ML19320A579
| ML19320A579 | |
| Person / Time | |
|---|---|
| Site: | 07106078 |
| Issue date: | 05/30/1980 |
| From: | Lichtenberger ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML19320A580 | List: |
| References | |
| 16519, NUDOCS 8007020102 | |
| Download: ML19320A579 (6) | |
Text
(1
~
C-E Power Systems Tet 203/688-1911 Combustion Engineenng, Inc.
Telex: 99297 1000 Prospect Hill Road
[
Windsor, Connecticut 06095 gr d POWER flHLaSYSTEMS License SNM-1067 May 30,1980 Docket 71-6078 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention: Mr. Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel. Cycle & Material Safety
Reference:
Letter from Mr. C. E. MacDonald to Mr. H. V. Lichtenberger, dated March 28, 1980; Certificate of Compliance No. 6078 Gentlemen:
This is in response to your request for revised drawings of the C-E Model 927Al and 927C1 containers as part of our renewal application for Certificate of Com-liance No. 6078 dated December 10, 1979. To preserve the continuity of our application, the drawings and associated changes are submitted in the form of revised pages to our original renewal application as listed below:
Delete Pages Add Pages 1-1 1-1 Rev. 1, 5/30/80 1-2 1-2 Rev. 1, 5/30/80 Appendix 1.3-CE Drawing Appendix 1.3-CE Drawing NFM-E-4108, Rev. O sheets NFM-E-4108, Rev. 1, sheets 1 and 2 dated 11/27/79 l-4 dated 5/29/80 2-4 2-4 Rev. 1, 5/30/80 4-1 4-1 Rev.1, 5/30/80 8-1 8-1 Rev. 1, 5/30/80 Very truly yours, LU H. V. Lichtenberger Vice President-Nuclear Fuel Nuclear Power Systems-Manufacturing HVL/GAJ/ssb Enclosures 1b,. 3 B007020/@Jlc_
e-1..
GENERAL INFORMATION 1.1 Introduction This renewal application is submitted for approval of Combustion Engineering's fuel assembly shipping containers, identified as Model 927Al and Model 927C1. The Model 927Al container is structurally identical to the Model 927C1 container with the exception of its reduced length.
These containers meet the criteria of 10 CFR Part 71.40(a) for shipment as Fissile Class III, with a limit of 8 packages per shipment.
1.2 Package Description 1.2.1 Packaging The 927Al and 927C1 containers are fabricated of carbon steel and consist of a strongback and fuel bundle clamping assembly, shock mounted to the steel outer container. The fuel bundles are separated by 1/4" thick, 6" x 6" x 8" high carbon steel spacer blocks bolted between tH bundles to maintain a minimum bundle to bun-die separation of 6 inches. The Model 927Al container is approximately 43" in dia-meter by 189" long with an approximate gross weight of 6,200 lbs. The Model 927Cl container is approximately 43" in diameter by 216" long with an approximate gross weight of 7,000 lbs.
All safety-related features of both containers are described in CE Drawing NFM-E-4108, Rev.1, sheets 1-4, dated 5/29/80 which are included in Appendix 1.3 of this application. Drawings of pressure relief valves and lifting devices are also shown in Appendix 1.3 with material lists, dimensions, gaskets, and weld speci-fications included.
1.2.2 Operational Features N/A (These containers are used for the shipment of unieradiated PWR fuel assem-blies, are of relatively simple desigr and do not incorporate cooling systems, shield-ing,etc.)
1.2.3, Contents of Packaging Each shipping container shall contain two fuel assemblies.
Each fuel assembly shall be unsheathed or shall be enclosed in an unsealed, polyethylene sheath which will not extend beyond the ends of the fuel assembly. The ends of the sheath shall not.be folded or taped 'in any manner that would prevent flow of liquids into or out of the sheathed fuel assembly.
The _CE Model 927Al package will contain two fuel assemblies consisting of 0.3765" diameter uranium dioxide pellets clad in.028" thick zircaloy-4 tubes in a 14 x 14 square array with a 0.58"p'tch.
