ML19296C788
| ML19296C788 | |
| Person / Time | |
|---|---|
| Site: | 07000033 |
| Issue date: | 10/10/1979 |
| From: | Sherman F TEXAS INSTRUMENTS, INC. |
| To: | |
| References | |
| 14434, NUDOCS 8002280473 | |
| Download: ML19296C788 (40) | |
Text
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TEXAS INSTRUM ENTS INCORPORATED MCT ALLU RGICAL M ATCRI ALS DIVISION October 10, 1979 g
If Kictivro
%e' hg7, 9197;?,,.
Mr. Leland C.
Rouse, Chief 01-gj Fuel Processing & Fabrication Branch 4
-~
Div. of Fuel Cycle & Material Safety g*Qr
' i' /
m, U.S.
Nuclear Regulatory Commission 6
w.,7 A
Washington, D.C.
20555
Reference:
SNM-23, Docket 70-33 Gentlemen:
It is requested that U.S.N.R.C.
License No. SNM-23, Docket Number 70-33, dated July 10, 1979, by latest Amendment Number 11, be amended to:
1.
Update page changes to reflect previous U.S.N.R.C.
authorized text changes.
2.
A thorize page changes to the " Health and Safety Manual" to remove requirements for beta-gamma surveys of surface contamination and update alpha surface contamination surveys.
3.
Authorize page changes to the " Nuclear Safety" portion of the license to permit the fabrication of box type fuel elements with less than or equal to 93 weight percent enriched utanium in the form of U 0g.
3 Please find enclosed ten copies of this letter, Attachment I (delineating page changes and/or additions), and associated page changes and/or additions.
Also, please find enclosed check number 253991 in the amount of $1400 to cover the license amendnent as per 10 CFR 170.31.
B-Sincerely, s
o; ww 9
DCCKETED J
F.
L. Sherman USNRC Manager HFIR Project
'7 -
OCT 0. 4 '979 > W h/
1 l' M * ".
/ck NMS5
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- Mall SECTICN
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EC Attachments 8002280 8D A TTLEBORO, W A55 AChusr TTS C2703 0 1 LEPHONE 61722. 2000 e, C ABLE: T E XINS
ATTACHMENT I The following delineates page changes and/or page additions as requested for license amendment (changes are indicated by asterisks in page margins).
HEALTH AND SAFETY MANUAL CHANGES Changed to Original Page No.,
Page No.
Rev.
Reason for Change 7
7, A Item 5.2.1.2 was changed to incorporate previous authorized change dated August 29, 1973, from 200 feet per minute to 125 feet per minute.
13 13, A Item 5.5.1.2.1 is changed to alter units of urinalysis measurements from disintegra-tions per minute per milliliter to pico curies per liter.
Item 5.5.1.4 is changed to alter the action level for urinalysis results from 75 dpm/
1500 m1 to 15 pCi/ liter.
Item 5.5.1.5.1.2 is changed to alter the levels at which graduated actions will take plate.
14 14, A Item 5.5.1.5.1.4 is changed to specify return to work criteria (i.e.,
15 pCi/
liter urinalysis result).
19 19, A Item 8.1 is changed to reflect reference sources used for alteration of alpha contamination control.
Item 8.2 is changed in its entirety to delete beta-gamma contamination control criteria and to update alpha contamination control criteria.
20 20, A Item 8.3 is changed to reference specific items of alpha contamination control measurement frequencies of item 8.2.
Item 8.4.2.1 is changed to specify actions taken in the event of alpha contamination found to exceed control limits of 8.2.
HEALTH AND SAFETY MANUAL CHANGES (continued)
Changed to 0,riginal Page No.,
Page No.
Rev.
Reason for Change 20A, o Page added to continue item 8.4.2.1.
Appendix D, Appendix D added to provide bases of Pages 1-11, bioassay monitoring program.
Rev. O SECTION II NUCLEAR SAFETY CHANGES Original Changed to Page No.,
Page No.,
Rev.
Rev.
Reason for Change 6A, O 6A, A Original paragraph C is changed to paragraph D and a new paragraph C is provided as a justification for permitting the processing of lesser uranium enrichments of U 0g.
3 6B, O Page added to continue paragraph D and to establish special handling of differing enrichments of U 033 APPENDIX 1 CHANGES Original Changed to Page No.,
Page No.,
Rev.
Rev.
Reason for Change 1, C 1, D Text is changed to make reference to lesser enrichments of U 08 and other 3
box type elements.
2, C 2, D Specifications are changed to incorporate lesser enrichments of U 03 3 and physical dimension limits of other compacts.
2A, O New page to continue physical descriptions of fuel plates.
3, C
3, D
Specifications for other fuel plates and other fuel elements.
APPENDIX 1 CHANGES (continued)
Original Changed to Page No.,
Page No.,
Rev.
Rev.
Reason for Change 4,
D 4, E A paragraph was inserted to make reference of 235U limit applicability to lesser enrichments in U 03 8 powder and other processing forms.
4A, O New page to continue description of
" Receipt and Storage of Fuel Material".
CHANGES TO APPENDIX I AS DOCUMENTED IN TI LETTER TO MR.
L. C.
ROUSE DATED MAY 5, 1978 Appendix 1, Page 8, first paragraph, last sentence 3.2 kg U should be 3.7 kg U.
Second paragraph; CI per cell of 0.3 should be 0.4.
Total for array of 1.5 should be 10.0.
Appendix 1, Page 9 Line 15 164 liters should be 55.7 liters.
Line 16 21'l/2" should be 15".
Line 25 1/32 should be 10/32.
Line 26 164 liters should be 55.7 liters.
Appendix 1, Page ll, revision D replaces revision C; Description of " Hot Roll Bond Packages" is expanded.
Page llA is added to continue description.
Appendix 1, Page 12, Note added under Cell Size - 24" x 24" x 36";
"These are the inside furnace dimensions occupied by fuel plates".
Appendix 1, Page 14, MSQ/ unit for " blank" (Ref. No. 59 ) change from "24 fuel plates, 468 gm 235U" to "48 fuel plates, 936 gm 2350 (24 fuel plates or less to be in temporary 3 FIR element assembly)".
Appendix 1, Page 15, third paragraph, 148/1000 should be 178/1000, and 14.8 should be 17.8.
Appendix 1, Page 16, MSQ/ unit for " Form" (Ref. No. 59 ) change from "48 fuel plates, 936 gm 235 " to "48 fuel plates, 936 gm 2350 (25 U
fuel plates or less to be in temporary HFIR element assembly)".
Appendix 1, Page 18, second paragraph, delete third sentence beginning with "The subcriticality of HFIR storage was...."
Also delete footnote number 2 at bottom of page.
Appendix 1, Page 19, second paragraph; add footnote (1) after box-type elements " minimum spacing between plates in a box-type element is 0.080 inches".
CHANGES TO APPENDIX I AS DOCUMENTED IN TI LETTER TO MR.
L. C.
ROUSE DATED MAY 5, 197'8 (CONTINUED)
Also, Appendix 1, Page 19, fifth paragraph, " Sixty-five fuel plates" changed to "67 fuel plates".
"46 plates" changed to "48 plates".
Appendix 1, page 20, third paragraph, third sentence, Mass category "B"
changed to "F";
CI per cart "0.1" changed to "0.5".
Fifth paragraph, add words at end of third sentence "in a 2 x = x 1 array".
Appendix 1, page 21, sixth paragraph, " Assay index" change to
" array index"; seventh paragraph, add sentence at end " Transport carts are not used for long-term storage next to a work station.";
and bottom ling of page - change sum of all CI values to "less than 150".
e
E.N.
79-59 Sept. 27, 1979 Rev. A Descriptions of operations, storage arrays, and assembly of fuel elements are containti in Appendix 1.
This appendix also presents the nuclear criticality safety evaluations of individual operations, potential neutron interaction among operations at the facility and the influence of the water sprinkler system on the margin of suberiticality.
C.
