ML19310A052
| ML19310A052 | |
| Person / Time | |
|---|---|
| Site: | 07104986 |
| Issue date: | 04/02/1980 |
| From: | Battelle Memorial Institute, PACIFIC NORTHWEST NATION |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML19310A051 | List: |
| References | |
| 16060, NUDOCS 8006060005 | |
| Download: ML19310A052 (16) | |
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VRf 2 I g3 d r*Ji Mr. C. E. MacDonald, Chief Division of Fuel Cycle and Material Safety yhm fc,/j Z
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U.S. Nuclear Regulatory Commission q'
Wdshington, D.C. 20555
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Dear Mr. MacDonald:
Reference:
Docket No. 71-4986 Pacific Northwest Laboratory (PNL) hereby requests that NRC Certificate of Compliance 4985 be amended as described.nerein.
Certificate No. 4986 authorizes the transport of nuclear fuel manufactured by General Electric Company and Exxon Nuclear Company, Inc. in General Electric's RA-Series packages. The nature of this requested amendment involves the use of RA-3 shipping containers to transport NRU-LOCA Test Trains or test train components.
The enclosed Application for Amendment includes information as outlined in
" Packaging of Radioactive Matecials for Transport" Part 71 of NRC Rules and Regulations, Title 10, Chapter 1 (10 CFR 71). This data demonstrates the safety of Class I shipments of low enriched UD2 fueled NRU-LOCA Test Train Assemblies, or their ccmponents.
This amendment is necessary to permit PNL to ship nuclear fueled test trains to the NRU Reactor Site at Deep River, Ontario. The tests are being Jesigned, fabricated, and performed under contract to the Fuel Behav.or i
Branch, Division of Reactor Safety, under the office of Nuclear Regr'a'ory Research of the NRC.
Since the amendment is being solicited to facilitate NRC funded work, PNL requests that the normal licensing fee be waived.
PNL personnel will be pleased to discuss details of this-submittal with yop or uenbers of your staf f.
If there are any questions pertaining to this requested amend.nent, please contact J. F. Nesbitt on (509) 942-4717 or J. P. Pilger on (509) 942-5603.
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Mr. C. E. MacDonald Page 2 April 2,1980 Your timely consideration of this submittal would be appreciated as PNL's contract with the fiRC includes a schedule to begin shipments in August,1930.
Sincerely,r
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C. L. Ibhr, Manager fluclear Fuels Section CLit:dc Enc.
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A. L. Kaplan
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PROPOSFD CllAi:GES TO !!RC CERTIFICATE OF COMPLI Ai:CE 4935 IOR Tile gel ERAL ELECTRIC RA-51~RII.S PACKAGES Presented below is infonaation pertinent for the amendment of the existing certificate to pemit the use of PA-3 containers for the shipment of special f;RU-LOCA Test Train Assemblies, or Test Train components.
v 1 ( A) Pa,cka.ne Identi f ication (1)
The packaga is General Electric's Model f o. P.A-3 as identified in Certificate rio. 4906 Revision 5 with a minor change incorporated in the inner container to permit the packaging of the specific test assembly.
(2)
Description Packages are right rectangular boxes consisting of an outer container of wooden construction and a metal inner container separated by cushioning material.
The metal inner container is 11-1/2 inches by 18 inches by 179 inches long for the Model i;o. RA-3 and it is positioned wit.hin an all-wood constructed outer container that is approximately 30 inches by 31 inches by 207 inches long.
Cushioning is provided between the inner and outer containers by phenolic impregnated honeycomb and ethafoam, or equivalent.
A pressure relief (breather) valve is installed on the inner container, and is set for 0.5 psi differential.
Closure is made by bolts, latches, or the equivalent.
The total weight of the packaging is either approximately 1400 pounds or 1450 pounds dependent on tha type of outer shipping container used.
(31 Drawings _
The RA-3 inner container of welded and riveted design is constructed in accordance with the following General Electric drawing numbers:
731E674, Revision 5 or 6 128D5211, Revision 1 or 2 128D5212, Revision 0 or 1 128D5177, Revision 0, 2, 3, or B 128D5178, Revision 1 or 2
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ll7C3979, Revision 2, 3, or 4 159C5372, Revision A 159C5373, Revision A
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2 Also included is the inner liner assembly constructed in accordance with GE Drawing flo.159C5411, Revision 2 that will be ir.adi fied as sho<:n on Piil. Drawing 11-3-41798.
