ML19207B471
| ML19207B471 | |
| Person / Time | |
|---|---|
| Site: | 07000033 |
| Issue date: | 05/01/1979 |
| From: | Hopper C TEXAS INSTRUMENTS, INC. |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 7908290626 | |
| Download: ML19207B471 (13) | |
Text
k(a PPR
/
TEXAS INSTRUMENTS INCORPORATED MATERIALS & ELECTRICAL PRoOUCTS GROUP May 1, 1979 Leland C. Rouse, Chief Fuel Processing & Fabrication Branch Div. of Fuel Cycle & Material Safety U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Reference:
SNM-23, Docket 70-33 e - memmusuu Gentlemen:
It is requested that USNRC License No. SNM-23, Docket No. 70-33, Amendment No.
8, dated July 28, 1978, be amended to:
Permit the use of a newly developed borated phenolic foam insulated shipping container for storage and transfer of HFBR, NBSR, ORR, or other box type fuel elements within the HFIR Facility (with no greater 235U content than HFBR fuel elements, approximately 351 g 235U).
As presented in the enclosures, designer and independent calculations demonstrate that the newly developed container meets Fissile Class I package requirements of 10 CFR Part 71.
Therefore, the storage of box type fuel elements within the newly developed container will not affect the nuclear criticality safety of fuel storage at TI.
Use of the newly developed shipping containers are limited to available shipping container storage space within location numbers (30), (31), (41), (51),
and (57) as permitted by Table 1, Appendix 1, of Amendment No. 8.
Enclosures I and II provide information and form the justifi-cation of this recuest, and Enclosure III provides an update of Table 1 of Appendix 1 in accordance with past correspondence between TI and yoar staff.
All changes to Table 1 are itemized in the enclosure.
Also enclosed is a check to cover the administrative amendment fees associated with this request.
Sincerely, C A M 6;P' 1596 74 Calvin M. Hopper Manager Nuclear Safety
/ck Enclosures I, II, III, Check for Administrative Amendment.
Check #077082 ATTLEBCRO, MA$$ACMU$ ETTS C2703 e TELEPHONE: 617 222 2800 e CAGLE: TEXINS
-WWQ.
176229062G
tb PPR
(
TEXAS INSTRUM ENTS INCORPORATED MATERIALS & ELECTRICAL PRODUCTS GROUP May 1, 1979 Leland C.
Rouse, Chief Fuel Processing & Fabrication Branch Div. of Fuel Cycle & Material Safety U.S.
Nuclear Regulatory Commission Washington, D.C.
20555
Reference:
SNM-23, Docket 70-33 gammaussesume Gentlemen:
It is requested that USNRC License No. SNM-23, Docket No. 70-33, Amendment No.
8, dated July 28, 1978, be amended to:
Permit the use of a newly developed borated phenolic foam insulated shipping container for storage and transfer of HFBR, NBSR, ORR, or other box type fuel elements within the HFIR Facility (with no greater 235 0 content than HFBR fuel elements, approximately 351 g 235U).
As presented in the enclosures, designer and independent calculations demonstrate that the newly developed container meets Fissile Class I package requirements of 10 CFR Part 71.
Therefore, the storage of box type fuel elements within the newly developed container will not affect the nuclear criticality safety of fuel storage at TI.
Use of the newly developed shipping containers are limited to available shipping container storage space within location numbers (30), (31), (41), (51),
and (57) as permitted by Table 1, Appendix 1, of Amendment No.
8.
Enclosures I and II provide information and form the justifi-cation of this request, and Enclosure III provides an update of Table 1 of Appendix 1 in accordance with past correspondence between TI and your staff.
All changes to Table 1 are itemized in the enclosure.
Also enclosed is a check to cover the administrative amendment fees associated with this request.
Sincerely, 6
- ,47 C & ~ m. $ ; y,_
Calvin M.
Hopper Manager Nuclear Safety M b2TOI C
/ck Enclosures I, II, III, Check for Administrative Amendment.
Check #077082 ATTLEBORO, M LSS ACHUSETTS 02703 e TELEPHONE: 617 222-2800 e CABLE: T E XINS
ENCLOSURE I P
Justification for Use of Borated Phenolic Foam Seven Element Container (Reference ORNL/CSD/TM-77 and Enclosure II) a Analyses:
ORNL/CSD/TM-77 provides the primary nuclear criticality safety demonstration for the seven element shipping container loaded with approximately 351 g 235U HFBR box type fuel elements.