JUSTIFICATION FOR APPLICATION OF HIGHLY ENRICHED (93 W/O U)
LIMITS TO LESSER ENRICHMENTS (10-93 w/o 235U) IN THE HFIR PROJECT FABRICATION PROCESS 35 The application of 93 w/o enriched uranium U limits to lesser enrichments within the HFIR Project is acceptable (despite the reporting of numerous anomalies for arrays of fissile units under varying conditions of unit moderation, inter-unit moderation, array reflection, unit density, unit shape, unit enrichment, and unit containment) for the following reasons.
1.
All units for processing and storing fissile material in large quantities (i.e.,
1-liter polyethylene bottles) are restricted in volume and, therefore, do not suffer the consequences of expanded unit volumes as reported anomalies for reduced enriched units.
That is to say, that no more than 1-liter of U 03 8 at any enrichment is processed as a single bulk unit.
2.
All units for processing and storing fissile material in discrete single lot quantities as specified in Appendix 1,
" Nuclear Safety Justification", are restricted in overall unit volume by virtue of unit containment (i.e.; compact charge jar, compact and plate trays; compact storage and annealing units; plate rolling; annealing; forming; storage and testing; element assembly; storage and packaging).
Since processing and storage volumes of units within the HFIR Project are not altered (i.e., expanded) and since the units have been evaluated under conditions of maximum reactivity (optimum inter-unit moderation and fulg3geflection),
the reported anomaly due to dilution with U does not parallel conditions of processing or storage within the HFIR Project.
Unit 35U densities, surface-to-surface separations and unit cror.-sectional areas remain constant.
l E.D.
Clayton, " Anomalies of Nuclear Criticality" PNL-SA-4868 Rev.
5, Pacific Northwest Laboratory by Battelle Memorial Institute, June 1979.
- 6A -
E.N.
79-59 Sept. 27, 1979 Rev. 0
- D.
' ADMINISTRATIVE PROCEDURES Maximum safe quantities (ME2) are those specified in Appendix 1.
All fuel plates not in process are returned to storage locations in storage arrays at the completion of a work shift.
Management shall assure that approved operating procedures associated with radiological safety and criticality shall be followed.
MSQ's will be posted at each work station, each storage array and on each transportation or storage cart used for SNM The 235 MSQ's will be defined as listed (e.g.,
grams contained U,
number of SNM bearing plates or elements, number of shipping containers, number of storage units of SNM in Table 1 of Appendix 1).
To assure control of potential material cross-over and mis-identification of uranium enrichments:
a.
Only U 08 powder material of identical enrichment is 3
processed through the powder-handling operations at one time.
b.
Color-coded follow sheet booklets (distinctive of enrichment) accompany U 038 through the powder-handling-phases of the operation.
c.
Only supplied enrichments of U 03 8 are utilized within the facility (i.e.,
no blending of differing enrichment U03 8 occurs).
d.
Containers of lesser than 93 w/o U-235 U 03 8 are identified as to material enrichment contained.
- 6B -
E.N.
79-59 Sept. 26, 1979 APPENDIX 1 Rev. D I.
GENERAL INFORMATION TI proposes to fabricate and assemble fuel elements for the ORNL High Flux Isotope Reactor (HFIR) and for various box-type elements, such as the BNL High Flux Beam Reactor (HFBR), the ORNL Oak Ridge Research Reactor (ORR) and other similar test reactor fuel elements and plates with no greater 235U content than HFBR 235U).
fuel elements at cqual to or lesser enrichments (10-93 w/o All operations will be performed in the nuclear facility which has been described in the Consolidated Renewal Application for Special Nuclear Material License No. 23 April 2, 1973.
It is the purpose of this appendix to analyze all fuel handling operations which will be required for the performance of this work and to set forth nuclear safe operating procedures.
HFIR fuel elements consist of two arrays of curved aluminum
- clad, U 08-aluminum matrix plates which are arranged in the 3
form of annuli.
Both inner and outer elements are fabricated by TI; however, final assembly of the two elements will take place at ORNL.
Box-type fuel elements consist of fuel plates in a stack, separated by cooling channels.
HFBR assemblies have 18 plates, ORR assemblies have 19 plates.
Other test reactor fuel elements may range from 17 to 21 plates per element.
Plates are fabricated from a mixture of aluminum and U 038 (93%
enriched maximum) powders which are formed into compacts, assembled into aluminum picture frames, clad with aluminum cover plates, and hot roll bonded.
Those plates which form the inner annulus of the HFIR assembly will contain a small amount of B4C powder as a burnable poison.
A process flow diagram (Attachment "I"
1973) presents the sequence of manufacturing and assembly operations.
II.
NUCLEAR SAFETY CONSIDERATIONS The primary method used to insure nuclear safety is batch size control of fissionable material in all processing, handling, and storage areas.
A safe batch size for an operation is defined as " Maximum Safe Quantity" (MSQ).
Flooding with water is not considered a credible possibility, since Attleboro is not located on a flood plain and there are flood doors in the manufacturing area.
All SNM is handled and stored at least four inches above the floor, except for waste and laundry drums, 6M containers, and the vacuum cleaner in the press room.
Full reflection is assumed in evaluation for MSQ for each operation.,
APPENDIX 1 E.N.
79-59 Rev.
D Sept. 26, 1979 The following di.ta represent significant parameters of fuel material consideced in nuclear safety evaluation.
U Og Powder 3
Enrichment i 93 w/o 8.2 gm/cc Density
=
84.5 w/o
% Uranium
=
235U Density i 6.45 gm/cc Fuel Compacts HFIR Inner HFIR Outer Dimensions (nominal)
Dimensions (nominal) 0.269" x 2.162" x 2.927" 0.269" x 2.166" x 2.642" Loading (nominal)
Loading (nominal) 15.18 grams 235U 18.44 grams 2350 0.164 grams B-10 HFBR ORR Dimensions. (nominal)
Dimensions (nominal) 0.213" x 2.1505" x 2.458" 0.200" x 2.368" x 2.517" Loading (nominal)
Loading (nominal)
Up to 19.5 grams 235U Up to 15.9 grams 2350 Overall Maximums for Other Compacts Dimensions 0.4" x 2.6" x 3.3" 235 Total Loading (nominal) up to 19.5 grams U.
E.N.
79-59 Sept. 26, 1979 APPENDIX 1 Rev. O Fuel Plates HFIR Inner HFIR Outer Overall Dimensions (nominal)
Overall Dimensions (nominal)
Length
= 24" Length
= 20" Width
= 3.626" Width
= 3.213" Thickness = 0.050" Thickness = 0.050" Fuel Dimensions (nominal)
Fuel Dimensions (nominal)
Length
= 20" Length
= 20" Width
= 3.067" width
= 2.762" Thickness = 0.029" Thickness = 0.029" Leading (nominal)
Loading (nominal)
=
=
235U 15.18 gms 235U 18.44 gms Poison content = 0.0164 gram B-10 HFBR ORR Overall Dimensions (nominal)
Overall Dimensions (nominal)
Length
= 23.750" Length 24.625" or longer
=
Width
= 2.627" Width
= 2.797" approx.
Thickness = 0.050" Thickness = 0.050" or 0.065" Fuel Dimensions (nominal)
Fuel Dimensions (nominal)
Length 22.875" Length 23.562"
=
=
Width
= 2.243" Width 2.473"
=
Thickness = 0.023" Thickness = 0.020" Loading (nominal)
Loading (nominal) 35 235 Up to 19.5 grams U
Up to 15.9 grams U
Overall Maximums for Other Fuel Plates Overall Dimensions (nominal)
Length 30"
=
Width 4"
=
Thickness = 0.065"
- 2A -
E.N.
79-59 Sept. 26, 1979 APPENDIX 1 Rev. D Overall Maximums for Other Fuel Plates (continued)
Fuel Dimensions (nominal)
Length
= 25.5" Width 3.25"
=
Thickness =
0.040" Loading (nominal)
Up to 19.5 grans U
Overall Maximums for Box Tv-e Fuel Elements Overall Fueled Core Dimensions Length 25.5"
=
Width 3.25"
=
Thickness =
3.50" Loading (nominal)
Up to 351 grams 235U since the plates assembled into HFBR elements have the highest fuel loading and do not contain boron, they are the most reactive of the several types.
