ML19282C784
| ML19282C784 | |
| Person / Time | |
|---|---|
| Site: | 07106387 |
| Issue date: | 04/05/1979 |
| From: | Fitzsimmons T ENERGY, DEPT. OF |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 7905020270 | |
| Download: ML19282C784 (8) | |
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Department of Energy t
Richland Operations Office
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P.O. Box 550 Richland, Washington 99352 x
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..a f1r. Charles E. fiacDonald, Chief
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Transportation Branch Division of Fuel Cycle and flaterial Safety
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U. S. Nuclear Regulatory Commission Hashington, D. C.
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Dear !!r. liacDonald:
PROPOSED REVISIOlS T0 flRC CERTIFICATE OF C0:4?LIAiCE 6387, REVISIO:13 Enclosed are ten copies of a letter written by the Hanford Engineering Development Laboratory (HEDL), an RL contractor, requesting that changes be mada tc the NRC Certificate of Compliance 6337, Revision 3.
Requirements for shipping new types and sizes of fuel pins in the Model 60 container necessitates these proposed changes.
These changes have been revicued by RL's Safety and Environmental Protection Division and have their concurrence. A revised RL certificate will be issued in the near future.
He would appreciate your immediate review of the proposed changes and the issuance of a revised certificate, since HEDL has a number of pending shipments for which revisions to this certificate will be required.
Any questions concerning these changes, should be directed to J.11. Peterson, FTS 444-6731, of my staff.
Very truly yours,
m
. R. ~F1 tnimons, Director Facilities and Site Services Division Enclosures cc:
David E. Patterson, OES, DOE-HQ a "; >
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ilanford Engineering DeVe!0pment LabDratory P.o. co a - cn m o. u,, m 7951005 March 19,1979 Director, FFTF Project Office (4)
Department of Energy Richland, Washington 99352 Attention: Director, Facilities and Site Services Division Richland Operations Office REVISION OF THE NRC CERTIFICATE OF COMPLIANCE 6387, REVISION NO. 3 DOCKET NO. 71-6387 Requirements for shipping new types and sizes of fuel pins in the Model 60 con-tainer necessitate revising the NRC Certificate of Compliance 6387, Revision No. 3.
In making the proposed changes the HEDL Nuclear Safety and Safeguards and Materials Management groups made a detailed examination of the existing certificate.
Several statements or use conditions were found inconsistent with data contained in the SARP.
These discrepancies are corrected in the proposed certificate revision.
Suggestions and conments applying to individual sections are listed and treated below in the same order as they appear in the certificate, and only those sec-tions affected are discussed.
The proposed wording for the revised sections are in italic type.
Section 3 (a) This certificate was issued as the result of a major revision of the Model 60 SARP, HEDL TC-138, Rev.1, by the Hanford Engineering Devel-opment I.aboratory, Richland, Washington 99352.
HEDL proposes it be listed as author of the document.
(b) The referenced report should be: HEDL Model 60 Unirratiated Fission-able Material Shipping Container Safety Analysis Report for Packaging (SARP), TC-138, Ecv. 1, January 1978.
Section 5 (a)
(2) Description HEDL proposes this section be amended by adding the following statement to the end of the first paragraph:
The cover plate is fitted uith a rupture disc asse-bly designed for up to 300 psi.
(FIEE 1/2 SP 10A).
Westinghossa Henterd Comrent/A subsidiary of westinghouse Electric Corp / Operating the Henford Engineering Co elopment Laboratory for the USDOE
Director, FFTF Project Of fice 7951005 March 19,1979 Page 2 Section 5 (a)
(3) Drawings This Certificate of Compliance is based on the document HEDL-TC-138, Rev.1, therefore the first paragraph in this section is obsolete and should be omitted.
HEDL proposes the second paragraph be revised as follows:
The packaging is constructed in accordance uith Dra: Jing No. H-3-32429 (7 sheetc) chcran in Figurca 3 through 9 in Hanford Engineering Davclopment Labora-tory Ecport TC-138, Rev. 1, January 1978.