Thi s r.odi fi-cation consists of one 2 inch by 5-3/3 inch notch that is located in one end of the center section of the inner container.
The contents of this particular container will be supported and held in place with saddles and dunages that raate with the test train or sub-bundle assemblies.
These will be fabricated in accordance with Piil Drawings 11-3-41793 and H-3-41799.
The RA-3 outer shipping container is constructed in accordance with GE Drawing I;o. U29E209, Revision 0, 3, 4, or it rc.ay be constructed in accordance with GE Drawing I'os. 761E529, Revision 2 or 731E283, Revision 0,1, 2, 3, or 4.
1 (B) Contents of Package (1)
The contents for this application consists of an f$U-LCCA Test Train Assembly in accordance with BNW Drawing li-3-41833 " Test Train Arrangenent" Rev 1 and the latest revision of the following BriU drawings:
11-3-41801 H-3-41851 05 52 07 58 11 59 12 60 13 61 14 62 15 63 16 64 17 65 11-3-41818 11-3-41867 19 68 20 69 21 70 23 71
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24 72 25 73 28 74 29 76 a
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3 11-3-4110 0 11-3-41877 32 78 33 80 34 81
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36 83 37 84 33 85 39 86 40 87 41 11-3-42030 42 81 46 47 48 Basically one-half of the test train consists of a support mechanisa and service leads while the other half contains the fuel material.
The fuel assemblies are constructed of multiple parallel rods of enriched uraniun, clad in Zircaloy-4, held in a modified square array (no rods in the four corner positions) inside of a shroud by means of end fittings and intermediate spaced grids.
An alternate content for this application consists of test bundle subassemblies in accordance with BlT.4 Di' awing fio. H-3-41814 and 11-3-41815. A maximum of eight sub or individual test bundle assemblies are to be arranged as shown in BriW Drawing fio. 11-3-41799.
The rods of the subassemblies are located and held in position by grids spaced along their length.
Four subtest bundle assemblies shall be strapped together at three or more locations with steel strappings.
The total breaking strength of the strappings shall be at least 30 times the weight of the bound subassemblies.
(2)
Type and Fona of I'aterial (i) A UO2 fueled I;RU-LOCA Test Train Assembly contains a maximuu average U-235 enrichment of 2.945 by weight. Assembly rods are clad with a' minimum 0.022 inch thickness of Zircaloy and have a maximum fuel pellet outside diameter of 0.3255 inches.
Each assembly of 32 rods, 31 of them containing 002 fuel, are arranged on a basic 6x6-grid and located on a.502 inch pitch.
The fueled rods contain 144 lineal inches of fuel.
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4 (ii) An arrangement of test bundle subassemblies contain a maximm average U-235 enricirnent of 2.94% by veight.
Sub-assembly rods are clad with a minimum 0.022 inch thickness of 7.ircaloy and have a maximum fuel pellet diameter of 0.3255 inches.
Each arrangement of 24 rods, 22 of them fuel, are arranged on a basic 4x8 grid and containing UO2 located on a.502 inch pitch.
The fueled rods contain 144 lineal inches of fuel.
' (3) i4aximudantity_of f.:aterial Per T'ackage, Caly one !!RU-LOCA Test Train Assembly shall be shipped per container.
i The maximum ;;cight of an assembly is 450 pounds.
A raximum of one subassea.bly arrangement shown on BNW Drawing !!o. 11-3-41799 shall be shipped per container.
The maximum weight of this arrangement, consisting of a total of eight individual test bundle subassemblies is 290 pounds.
(4)
Each test assembly may be unsheathed or it may be enclosed in an unsealed, polythylene sheath which will not extend beyond the ends 4
of the fuel portion of the assembly. The ends of the sheath shall I
act be folded or taped in any manner that would prevent the ficw j
of liquids into or out of the sheathed fuel assembly.
2.
P_ackage Evaluation l
The package covered in this amendment application is the same as the tested General Electric RA-3 shipping container with one exception.,
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(i.e., the 2 inch by 5-3/8 inch notch made in the trailing end of the center section of the inner container).
It is the considered opinion of 4
PiiL that this change as shown on Ptil Drawing H-3-41798 has not affected the structural strength, integrity, or the required function of the RA-3 i
package in any canner.
The only other difference affecting the ability of the package to meet and withstand the requirements of 10CFR71 is that the weight of the package contents for this applied use will be considerably less than those of normal PA-3 usages.
