ML20148E471
| ML20148E471 | |
| Person / Time | |
|---|---|
| Site: | 07109029 |
| Issue date: | 02/28/1997 |
| From: | Roughan C AMERSHAM CORP. |
| To: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9706030107 | |
| Download: ML20148E471 (18) | |
Text
PV l
y
)
1 1
i SENTINEL
.~
,4 Amersham Corporation 40 North Avenue Burlington, MA 01803 tel (617) 272-2000 k
28 February 1997 tel (800) 8151383 fax (617) 273-2216 l
Mr. Cass R. Chappell, Chief Spent Fuel Project Office 1
Office of Nuclear Material Safety and Safeguards Musham United States Nuclear Regulatory Commission 1 White Flint North QSA 11555 Rockville Pike Rockville, Maryland 20852 Reference Docket Number 71 9029
Dear Mr. Chappell:
I have enclosed information to respond to your request for additional clarification as discussed i
during our telephone conversation on 20 Nov 96 and in your letter dated 25 November 1996.
1 i
1.
The following engineering analysis demonstrates that the supplemental lead shielding remains in place throughout the normal conditions of transport and throughout the service life of the package.
[I The model 676 that was subjected to the drop and puncture test requirements had supplemental lead shielding secured in the normal manner, le glass tape. This 676 was inspected at the conclusion of these tests to determine damage. The inspection revealed
)
(af ter removing the foam) that the lead had remained secured in its original location, ie the glass taoe was still secure. As there was no movement of the lead shielding as a result of the 30 foot drop and subsequent puncture test, we conclude that there would be no j
movement of the lead of the less severe test of a 4 foot drop for normal conditions of transport.
The 676 when originally built (using the supplemental lead shielding) had a radiation profile performed which indicated that the radiation levels were less than 200 mR/hr at the surface and less than 10 mR/hr at one meter from the surface. As the lead did not shift as a result of the 30 foot drop, this demonstrates that the method of securing the lead is robust j
enough to remain in place under normal conditions of transport (the 4 foot drop). Therefore the radiation levels would remain the pme as the original results.
)
In addition we have received, serviced and reloaded mainy 6?5 that have been used in the I
field (some to the end of their service life) and in the normal conditions of transport and
/
have not had a 676 that ' id not meet the required radiation levels at any time. This d
s 9706030107 970228 1111111IIHHElllHHilllillilHIE
(
- IlliI,lin,Illill,illli,l111,11ll11,11 C
)
l historical information demonstrates that the supplemental lead shielding and the method of I
securing the lead is adequate to withstand the normal conditions of transport.
2.
The drawings have been revised as requested.
3.
a)
A copy of the video is enclosed for your review. Ths shipping cover plate damage l
will be shown in this for clarification.
I b)
The total weight of the package was 625 lbs. This represents the maximum weight I
of the 676 device. No additional shielding material was added to the tested device, but a steel plate was welded to the shell of the device to increase kinetic energy i
during the test to represent the worst case, i.e. maximum weight, condition.
Structurally, this plate did not contribute any significant strength as it was added to an already robust component, the shell.
i On any one projector, the weight of the DU shield and the weight of the l
supplemental lead would not both be at the maximum weights specified by the j'
drawings as the lead was added to supplement DU shields that were not able to reduce surface readings to 200 mR/hr. Hence, these shields would not be at the l
maximum specified weight. Additionally, the maximum.eight specification for the projector does not allow both the DU and the supplemutallead to be at their maximums.
1 c)
The drop test was executed such that the maximum loading was put upon the 1/4 inch thick retaining bars. These bars and their geometry relative to the shield represent the area most likely to be damaged during the 30 foot drop test.
Additionally, this placed the highest loads upon the adjusting screw threads and nuts. No damage resulting in shield movement were noted.
In reviewing the puncture testing, we identified impact on the open face of the device as an area of possible concern. An additional puncture test was performed on 676 serial number 1003 that had previously been subjected to the 30 foot drop test and the puncture test. The additional puncture test was performed and impacted the side of the 676 that the side frame had fallen off as a result of the l
earlier 30 foot drop test. The 676 was below 40 degrees C and weighed approximately 625 pounds during the performance of the test. A radiation profile i
performed before and at the conclusion of the additional puncture test did not show i
l any additional increase in radiation levels. A copy of the test report is enclosed.