The primary demonstration justifies the use of the container as a Fissile Class I package.
Enclosure II provides the fabrication engineering drawings as a reference of geometry and material descriptions.
An independent nuclear criticality safety review of ORNL/
CSD/TM-77 results was accomplished utilizing the same KENO IV cuae and cross-section sets.
The code and cross-sections have been demonstrated to be adequate for calculations involving materials and geometries consistent with those encountered in the package analysest,2,3,4,s,s To provide an independent calculational approach to the review, HFBR fuel elements were assumed to be homogenized throughout the fueled regions rather than using discrete geometries.
Comparisons of the discrete geometry calculational results presented in Table 4 of ORNL/CSD/TM-58 and this review are shown in Table 1.
TABLE 1 Comparison of Discrete Versus Homogenized Geometry Calculational Results for HFBR Fuel Elements, Closq; Packed, Submerged in Water Number eff of Fuel Element This Review Elements Arrangement TM-58 (Discrete)
(Homogenized)
XXXX 16 1.2 32 0.008 1.137 1 0.006 X
XXXX XXXX 12 XXXX 1.054 i 0.010 1.059 1 0.006 XXXX 1596 348 xx s'
10 XXXX 1.007 0.007 XXXX I'
XXX 9
XXX 1.004 i 0.005 XXX 12744
Results shown in Table 1 demonstrate the validity of utilizing homogenized descriptions of HFBR fuel elements in calculations.
Independent calculations of the tnird, fifth, and sixth results presented in Table 4 of ORNL/CSD/TM-77 were made with the HFBR fuel elements homogenized within the proposed container.
Comparisons of the discrete geometry calculational results presented in Table 4 of ORNL/CSD/TM-77 and this review are shown in Table 2.
TABLE 2 Comparison of Discrete versus Homogenized Geometry Calculational Results for 9 HFBR Fuel Elements within the Damaged Proposed Borated Phenolic Foam Seven Element Shipping Container.
keff Number of This Review Packages Conditions TM-77 (Discrete)
(Homogenized)
Water in fuel region Single package closely 0.688 i 0.009 0.729 0.005 reflected by water
?
Infinite Water in fuel 0.739 1 0.008 0.857 1 0.005 Array region Infinite Water in fuel region 0.682 0.007 0.778 1 0.006 Array water filling void between packages The effects of 0.05 g/cm3 density borated phenolic foam were examined also.
Calculational results presented in Table 2 utilized 0.2 g/cm3 borated phenolic foam.
Comparative results of homogenized fuel elements are presented in Table 3.
TABLE 3 1596 349 Results of Varying Borated Phenolic Foam Density Number of eff Packages Conditions 0.2 g/cm3 0.05 g/cm3 Water in fuel region Single package closely 0.729 1 0.005 0.715 1 0.005 reflected by water Infinite Water in fuel region 0.857 0.005 0.889-0.006 Array SNdh
__ ^
TABLE 3 (Continued)
.s Results of Varying Borated Phenolic Foam Density Number of Packages Conditions 0.2 g/cm3 0.05 g/cm3 Infinite Water in fuel region 0.778 1 0.006 0.794 0.007 Array water filling void between packages An independent review of the physical characteristics of the container (geometries, materials, densities) was accomplished.
This review indicated that:
1.
The basic elemental composition of the borated phenolic foam as calculated in ORNL/CSD/TM-77 and this review are within the specifications for borated phenolic foam,8,9,10 7
as presented within ORNL/CSD/TM-77.
r-2.
The basic calculational geometries and materials descriptions conform to the expected results of thermal tests described in references 7 and 8.
It is concluded that the designer's nuclear criticality 3
safety assessment of the described borated phenolic foam seven element shipping container is adequate to demonstrate the safe use of the container within the HFIR Project Facility and will not affect the nuclear criticality safety of fuel storage at TI.
1596 350 s
l M
i 12744 s
BIBLIOGRAPHY a
1.
J.T.
Thomas, Nuclear Criticality Assessment of Oak Ridge Research Reactor Fuel Storage, ORNL/CSD/TM-58, Oak Ridge National Laboratory (1978).
2.
J.T.
Thomas, Nuclear Criticality Safety of the Fuel Element Fabrication Facility at Attleboro, Massachusetts, ORNL/CSD/
TM-55, Oak Ridge National Laboratory (1978) 3.
J.T.