Their parameters therefore, are used in all nuclear safety calculations, since the MSQ's established are the same for all plates regardless of type.
Those evaluated operations having hydrogen present are the ultrasonic irlpection (wa ter), the pickling (water and acid), the element clea sng (water) and the vapor degreasing ( t)
- hloro-ethylene).
Equivalent cell size for use with ANSI N16.5 is determined by the cube root of the volume.
ANSI N16.5 may be applied for fuel plates per paragraph 6.3 (non cubic cells).
The shape of the cell in storage arrays holding lots of fuel plates is consistent with the shape of the lot of fuel plates in a tray or box.
All arrays of compacts, compact charges, lot charges and fuel plates have the following properties:
1.
Be constructed of metal 2.
All storage locations are a minimum of 4" above the floor.
3.
Spaces between storage locations are covered with metal sheet.
4.
The mass limit assigned to each storage location will be consistent with ANSI N16.5-1975.
In addition, storage arrays not subject to hydrogenous moderation, the vault, will have limits based on a maximum H:U atomic ratio of 0.4 and limited in mass to 3 2 Kg 235U (4.0 Kg U308).
Storage 3_
E.N.
79-59 Sept. 27, 1979 APPENDIX 1 Rev. E arrary of compacts, compact charges, lot charges, and fuel plates in areas employing water sprinklers for fire protec-tion will have a protective covering of metal sheet sloped to prevent water accumulation and the mass limit for each storage location will not exceed 500 grams 235U (537 grams U0)-
38 The water reflected spherical critical mass' of hiah density U038 is greater than 33.5 Kg U (93.2) (or 31 Kg 233U), thus, double batching a single unit of either type of array is not a significant contingency.
The mass limits of 500 g and 3.2 Kg 235U and their associated number and all volumes are such that double batching all the units in an individual array would not result in a criticality incident l.
III.
JUSTIFICATION FOR NUCLEAR SAFETY **
Unit 235U limit values and justifications presented herein for U(53.2)3 8 are applicable for the processing, transporting, 0
and storing of U 03 8 of lesser enrichments (i.e., 10-93 w/o) providing overall unit volumes are restricted to those described in this part (i.e.,
compact and charge jar trays, 1-liter polyethylene bottles, 0.5 liter SS issuing cans, 3.2 liter SS issuing cans, V-blender, overall compact dimensions, overall plate dimensions, overall element dimensions, plate storage boxes and storage trays, criticality carts, etc.).
The demonstration of applicability is provided in Section C of this part.
A.
FABRICATION OF FUEL COMPACTS 1.
Rece'ipt and Storage of Fuel Material The U 03 8 powder used in fabrication of compacts is received from a supplier who is licensed by the Nuclear Regulatory Commission (NRC) or under contract to the Department of Energy (DOE).
The powder is received in NRC or DOT approved shipping containers.
Any received container found to be wet or damaged is brought to the attention of the Health / Physics officer who will determine the appropriate procedures to be followed in unpacking.
As many as twelve containers, each holding up to three 1-liter bottles, each bottle containing a maximum of 3.2 Kg 235U (4.0 Kg U(93) 3 3), may be 0
L ANSI N16.5-1975, Table 5.2 Numbers in circles refer to descriptions in Table 1.
-4
E.N. 79-59 Sept. 27, 1979 APPENDIX 1 Rev. O 1.
Receipt and Storage of Fuel Material (continued) re eived 'n a
' gl hipment and these are stored 2
30 in an arrangement no more reactive han t at o the shipment.
One container at a time is opened and individual bottle are transporte on a cart to gamma counting 79 and weighing 3
After these operations, a maximum of two bot les are stored in each birdcage or 6M container.
Sampling is also erformed, one bottle at a time, in a drybox 2), after which the bottles re returned to bir cages of 6M containers
-4A-
v E.N.
79-59 APPENDIX 1 Rev. D Sept. 27, 1979 J
Basis:
Sieve, Blend and Weigh:
The 3.4 and 3.7 Kg U of these operations is abcut 1/8 of the water reflected subcritical mass of the 33.5 Kg U unit in Table 5.2 of ANSI N16.2-1975.
The assumed concrete reflection at the cell boundaries reduces the 33.5 Kg to 25.2 Kg U.
Double batching the MSQ, therefore, does not compromise the sub-criticality of the operations.
To address the possible neutron interaction with other MSQ's or storage arrays, the dryboxes are considered as cells in a 1000 unit array, the array referenced in Table 5.2 of ANSI N16.2-1975 in the analysis of the birdcage arrays in 2 above.
Specifically, 8.7 Kg U with an H:U < 0.4 in a 1000 unit array reflected by 20.3 cm of concrete.
These dry operations would be assigned an array index (Section 5.1 of ANSI N16.5-1975) of 3/1000.
Under the CI system, 3.7 Kg U is a mass category A in a 227 liter volume giving a CI for each of 0.1 and a total CI of 0.3.
Vault Storage Array and Vacuum Storage:
The 3.4 Kg U in 40.6 cm cubic cells is addressed in Table 5.2 of ANSI N16.5-1975 by conservatively choosing the smaller cubic cell dimension of 38.1 cm, the 1000 unit array of 8.6 Kg U
(_/
units.
This mass limit is reduced to 6.45 Kg U because of the concrete reflector, a factor of 0.75 for 20.3 cm thick concrete.
The 3.4 Kg U MSQ is less than the allowed 6.45 Kg U.
Double batching of all units in the 1000 unit array would reduce the margin of subcriticality specified for arrays in Table 5.2 but 1
by less than 0.02 in keff. Double batching does not lead to criticality.
The array index for the 25 units is thus 25/1000 and in the CI system, the mass category is A, gives a CI per cell of=3.4 and the total for the array is 10.0.
The 12.1 Kg U in the vacuum storage chamber as oxide at an H:U < 0.4 is subcritical double batched, being less than the subc?itical value of 33.5 Kg U.
An array index is assigned from the 216 unit array of Table 5.2 in ANSI N16.5-1975 having an allowed mass limit of 17.8 Kg U.
This is reduced to 13.3 Kg U because of the concrete reflector.
The index is 1/236.
The CI value for a mass category J in a cell volume of 95 liters is 12.2 Double batching is not possible in vacuum storage because of limited capacity.
Press Room Storage and Work Station:
Each compact tray is covered to prevent internal moderation and has typical dimensions of 8 3/8 : 5 3/8 x 3 1/4 in.
1 J.
T.
Thomas Nuclear Science & Engineering Vol 62 page 424 1977
-3
+/
E.N.
79-59 Sept. 27, 1979 APPENDIX 1 Rev. E J
The cor,act trays contain a mass of 469 g 235U and each is assigned a volume of 80 liters in storage.
Table 5.2 of ANSI N16.5-1975 provides a maximum mass limit of 8.6 Kg U in a 38.1 cm cubic cell of a 1000 unit array, a limit adequate for the ccacrete reflection assumed.
This is conservatively a smaller cell volume than exists in the storage array.
The 469 g 235U units may all be double batched without causing a significant change in keff. The array index for storage is 10/1000.
The units are a mass category A in the CI system and for a cell volume of 80 liters, the CI for a cell is 0.2 giving a total of 20 for storage.
At the press station, 24 Jars each containing a charge for a compact are stored in a single tray with dimensions 8 1/2 x 21 5/8 x 2 1/2 inches.
The assigned minimum 6" separation from other SNM defines a volume of 55.' liters and corresponds to a cubic dimension of 15".
The 0.5 Kg U in the tray is a suberitical quantity dry and in the event of immersicn in water because of quantity, slab-like geometry and low average uranium density.
The tray of jars is less reactive than a tray of compacts reflected and with optimum moderation!.