The RA-3 container is designed to hold two BUR type fuel bundles and it has been tested and evaluated with contents weighing up to 1234 pounds.
The use of the same basic container to' ship a test bundle with a maxinum weight of 450 pounds is an operation that will place less severe demands on the package than its present use for all normal transport or for. any hypothetical accident conditions.
- 3.. Criticality Safety Analysis l
The current contents of the subject certificate have been reviewed and compared to the NRU-LOCA' Test Train and it is the considered opinion of PNL that the shipment of fiRU-LOCA Test Train Assemblies o~r Test Train j
components will be safer from the criticality aspect than the fuel bundles i
presently identified as contents of the RA-3 shipping container.
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5 Our conclusion and submittal is based on tha In the GE application for the RA shipping containersN)following.
the fuel considered in the c'alculational models had the following properties:
(1) 3.2 wtg 2350 enrichment maximum (2)
.032" Zircaloy clad thickness (3) fuel pellet OD of 0.410"
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(4) fuel column length of 174"
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[(5) 0.640" pitch.
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~The liRU fuel properties, on the other hand are:
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(1) 2.94 wt;; 235U enrichment maximum (2) 0.022" 3ad thickness (3) fuel p.
.t OD of 0.3255" (4) fuel column length of 144" (5) 0.502" pitch.
The 3.2 wt;; fuel described in the GE analysis complies with requirements of a fissile Class I ph{pping container.
With reference to data inter-polated from DP1014, N/ for unciad arrays of 3.2 wt5 fuel rods, full water reflected, the number of rods required for criticality is s 270 rods.
The i;RU fuel requires >440 rods for criticality.
The above analysis takes into account the slightly larger pitches which occur due to including clad thickness and holding the water to fuel ratio constant.
It is estimated that even at optimum fuel moderation, the critical number of fuel rods is still %270 rods.
11ence, the NRU fuel is less reactive than the GE fuel analyzed and will meet the requirements for a Fissile Class I shipping container.
In the event that geometry control is lost, there are additional features which make the NRU fuel shipment much less reactive than that fuel originally prescribed in the GE analysis. A nfaximum of 44 pins fixed on a square pitch will be shipped per container.
In the GE analysis, two 8x8 bundles were modeled per container.
Thus in the GE analysis, 128 pins were shipped per container compared to 44 less reactive pins in the NRU shipment.
4.
Procedural Controls 1
The attached Quality Assurance Program QAP No. MD-1, Revision 0, has been established to control the design, procurement, fabrication, assembly, l
inspection, and shipment of the NRU-LOCA Test Train Assemblies.
The plan iis in accordance with Battelle's Quality Assurance Manual PNL-MA-65 tihich has been established to interpret the requirements of DOE RL's Appendi.x to Manual Chapter 0820 and Appendix B of 10 CFR50.
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(1) Letter A. L. Kaplan to C. :E. MacDonald, " Application for Amendr.ent of HRC Certificate of Compliance 4986." December 20, 1976.
(2)~ Clark, H. K. Critical and Safe Masses and Dimensions of Lattices of'U and Uh Rods Tn7?ater.
DP-f014, E. 1. Du Pont De Nenours &
Com6cny,~SivannaIIllTJer Laboratory, Aiken, South Carolina, February 1966.
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,j Revision flo. O i
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@ R&D Project C Service Activity I
t Pe eject /Sorvice Activity:
!!RC-10CA Sirculation in I:RU l
_ _... _ -3 Sponsor:
!!RCLRSR.. __0. lloAtson Autiiorized Gy(DOC.No.)-
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I QA Requirement Specification:
RL Appandix to 0820 _.___liLinterpreied_by PiiL-lMS._.
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1 Approvals:
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DATE A" PROVED SIGNATURE ROJECTIACTIVITI t/. At; AGER)
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- MwJ DATE APPROVED SIGNATURE INE FAANAGEpfa)
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- The Sections or se!ccted paragraphs of PNI.-f/.A-65 (as identified by section or paragraph number!
t designated in this OA Plan are applicab!c to this Project / Service Activity. Additional information is
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- also provided when useful to provide clarification of the selected requirement.
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Distribution:(Project GA Files.OAO, and otherses affer,riate) R.,.P_,_L3.tshall.. C.R.
flannmd ? Sil' tr-l rop R.L. Goodmn, S.W.. lleaberlin,sU.D. Hei t G.M. Ilesson, L.L. King, R.K. l'arsh:.ll, LTJrterchtTr,-fCErschrichinT'Redhaub, n-e;--Ryder7-Qt,0,
itOJukirkrt-tr:W -
L WDyattment or Section fanager as designatr d by Departrnent Pohey or the Project Pian D:curnent.