Thomas, Nuclear Criticality Safety Assessment of ORR, NBS, and HFBR Fuel Element Shipping Package,.ORNL/CSD/
TM-77, Oak Ridge National Laboratory (1979).
4.
L.M.
Petrie and N.F.
Cross, KENO-IV:
An Improved Monte Carlo Criticality Program, ORNL-4938, Oak Ridge National Laboratory (1975).
5.
G.R.
Handley and C.M.
Hopper, Va.lidation Checks of the "ANISN", and " KENO" Codes by Correlation with Experimental Data, Y-1858, UCC-ND Y-12 Plant (1972).
6.
G.R.
Handley and C.M.
Hopper, Validation of the " KENO" Code for. Nuclear Criticality Safety Calculations of Moderated, Low-Enriched Uranium Systems, Y-1948, UCC-ND Y-12 Plant (1974).
7.
A.J.
Mallett and C.E.
Newlon, Protective Shipping Package for Five-Inch-Diameter UF6 Cylinder, X-1716, Oak Ridge Gaseous Diffusion Plant (1967).
8.
A.J. Mallett and C.E.
Newlon, "New End-Loading Shipping Container for Unirradiated Fuel' Assemblies", Proceedings of Second International Symposium on Packaging and Trans-portation of Radioactive Materials, CONF 681001 USAEC (1968).
9.
C.E.
Dougherty, G.E. Harris, and R.R. Wright, Evaluation of Materials Used in Fire Resistant Phenolic Foam, K/TL-729, Oak Ridge Gaseous Diffusion Plant (1978).
159.6 351 10.
Personal communication with J.T. Thomas (1979).
(
mm
ENCLOSURE II The attached Engineering Drawings for the borated phenolic foam insulated seven element shipping container form the bases for calculational mock-ups.
d 1596
.552
['
i ai +' ' /t.4 22
JOCU V E \\~~
3 AGE DU
_ _ EJ A\\C,a W08090b2N NO. OF PAGES
/
REASON:
O PAGE ILLEGIBLE:
O HARD COPY FILED AT:
PDR CF OTHER O BETTER COPY REQUESTED ON
/
/
@ PAGE TOO LARGE TO FILM:
@ HARD COPY FILED AT:
PDR h
OTHER
@ FILMED ON APERTURE CARD NO.190F29o02.G 1596 Y53
DOCU V E \\~
3 AGE 3J__EJ A\\!
a 9 9 0 E 2 9 0 fo A b NO. OF PAGES
/
REASON:
O PAGE ILLEGlBLE:
C HARD COPY FILED AT:
PDR CF OTHER O BETTER COPY REQUESTED ON
/
/
Z PAGE TOO LARGE TO FILM:
2 HARD COPY FILED AT:
PDR OTilER
@ FILMED ON APERTURE CARD NO. Wo8o29000'O/
1596 454
ENCLOSURE III The following Table 1 of Appendix 1 of SNM-23 License Amendment No.
8, is attached to update the table to conform to this amendment request and previous corrections prior to NRC approval of Amendment No.
8.
Changes indicated on the following sheet revisions were documented by letters as follows:
Letter to NRC from Work Location No.
T.I.
dated:
Wording Change April 13, 1978 (21), (68)
May 5, 1978 (22), (2L), (24), (32), (33),
(48), (54), (55), (59), (67),
(79)
~
This request (30) to eliminate reference to four elements 1596 !55 12744
E.N.
79-10 Feb. 12, 1979 TABLE 1
?
LOCATION LOCATION NO.
NAME MSQ OPERATION GENERAL MFG. AREA CLEANING ROOM (20)
Pickling & Rinse I lot fuel plates, each Pickle fuel plates tanks lot of plates 7 468 gm 235U (21)
Degreaser 1 lot fuel plates Degrease fuel cach lo.t of plates plates I 468 gm 235U
< 12 fuel plates in the degreaser at one time.
(22)
Rinse tanks 1 HFIR outer element Rinse elements (deionized water) or 1 HFIR inner element one HFIR element or 10 HFBR or similar at a time or up elements with 7 235 U to five box-type content (a cart of elemen$ at a time 10 HFBR or similar (remainder of box-elements may be in elements to be in-the work area) side storage cart)
(23)
Deburr & clean 1 HFIR outer element Remove burrs and or 1 HFIR inner element chips and wipe or 10 HFBR or similar clean elements with 7 235U content (a cart of 10 HFBR or similar elements may be in the work area) maximum no. of elements being deburred & cleaned Element Assy. Room at a time - 2.