As many as 32 trays of compacts in a 4 x 4 x 2 arrangement, in contact horizontally and separated 5.7 cm vertically is subcritical with the trays flooded, optimum moderation between trays and the array re-flected by 30 cm of water'.
The array index is, therefore,
\\/
10/32. This is a category A unit in the CI system and is assigned a value of 0.1 with the associated volume of 55.7 liters.
3.
Vacuum Anneal comoacts Compacts are transported to the vacuum anneal operation on a cart.,The cart has a capacity for six trays and each has an associated volume defined by 9 x 20 x 15.25 inches.
The SNM per tray is 0.5 Kg U.
The vacuum furnace is cylindrical in shape with its axis horizontal.
The furnace door is at one end of the cylinder and the lowest part of the furnace chamber is 38" above the floor.
The exterior of the chamber is water cooled and there is no access of water to the interior.
The furnace h as three shelves each accommodating a tray with dimensions 11 1/2 x 20 x 2 inches.
Each tray holds 48 compacts and the shelves have a minimum separation of 4 1/2 inches.
The vacuum furnace door will be opened with an operator in attendance when loading and unloading compacts.
1 ORNL/CSD/TM55 v.
E.N.
79-59 APPENDIX 1 Rev. C
~
Sept. 27, 1979
)
Equiva-MSQ/
Ref. Number No.
Cell lent Assumed Un'it Table 1 Units Size Cell Size Reflection (j)(])
24 fuel 01.
2
- 24" x 24" 27" 30 cm water 468 gms 235U x 36" (These (0.503 Kg U) are the inside fur-nace dimensions occupied by fuel plates).
Basis:
By Table 5.2 of ANSI N16.5-1975, a 1000 unit array of 61 cm cubic cells is allowed a mass of 18.3 Kg U.
This cell is smaller than that associated with the operation (68 cm) and the mass of 0.5 Kg U is adecuate to compensate for double batching.
An array index of 2/1000 may be assigned to this operation.
The volume of 322 liters and a mass category A unit gives a total CI of 0.2.
3.
Degrease, Anneal, Store, Inspect & Cold Roll Fuel Plates After hot roll bonding, fuel clates are varor decreased 21 in trichloroethylene.
A degr' easing rack $3 holds a maximum of 12 plates and the hoist that lifts the rack into the degreaser can only accomIcodate one rack at a time.
There are no more than 12 plates in the degreaser at one M...e.
m The next operation istoanneal(})the#uelplatesupto 1000*F in an air furnace.
The annealing rack holds 24 plates maximum.
After annealing, the plates are cooled outside the furnace and the plates stacked in aluminum trays.
Bef, ore and after inspection for visible defects and also for cold rollin the plates are stored in an array in aluminum trays 8)
The inspection is performed on soecified fuel p ter and at a work station in the i.kspection area (63) O h ~
6 83, one lot at a time.
v v v Cold rolling is c~one at t.e cola rolling mill 56 one lot at a time.
After cold rolling, fuel plates are degreased in the degreasing racks and equipment described following hot roll.
o E.N.
79-59 APPENDIX 1 Rev. B Sept. 27, 1979 J
geometry less favorable than a sphere, thus obviating concern with double batching.
The array index value for this storage configuration is 48/1000.
The small cell has a volume of 131 liters which may be used for both cell volumes in the assignment of a CI value.
The mass category is A giving 0.1 for the CI and a total CI of 4.8 for the storage array.
4.
Flat Anneal, Inspect, Fluoroscope and Blank Fuel Plates Cold rolled fuel plates may be flat annealed by stacking the-between aluminum platens and heating them (900 F typ)
~0 Up to six lots of fuel plates (144 plates) are annealed at one time.
After this anneal, fuel plates may be i scope (h)nspectedforvisualdefects, inspected by fluoro-where reference hola are punched and later using the re:erence holes blanked 5)9 to final size.
Aluminum or cardboard boxes are used to hold each lot of fuel plates thru all suasequent operations.
Plates may also e ored a
in various arrays both before and after blanking 58 61..
The nuclear safety justification is based on the storage array with the minimum spacing.
NSJ Ecuiva-
\\/
MSQ/
Ref.. Number No.
Cell lent Assumed Unit Table 1 Units Size Cell Size Reflection Flat Anneal 50 144 fuel pl.
1 17" x 36" 13" Concrete 2.808 Kg 235U x 3.6" 8"
( 3. 014 Kg U) h 69)h Inspect 24 fuel ol.
) L, 3) 1 25.5" x 40" 26.13" 30 cm water 468 gm 235U x 17.5" Fluoro-(])
scope 24 fuel pl.
1 25.5" x 40" 26.13" 30 cm water 468 gm 235U x 17.5" (h
Blank
- 43 fuel pl.
936 cm 235U(24 fuel clates or 1 25.5" x 40" 26.13" 30 cm water less to be in tempo'ary HFIR x 17,5a r
element assembly)
Storage Arrav 8)(61)[68) us us 24 fuel pl.
Q (2 '5) 178 20" x 13" 18.4" Concrete 468 gms 2350 x 24" 3"
(0.503 Kg U)
- 14
"*N*
79-59 APPENDIX 1 Rev.
B Sept. 27,-1979 J
B a, sis :
Flat Anneal The cell associated with the 144 fuel plates is 17 x 36 x 3.6" giving an equivalent cubic cell dimensions of 13".
Using the 1000 unit array in Table 5.2 of ANSI N16.5-1975 with cubic cells of 30.5 cm, a mass limit of 5.8 Kg U would be allowed.
This is reduced to 4.3 Kg U for concrete reflection.
The single cell is a subcritical quantity and by Section 5.5 of N16.5 may be double batched without incident.
An array index of 1/1000 is assigned this operation and a CI value of 0.9 for a mass category A and cell volume of 36 liters.
Inspect, Fluoroscope and Blank Each of these is a suberitical operation by the above reference array and by the 0.76 Kg 235U limit of ANSI N16.1-1975.
Each would be conservatively assigned an array index of 1/1000 and a CI of 0.1 for a volume of 292 liters and mass category A unit.
Storage Array The 0.5 Kg U unit in an equivalent cubic cell of 46.7 cm satisfies the limits of the 1000 unit array of 45.7 cm cells in Table 5.2 of ANSI N16.5-1975 which allows 11.7 Kc U for a
\\*/
water reflected array and 8.8 Kg U for a concrete reflected array.
Double batching all units in the 1000 unit array is a subcritical configuration.
The array index for the storage array totals 178/1000.
Under the CI system the cell volume of 102 liters and a mass category A unit yield CI = 0.1 per cell and a total of 17.8 for the array.
5.
Inspect and Form Fuel Plates Fuel plates may be inspected for ultrasonic indications, fluoroscoped for internal dimensions, radiographed, X-ray scanned for uranium homogeneity, inspected for visual defects and dimensions, gamma counted, and alpha counted.
One lot of fuel plates is at each inspection at a time.
Ultrasonic inspection and gamma scan require standard fuel plates present, raising the quantity of fuel plates at those inspections to as high as 30 plates.
At ultrasonic inspection, up to six plates may be immersed at one time.
The ultrasonic tank is about 8' x 2' x l' deep.
One storage box of plates and the six standard plates may be adjacent to the tank during their inspection.
E.N.
79-59 APPENDIX 1 Rev. B Sept. 27, 1979 J
After comoletion of the various insoections listed above, plates are formed.
Again one lot o'f plates is processed at a time except in the case of HFIR fuel plates, a partially assembled element containing no more than twenty-four additional plates is at the work station.
This element is used for trial fitting.
NSJ Equiva-MSQ/
Ref. Number No.
Cell lent Assumed Unit Table 1 Units Size Cell Size Reflection h
All 63
)
Inspections 0
91 Q3 30 fuel ol.
63T 1
25.5" x 40" 26.13" 30 cm water 585 gms 235U x 17.5" (fh Form 48 fuel ol.