The pin holdcr in-certs for the Model CO are detailed in HEDL Dra::ings Noc. H 32429, Shccts 2 and 3, (120 pinc); H-3-42514 (90 pinc); H 39C91, Shcets 1 and 2 (58 pinc); and H-3-44280 (36 pins).
(b)
(1) Type and Form of Materials Several changes are required in this section.
The SARP (HEDL-TC-138, Rev.1) stipulates that only special form material is allowed to be shipped in the Model 60 container.
This must be emphasized.
The substitution of Th0g for natural or depleted U02 should be included. Thoria (Th0 ) and natural or depleted UOp are all 2
nonfissionable and approximately equal in density characteristics, scattering cross sections and absorption cross sections. There-fore, Th02 m y be substituted for natural or depleted U07 with-out changing any limits specified in this certificate.
Specifying a particular stainless steel for cladding may limit the types of fuel pins to be shipped.
The calculations for the Model 60 SARP assumed all stainless steel was composed of 74 wti iron,18 wt% chromium and 8 wt% nickel.
HEDL Nuclear Safety completed further evaluations and concluded that changes from the nominal amounts will show only negligible differences in the reactivity of a fuel shipment.
Although there is no need to specify a specific type of stainless steel for pin cladding, ferritic or austenitic stainless steels or precipitation strength-ened super alloys will cover all cladding materials currently used and those projected for the future.
The maximum linear density of fissile material, 2.0 kg/f t stated in Section 5(b)(1)(iii) of Revision 3 is misleading.
First, it is incorrectly specificd since it specifically applies to the whole container and not to just a single pin as implied here.
Secondly, this limit should be in Section 5(b)(2).
This is fur-ther addressed below.
Based on the above statements, HEDL proposes Sections 5(b)(1)
(i) (ii) and (iii) be revised as follows:
Director, FFTF Project Office 7951005 fia rch 19, 1979 Page 3 Section 5 (b)
(1)
(i) All radioactive matcrial chall be either in fuct pins or capsulcs which meet the requirements of special form material ai defined in 10 CFR 71.4 (o).
(ii) Unirradiated fuct pinc containing mixed PuCg in depicted or natural UO.,or Th0 ac procced cintered pcilets of the g
fol2owing cpccificationc:
Pellet diamatcr, inch 0.205 (mar. )
Pin outside dic=cter, inch 0.22 to 0.24 Fuct colic =n length, inch 37.0 (max.)
PuOg, v/o 31 (max.)
Pu-240 content, v/o 10 (min.)
Cladding material Ferritic or custenitic SS or precipitation strcngthened super alloys Cladding thickness, inch 0.015 (min.)
(iii) Univradiated fuct pinc extcining mixcd PuC2 in UO., from dcpictcd to to any degree of cnrichment in the U-2$5 ico-tcpe ac calid pelletc of the following cpecificationc:
Pcilct dic=cter, inch 0.000 (max. )
Fuct column icngth, inch 37.0 (ma=.)
Pu-240 content, v/o 10.0 (min.)
Pu-242 content
<1/2 content of Pu-240 Cladding material Ferritic or ausicnitic SS or precipitation strengthcncd super alloys Cladding thickneca, inch 0.010 (min.)
Notc:
ThOg may be cubstituted for depicted or natural UOg.
Plutoniten or urani:en carbides and nitridcc arc allowed cub lcct to additional limitations in 5(b)(2)(i).
(b)
(1) (iv)
HEDL recommends this section should be omitted entirely.
It is covered in Section 5(b)(1)(ii).
(b)
(1)
(v) through 5(b)(1)(ix)
Assuming the foregoing changes, these sections will require section number changes but are other-wise correct as they stand.
The section number cha.ges will be as follows:
5(b)(1)(v) becomes 5(b)(1)(iv) 5(b)(1)(vi) becomes 5(b)(1)(v) 5(b)(1)(vii) becomes 5(b)(1)(vi) 5(b)(1)(viii) becomes 5(b) (1)(vii) 5(b)(1)(ix) becomes 5(b)(1)(viii)
Director, FFif Project Office 7951005 "a rch 19,1979 Page 4 Section 5 (b)
(2)
In section 5(b)(1)(iii) of the Revision 3 certificate limits 2350 are for pins containing mixed Pu02 with UOp enirched in improperly stated.
