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.J A W E W W W W W,313rW W w W W W W W W W W W W W W W W W W W W W W W W W u<W W W W g 3 ( | |||
i Ig NRC FORM 618 U.S. NUCLEAR REIULATORY COMM:CSION g. | |||
i nw N S C"'" | |||
: a. This cemficate is issued to certify that the packaging and contents descnbed in item $ below, rnects the applicable safety standards set forth in Title 10, | CERTIFICATE OF COMPLIANCE i | ||
* Packaging and Transportation of Radioactise Material." | I l'OR RADIOACTIVI: M ATI:RI ALS PACKAGl3 k | ||
i i a Cl'RTillCATh NUMBLR b kEvlslON NUMBf k e PACAAGEIDENTillCATION NUMhtR d PAOL NUMhER e TUTAL NUMBLR PAGES nl 6568 11 USA /6568/A 1 | |||
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sj | : a. This cemficate is issued to certify that the packaging and contents descnbed in item $ below, rnects the applicable safety standards set forth in Title 10, N-N Code of Federal Regulations, Part 71. | ||
(2) | * Packaging and Transportation of Radioactise Material." | ||
Ni The cask is cylindrical in shape 93 inches long and 82.5 inches in | d' | ||
%g b This ccmficate does not reheve the consignor from comphance with an) requirement of the regulations of the U.$ Department of Transportation or other h | |||
inner and outer steel shells that are welded to a laminated steel base | apphenble regulatory agencies, including the gesernment of any country through or into w hich the package aill be transported. | ||
E 3 TH15 CL RTil1CATE 15 ISSULD ON THE B Asis Of A 5 AfITY AN ALY$15 RINRT OF THE PACK AOL DL$lGN OR APPLIC ATION a ISSULD TO f %me sinJ AJJersu b TITLE AND IDENT1f1 CATION OF Rf PORT OR APPLICATIOk N | |||
4, E | |||
W l | |||
4 p | |||
Chem-Nuclear Systems, Inc. | |||
Tennessee Valley Authority application g | |||
"Q 140 Stoneridge Drive dated August 16, 1976, as supplemented, l | |||
Columbia, SC 29210 g | |||
p! | |||
71-6568 g | |||
p e DoCAETuUuBE, y | |||
$ 4 CONDITION 5 g | |||
g This cemficate is conditional upon fulfilhng the requirements of 10 Cf1 Part 71, as appikable, and the conditions specified below. | |||
g A 5 g | |||
( | |||
sj E | |||
f (a) | |||
Packaging I | |||
l (1) | |||
Model No.: | |||
LL-60-150 (2) | |||
Description l | |||
Ni The cask is cylindrical in shape 93 inches long and 82.5 inches in E | |||
1 diameter. | |||
Lead shieldir:g, 3-1/2 inches thick, is encased within the E | |||
!I inner and outer steel shells that are welded to a laminated steel base E | |||
8 plate assembly. The cover is a steel plate assembly secured to the top E | |||
flange by 36 steel bolts. | |||
Encircling the top of the cask is a partial E | |||
sj length steel shell of 1/2-inch thickness. Silicone 0-rings provide seals E | |||
si at the top cover and at-all plugs. | |||
The inner container is right circular E | |||
#j steel cylinder with a capacity of 150 cu ft. The total weight, when E | |||
Bj loaded, is approximately 73,000 pounds. | |||
E Sj E | |||
s (3) | |||
Drawings E | |||
i E | |||
The packaging is constructed in accordance with the following ATCOR Inc. | |||
E s | |||
Drawing Nos.: 0568-B-0005, Rev. H; 0568-C-0008, Rev. E; 0568-B-0010, l | |||
E t | |||
#{ | |||
Rev. E; 0568-B-0016, Rev. D; 0568-B-0018, Rev. A; 0568-B-0025; and E | |||
0568-R-0001, Rev. J. | |||
E Sj E | |||
#l 6 | |||
#j E | |||
h} | |||
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g PDR ADOCK 07106568 g | |||
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waw w w w w w w w w w w w w w w w w w w w w w =usur = = = w w w w w w w w w w w w w w w w w g g | |||
g NRC FORM 618A CONDmoNs inmunu.es U.S. NUCLEAR REoVLATORY COMMIS$10N g | |||
e | ei a | ||
Bj Page 2.- Certificate No. 65f>8 - Revision No. 11 - Docket No. 71-6568 q | |||
B e | |||
Bf q | |||
B; 5. | |||
(b) | |||
Contents u | |||
Dj E | |||
b; (1) | |||
Type and form of material e | |||
(2) | #j d | ||
W Process solids, either dewatered, solid, or solidified waste, in g | |||
B sealed containers, and limited to the following: | |||
q | |||
#j N | |||
Bj (i) | |||
Materials in which.the radioactivity is essentially uniformly a | |||
W; distributed and in which the estimated average concentration a | |||