1 25.5" x 40" 26.13" 30 cm water 936 gm 235U(25 fuel plates x 17.5" or less to be in temporary HFIR element assembly).
%,j Basis:
The inspection and ultrasonic operations each involve a mass les's than the subcritical limit of 0.76 Kg U given in ANSI N16.1-1975.
The forming operation involving 0.94 Kg U in an equivalent cell of 26" is less than the allowable limit of 18.3 Kg for a 1000 unit array in.61 cm cell tabulated in ANSI N16.5-1975.
C.
FABRICATE FUEL ELEMENTS 1.
Pickle, Inspect & Store Fuel Plates Fuel plates for use in elements are sometimes vapor degreacad and then pickled twelve per rack up to two racks 20 at a time in acid water solution and then rinsed and dried.
The pickle tank is 24" x 48" with 20" of solution (377 liters).
The rinse tanks are either 24" x 47" with 20" water (369 liters), 24" x 47" with 17" water (314 liters) or 24" x 48" with 15 1/2" water (292 liters).
After nichling,, fuel plates are stored in an arrav in boxes OS tS 8) f6 L' f6 8) (753.
LI vw vv v
- lo
E.N.
79-59 APPENDIX 1 Rev. A Sept. 27, 1979
)
Since the outer fuel element is the more highly loaded, its parameters are used in the establishment of nuclear safety procedures are are applicable to the inner element.
Operations involved in assembly of an element are performed dry with the exception of cleaning of the finished element.
HFIR element criticality control parameters have been obtained from experiments performed with the elements at Oak Ridge National Laboratory Critical Experiments Facility l.
On the basis of, and evaluation by a member of the ORNL criticality group, a spacing of 24 inches from center to center of element is adequate to maintain subcriticality in the storage of elements (see Attachment "P"
letter dated 3-18-74 J.
T.
Thomas to R.
Knight:
A conservative value for an array index would be 1/9000 for each HFIR component in storage.
This value would also be applicable to HFBR and ORR elements in storage.
Fuel elements are set into positioning rings on wheeled carts and covered with fibre drums having metal covers while in storage or transport.
This prevents the possibility of internal hydrogenous moderation from the discharge of over-g,j head sprinklers.
The bottoms of the wheeled transport carts elevate the elements at least 4" from floor level.
A transport cart holds only one element in the center of its 32 in. square surface.
All operations and storage subsequent to welding which includ' e
inspection and machining, are performed with an MSQ of one element per work station.
For the purpose of assembling an HFIR element, there can be up to 369 fuel plates in an element and 23 fuel plates no closer than 6" to the exterior of the element at the element assembly work station.
The nuclear safety justification is the same as the calculations ~ which confirm the subcriticality of carts within 6" of SNM at work stations.
Elements are cleaned by immersing them in water and flushing.
1 Criticality studies have found that the complete immersion of an outer element in water is subcritical, the cleaning operation is safe.
Only a single element (inner or outer) will be cleaned at any one time.
I E.B.
Johnson.
" Critical Lattices of High Flux Isotope Reactor Fuel Elements", ORNL-TM-1808, (March 20, 1967) 2 ORNL/CSD/TM-55 18 -
E.N.
79-59 APPENDIX 1 Rev. A Sept. 27, 1979
)
Fabrication ocerations and storaces are cerforged in the following suc'cessive locations @ h h h h gj) h h h 8 0 8 0 0 0 0 0 0-3.
Box-Type Elements TI fabricates HFBR and similar box-type elements *with pro-cedures comparable to those shown in Attachment J, Page 2 (1976).
The HFBR element contains 18 N tel plates (0.351 Kg 235U) in a box arrangement separated by cooling channels, as shown in Attachment M (1976).
The HFBR element contains the highest fuel loading of the box-type elements, therefore the nuclear safety evaluations are based on HFBR elements.
MSQ's established will also be used for similar box-type elements with fuel loading not exceeding HFBR elements.
All operations on HFBR elements are performed dry with the exception of cleaning of the finished element and the use of alcohol (as a lubricant at assembly and machining operations).
,_j Sixty-seven fuel plates can be at the roll swage operation.
Up to nineteen of these plates can be in a fuel element and the remaining forty-eight plates are from fuel plate lots required to continue assembling fuel elements.
The remaining 43 plates are in respective lot boxes which are separated by 6" at the work station.
Some assembled HFBR fuel elements are stored in fuel plate racks..The 351 grams in an HFBR element is less than the 468 grams MSQ allowed per position.
Also, some assembled HFBR elements are in compartments on wheeled carts covered with fibre drums having metal covers in storage or transport.
This prevents the possibility of internal hydrogenous moderation from the discharge of overhead sprinklers.
The metal covering on top is firmly attached to the fibre drum.
The drum fits snugly on the floor of the cart.
The drum is not lifted off the cart to put in or remove elements.
Rather, the drum is rotated so that an 8" opening in the drum is over the desired element compartment.
In this way, only one element is exposed at a time.
A metal disc, with fingers welded on it, maintains the elements in compartments.
The annulus formed by the ten elements thereby has an internal diameter of approximately 10".
The bottoms of the wheel transport carts elevate the elements at least 4" from floor level.
These carts have a 32 inch square surface, and compartments for 10 HFBR or similar box-type elements as shown in this 1
Minimum spacing between plates in a box type element is 0.080 inches. -
E.N.
79-59 APPENDIX 1 Rev. A Sept. 27, 1979 appendix.
The carts are the same size as HFIR carts and
\\=
are kept in the same storage spaces as the HFIR carts The carts are no more reactive than the HFIR carts and would be assigned an array index of 1/9000 each.
Criticality justification for these carts is by the criticality indicator (CI) method.
The criticality indicator (CI) method used throughout is described in ORNL-CSD-INF4 8.
Applied to the carts having ten elements, giving a total mass of 3.76 Kg U and an effective volume of 336 liters defined by 32 x 32 x 22.875 inches.
The mass category is F giving a CI per cart of 0.5.
No more than 24 carts for HFBR or similar box-type elements or HFIR elements are utilized in operations.
The HFIR carts may contain 7.4 Kg U in an associated volume of 386 liters and also would be assigned a CI value of 0.1.
Operations following roll swage which may include weld-ing, riveting, machining, comb assembly, numbering, deburring and inspection are performed on one element at a time except for some welding operations when two elements are being alternately processed.
This is to allow for cooling.
The optional radiograph inspect g,j operation may be performed one element at a time.
Radiography is performed in a lead lined room and the element is on a table 24" above the floor.
Elements are cleaned by immersing them in water, flushing and drying.
Up to five elements are cleaned at a time with up to ten elements maximum in the work station.
l Calculations of HFBR elements immersed in water are shown to be subcritical when separated in water by 2" independent of the number of elements in a 2 x = x 1 array.
The 5 elements in the rinse tank have a minimum 2
surface separation of 6".
Nine or more elements are require.
at optimum spacing for criticality. It follows, therefore, that 5 elements at any spacing are suberitical.
Fabrication operations and stora as ar perf "m
'n the m
following successive locations: 54 41 47 Ss 68 81
@ @ @ @ @ @ @ @ @ @ @ e(55) 29D @
D.
TRANSPORTATION Move by Hand One lot of fuel plates, compacts, charge jars, compact lot charge or less or a single box-t/pe element may be hand carried.
s_-
3 ORNL/CSD/TM55 2
J.
T.
Thomas, Nuclear Criticality Assessment of ORR Fuel Element Storage ORNL/CSD/TM58.
E.N.
79-59 APPENDIX 1 Rev. A Sept. 27, 1979 j
HFIR elements are carried on transportation / storage carts designed to hold one inner or one outer HFIR element.
Box-type elements are carried on transportation / storage carts designed to hold 10 box-type elements.
Fuel plates in degreasing racks are moved on fuel plate carts designed to hold 12 fuel plates on each of two shelves.
Fuel compacts or charges in trays are moved on compact / charge carts with up to two lots of compacts or one lot of charges per shelf for each of three shelves.