1 HFIR outer element Assemble element (24)
Assembly stand or 1 HFIR inner element
+ 23 fuel plates in box, the box of plates at lease 6" from the element.
(25)
Storage array
_20 storage positions Store fuel
< one lot of fuel plates plate in per position preparation each lot of plates for assembly 7468 gm 235U or 24 plates.-into elements.
(26)
Bench Tone lot of fuel plates Inspect and each lot of plates deburr fuel 7468 gm Z350 or 24 plates plates.
1596 756 12744
E.N.
77-10 TAllLE 1 Feb. 12, 1979 Rev.B LOCATION LOCATION NO.
NAME MSQ OPERATION
~
GENERAL MFG. AREA
~
7 235U or Assemble compacts,
_ 468 gm (27)
Fuel plate assy.
< 24 compacts or 12 frames & covers.
assemblics One assy. has 2 compacts (28)
Vacuum storage 8 storage positions Store 'as welded' array 3 468 gm 235U or fuel plate
< 12 assemblies per assemblies.
One position assy. has 2 compacts (29)
Element storage 3 element carts Store 'in process' array or 3 6M containers elements or 'as (near auxiliary 6M containers to received' U038 generator) have 7 9.6 Kg 235U per container (30)
Storage array 10 shipping containers, Store completed (near overhead 5 inner HFIR elements elements or door) and 5 outer HFIR
'as received' U030 elements with one element per container; or 10 containers with
~
HFBR or similar elements with 7 235U content per element or 10 6M containers 7 9.6 Kg 235U per container; or a total of 10 of any of the above containers 235U Trim edges and/or (31)
Shear
] 468 gm
< 24 fuel plates or ends of fuel 5 GM containers plates or 7 9.6 Kg 235U per temporarily store container as received U308 (32)
Weld 1 element cart; maximum Weld fittings or Milling machine shop number of elements being store elements worked on in work station at a time - 2.
(33)
Miller, Kearney 1 element cart; maximum Mill or store and Trecher number of elements being clcmants worked on in work station at a time - 2.
(34)
Drill press 1 HFBR or similar Drill holes in element elements as required.
. 1596 57 1z744
E.N.
79-10 Feb. 12, 1979 TABLE 1 Rev. B 3
LOCATION NO.
LOCATION NAME MSQ OPERATION (46)
Monarch lathe 7 one inner or one Machine HFIR outer HFIR element elements (47)
Storage array 4 element carts Store 'in process elements.
General Mfg. Area 235 (48)
Hot bond mill 7 936 gm U
Hot roll bond
& Grieves Hendry 24 fuel plates and and load oven.
12 bonding assys; degreasing 12 bonding assemblies rack.
are to be at least 6" from the nearest fuel plate and remain on work bench until oven is empty.
(49)
Trent furnace 7 4 68 gm 235U Anneal fuel 24 fuel plates plates (50)
Hevi-Duty 7 2.808 Kg 235U Anneal fuel furnace or 144 fuel plates plates (51)
Storage array 5 HFBR shipping Store completed containers or similar elements shipping containers for box-type fuel elements (4 elements maximum per container)
(52)
Sciaky welder one inner or one Weld, assy. or outer HFIR element remove rings, remove spacers, HFIR elements (53)
Dispatch oven one inner or one Assemble or re-outer HFIR element move spacers HFIR elements (54)
Roll swage BNL one HFBR or similar Assemble & roll element plus 48 swage elements fuel plates. Fuel l}g6 lJO plates in boxes to be ycg placed in designated areas on work bench. Boxes separated by 6" min. spac-ing.
No element to be placed on work bench. Work bench to be used with one roll swage at a time.
(55)
Roll swage ORR one HFBR or similar Assemble & roll element plus 48 fuel swage elements plates.
Fuel plates in ~
boxes to be placed in designated (cont) 12744
E.N.
79-10 Feb. 12, 1979 TABLE 1 Rev. B LOCATION #
LOCATION NAME MSO OPERATION (55) continued areas on work bench. Boxes separated by 6" minimum spacing. No element to bc placed on work bench. Work bench to be used with one roll swage at a time.