4; per gram of contents does not exceed: | |||
i | q | ||
m m m m m m m m m m m m m m m m m m_m_ m m m m m m m m m m m m m m m m m , m m | #i d | ||
p 0.0001 millicurie of radionuclides for which the A, quantity g | |||
e in Appendix A of 10 CFR Part 71 is not more than 0.05 curie; g | |||
r a | |||
p 0.005 millicurie of radionuclides for which the A, quantity in y | |||
p Appendix A of 10 CFR Part 71 is more than 0.05 curie, but not g | |||
4 more than 1 curie; or g | |||
>l 0.3 millicurie of radionuclides f$r:which the A quantity in d | |||
p AppendixAof10CFRPart71ismorethan1 curie. | |||
g g | |||
h (ii) Objects of-nonradioactive material externally contaminated l | |||
g! | |||
with rr.dioactive matarial, provided that the radioactive N | |||
g material.is not readily dispersible and the surface i | |||
l I | |||
g contamination, when averaged over an area of I square meter, l | |||
U g | |||
does not exceed 0.0001 millicurie (220,000 disintegrations 1 | |||
I 9 | |||
per minute) per square centimeter'of radionuclides for which U | |||
y! | |||
the A, quantity in Appendix A of 10 CFR Part 71 is not more J | |||
than 0.05 curie, or 0.001 millicurie I | |||
E h | |||
'2,200,000 disintegrations per minute) per square centimeter l | |||
? other radionuclides. | |||
8 g | |||
(2) h a | |||
)ity cf material per package U | |||
l}l ype A quantity of radioactive material with the 4 | |||
Grea > | |||
weight ta | |||
.a package contents and secondary containers not E | |||
ll exceeding 12,500 pounds. | |||
E | |||
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B e | |||
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M i | |||
l-i 5 | |||
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m m m m m m m m m m m m m m m m m m_m_ m m m m m m m m m m m m m m m m m, m m | |||
M A gr y _prw w w w w w w w w w w w w w w w w w[w w w w w w w w w w w w w w w w w w w w I | M A gr y _prw w w w w w w w w w w w w w w w w w[w w w w w w w w w w w w w w w w w w w w I | ||
CONDmo% tomsawe | gl NRC FORM 818A Wl CONDmo% tomsawe U.S. NUCLEAR RE2VLATORY COMMISSION gl p* | ||
h' f. | |||
Page 3.- Certificate No. 6568 - Revision No. 11 - Docket No. 71-6568 8 | |||
6. | |||
(a) | |||
#l | For any package containing water and/or organic substances which could f | ||
'l | 8 radiolytically generate combustible gases, determination must be made by n; | ||
(1) | #l tests and measurements or by analysis of a represeqtative package such | ||
'l that the following criteria are met over a period of time that is twice i, | |||
t the expected shipment time: | |||
(1) | |||
The hydrogen generated must be limited to a molar quantity that E | |||
expected shipment time, | would be no more than 5%.by volume (or equivalent limits for other E | ||
E p | inflammable gases) of the secondary container gas void if present i | ||
at STP (i.e., no more than 0.063 g-moles /ft3 at 14.7 psia and E | |||
p | 70*F); or B | ||
E l | |||
E D | (2) | ||
The secondary container and cask cavity must be inerted with a 6 | |||
diluent to assure that oxygen must be limited to 5% by volume in E | |||
Bj those portions of the package which could have a hydrogen a | |||
D concentration greater than 5%. | |||
E j | |||
D E | |||
M; For any package delivered to a carrier for transport, the secondary 8 | |||
9, container must be prepared for shipment in the same manner in which determination for gas generation is made. | |||
Shipment period begins when d | |||
4 3, | |||
the package is prepared (sealed) and must be completed within twice the 5 | |||
expected shipment time, d | |||
s,i 4 | |||
5'; | |||
(b) | |||
For any package shipped within 10 days of preparation, or within 10 days 4 | |||
4 after venting of drums or other secondary containers, the determination d | |||
M in (a) above need not be made, and the time restriction in (a) above does a | |||
p! | |||
not apply, d | |||
N d | |||
p 7. | |||
In addition to the requirements of Subpart G of 10 CFR Part 71: | |||
5 9 | |||
d p! | |||
(a) | |||
Each package must be maintained in accordance with Reactor Cleanup Cask 8 | |||
le Maintenance Program in the supplement dated February 20, 1991. | |||
g B | |||