Bottles containing 'as received' U30s are transported on a bott.la cart that holds a maximum of one bottle or the cart for fuel plate degreasing racks.
Administrative control limits one bottle to this latter cart.
The nuclear criticality safety evaluation of SNM materials being moved by hand or on carts is a benefit of the array index or criticality indicator method of analysis.
Calcu-lations have confirmed the suberiticality of carts within 6" of SNM material at work stations and materials in storage g,j arrays.
' Transportation and storace
- c rt are involved in he cartsarenotusedfo@rl@ong-termstoragenexts68 @ h h h h
. Transport following locations:
47 5e to a work station.
E.
PACKAGING AND SHIPPING TI packages fuel elements in containers supplied by the customep and under their direction.
TI packages fuel plates (scrap, sectioned or otherwise) in customer supplied 6M containers with maximum of 50 fuel plates or ecuivalent per container.
Waste drums of 30 or 55 gallons containing no more than 24 gms 235U are sealed and shipped.
Samples of fuel plates, U308 or elements containing no more than 350 gms 235U are packaged and shipped.
SUMMARY
The permitted total array index is 100.
The sum of all array indices for the f acility is less than 0.362 x 100.
The permit-ted total CI value is 1000 while the sum of all CI values in the facility is less than 150.
The effect of hydrogenous 1
ORNL/CSD/TM55,
E.N.
79-59 Page 7 Oct. 10, 1979 Rev. A 4.7.2 Commonwealth of Massachusetts 4.7.2.1 An exposure to the whole body of 5 rems or c- 'e of
_c to the radiation, to the skin of 30 rems or more.
extremities of 75 rems or more of radiation shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone or telegraph to the Commissioner, Division of Industrial Safety, Department of Labor and Industries, followed by a report in writing.
4.7.2.2 Each exposure to an individucl to radiation in excess of applicable limits shall be reported in writing to the Commissioner within thirty days of the discovery of such exposure.
5.
INTERNAL RADIATION PROTECTION 5.1 P URPOSE This part concerns the uptake of radioactive material into the human body.
It outlines the three avenues of entry into the body -- inhalation, ingestion, and through breaks in the skin -- and the appropriate methods of source detection and control, personal protection, and bioaasy program.
5.2 I mALATION 5.2.1 All work with radioactive material susceptible to atmospheric distribution shall be done under the influence of adequate ve nt ila t ion.
Recommended standards as defined in Industrial Ventilation, A Manual o f Recommended Practice, shall be followed.
5.2.1.1 Dust collected in dryboxes, hoods, and flexible pickups shall be drawn through negative pressure sheet steel or PVC ducts to cleanable metal-mesh prefilters and then high efficiency paper or glass fiber filters.
Air which has passed through the high efficiency filters may be released to non-restricted areas.
5.2.1.2 The velocity of air at the faces of all hoods and flexible pickups shall be at least 125 feet per minute.
5.2.1.3 The efficiency of filters and exhaust systems shall be tested by continuous collection and counting of stack samples by Health / Physics on a weekly basis.
5.2.1.4 Maintenance:
5.2.1.4.1 Protective clothing and respirators shall be worn while working inside filter boxes.
_/
5.2.1.4.2 Clean high ef ficiency filters shall be visually inspected on receipt by Health / Physics.
De fec tive filters will be returned to the supplier.
6
E.N.
79-59 Page 13 Oct. 10, 1979 Rev. A
- 5. ~5.1. 2 Analytical procedure for the determination of enriched g,j uranium in urine shall consist of a radiometric technique whereby the uranium is extracted, quanti-tatively transferred to a planchet, and alpha counted.
5.5.1.2.1 Sample results are calculated and reported in t9rms of pCi/ liter of solution.
5.5.1.3 All urinalyses procedures shall be performed by a qualified laboratory whose results shall be reported to Health / Physics.
5.5.1.4 The maximum acceptable levels for uranium urinalyses for the specified sampling frequencies are 15 pCi/ liter.
5.5.1.5 Results of all urinalyses shall be reviewed by Health / Physics within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after receipt from the laboratory.
5.5.1.5.1 Samples showing levels in excess of the maximum acceptable levels shall be reported immediately to Health / Physics by telephone
\\./
from the laboratory.
5.5.1.5.1.1 When reported results are in excess of the maximum acceptable levels by 2007., the individual shall be removed from the bare fuel processing area, a new sample shall be requested and
+
analyzed, and an investigation initiated by Health / Physics to determine the source of the exposure.
5.5.1.5.1.2 When reported results are in the range of ED% to 200% of maximum acceptable levels, a new sample shall be requested and analyzed, and an investigation initiated by Health / Physics to determine the source of the exposure.
5.5.1.5.1.3 When a second sample shows re.ults in excess of the maximum ac eptable levels, the individual she i be removed from the bare fue.
processing area and the investi-gation continued to determine the source of exposure.
E.M.
79-59 Page 14 Oct. 10, 1979 Rev. A 5.5.1.5.1.4 Af ter the source of exposure has been determined and corrective action has been taken, the ind iv i-dual may return to the bare fuel processing area only after two successive samples give results less than the maximum acceptable levels.
5.6 PESPONSIBILITIES 5.6.1 Health / Physics is responsible for determining airborne ccncen-trations for monitoring the ef ficiency of the exhaust systems, for notifying appropriate supervisors of abnormal conditions and enforcing the provisions of this procedure.
5.6.2 Health / Physics is responsible for tilter cleaning and changing.
5.6.3 Supervisors are responsible for notifying Health / Physics of all changes which might affect the production of radioactive aerosols.
5.6.4 Each individual is responsible for his own adherence to the provisions of this procedure.
6.
PROTECTIVE CLOTHING AND EQlTIPMENT 6.1 CENE RAL Employees shall wear protective clothing in all areas where the possi-bility of contamination of personal clothing exists, where personal clothing is likely to be damaged by acid ti other materials, er where required by product cleanliness standards.
6.1.1 Jhe protective clothing to be wocn oy all personnel working full time in the fuel manufacturing area shall consist of siirts, pants, and safety shoes.
6.1.1.1 Clean clothing shall be issued at the beginn:ng of each week.
6.1.1.2 Used clothing which is ready for washing shall be placed into special metal collection drums in the c intaminated locker room.
6.1.1.3 When the drums are full, they shall be sealtd and shipped to a nuclear laundry se rvice licensed by th-AEC.
All drums must be monitored by Health / Physics prior to shipment.
6.2 REGULATIONS 6.2.1 The following regulations apply to the wearing and use of protective clothing in the D!A.
E.N.
79-59 Page 19 Sept.
4, 1979 Rev. A 8.
SURFACE CONTAMINATION CONTROL 8.1.
GENERAL It is the purpose of the HFIR Project Health / Physics Program to conform with U.S.N.R.C.
established surface contamination limits as outlined in " ANNEX C, Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material, dated November 1976" and proposed limits and frequencies within " Regulatory Guide 8.24, Health Physics Surveys During Enriched Uranium-2 35 Processing and Fuel Fabrication", dated November 1978.
8.2.
CONTROL LIMITS OF SURFACE CONTAMINATION ARE AS FOLLOWS Alpha Fixed Removable 8.2.1 Fuel Manufacturing Area (d/m/100 cm )
(d/m/100 cm2) 2 8.2.1.1 General except as noted in 8.2.4 5000 8.2.1.2 Equipment and 5000 work surfaces 8.2.1.3 Containment Internal Surfaces 8.2.2 Other Areas 8.2.2.1 Smidgen Clean Area (Genera]
Manufacturing Area) 2000 200 8.2.2.2 Health Clean Area (Ante-Foom of Fuel Manufacturing Area) 2000 200 8.2.2.3 Equipment for Release from Fuel Manufactur-ing Area 2000 200 8.2.3 Shipments or Transferrals 8.2.3.1 For Smidgen Cleanliness 2000 200 8.3.2.2 Other 2000 200 e
E.N.
79-59 Page 20 Sept.