Past testing of the locking mechanisms has shown that when impacted "end-on", damage is first seen in the S-tube between the locking mechanism and the shield thus clamping the source wire in a fixed position, i.e. the fully stored l.
position, within the shield, d)
All materials used to support the shield (steel and copper) and the materials used in the shield itself (uranium, titanium, zircalloy. end ateinless steel) do not melt until temperatures are wellin excess of 800 degrees C are achieved. Initial engineering analyses concerning the strength of the screws at elevated temperatures have been complex and inconclusive. We are evaluating the best method to demonstrate that the shield will not be move as a result of the fire test. This information will be forwarded shortly.
3 No direct uranium to steel interfaces exist in this device as copper is used as an intermediary material at these potential interfaces, thereby alleviating concerns
_ ~. -.
- - ~ _ ~
about potential eutectic formation. As the uranium is not damaged as a result of the I
30 foot and subsequent 4 foot puncture, ie no cracking in the shield as evidenced by the satisfactory radiation profile result, and the uranium does not melt at 800 C there will be no mechanical damage to the shield as a result of the hypothetical i
accident test sequence. Damage to the S-tube as a result of the thermal test would be inconsequential and the source would still remain in the stored position as evidenced by the successful drop test results.
?
4.
.The operating procedures in the SAR have been revised to require the installation of the shipping plate. This installation has always been shown on the drawings and the actual i
operations manual provided to users already contains this requirement. In addition,' revised l
pages are submitted for Sections 7 and 8 to incorporate comments on recent Type B i
reviews for other packages.
t 5.
After the conclusion of the hypott.,dcal accident conditions, a radiation profile was performed by installing a source it.to the damaged device and radiation readings taken at j
the surface and at one neter from the surface. There were no changes made to the damaged device for tb s profile. As tha earlier test report indicates, the dummy source t
j-assembly did not trove out of the stored position as a result of the hypothetical accident l-conditions. Therefore the profile source was in the same location as the simulated source
[
l that was used.
l The dose rates indicated on the profile sheet are the highest values for each surface l
obtained as a result of the profile. The profile consists of a slow scan survey of the entire j
surface indicated and includes the locking assembly for the rear surface. The slow scan i
j allows for detection of pin hole beams or any streaming. The reading listed for the rear 1-surface is the highest reading for that surface including the locking assembly, this was l
extrapolated to be 160 mRlHr As this was the highest value obtained, the dose rate l
directly over the locking assembly would have been 160 mR/Hr or less.
I I trust this provides the necessary information to review and approve the increased weight request for the model 676 that was submitted January 1996. If you require any additionalinformation, l
please contact me.
Sincerely,
- l. k
'Cathleen Roughan Regulatory Affairs Manager 1
i
~
i 1
p L
t
- Addendum' Test Plan 35 l
Datei 22.Nov 1996
References:
ANSI N432-1980 Section 8.4.4
+
j.
- 10CFR71 Section 71.73 (c)(2)
Test:
The Model 676 SN 1003 was subjected to another 1 meter drop test as described in -
. ANSI N432 1980 Sec. 8.4.4. Prior to the test, the polyurethane foam that was removed after the i
first series of tests to inspect the shield support system was replaced and the side plate that i
detached from the projector during the 9 meter drop test, performed on 21 Nov.1995, was removed. A radiation survey was conducted and the results recorded. The 676 was packed in dry
. ice until the temperature was below -40 deg F. The device was suspended so that the point of j
impact would be the exposed surface of the polyurethane foam that helps to protect the DU shield. The distance from the surface of the polyurethane foam to the target was measured at 4 ft.
The device was released and impacted the target at the center of the DU shield. The foam was -
crushed in the area of the impact and two pieces of foam broke off exposing a small area of the DU shield. No movement of the shield was apparent.
l A radioactive source was loaded into the 676 device and a radiation survey conducted. The
.i results of the survey was the same as the survey before the test. All readings were less than L
1R/hr at one meter.
