ML19323C283
| ML19323C283 | |
| Person / Time | |
|---|---|
| Site: | 07105939 |
| Issue date: | 04/17/1980 |
| From: | Travis W ENERGY, DEPT. OF |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 16097, NUDOCS 8005150260 | |
| Download: ML19323C283 (7) | |
Text
- _ _
7/- 5 739 i i
- "'i THIS DOCUMENT CONTAINS
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I POOR QUAUTY PAGES 8005150 4 o s @%'Ny?
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Department of Energy Oak Ridge Operations G,7; p12 43
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P.O. Box E
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's Oak Ridge, Tennessee 37830 j'.;(/'_
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.._: y April 17, 1980 /g
--t V. S. Regulatory Commission
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ATTN: Mr. Charles E. MacDonald, Chief q
Transportation Certification Branch 04i 1
Washington, D.C.
20555 Gentlemen:
MODIFICATION OF CERTIFICATE OF COMPLIANCE (USA 5939 BF) (YOUR LTR DTD 2/1/80)
Enclosed are ten copies of the letter dated April 3,- 1980, from C. C. Hopkins to J. A. Lenhard with the above subject with enclosures.
The OR0 Safety and Environmental Control Division has reviewed the enclosed letter, and we fully concur with ORNL's tests and evaluation confirming that the capsules fully meet leakage tests provisions of Regulatory Guide 7.4.
Since the capseles will be checked for surface contamination to assure nonleakage prior to shipment, we recommend that NRC approve the use of the GE-1500 cask as requested.
We request a priority review of this request so that shipments can commence.
Your early attention to this matter will be appreciated.
Sincerely, dibw) IME William H. Travis, Director MS-332:WAP Safety & Environmental Control Division FSS: 0116
Enclosures:
As stated (10)
E"'7~ $
cc w/ encl:
i.'
T. H. Hardin, AD-46 R. Garrison, HQ-ECT, EV-131, E-201, GTN D. M. Ross, HQ-0ES, EV-125, E-201, GTN 4
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-l OAK RIDG E: N 'si lO N A t LAeORATOPY i
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- 960 Department of Energy, Oak Kicge Operatt 'ns Attention
Mr. J. A. Lenhard,.issistant Manager for Energy Research and Development Post Of fice Box E Oak Ridge, Tennessee 37830 Centle=en:
Modification of Certifycits of Cer-liance (USA 5939 BF)
Reference:
W. E. Terry (OF1;L) :.e tte r dated Neverber l'.,
- 1979, to L. G. 31alock (DL)E) cnc Charlss E. MacDcnald letter dated Februa: y 1, i9 30, tc L. d. Blalock ORNL has recelyed an order f ar the f abricati >n of isotopic pcwer sources utilizing "SrF; as the faci fcrm.
This is the only fcre now produced by Rockwell '!anfora Operations (RE) in the '.Jas te Incapsulitica Storage Facility (VEST).
'a'e p r o p > s e te obta13 stinderd WESF capsules, each containing acproximatel: 10,0' O Ci of N 5rF;. f ram RH'1 with shipment to be mad, in a ren:ed GE-1310 can. Tl is transf u e shoulc ta', e place as soon as po ssible in or icr to rat the f ealing date c f the generators for the c ustomer.
1 7 Shipments of Csci in th. standard WESF capsale have been made f rom RHO to 0?.NL in an NRSK cask. We'balieve it ay become necessary to make 137
~
CsCl shipments in a GE-L530 cask in the future since the NRBK cask is used for other radioacttve's.hipments.
4 The existing U. S. Nuclear Resp-latory Commission Certificate of Compliance (USA '5939 BF) for tb SE-15C0 cask allcws a. shipment of radioactive material as metal c : o:c:.de in quantities having maximum thermal power generation rate ci 3120 14 We request that you obtain an amendment to the Certificate of Com;iliance to permit the shipment of 90 137 SrF; and CsC1 containea it the WESF capsules in the GE-liOO cask within the~present limitation ct the thermal pe er generation rata. We request that DOE-Richland Opers.:1on: Of fice and Ur.ian Carbide-Nuclear
. Division. Oak Ridge National Lasorat ory, be listed as authorized shippers.
4 C. O ' r.
--us..
9 i
4 DOE, Mr. J. A. Lenhard 2
April 1 1980 The WESF capsules used for SrF: and O'CsC1 (attachel drawings)
M are identical in closure desigr i anc autside diareters of both the inner I U r:1 psule is 0.(~5 inches 13nger than C
and outer containers; the 137Csci
.q sale is fabrica:ed of T<pe 316L the 3CSrF2 capsule. TheSrF ceasule is fabricated ci " Haste 11'oy C-276" stainless steel. The M high-temperature alloy, and the wal. s c f the i nr.e: and outer containers are thicker (0.02S inches and C.011 inenes) thar the corres7ce. ding CsC1 capsule walls. Cesim:1 :hlo:-ilc has a ickt: seltin; point (646 C) 137 than SrF2 (1450+0C and al!o e>11bi s n larger thctmal expansicn.
For thesereasonsthe{37CsC1 capst ie desis, was se!(c ted for testing to demonstrate leak tightness fleg alatory Juide 7.c.
By ar.alysis, if the 137CsC1 design passes all appli:abir t(sts tre
-SIF: wCuld also be qualified.
A capsule containing inert cesium chloride wc.s fabricated at RHO under conditions which simulated as cic sely as pos sible those used in i
fabrication of the CsC1 capsales.
The capsule was shipped to ORNL 137 and subjected to the series of 3 rec.a1 forn tests prescribed in Safety Series No. 6, Regulations for tae S.ife Transport of Radioactive Materials, 1973 Revised Edition, IAEA, Vienna, 19'3 and in WCFR 173.393 (a).
These tests included a 30-ft. er:p nest, an impact test, and a high-temperature (800 C) test.
Befare and after each test the capsule was leak tested using both an ethylene 11ycol-vacuun t cst described in Leak Testing of Radioactive sources, Oh5L '529, in> a helium leak test was made at a sensitivity of <I.; x 10-8 STD ccNec.
No leaks were detected in any of the tests and th: capsule sustained no visibic structural damage. Records of these tests s.re on ' file at OP.NL.
The MSrF2 and 137CSC1 capsules loaded at RHO at c 101.um leak tc.ted after fabrication (leak test sensitivity <1 x 10" ST) cc/sec), anc they are ch:cked for surface contaminaticn immediately prior to shipm.nt as additional demon-stration that no leaks are are:er.t.
We conclude that since the protot:pe capsute of the ' FCsC1 design 32 passed all applicable special 'orm :ests the 3 r., design woald also.
We would appreciate ycur eb:ai ing the mocified Certificatien of Ccmpliance.
' e ry A rt. '
von' s,
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r N-hrC. C. hopkinyr N
..P A b..ecative O ructor for
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Sappor and wrvices CCH:JE2:gfm 4
Enclosures cc:
L. Brecke W. F. Ra;;1and J. A. Cox M. E. Ransey R. F. Hibbs J. E. Ratied ;e E. Lamb
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