4, 1979 Rev. A Alpha Fixed 2
8.2.4 Clothing (d/m/100 cm )
8.2.4.1 Protective clothing worn in Fuel Manufacturing Area 20000 8.2.4.2 Clean Protective Clothing 200 8.2.4.3 Personal Clothing 200 8.2.4.4 Personal Shoes 200 8.2.4.5 Skin Bkgd.
8.3.
FREQUENCY OF MEASUREMENTS (During Production Periods) 8.3.1 Measurements shall be made and recorded at least weekly for items 8.2.1.1, 8.2.1.2, 8.2.2.2, and 8.2.4.1.
Item 8.2.2.1 shall be measured and recorded at least monthly.
Items 8.2.2.3, 8.2.3.1, and 8.2.4.2 sball be measured and recorded as the need arises (i.e.,
release of material from the Fuel Manufacturing Area, release of protective clothing after laundering, etc.).
Items 8.2.4.3, 8.2.4.4, and 8.2.4.5 are measured by personnel before entering the Smidgen Clean Area (General Manufacturing Area) from the Fuel Manufacturing Area.
8.4.
PROCEDURE FOR MEASUREMENT 8.4.1 Fixed alpha activity shall be determined by direct measurement with survey meters.
8.4.2 Removable alpha activity shall be detegmined by)taking smear samples of approximately 1000 cm' (1 ft.
on Whatman 441 Filter Paper Discs (29 mm).
The discs are counted for a minimum of five minutes each in scintillation detection equipment.
8.4.2.1 When contamination levels are discovered in excess of those specified in 8.2, conditions and/or operations will temporarily continue under written e
e y
E.N.
79-59 Page 20A Sept.
4, 1979 Rev. o 8.4.2.1 authorized instructions by Health /
(cont)
Physics until remedial actions of decontamination are completed.
Decontamination will not be considered complete until measured contamination levels are reduced below the limits specified in 8.2.
E.N.
79-59 Health & Safety Manual Page 1 Oct. 10, 1979 Appendix D Rev. O JUSTIFICATION OF HFIR PROJECT PERSONNEL MONITORING PROGRAM
(*tIRINALYSIS AND IN VIVO)
Purpose The purpose of the justification is to demonstrate the applicability of the urinalysis and in vivo body counting monitoring as stated within the Health and Safety Manual by presenting historical monitoring results and referencing U.S.N.R.C.
Regulatory Guide 8.11 dated June 1974.
Scope The justification applies to urinalysis and in vivo body counting for the processing of U Og at less than or equal 3
to 93 w/o enriched uranium.
Presentation of Historical Data Table 1 of this appendix provides two years (by week) of specific bioassay and air monitoring results for persons working within the HFIR Project Fuel Manufacturing Area (FMA).
Employees A and B (designated in the table) perform work within the FMA for more than 50% of their work assignment (approximately 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week).
Employee C performs work within the FMA for less than 50% of his work assignment.
Figures 1 through 3 provide a five-year summary (by calendar quarters) of bicassay and air monitoring results for the same employees reported in Table 1.
Observations of Historical Data The maximum single breathing zone air sample result for individuals with more than 50% of their work assignments within the FMA was less than 25% of the permitted air concentration for 235U as specified in Title 10 CFR Part 20, Appendix B, Table 1, and the maximum calendar quarterly average is less than 10% of the permitted air concentration as presented in Table 1.
The maximum single calendar quarter urinalysis result was 4 pCi/ liter with typical results averaging approximately 0.8 pCi/ liter.
The maximum sincie annual in vivo body count result was 124 + 52 ug 2356 (followed by 56 + 40 pg 235U within three months) with fluctuating between 0 1 40 and 70150pg~3gypicalresults U.
I l
APPEtJDIX D (continued) l E.N.
79-59 TABLE 1 Rev. O Oct. 10, 1979 SUtV1ARY OP PERSOllflEL AtID AIR t10tlITORIllG RESULTS Page 2 Emplovce A Employee B Employee C Air Concentrations 235
- 8 B.Z.
Urine B.Z.
Urine B.Z.
Urine Unfiltered Filtered I u a
Re s(il t Result Result Result Result Result Exhaust Exhaust 10~ 2 p
pCi/1 10-12 to-12p p
pCi/1 10-12p pCi/l 10-12 p
tion !
Ci/ml Ci/ml Ci/ml Ci/ml Ci/ml 1.25 2.67 0.078 0.009 5.34 23.1 42.3 0.010 0.029 i
3.40 4.08 62.3 0.072 0.018 9.75 6.01 0.006 0.004 0.44 0.73 18.5 0.287 0.025 18910 IST 5.75 8.85 95.9 0.125 0.002 UTR 3.47 2.17 0.106 0.006 1977 2.99 2.14 58.5 0.043 0.013 l
2.56 5.39 0.001 0.009 6303 l
14.5 1.66 0.074 0.009 16.2 1.35 0.37 4.05 76.8 0.86 0.150 0.001 2.21 1.40 93.2 0.025 0.003 7.45 65.2 0.165 0.006 18915 I
'l s
0.85 4.25 9.32 0.008 0.00' 1.27 33.6 0.111 0.001 j
3.42 1.34 0.095 0.006 j
3.47 0.43 57.7 0.445 0.026 12623 2tlD 2.12 3.03 36.0 0.154 0.001
?
QTR 5.08 1.30 0.540 0.003 1977 3.02 8.05 50.8 0.002 0.001 4.31 3.02 43.1 0.007 0.001 3.32 0.43 0.}l6 0.011 12616 3.27
'l.07 3.74 3.46 59.2 1.55 0.050 0.002 2.50 0.00 66.5 0.077 0.001 0.03 54.2 0.072 0.001 1
1.44 0.055 0.002 18933 O
.. F
~
a
APPENDIX D (continued)
J
(
E.N.
79-39 TABLE 1 (continued)
Rev. O Oct. 10, 1979
SUMMARY
OF PERSOMilEL AtlD AIlt MO!1ITORIHC RESULTS Page 3 Employee A Employee B Employee C Air Concentrations 235 f"##*8
~~11. Z.
Urine B.Z.
Urine B.Z.
Urine Unfiltered Piltered "U P"'
Resp *p t
Result-Re s ta l t.
Result Result Result Exhaust Exhaust in FMA per y
10-pCi/l 10-12 p pCi/l 10-12 p pCi/l 10-12 10-12p p
M nth Ci/ml Ci/ml Ci/ml Ci/ml Ci/ml 2.74 36.5 0.000 0.002 i
2.66 21.3 0.111 0.001 3RD 0.'
2 0.001
[
QTIt 0.u24 0.001 1977 0.00 0.110 0.001 3.01 41.4 0.128 0.001 16310
-~~-
1.73 25.9 0.109 0.001 1.92 1.30 2.73 43.2 1.45 0.136 0.004 l
3.01 2.73 0.118 0.001 9.91 0.46 14.8 0.271 0.004 42911 i
3.65 2.30 0.144 0.001 0.43 0.91 0.264 0.001 4.73 0.00 95.1 0.058 0.001 0.48 0.43 0.116 0.001 0.95 1.43 0.075 0.001 12629 4 Til 2.73 0.95 0.105 0.007 OTit 1.82 0.95 112.5 0.114 0.005 l
1977 7.84 1.36 0.106 0.001 AAAAAAAAA 4AAAAAAA AAAAAAAA' AAAAA&&
AAAAAAAAA AAAAAAAA e
In Vivo
.tesul t In Vivo 1 :esult In Vivo Ite su l t 235 235U 2350 0+
36 p g U
55 + 34p g
0 t 49 p g
AAAAAAAAA 4AAAAAAA AAAAAAA&d AAAAAAA AAAAs&AaA AAAAAAAA 1.43 3.43 0.259 0.001 18950 1.72
< 0.18' l.43 1.43 139.4 2.73 0.141 0.004 0.48 0.86 0.109 0.001 0.00 3.34 0.006 0.001 4.30 0.059 0.003 25232 t
j d
'r APPENDIX D (continued)
TABLE 1 (continued) hev. O E.N.