Note: For this test the side plate that was displaced 3 inches from the projector shell on one end and 1 inch from the shell on the other end, was attached to its normal position on the projector.(see figure 3)
Since the side plate is not connected to the shell but to the 4 connecting rods that go through the polyurethane foam, (see figure 3) it does not contribute to the strength of the shield support system. It only adds weight to the package.
George Parsons is.L i7 j7 g.
p r
l l
m 2
f 8
i I
l I
l l
E #
N. E s s xs s s@
, s N- \\\\Ys s s fs
/,-
l'
'N'N N ' '
e,[jskr<i$
f' '
\\
f f
( s r----C r
s
',/ yp b
,[/ /
5
!F Ng
,,0,j%' ;'g s
\\
r s M s
- d4NTF fM
\\'6 i
f f
l
/-
g\\' -q s
l b
[ s 'N 's \\ 'YD s
l-l l
l i
i e
3 l
SECOND 4 FT DROP TEST l
7: G3 l
._._m p
r FINAL DEVICE INSPECTION i
Guide Tube Connection Functions Properly Proper identification / Labels Attached Lock Functions Properly Painted Surfaces Not Damaged j
S: lector Ring Functions Properly Fasteners Installed Properly Control Unit Connects Properly.
Proper Continuity "E" Machines Only Total Mass of Device Source Travels Properly.
Rear Plate Serial No.
- Source Stores Properly Date inspected l
NCR No.:
C 4-FOAM \\
- '"Y J
pevi ce SHIELDING EFFICIENCY TEST FINAL DEVICE ASSEMBLY
&07*5 dE i
l Source Model No.: D 'l-14 Source Serial No.:
15?7 Activity t-InD 7 R erial No.:
E-13d Date Cal. 3 0 er 46 Due 3 U&a T '1 S
Survey instrument:
d 6bbQp ND 1 o 00 IN9 d '5 OM 9 6 M Ydd 47 I
i OBSERVED llNENSITY mR/hr ADJUSTED INTENSITY mR/hr SUMACE AT ONf.
AT SU MACE AT ONE suMAce connecnow ucrea ucrea
(
FACTOR l-TOP T0
- 1. Il Y, O TOP l69 T.4 2.
j RIGHT 31.0
- 1. 8 Y IJ. o
=
RIGHT A~79 i T. ~14 FRONT 70
(. 6 9
' 5. e FRONT h
6,I5 l
i LEFT l36 l.07 60
/, g3 EFT (M
7.W REAR lI0.
- 1. 8.9 6<0 REAR.
I 'I ~7
- 7. W L
BOTTOM 10"0 l /l k.0 BOTTOM (3'T
'/.2P f
)1 Inspector's Signature _
~
4
l t
l:
. FINAL DEVICE INSPECTION l _ Guide Tube Connection Functions Properly Proper identification / Labels Attachcd l' Lock Functions Properly Painted Surfaces Not Damaged l S::l::ctor Ring Functions Properly Fasteners installed Properly Control Unit Connects Properly Proper Continuity "E" Machines Only Source Travels Properly Total Mass of Device Rear Plate Serial No.
Source Stores Properly,
Date Inspected NCR No.:
R t erlitt r[>rrfAF
( R6-F a h) &
SHIELDING EFFICIENCY TEST 0 FF FINAL DEVICE ASSEMBLY l
Sourca Model No.:
T3 9-13 Source Serial No.: 3677 Activity M 7.b Cd Survsy instrument: 6 3 Mk Serial No.: T-l 3 0 Date Cal. d 0 IX 4 Due 2 TA. 9 '7 l
lN bu 4 p.3 6 60
') Yg) g E o cR R L DG Jy,99 OBSERS/ED IN' TENSITY mR/hr ADJUSTED INTENSITY mR/hr AT SUMACE AT ONE SUMACE AT ONE I
SUKACE COfmECTION METER g
FACTOR TOP' ig
- f. ll 46 TOP ld9
% j,L f
RIGHT MO l.69 l 4. O g
RIGHT 37.1, 17.M l-FRONT 76 1.09
- 6. 6 FRONT 9Y
- 4. I 5 i
LEFT'
-I73
~7.J7 N
I20
- f. d f lo. 0
[
7,,73 REAR l( 0 f.09 (o. O REAR I 'f7 7.7T B01 TOM
.l00 hIl l,. o BOTTOM 13 7 7Jf h
insptctor's Signature L) fa 3b Date di Nod 34 NCR NO.