As stated each fuel pin can contain up to 2.0 kg/f t of fissile material, whereas the proper limit per-mits 2.0 kg/f t of fissile material total for all pins combined.
The limit should be 2.0 kg of fissile material per linear foot of the containment vessel (not to exceed 37.0 in total length).
HEDL Nuclear Safety suggests an expanded table based on the one in the Model 60 SARP (TC-138, Rev.1, Page 20) be included in this section to reduce potential miscalculation of limits for pins.
Section 5(b)(2)(i) infers that all pins containing Pu02 with U(enr.) 02 can be handled under a limit of 120 pins.
Based on the above discussions, HEDL recommends Section 5(b)(2) be revised to read as follows:
Marinum Quantity of Material per Package ne ma=im:en package heat load shall not c=ceed 2 2. 3 vatts/ft of fucl length uith the ma=imum package heat load not to c:ceed
- 37. 0 vatic, and plutoniten in c= cess of tucnty (20) curico per package must be in the fom of metal, metal alloy or rcactor fuct cicmcnts; c~:d:
(i) For the contents described in 5(b)(2)(ii): 220 fuel pinc.
Fcr the oxide fuct contents dcscribcd in 5(b)(2)(iii): cec Table I.
Carbide and nitride fuei pin chipmcnts are ai2oucd uith the foiloving additional rastriction: % c Pin Limit
!; umber of Table I chall be multiplied by 0.8 to compincate for the highcr densitics of carbidcs and nitrides.
'T hog may be substituted for dcpleted or natural UOg vithout chmging any linits cpecified in this certificatc. All pins si:all be ccnstraincd in the appropriata pin holders chcun in drauings specified in 5(a)(3) and diccucccd in .
Table I appears as page 5 of this letter.
(ii) For the conicnts dcccribed in 5(b)(1)(iv): Grcater than Type A quantity of radioactive matcrial and ficcile material contents not to c ceed the generally licensed macc limits as cpecified in 72.22(a) of 20 CFR Part 72.
iiii) For the contents daccribed in 5(b)(1)(v):
280 grams.
(iv) For the contents described in 5(b)(1)(vi):
25 kgo total.
(v) For the contents describcd in 5(b)(1)(vii):
3 gra c total.
(vi) For the contcntc dcccribcd in 5(b)(1)(viii). 503 grams fissile.
Y.c nor, rFT' 'i.
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73] g.3 TAbtE 1
- arch 19,1979 Lli1ITS TOP. Pit:5 CD:;iAIT;1t;3 PLUTO ;IU: A;D URA:;IUti Page 5
( Applicable to Sections 5(b)(1)(ii) and 5(b)(1)(iii)
MODEL 60 Fuel Column Fuel Column Diameter Pu+235U Content Limit liumber*
Diameter Pu+235U Content Limit tiumber*
(in. max)
Wt.% Max.
(Pins Max)
(in. max)
Wt.% liax.
(Pins Max) 0.205 100 30 0.350 100 10 75 40 75 13 50 60 50 20 35 85 40 25 33 90 35 28 30 100 30 33 28 107 25 40 25 120 0.400 100 7
0.230 100 24 75 10 75 32 50 15 50 48 40 19 35 68 30 26 30 80 25 31 28 85 20 39 26 92 24 100 0.500 100 5
22 109 75 6
20 120 50 10 40 12 0.250 100 20 30 16 75 26 25 20 50 40 20 25 35 57 15 33 30 66 28 71 0.550 100 4
25 80 75 6
23 86 50 8
20 100 40 10 18 111 30 13 16 120 25 16 20 20 0.270 100 17 15 26 50 34 45 37 0.600 100 3
40 42 75 4
35 48 50 7
30 56 40 8
28 60 30 11 25 14 0.290 100 15 20 17 75 20 15 23 50 30 40 37 35 42 30 50 25 60
- Combinations of fuel types may be shipped within a single package as lona as the sum of the masses for each fuel type divided by its batch limit'does not exceed
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unity.
