evaluation of the fuel handling and storage may be made (e.g., materials of construction, fuel rod diameter,
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maximum fuel density, cladding, rod pitch, number and location of void positions,_ number of fuel rods / assembly).
2.
Page 6 Section 1.2.1 a.
Describe the design of the new and spent fuel storage racks.
I b.
Provide sketches. identifying the fuel storage areas that indicate their relative location to each other.
. 3.
Page 7 a.
Section 1.2.2 1.
Specify the minimum spacings between fuel handling (e.g.,
4 carrier' unloading, assembly inspection) and fuel assembly storage areas.
2.
Provide the restrictions on activities in adjacent areas.
Include the limitations on ' crane operations over the. fuel j
assembly storage areas.
.b.
Section 1.2.3 l
1.
' scribe ~ the fuel handling activities in the fuel storage area
[:
receipt of the_ fuel in shipping containers to their place-
. in the storage racks.
Include safety-related features for
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_..tainer unloading, fuel assemblyJinspection and repair, i-transfer to and storage in the racks, and return to the tuel l
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fabricator, if necessary.
t 2.
Identify the -responsibility for administrative. controls and for ttle development.and approval-req'uirements to ensure safety of na il -fuel. handling and stora'ge operaticns.
Specify the approval re quirements.-
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I 3.
Confirm all fuel handling operations will be performed in accordance with approved written procedures.
4.
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.
5.
Clarify what you mean by "long term" storage.
Provide justi-fication for "long term" outside storage of loaded shipping containers and include the quantity of fuel to be stored, the length of time for storage and the spacing between groupings of shipping containers.
Describe the means for protecting the acrage area from " adverse weather conditions."
4 Page 8 Section 1.2.4 1.
Briefly describe the fire protection and fire control system (water hoses, sprinklers, dry chemicals, location) in all fuel storage areas.
Include the fuel-rack and long term storage arers.
2.
Confirm all construction related to fire protection of the fuel handling and storage areas is completed prior to receipt of unirradiated fuel.
3.
Confirm preoperatianal acceptance testing is completed, reviewed and approved prior to the use of fuel storage areas.
5.
Page 9 a.
Section 1.4 Confirm the Grand Gulf Nuclear Station is responsible for the packaging of the fuel returned to Wilmington.
Until the shipment is transferred to a carrier for transport, responsibility for it belongs to the Station.
b.
Section 2.1 1.
Identify the personnel responsible for nuclear criticality safety related to the fuel handling and storage operations and for the training they receive.
1
[,
. 2.
Describe the administrative controls and contamination monitoring operations to ensure protection of personnel and the environment from the time of receipt of the fuel to its storage in racks or in the shipping containers.
Include the monitoring station (s) where personnel exiting the storage area will be ch cked for radioactive contamination.
3.
State the frequency and methods for calibration and testing of portable radiation survey instrumentation and laboratory radiation instrumentation.
6.
Page 10 Section 2.2.2
-1.
Confirm the structural integrity of the racks has been analyzed from the standpoint of possible failure due to such factors as loading, shock,. fire, corrosion, etc.
2.
Specify the minimum center-to-center spacing between fuel assemblies in the new fuel vault and in the othe~r storage racks.
3.
Provide the results of the nuclear criticality safety analyses, F
the method of analysis used, and the assumptions made in the analysis (e.g., degrees of water moderation, dropping of a crane loading on top of the rack).
4.
Specify the controls to be exercised in placing the elements-only in the designated storage locations.
'7.
Page 11 a.
Section 2.2.3-1..
Confirm all degrees of credible interspersed noderation (e.g.,
from sprinklers) have been considered in the nuclear criticality
- safety evaluation.
2.
Confirm the fuel assemblies are packaged in the storage racks so that 'if the fuel were flooded and then drained, the water could-not be. retained 'around or within an assembly.
If this is not the; case,. provide a nuclear criticality safety evaluation of the carrays with water retention within an assembly and optimum credible interspersed moderation between assemblies.
- b.
Section 2.2.4-
.l.
Provide' verification of the minimum critical number of. fuel
. assemblies at ' optimum spacing and full water moderation and
-reflection.
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Confirm the maximum safe number of assemblies that will be outside the shipping containers and storage racks, at any one time, cannot be made critical.
Confirm no shipping containers will be opened in the outside storage areas.
c.
Section 2.2.5 Specify the type (s) of radiation detectors and instrumentation in the auxiliar-and containment buildings.
d.
Section 2.3.1 1.
Confirm the nuclear criticality safety of a loaded storage rack '
is not compromised by accidentally dropping the maximum crane load on top of the storage rack.
2.
Provide the administrative controls to assure no greater loads will be carried by the crane while passing over the fuel-loaded storage racks.
8.
Page 13 Section 3.1 y
Describe the administrative controls to ensure protection of personnel from radiation from the byproduct sealed sources.
Specify the precautions to be taken to meet ALARA.
9.
Pages 15-16 Describe t!'e arrays shown in the Figures.
Include the definition of
" crates."
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