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QAP rio. ID-1 Page 2 of 4
- - e Itevision No. 0 Project:
ilRUL 1.
ORGAfil ZATIO*l 1.1 The relationship of the QA0 to other Battelle components is descrited in Section 1.1 of PGL-MA-65.
l Colicborating Organizations:
l l
Organi za tion Contact /, Quality Engineer l
AECL, Chalk River, Ontario C. A. lierriot/ttone at this time.
^
2.
QA PROGRAM 2.1 The Battelle QA Program shall be applied as described in this QA Plan.
The following detail has been included to provide additional informa tion concerning this section.
i 2.1.1 Subtasks performed by Pi:L shall be in accordance with the requirements of this document.
Additional project control data is furnished in the " Fuels Design & Development Section Quality Control Plan to Cover liardware Design and Assembly Projects."
i 3.
DESIGN C0flTROL & METiiOD REVIEW 3.1.2 The project approach and method is reviewed and approved as part of the Project Plan Document.
3.1.3.1 This subsection applies.
5 3.1.3.3 This subsection applies.
3.1. 4. 3 Results of investigations, calculations, and experiments will te documented in final or summary reports. When reportable calcu-10tions are documented the name and version of the computer code.
shall be recorded.
3.1. 5 This subsection applies.
3.1. 6 Design review shall be conducted by a design review team corposed a
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of members from Pl;L. designated by the Project Manager.
3.1.7 'This subsection applies.
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QAP fio. f D-l Page 3 of 4
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Revis ion !;cr. 0 P ;ojec t:
liiWL 4.
PROCUREITriT 4.1 This section applics.;hrn a purchise requisition is processed.
b II;5 l.2.UC T!0i;S, PROCLDUP.ES f. DP/,'.llI;GS 5.1 This section applies and.*dditional infor.ntion is pro.idcd in :
follo.ii ng s ta ta..ents :
5.1.1 Project Ibnager designitcJ personnel will be responsible ;ur naintaining a list of generated procedures.
5.1. 2 lhis QAP shall be transuitted to other P:;L sections or departments schen authorized stork in support of this project occurs.
6.
DOCUMEf;T CO.*;IROL 6.1 This section shall be applied to the procedures identified in 5.1.1 above.
7.
IMTERI AL IDEtiflflCATIO:t & C0i4TROLS 7.1 This section applies.
9.
II;SPECTIO!i & TEST 9.1 This section applies; classification of defects ray be utili7.cd for dimensional inspections as directed by the Project Manager.
10.
CALIBRATI0li 10.1 This project involves the use of M&TE that will require the appli-cation of th'e controls described in Section 10.1.
Additional information is provided in the follcuing stater.ents:
The Project Manager will detennine, identify and. document t' e calibrction level requirements.
Performance of operational checks and adjustrents will be recorded in lab books.
flote the procedure /tethod used and tr.2 adjus t. cents made.
.- Qap rio. 1D.1 Page 4 of 4
- Revision Ito. 0 P rr.j et. L :
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10.1.3.2 tiiw Reactor /Pt:L Tes t Train interf ace dinensions are con-considered cri tical.
The Project lunager, or his de.igne,.,
will be responsible for assuring the 1%TE titilized for mtasurewnt of these disaensions are within talibration anii of suf f icient accuracy.
11.
Hl'.U!.I!;G, STOP/.GE A::D S!i!PPlf!G 11.1 This section applies and additional infonration is provided in the following s tatement.
Project 14anager, or his designee, shall be responsible for obtaining the export license and shipment of radioactive r,a terial to AECL.
12.
II;SPECT10!!S, TEST Al;D OPERATlilC STATUS 12.1 This section applies.
13.
I;0::C0iiFORIG!;CE & CORRECTIOil ACTIO!i 13.1 This section applies when one of the described conditions occurs.
14.
QA RECORDS 14.1 This section applies and additional information is provided in the following statement.
The Program lianager shall provide to praject personnel a list of those documents that are to be generateo and maintained as QA records.
15.
QA AUDITS 1.
15.1 Scheduled audits will be conducted once each one-year perird as a minimum.
The first audit shall be scheduled three months from z.
the issue of this QAP.