Director, FFTF Froject Of fice 7951005 March 19,1979 Page 6 Section.5-(c)
(1) HEDL proposes this section be corrected to read as follows:
Mini r: trancport inder to bc "hc:n on label for Claco II.
(i)
For contents deceribed in 5(b)(1)(ii) and limited in 5 (b)(2) (i):
- 0. 4 (ii) For contents dcccribcd in 5(b)(1)(iii) and lidtcd in 5(b)(2) (i):
- 7. 0 (iii) For contents dcccribed in 5(b)(1)(v) and lidtcd in 5 (b)(2) (iii):
- 1. 3 (iv) For contents daccribcd in 5(b)(1)(vi) and iinited in 5 (b) (2)(iv):
0.2 (v) For cantcnts describcd in 5(b)(1)(tr:i) and limited in 5(b) (2) (v):
0.6 (vi) For contents described in 5(b)(1)(viii) and limited in 5(b)(2)(vi):
Ma=L=:cn Grec F:ccile var Container Trancocrt Indc:
15C
- 0. 2 500 1.3 900
- 7. 0 (2) HEDL proposes this section be corrected to read as follows:
Ma=imwn n:c.bcr of packages per chip ncut for Cl:cc III Contente dcccribcd in 5(b)(1)(iv) and linited in 5(b)(2)(ii):
One (1)
Section 6 HEDL proposes this section be revised and corrected to read as follows:
When icoto;,cc cpccified in 5(b)(1)(v) [and LL=ited in 5(b)(2)(iii) and 5(c)(1)(iii)] arc combincd with isotopcc cpecified in 5(b)(1)(viii) [and lidtcd in 5(b)(2)(vi) and 5(c)(1)(vi)], the c:cn of the ratios of the con-tent nacccc to thcir rccpective approved racc lidts chall not c=cced ic;ity.
The trancport indc: chall bc at Icact 1.3 if lecc than 500 gr=c ani 7. 0 if cycr 500 gr=c.
Section 7 HEDL proposes this section be revised as follows:
All plutoni:c and uranize-fuct pina doccribed in 5(b)(1)(ii) and 5(b)(2)
(iii) and IL-ited in 5(b)(2)(i) chall be confined in pinhcidcr incerte dcccribed in ccccion 5(a)(3).
Tr.cy are ccqcccd of stainlccc cccci t:bcc clccc packti ::ithin a cylindrical vol:cnc of 5. 7 inchcc (nr. ) dimatcr.
Ib: hol.icrc con:=ining bctuccn SS and LEG ::acc chail have a rbnL=:cn ::Ec
- ll thichnccc of 0. 035 in.
Pinholdarc cantaining bctuccn 35 and 57 i:bcc chall h cc a
-ir'- - **c call thicknccc of 0. 050 inchcc.
^'
Director, FFTF Project Office 7951005 l' arch 19,1979 Page 7 Section 8 HEDL proposes this section be revised as follows:
The rupturc disc fitting (FIKE 1/2 SP JOA) it an integral part of the Model CD packaging.
The Model 60 Safety Analysis Ecport for Packaging HEDL-TC-138, Ecv. 1, addracces this fact.
Thcre is no restriction placed on moscration in the containcr.
No li-it is placed on the ancunt of packaging r:ateria:
uccd.
REFEREtiCES All items in the certificate are covered by the SARP HEDL TC-138, Rev.1. TC-138 should be the only reference needed.
We believe these proposed changes will result in a practical certificate of in-creased versatility and flexibility.
HEDL has a number of shipments pending for which revisions will be required.
We will appreciate any assistance you can give to expediting these changes and the issuance of a new fiRC Certificate and the corresponding Certificate of Competent Authority.
If there are any questions, please call (2-3388).
Lfk,a/
CA P m F. M. Smith fiuclear Safet(yC.A.Rogersj fluclear liaterials Management
. W. EngeY( ianager fiuclear Materials Management bn DDE/RL -
J. !!. Peterson