(56)
Cold roll mill 7 468 gm 235U Cold roll fuel or 24 fuel plates plates and load degreasing rack Check single plates at fluoroscope (57)
Work place under 1 element cart Store 'in process' crane and/or shipping or completed container element or per-form misc.
operations on element Load shipping containers (58)
Storage array 48 storage positions Store 'in process'
< one lot of fuel or completed plates or one HFBR fuel plates, or or box-type element HFBR and/or ORR Each lot of plates elements 7 468 gm 235U w
24 plates (59)
Press Drake 7 936 gm 2350 or 48 Blank, form fuel plates; up to 25 plates plates or load may be in temporary degreasing rack assembly, w/no more than 24 plates outside temporary element assembly.
(60)
Storage array 710 waste or material Store sealed discard (laundry) drums waste material Any drum to contain 7 discard drums 235 24 gms U& 6 6M and load, seal containers with < 50 and store GM f uel plates or equival-containers ont with 7 975 gms 235U each container.
Inspection (61)
Storage array 52 storage positions Store 'in process'
< one lot of fuel or completed fuel plates per position plates Each lot of plates 7 468 gm 235U 1596 J59 24 plates 13744
E.N.
79-10 Feb. 12, 1979 TABLE 1 Rev. B f
LOCATION #
LOCATION NAME MSQ OPERATION (62)
Surface plate 1 IIFIR inner or Inspect element outer fuel element (63)
Inspection 7 468 gm 235U or Inspect fuel Table #1 24 fuel plates plates 235 (64)
Inspection
< 468 gm U or Inspect fuel Table #2 24 fuel plates plates (65)
X-ray homogeneity 7 468 gm 235U or Inspect fuel scanner #1 24 fuel plates plates (66)
X-ray homogeneity 7 468 gm 235U or Inspect fuel scanner #2 24 fuel plates plates
- (67)
Ultrasonic test 7 585 gms 235U or Inspect fuel
< 30 fuel plates with plates up to 6 plates immersed in water. All fuel plates not being proces-sed are to be in boxes.
Boxes of fuel plates are to be separated from other boxes of fuel plates by at least 6".
- (68)
Storage array 18 storage positions Store "in process" 16 positions for < one or completed fuel lot of fuel plates per plates position, each lot of 235U Store "in process" plates < 468 gms or 24 plates and 2 or completed element carts.
elements 235U or Inspect fuel (69)
Inspection
< 468 gm Table #3 24 fuel plates plates (70)
Inspection 7 468 gm 235 U or Inspect fuel Table #4 24 fuel plates plates (71)
Inspection 7 468 gm 235U or Inspect fuel Table #5 24 fuel plates plates 235 (72)
Inspection 7 468 gm U or Inspect fuel Table #6 24 fuel plates plates (73)
Inspection 7 468 gm 235 U or Inspect fuel Table #7 24 fuel plates plates (74)
Element channel one element liFIR Probe element probe or box-type channels 1596 360
E.N.
79-10 TABLE 1 Rev. B Feb. 12, 1979 c
5 LOCATION LOCATION NO.
NAME MSQ OPERATION (75)
Storage array 40 storage positions Store 'in process'
< one lot of fuel or completed fuel plates per position plates Each lot of plates 7 468 gm 235U 24 plates 2350 or Fluoroscope and (76)
Fluoroscope 7 468 gm room 24 fuel plates punch or fluoro-scope inspect fuel plates (77)
Radiography one (1) inner or Rediograph room outer HFIR element elements or or one (1) cart of fuel plates HFBR or ORR elements or 1 lot of fuel plates 7 468 gm 235U or 24 fuel plates (78)
Storage array 20 storage positions Store 'in process'
< one lot of fuel or completed plates per position fuel plates Each lot cf plates 7 468 gm 235U or 24 fuel plates 235U or Gamma count and (79)
Gamma count 7 585 gm and Alpha count 7 30 fuel plates alpha count 235U (includes 6 standard content of fuel plates). All fuel plates plates not being processed are to be in boxes.
Boxes of fuel plates are to be separated from other boxes of fuel plates by at least 6".
(80)
Storage array 4 standard 30 901.
Store standards waste drums with 3,7, for waste drum 12, & 24 gms 235U counting (81)
Storage array 1 element cart Store 'in process' elements (82)
Degreasing rack 7 468 gm 235U or 24 flove one lot of g
cart (two) fuel plates or < 3.3 fuel plates in two 235U 7 one bottle degreasing racks or Kg of U 03 8 Per cart.
one bottle of U 038
}$9f
}fl.
--