E p | |||
(b) | |||
The package must be prepared for shipment and operated in accordance with d | |||
p. | |||
the Reactor Cleanup Cask Operating Procedure in the supplement dated a | |||
p February 20, 1991. | |||
g d | |||
p 8. | |||
The package authorized by this certificate must be trans)orted on a motor l | |||
g g | |||
vehicle, railroad car, aircraft, inland water craft, or Told or deck of a g | |||
pl seagoing vessel assigned for sole use of the licensee. | |||
g B | |||
E p | |||
9. | |||
Fabrication of additional packagings is not authorized, g | |||
b d | |||
p 10. | |||
The package authorized for use by this certificate is hereby approved for use g | |||
g under the general provisions of 10 CFR 571.12. | |||
g B; | |||
E D | |||
E D | |||
d 4 | |||
a d | a d | ||
d a | d a | ||
d | d D | ||
d j | |||
Emmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmm$ | |||
-,w_.. w w ws w w w w_w w w w w w w w w w w w w. w w w w w w w w w w w w. w w w w. w w w g | |||
FORM 618A CONDm0NS (nmimwds U.S. NUCLEAR REGULATORY COMMISSION | |||
*l Page 4,- Certificate No. 6568 - Revision No. 11 - Docket No. 71-6568 p' | |||
E b | |||
Bj E- | |||
D | #{ | ||
g | E D | ||
11. | |||
Expiration date: April 1, 1999. This certificate is not renewable, g | |||
E D | |||
E | |||
.l p | |||
g | REFERENCES g | ||
E | |||
1 | #,j E | ||
4, Tennessee Valley Authority application dated August 16, 1976. | |||
g 4p!' | |||
Su)plements dated: October 8, 1976; Octob.ar 5, 1979; October 23, 1980; g | |||
E l | |||
p Fe)ruary 20, 1991; February 29, and September 30, 1996. | |||
g E | |||
g Chem-Nuclear Systems, Inc. supplement dated December 20, 1996. | |||
g 3 | |||
i g | |||
l FOR THE U.S. NUCLEAR REGULATORY COMMISSION | |||
E B | !{ | ||
E h | |||
E h | |||
Cass R. Chappell, Chief 8 | |||
1 Package Certification Section E | |||
9i g | |||
Spent Fuel Project Office E | |||
~I Office of Nuclear Material I | |||
Safety and Safeguards I | |||
Date: August 14, 1997 E | |||
E | |||
#,i E | |||
!I E | |||
5; E | |||
E S | |||
i E | |||
5; E | |||
B i | |||
E | |||
!i E | |||
S i | |||
E | |||
!i E | |||
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5 B, | |||
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1 4 | |||
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9 s! | |||
E i | |||
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E | E | ||
$m m m m m m m m m m m m m m m m m m un < = m m m m m m m m m m m m m m m m m m m m m m,,,,m E | |||
7t:y | 7t:y UNITED STATES | ||
[f j | [f j | ||
NUCLEAR HEGULATORY COMMISSION t | |||
WASHINGTON, D.C. *anas % | |||
APPROVAL RECORD | ...../ | ||
Model No. | APPROVAL RECORD Model No. | ||
LL-60-150 Certificate of Compliance No. 6568 Revision No. 11 In Certificate of Compliance No. 6568 for the Model No. LL-60-150 package, Revision No.10, Condition No. 5(a)(3), there was a typographical error in the third drawing number referenced. The Certificate of Compliance has been amended to correct the typographical error. | |||
f Cass R. Chappell, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Dato: | $ >f-ed( | ||
f Cass R. Chappell, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Dato: | |||
August 14, 1997 | |||
- - _ - _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _.}} | |||
Latest revision as of 02:13, 6 December 2024
| ML20210L717 | |
| Person / Time | |
|---|---|
| Site: | 07106568 |
| Issue date: | 08/14/1997 |
| From: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20210L710 | List: |
| References | |
| NUDOCS 9708210285 | |
| Download: ML20210L717 (5) | |
Text
i
.J A W E W W W W W,313rW W w W W W W W W W W W W W W W W W W W W W W W W W u<W W W W g 3 (
i Ig NRC FORM 618 U.S. NUCLEAR REIULATORY COMM:CSION g.
i nw N S C"'"
CERTIFICATE OF COMPLIANCE i
I l'OR RADIOACTIVI: M ATI:RI ALS PACKAGl3 k
i i a Cl'RTillCATh NUMBLR b kEvlslON NUMBf k e PACAAGEIDENTillCATION NUMhtR d PAOL NUMhER e TUTAL NUMBLR PAGES nl 6568 11 USA /6568/A 1
4 m
h2PREAMBLia N
kl
- a. This cemficate is issued to certify that the packaging and contents descnbed in item $ below, rnects the applicable safety standards set forth in Title 10, N-N Code of Federal Regulations, Part 71.