Each fuel bundle ' consists of a maximum of 176 fuel i
rods enriched to a maximum of 4.1% U235 The maximum radioactivity for each fuel bundle is 0.80 curies.
The maximum for each loaded fuel container is 1.60 curies, with the maximum radioactivity for a shipment of eight containers or sixteen fuel
. bundles-being'12.8 curies.
The CE Model 927Cl package will contain two fuel assemblies consisting of 0.325" diameter uranium dioxide pellets clad in ~.025" thick zircaloy tubes in a 16x16 square array withia.506" pitch.
Each fuel bundle consists of a maximum of 236 fuel rods Revision:
1
),)
Date:
5/30/80
n enriched to a maximum of 4.1% U235 The maximum radioactivity for each fuel bundle is 0.90 curies. The maximum for each loaded fuel container is 1.80 curies, with the maximum radioactivity for a shipment of eight containers or sixteen fuel bundles being 14.4 curies.
For 'both the Model flo. 927Al and 927C1 container, the upper bundle bracket may be secured to the strongback by either of the following hardwares:
(1)
Ten 3/4-16 UtlF Hex Head bolts with associated washers and nuts, or (ii)
Eight 3/4-inch diameter steel clevis pins with associated steel hair pin cotters, and two 3/4-16 UtlF Hex Head bolts with associated washers and nuts.
The two bolts shall be placed in the uppermost position for that specified part.
1.3 Appendix Dimensional details of both containers are described in Drawing flFli-E-4108, Rev.1, sheets 1-4 dated 5/29/80.
Revision:
1 I-2 Date:
5/30/80
m 2.7 Hypothetical Accident Conditions _
This package was subjected to the hypothetical accident conditions as speci-fied in Appendix B to 10 CFR Part 71 and meets the standards specified in 71.36 of 10 CFR Pa'rt 71.
2.7.1 Free Drop a) Analysis The container ms subjected to two 30-foot drops.
The first drop was made with the longitudinal axis of the container at an angle of approximately 30 to the horizontal. The angle was such that the af* end of the container stru x first, the container then rotating so that the bottom of the fore and skids hit the concrete slab. The container cover was removed at the test site aftea the 30 angle, 30-foot drop and the container visually inspected. The simulated fuel bundles were retained in the container cradle assembly and little relative movement of one fuel bundle with respect to the other was noted. The most notable deformation as a result of this i.est was in the skid brackets.
See Appendix 2.10 Reference B.
See photographs No. 6 through fio.17 for various views of the container during and after this test.
The second 30-foot drop was made with the container oriented such that the left side closure flange struck the concrete slab. The simulated load utilizing tubu-lar construction was nearest the ground. Upon impact the container remained stable on its side without any rotation about its axis.
After the 30-foot side drop, the container was inspected as above. Although the simulated fuel bundles had shifted sidewise from their original mounting positions the fuel bundles did not come loose and were contained in the container shell after testing. The most notable deformation in the container shell is at the forward right closure flange. Refer to Appendix 2.10 reference B, photographs flo.18 through No.
30 for various views of the container duriN and after this test.
It is concluded that the container satisfies the test requirements by retaining the two fuel bundles within the strongback with complete separation of the two bun-dies.
Further, the strongback with fuel bundles installed were contained within the container structure.
b) Prototype Testing The testing was parformed on the CE flodel 927Al container by Applied Design Co.,
in February 1969. The only major difference between the tested container and the existing container is the method of separating the fuel bundles.
The boral plate in the original container has been replaced by carbon steel separator blocks. A struc-tural analysis was performed and completed in February 1971 to show that the modified container was covered by testing performed on the original container. This analysis was then submitted and approved by the Commission.
(See Appendix 2.10 reference C).
As previously mentioned, the CE Model 927Cl container is structurally identical to the tested 927Al container except for its additional length.
The Humidity Indicator and the Filling Valve are listed as optional on Drawing NFM-E-4108, Rev.1, sheet 1, dated 5/29/80.
(Appendix 1.3).