QAP No. l.:D-1 Page 2 of 4 7
Itevision tio. 0 Project:
NRUL 1.
ORCAN17ATIO:1 1.1 The relationship of the QA0 to other Battelle corrponents is descrN in Section 1.1 of Pl;L-l%-65.
Colleborating Organizations:
Organization Contact /Ouality Emjineer AECL, Chall River, Ontario C. A. lierriot/None at this tive.
2.
QA PROGRAM 2.1 The Battelle QA Progran shall be applied as described in this QA Plan.
The following detail has been included to provide additional inforru tion concernir.9 this section.
2.1.1 Subtasks performed by Pi!L shall be in accordance with the requirements of this document.
Additional project control data is furaished in the "Fuais Design & Development Section Quality Control Plan to Cover liardware Design and Assembly Projects."
3.
DESIGN C0llTROL & !!ETil0D REVIEW 3.1.2 The project approach and method is reviewed and approved as part of the Project Plan Document.
3.1.3.1 This subsection applies.
3.1.3.3 This subsection applies.
3.1.4.3 Results of investigations, calculations, and experiments will be docun.ented in final or summary reports. When reportable calcu-lations are documented the name and version of the computer code shall be recorded.
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3.1. 5 This subsection applies.
3.1. 6 Design review shall be conducted by a design review team corposed of uenbers from Pt;L designated by the Project Manager.
3.1.7 'This subsection applies.
QAP fio. l'D-1 Page 2 of 4 Revision fio. 0 Project:
fiRUL 1.
ORGAfil 7ATIO:1 1.1 The rela tionship of the QA0 to other Battelle ccmonents is descri..d in Section 1.1 of PHL-l'a-65.
~
Collebora ting Organizctions:
0,rga ni za tion Contact / Quality Enoineer AECI., Chall P,i ver, 01.ta rio C. A. lierriot/None at this tire.
2.
QA PROGRAM 2.1 The Battelle QA Prograu shall be applied as described in this QA Plan.
The following detail has been included to provide additional informa tion concerning this section.
2.1.1 Subtasks performed by PML shall be in accordance with the requirements of this document.
Additional project control data is furnished in the 'Tuais Design & Development Section Quality Control Plan to Cover liardaare Design and Assembly Projects."
3.
DESIGN C0fiTROL & T1ET110D REVIEW 3.1.2 The project approach and method is reviewed and approved as part of the Project Plan Document.
3.1.3.1 This subsection applies.
3.1.3.3 This subsection applies.
3.1. 4. 3 Results of investigation;, calculations, and experiments will te documented in final or sumnary reports.
L' hen reportable calcu-lations are documented the name and version of the computer code shall be recorded.
3.1.5 This subsection appihes.
3.1. 6 Design review shall be conducted by a design reviep team corposed of members from PNL designated by the Project Manager.
3.1. 7 'This subsection applies.
Revision lio. 0 Project:
!!RUL l.
ORGAril 7ATio:1 1.1 The relationship of the Qt,0 to other Battelle components is descriM i n Section 1.1 of Piil-l'/,-65.
Colleborating Orginiznions:
Orqa ni za tion Co n t a c t]_ qual i tv _Egjineer ALCl., Chali. ki ver, Onta rio C. A. lierriot/tione at this tiu e.
2.
Qfi l'ROGRAM 2.1 The Battelle QA Prograa shall be applied as described in this QA Plan.
The following detail has been included to provide additional inforru tion concerning this section.
2.1.1 Subtasks performed by Fi!L shall be in accordance with the requirements of this document.
Additional project control data is furnished in the " Fuels Design & Development Section Quality Control Plan to Cover liard,;are Design and Assembly Projects."
3.
DESIG!i CONTROL & i ETilDD REVIEW 3.1.2
'he project approach and method is reviewed and approved as part of the Project Plan Document.
3.1.3.1 This subsection applies.
3.1.3.3 This subsection applies.
3.1.4.3 Resul ts of investigations, calculations, and experiments will be docun.ented in final or summary reports. When reportable calcu-lations are documented the name and version of the computer code shall be recorded.
3.1.5 This subsection applies.
3.1. 6 Design review shall be conducted by a design review teara cor,posnd of penbers from Pt;L designated by the Project Manager.
3.1. 7 'This subsection applies.
QAP rio, i'D-1 Page 2 of 4 Itevision flo. 0 Project:
flRUL 1.