- Packaging and Transportation of Radioactise Material."
d'
%g b This ccmficate does not reheve the consignor from comphance with an) requirement of the regulations of the U.$ Department of Transportation or other h
apphenble regulatory agencies, including the gesernment of any country through or into w hich the package aill be transported.
E 3 TH15 CL RTil1CATE 15 ISSULD ON THE B Asis Of A 5 AfITY AN ALY$15 RINRT OF THE PACK AOL DL$lGN OR APPLIC ATION a ISSULD TO f %me sinJ AJJersu b TITLE AND IDENT1f1 CATION OF Rf PORT OR APPLICATIOk N
4, E
W l
4 p
Chem-Nuclear Systems, Inc.
Tennessee Valley Authority application g
"Q 140 Stoneridge Drive dated August 16, 1976, as supplemented, l
Columbia, SC 29210 g
p!
71-6568 g
p e DoCAETuUuBE, y
$ 4 CONDITION 5 g
g This cemficate is conditional upon fulfilhng the requirements of 10 Cf1 Part 71, as appikable, and the conditions specified below.
g A 5 g
(
sj E
f (a)
Packaging I
l (1)
Model No.:
LL-60-150 (2)
Description l
Ni The cask is cylindrical in shape 93 inches long and 82.5 inches in E
1 diameter.
Lead shieldir:g, 3-1/2 inches thick, is encased within the E
!I inner and outer steel shells that are welded to a laminated steel base E
8 plate assembly. The cover is a steel plate assembly secured to the top E
flange by 36 steel bolts.
Encircling the top of the cask is a partial E
sj length steel shell of 1/2-inch thickness. Silicone 0-rings provide seals E
si at the top cover and at-all plugs.
The inner container is right circular E
- j steel cylinder with a capacity of 150 cu ft. The total weight, when E
Bj loaded, is approximately 73,000 pounds.
E Sj E
s (3)
Drawings E
i E
The packaging is constructed in accordance with the following ATCOR Inc.
E s
Drawing Nos.: 0568-B-0005, Rev. H; 0568-C-0008, Rev. E; 0568-B-0010, l
E t
- {
Rev. E; 0568-B-0016, Rev. D; 0568-B-0018, Rev. A; 0568-B-0025; and E
0568-R-0001, Rev. J.
E Sj E
- l 6
- j E
h}
E bj E
B, a
W
- i E
4 E i E
4 W
D 9708210285 970814 I
5
!= = m um m m m m m m m m m m m m m m m. m m m m m m_m m m s m m m m m, u. m m m m, J
waw w w w w w w w w w w w w w w w w w w w w w =usur = = = w w w w w w w w w w w w w w w w w g g
g NRC FORM 618A CONDmoNs inmunu.es U.S. NUCLEAR REoVLATORY COMMIS$10N g
ei a
Bj Page 2.- Certificate No. 65f>8 - Revision No. 11 - Docket No. 71-6568 q
B e
Bf q
B; 5.
(b)
Contents u
Dj E
b; (1)
Type and form of material e
- j d
W Process solids, either dewatered, solid, or solidified waste, in g
B sealed containers, and limited to the following:
q
- j N
Bj (i)
Materials in which.the radioactivity is essentially uniformly a
W; distributed and in which the estimated average concentration a
4; per gram of contents does not exceed:
q
- i d
p 0.0001 millicurie of radionuclides for which the A, quantity g
e in Appendix A of 10 CFR Part 71 is not more than 0.05 curie; g
r a
p 0.005 millicurie of radionuclides for which the A, quantity in y
p Appendix A of 10 CFR Part 71 is more than 0.05 curie, but not g
4 more than 1 curie; or g
>l 0.3 millicurie of radionuclides f$r:which the A quantity in d
p AppendixAof10CFRPart71ismorethan1 curie.
g g
h (ii) Objects of-nonradioactive material externally contaminated l
g!
with rr.dioactive matarial, provided that the radioactive N
g material.is not readily dispersible and the surface i
l I
g contamination, when averaged over an area of I square meter, l
U g
does not exceed 0.0001 millicurie (220,000 disintegrations 1
I 9
per minute) per square centimeter'of radionuclides for which U
y!
the A, quantity in Appendix A of 10 CFR Part 71 is not more J
than 0.05 curie, or 0.001 millicurie I
E h
'2,200,000 disintegrations per minute) per square centimeter l
? other radionuclides.