These two features are not being utilized any longer and have been eliminated from some of the 927C1 l
containers.
l l
2-4 Revision:
1 Date:
5/30/80
V 4.0 CONTAINMENT 4.1 Containment Boundary The 3rimary containment of the CE Model 927Al packages is the 11 gauge steel shell. The unirradiated U02 fuel pellets are placed within zircaloy fuel rods of approximately.025 inch thick walls. These fuel rods are then assembled into bun-dies.
4.1.1 Containment Vessel The outer shell is composed of 11 gauge steel.
4.1.2 Containment Penetrations There are a total of 5 penetrations into the primary containment.
Of these, only 2 are presently needed. The remaining three are listed as optional and may be eliminated upon construction of any new containers.
Those which are no longer used are the Desiccant Access Hatch, Humidity Indicator, and the Filling Valve. The Humidity Indicator has been eliminated on the longer con-tainers because of its lack of reliability. The filling valve has also been removed because the containers are no longer pressurized.
The desiccant access hatch is still on all containers; however, the desiccant bags are presently placed in the container before the container is closed.
4.1.3 Seals and Welds All seals and welds are specified on Drawings NFM-E-4108, Rev.1, sheets 1-4, dated 5/29/80.
4.1.4 Closure The "T" Head Special-Bolt is presently being u' sed for closure of the containers.
It is requested that the Round Head Square Neck bolt shown in Appendix 2.10 be app-roved for closure of the containers also. The replacement bolt is equal to or greater than the "T" Head Special Bolt in mechanical properties.
4.2 Requirements for Normal Conditions of Transport It is concluded that under normal conditions of transport (as specified in 10 CFR Part 71, Appendix A) the tests results described in Section 2.6 of this applica-tion indicate the following results:
(1) There will be no release of radioactive material from the containment vessel.
(2) The effectiveness of the packaging will not be reduced.
(3) There will be no mixture of gases or vapors in the container which could, through any credible increase of pressure or an explosion, significantly
~. reduce the effectiveness of the package.-
(4)_ The package is so designed and constructed, and its contents so limited, that under the normal conditions of transport specified in Appendix A of 10 CFR Part 71:
Revision:
1 Date: 5/30/80
..,,s'....
8.
ACCEPTANCE TESTS AND MAINTENANCE PROGRAM 8.1 Acceptance Tests All ' containers to be fabricated will be constructed in accordance with drawings NFM-E-4108, Re".1, sheets 1-4, dated 5/29/80 and shall be source 1
inspected prior to leas.ng the vendor's facility. Changes to the design of the container which fall outside of the safety envelope specified in this application ~
will be submitted to NRC for approval. This may include retesting of the container if analytical results are not capable of demonstrating that the test sequence pre-viously performed would be applicable to the changes made.
8.2 Maintenance Program The maintenance program uses the Quality Assurance inspection procedures to determine when any r2 pair or replacement of material is required.
L These inspections include:
4 a) Visual Inspection y
- 1) Container External Condition j
- 2) Container Internal Condition I
- 3) Cover Gaskets b) Tests Performed 1)
Impact Records Tested
- 2) Test ci' Manual Pressure Relief Valves l
I i
i 1
I r
l-Ud[il[).
f Revision:
1
+
Date:
5/30/Pu 8-1
N4 9oy
[e u;*%
UNITE 3 STATES g
R T
~*
NUCLEAR REGULATORY COMMISSION 3
..! '1 ) j WASHINGTON, D. C. 20536
',l * ' -u /,,,5 fll2 /70 5
s MEMORANDUM FOR: TERA Corp.
FROM:
US NRC/TIDC/ Distribution Services Branch
SUBJECT:
Special Document Handling Requirements 1.
Please use the following special distribution list for the attached document.
h 2
The attached document requires the following special considerations:
O Do not send oversize enclosure to the NRC PDR.
3Onlyoneoversizeenclosurewasreceived-please i
return f
_:rf T'1 agia;e fg, Proprietary information - send affidavit only to the NRC PDR O Other: (specify) cc: DSB Files TIDC/DSB Authorized Signature
_. _.