ORC A'il / AT I O:1 1.1 The relationship of the QA0 to other Battelle corrponents is descriNd in Section 1.1 of Pi;L-l'/,-65.
~
Collebora ting Organize.tions:
r Organi za tion Contac t/Quali ty Enqineer AECL, Chall River, On'.ario C. A. lierriot/fione at this ti;ne.
2.
(fi PROG!!AM 2.1 The Battelle QA Progran shall be applied as described in this QA Plan.
Tha following detail has been included to provide additional inform tion concerning this section.
2.1.1 Subtasks performed by Pi:L shall be in accordance with the requirements of this document.
Additional project control data is furnished in the " Fuels Design & Development Section Quality Control Plan to Cover liardaare Design and Assembly Projects."
3.
DES]G'i C0rlTROL & fiETil0D PEV1EW 3.1.2 The project approach and method is reviewed and approved as part of the Project Plan Document.
3.1.3.1 This subsection applies.
3.1.3.3 This subsection applies.
3.1. 4. 3 Resul ts of investigations, calculations, and experiments will be docun.ented in final or summary reports. When reportable calcu-lations are docunented the name and version of the compuer code shall be recorded.
(-
3.1.5 This subsection applies.
3.1. 6 Design review shall be conducted by a design review team corposed i
of members from PI'L designated by the Project Manager.
3.1.7 'This subsection applies.
QAP fio. 14D-1 Page 2 of 4 Itevision 110. 0 Project:
ilRUL 1.
ORCAfil Z AT IO.*l 1.1 The rela tionship of the QA0 to other Ba ttelle corrponents is descri:.2 i n Section 1.1 of Pl;t-l'/,-65.
~
Collaborating Organizctions:
Orga ni za tion Co n tac t/ Qual i ty_Engi neer AECl., Chall River, Ontario C. A. lierriot/!!one at this til..e.
2.
QA PROGRAM i
2.1 The Battelle QA Progran shall be applied as described in this QA Plan.
The following detail has been included to provide additional informa tion concernirg this section.
2.1.1 Subtasks performed by Pr!L shall be in accordance with the requirements of this document.
Additioral pmject control data is furnished in the " Fuels Design & Development Section Quality Control Plan to Cover liardaare Design and Assembly Projects."
3.
DESIG!i C0tiTROL A I ET!!0D REVIEW 3.1.2 The praject approach and method is reviewed and approved as part of the Project Plan Document.
3.1.3.1 This subsection applies.
3.1.3.3 This subsection applies.
3.1.4. 3 Results of investigations, calculations, and experiments will te docun.ented in final or summary reports. When reportable calcu-lations are documented the name and version of the computer code shall be recorded.
I 3.1.5 This subsection applies.
3.1. 6 Design review shall be conducted by a design review team corpos d of uenbers from Pt:L designated by the Project Manager.
3.1.7 'This subsection applies.
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e ps Ksor,,b UNITED STATES j'0-
,J NUCLEAR REGULATORY COMMISSION 3..k1'-) }
WASHINGTON, D. C. 20555 k 5' > g ]!
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MEM0kANDUM FOR: TERA Corp.
FROM:
US NRC/TIDC/ Distribution Services Branch
SUBJECT:
Special Document Handling Requirenents 1.
Please use the folioving special distribution list fcr the attachel document.
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2.
The attached docu=ent requires the following special considerations:
O Do not send overs 1=e enclosure to the sRC PDR.
Only one oversize enclosure was received - please
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return Sr ?.aguloim rile sim os *.
i h 04.C PCA
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Proprietary info ation - send a fidavit ly to the NRC PDR Other: (specify) b r
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UTIDC/DS3Authori:
cc: DSB Files Signature L __
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4 UNITED STATES j
NUCLEAR REGULATORY COMMISSION f
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WASHINGTON, D. C. 20556 hl!
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FROM:
US NRC/TIDC/ Distribution Services Branch SU3 JECT:
Special Docu=ent Handling Require =ents 1.
Please use the folieving special distribution list for the attached document.
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2.
The attached docu=ent requires the following special
/
considerations:
~
b Do not send oversi:e enclosure to the NRC PDR.
Only one oversize enclosure was received - please return M ".:;;ul ::rj ril:2::r-e. -
gg~ -
Proprietaryinfornation[-sendaffidavit[anlyc TO d40 4:04 A
~'
the NRC PDR O Other: (specify) l n
tcy%
cc: DSB Files C/DSB Authori:ed S g ture 1
,..