8 g
(2) h a
)ity cf material per package U
l}l ype A quantity of radioactive material with the 4
Grea >
weight ta
.a package contents and secondary containers not E
ll exceeding 12,500 pounds.
E
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gl NRC FORM 818A Wl CONDmo% tomsawe U.S. NUCLEAR RE2VLATORY COMMISSION gl p*
h' f.
Page 3.- Certificate No. 6568 - Revision No. 11 - Docket No. 71-6568 8
6.
(a)
For any package containing water and/or organic substances which could f
8 radiolytically generate combustible gases, determination must be made by n;
- l tests and measurements or by analysis of a represeqtative package such
'l that the following criteria are met over a period of time that is twice i,
t the expected shipment time:
(1)
The hydrogen generated must be limited to a molar quantity that E
would be no more than 5%.by volume (or equivalent limits for other E
inflammable gases) of the secondary container gas void if present i
at STP (i.e., no more than 0.063 g-moles /ft3 at 14.7 psia and E
70*F); or B
E l
(2)
The secondary container and cask cavity must be inerted with a 6
diluent to assure that oxygen must be limited to 5% by volume in E
Bj those portions of the package which could have a hydrogen a
D concentration greater than 5%.
E j
D E
M; For any package delivered to a carrier for transport, the secondary 8
9, container must be prepared for shipment in the same manner in which determination for gas generation is made.
Shipment period begins when d
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the package is prepared (sealed) and must be completed within twice the 5
expected shipment time, d
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5';
(b)
For any package shipped within 10 days of preparation, or within 10 days 4
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M in (a) above need not be made, and the time restriction in (a) above does a
p!
not apply, d
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p 7.
In addition to the requirements of Subpart G of 10 CFR Part 71:
5 9
d p!
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Each package must be maintained in accordance with Reactor Cleanup Cask 8
le Maintenance Program in the supplement dated February 20, 1991.
g B
E p
(b)
The package must be prepared for shipment and operated in accordance with d
p.
the Reactor Cleanup Cask Operating Procedure in the supplement dated a
p February 20, 1991.
g d
p 8.
The package authorized by this certificate must be trans)orted on a motor l
g g
vehicle, railroad car, aircraft, inland water craft, or Told or deck of a g
pl seagoing vessel assigned for sole use of the licensee.
g B
E p
9.
Fabrication of additional packagings is not authorized, g
b d
p 10.
The package authorized for use by this certificate is hereby approved for use g
g under the general provisions of 10 CFR 571.12.
g B;
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FORM 618A CONDm0NS (nmimwds U.S. NUCLEAR REGULATORY COMMISSION
- l Page 4,- Certificate No. 6568 - Revision No. 11 - Docket No. 71-6568 p'
E b
Bj E-
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11.
Expiration date: April 1, 1999. This certificate is not renewable, g
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REFERENCES g
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4, Tennessee Valley Authority application dated August 16, 1976.
g 4p!'
Su)plements dated: October 8, 1976; Octob.ar 5, 1979; October 23, 1980; g
E l
p Fe)ruary 20, 1991; February 29, and September 30, 1996.
g E
g Chem-Nuclear Systems, Inc. supplement dated December 20, 1996.
g 3
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l FOR THE U.S. NUCLEAR REGULATORY COMMISSION
!{
E h
E h
Cass R. Chappell, Chief 8
1 Package Certification Section E
9i g
Spent Fuel Project Office E
~I Office of Nuclear Material I
Safety and Safeguards I
Date: August 14, 1997 E
E
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7t:y UNITED STATES
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NUCLEAR HEGULATORY COMMISSION t
WASHINGTON, D.C. *anas %
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APPROVAL RECORD Model No.
LL-60-150 Certificate of Compliance No. 6568 Revision No. 11 In Certificate of Compliance No. 6568 for the Model No. LL-60-150 package, Revision No.10, Condition No. 5(a)(3), there was a typographical error in the third drawing number referenced. The Certificate of Compliance has been amended to correct the typographical error.
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f Cass R. Chappell, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Dato:
August 14, 1997
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