79-59 Oct. 10. 1979
SUMMARY
OP PERSON!!EL At3D AIR MOtlITORING R ES UI.TS Page 4 l
Employee A Employee B Employee C Air Concentrations Grams U
__B.Z.
Urine
_B.Z.
Urine B.Z.
Urine Unfiltered Filtered t
g
.g j,
Re s(11 t Result Result Result Result Result Exhaust Exhaust in[MAper 10- 2 p
pCi/l 10-12 p pCi/l 10-12p pCi/l 10-12 10-12p p
Ci/ml Ci/ml Ci/ml Ci/ml Ci/ml 3.55 0.059 0.000 i
7.12 1.90 2.40 0.012 0.004 19.4 0.00 0.17 0.027 0.001 17.3 3.59 0.161 0.000 t
0.97 0.48 0.44 0.028 0.000 18934 IST 3.43 20.6 11.6 0.062 0.004 QTR 1.96 23.0 19.5 0.004 0.000 1978 1.77 6.64 0.032 0.000 12616 12.8 3.54 2.46 0.090 0.000 5.86 1.35 2.32 0.125 0.000 3.44
<0.18 6.39 0.59 1.16 0.033 0.000 1.95 1.95 10.5 0.102 0.001 2.32 8.36 0.037 0.001 25240
(
l 5.57 0.00 8.31 0.108 0.000 0.93 9.75 2.79 0.053 0.001 9.75 1.86 13.9 0.018 0.000 5.57 2.32 3.10 0.043 0.001 18927 2ND 4.41 11.0 0.049 0.000 QTR 0.55 2.76 9.29 0.005 0.000 1978 0.55 2.20 11.1 0.037 0.000 0.55 0.47 23.6 0 029 0.000 0.49 2.94 0.071 0.000 25239 18.6 2.45 33.1 0.038 0.001 2.81 0.78 4.68
<0.18 3.31 1.21 0.056 0.000 2.41 6.27 7.35 0.011 0.000 3.38 0.48 4.90 0.047 0.003 12622 8
,e-
APPEtJDIX D (continued)
E. tl. 79-59 TABLE 1 (continued)
Rev. O October 10, 1979 suttftARY OF PERSO!1tlEL AtlD AIR 110tlITORIllG HESULTS Page L Emplovee A Employee B Employee C Air Concentrations Grams U
B.Z.
Urine D.Z.
Urine B.Z.
Urine Unfiltered filtered Throughput Heualt Result Result Result Result Result Exhaust Exhaust
- n ' A per 10- 2 p
pCi/l 10-12 10-12p p
pCi/l 10-12p pCi/l 10-12 p
Ci/ml Ci/ml Ci/ml Ci/ml Ci/ml 2.68 2.24 4.47 0.044 0.009 3.34 2.39 9.55 0.034 0.006 0.00 1.81 6.80 0.021 0.000 6308 0.91 2.27 14.4 0.012 0.000 3RD 5.63 1.92 3.09 0.047 0.003 QTil 1.81 2.32 0.00 0.033 0.000 1978 1.81 0.33 0.00
< 0.18 93.7 0.92 0.042 0.004 12618 1.02 1.90 42.2 0.160 0.000 1.04 2.71 6.54 0.045 0.000 3.65 19.0 0.022 0.003 0.00 5.42 0.058 0.005 25243 0.00 0.00 0.00 0.050 0.000 l
5.21 5.21 0.111 0.009 3.13 8.34 12.5 0.046 0.005 2.25 3.38 0.060 0.005 4 Til 0.00 3.38 12.5 0.049 0.005 12378 OTH 0.00 0.00 0.133 0.002 1978 1.47 0.74 12.5 0.081 0.000 0.00 0.00 0.076 0.002 0.38 0.00 11.1 0*062 0.000 18924 l
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4 t
t APPENDIX D (continued)?
Rev. O 979
SUMMARY
OF PERSOrlIEL All All iOfITORIllG RESULTS U"9".0 Employee A Employee B Employee C Air Concentrations Gramu U
B.Z.
Urine B.Z.
Urine B.Z.
Urine Unfiltered Filtered
,N ou@mut Re sgil t Result Result Result Result Result Exhaust Exhaust
. n I,,tA per 10- 2 p
pCi/l 10-12 10-12p p
pCi/l 10-12p pCi/l 10-12 p
Ci/ml Ci/ml Ci/ml Ci/ml Ci/ml 1
1.14 0.76 42.7 0.081 0.003 1
0.76 1.90 0.008 0.003 2.18 3.26 7.25 0.104 0.000 1.50 5.61 52.3 0.055 0.002 IST 1.17 3.52 0.045 0.010 25218 QTR 5.52 3.68 0.131 0.001 1979 4.84 5.81 19.4 0.069 0.012 l
4.94 0.077 0.030 8.49 0.046 0.004 18915 L
2.83 12.6 0.092 0.008 l
2.83 0.119 0.004 i
l.04
<0.14 8.34
<0.14 17.9
<0.60 0.028 0.014 3.13 4.17 0.143 0.005 18924 6
1 4.17 7.81 0.046 0.018 g
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,****aan 2tlD 7.61 0.077 0.005 QTH 14.7 Os283 0.014 1979 3.39 30.1 0.090 0.020 12612 3.33 0.075 0.010 1.07 19.3 0.175 0.009 3.21 0.302 0.005 l
17.6 27.5 0.015 0.029 28373 0.404 0.024 0.096 0.005 0.014 0.009 0.092 0.000 12604 f
k
Appendix D (continued)
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E.N. 79-59 Page 10 Oct. 10, 1979 Appendix D (continued)
Rev. O The FMA room air exhaust uranium concentration is typically
,one order of magnitude less thmn breathing zone air results.
Statements from U.S.N.R.C.
Regulatory Guide 8.11, June 1974 As per Section A of the reference, "a work area qualifies for the ' minimum bioassay program' so long as the quarterly average of air sample results is < 10% of the Derived Air Concentration (DAC) and the maximum used to obtain thc average is < 25% of DAC".
The technical " bases for the criteria appearing in the guide are provided in ' Applications of Bioassay for Uranium',
WASH-1251" which classifies U 03 8 as Class W, nontransportable dust with a 50-day biological half-life in the lung.
Table 2 of the reference specifies that the minimum frequencies of bioassay measurements should be annual for in vivo body counting and semiannual for urinalysis for Class W or Class Y material havi7g Class W material present.
Figure 12 of the reference specifies urinary uranium concentra-tion action guides relative to maximum permissible dose commitment.
Quarterly urinalysis results less than 15 pCi/ liter require no action for Class W material.
Figure 19 of the reference specifias the equilibrium Mass of U-235 in the lung equivalent to one maximum permissible lung burden relative to weight percent U-235 and demonstrates the conservatism of monitoring lung burden build-up as though it were attributable to 93 weight percent U-235.
Application of HFIR Project Personnel Monitoring Program Breathing zone air samples are utilized as the first line of detecting potentially excessive personnel intakes of uranium.
Quarterly urinalyses are utilized to support and demonstrate the predictability of breathing zone air sampling and to monitor for single uptakes of uranium for bone burden build-up.
Annual in vivo body counting is utilized to monitor lung burden build-up.
Conclusions The presented historical data demonstrates that contamination confinement within the HFIR Project FMA provides consistently low internal exposures to personnel that are below maximum permissible limits specified within the referenced material.
E.N.
79-59 Page 11 Oct. 10, 1979 Appendix D (continued)
Rev. O Conclusions (cong Additionally, air sampling and bioassay results are consistently less than referenced specified limit values requiring remedial actions or evaluations.
The personnel monitoring program specified within the Heal a and Safety Manual is justified to be acceptable as specified by recommended criteria of U.S.N.R.C.
Regulatory Guide 8.11, June 1974, as applied to processing uranium enrichments of 93 weight percent or less in the form of U3Og.
=
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