t l
)
1
. ~ -
.~
~
FINAL DEVICE INSPECTION Guide Tube Connection Functions Prnnerly Proper identification / Labels Attached Lock Functions Properly Painted Surfaces Not Damaged Selector _ Ring Functions Properly Fasteners Installed Properly Control Unit Connects Properly Proper Continuity "E" Machines Only i
l' Source Travels Properly Total Mass of Device
! Source Stores Properly '
Rear Plate Serial No.
NCR No.:
Date inspected 4ff A FTER 16d/ S p TE,rF k CMT J f DFFRPrMf' SHIELDING EFFICIENCY TEST 86 *E D l
FINAL DEVICE ASSEMBLY Sourca Model No.: Yd b /2 Source Serial No.:
6689 Activity CM 7.8 4t PblL Survsy instrument: A Y d 7R Serial No.: I'IIO Date Cal. 3 deff 95 Dub d Ten. 9 7
{
l tiLTv Yi V l4f9 0 5 OCT Al iL I' %. 9 7 L
OBSERVED IN' TENSITY mR/hr ADJUSTED INTENSITY mR/hr j
AT SunFACE AT ONE SUfEACE AT ONE sunrAct connEcnow weren ucyca FACTOR TOP
[(g J. / J Y. 0 TOP (09 4.91 RIGHT Ago 1.J 7
/ Y.o g
RIGHT 37R
- 17. J a
- f.. FRONT-70
), og f, e FRONT 9Y f. (6 L
l LEFT
~ l30
(.bg (i. 0 l. 33 LEFT l73
~l.39 REAR ll0 f.:04
(, _ 0 REAR (f7 7.M BOTTOM
-100
- f. J l 6.o BOrrOM (37 7,37 r
3 inspector's Signature A
dd Date da Mov % NCR NO.
l 1
f
7.
Ooeratina Procedure 7.1 Procedure for Loadino the Packsae 1.
Ensure that the source is locked into place in its storage position. To check this, the lock should be in the down position, the key removed, and the selector ring should be immobile. Attach a tamper proof security seal with an i
identification mark to the storage plug.
l 2.
Install the shipping plate over the lock assembly using the required 4 bolts and lock washers. Wrench tighten the bolts with sufficient torque to l
compress the lock washer, i
1 3.
Assure all the conditions of the Certificate of Compliance are met and the package has all the required markings.
4.
If the 676 container is to be packaged in a crate or other outer packaging, the outer packaging must be strong enough to withstand the normal conditions of transport. These requirements are outlined in 10 CFR 71. The 676 container should be put in the outer package with sufficient blocking to prevent shifting during transportation.
5.
Perform a radioactive contamination wipe test of the outer shipping package.
This consists of rubbing filter paper or other absorbent material, using heavy finger pressure, over an area of 48 in.8 (300 cm ) of the package surface.
2 The activity on the filter paper should not exceed 0.00001 uCi per cm og 2
removable contamination.
Note: If the 676 container is to be shipped without an overpack, the radioactive contamination wipe should be made of the outer surfaces of the i
676 container, if the 676 container will be shipped inside of an overpack, the radioactive contamination wipe should be made of both the outer surfaces of the 676 container and the outside surfaces of the overpack.
6.
Survey the package with a survey meter at the surface and at a distance of one meter from the surface to determine the proper radioactive shipping labels to be applied to the package as required by 49 CFR 172.403. If radiation levels above 200 mR/hr at the surf ace or 10 mR/hr 40 inches (1m) from the surface are measured, the container must not be shipped.
Note: If the 676 container is to be shipped without an overpack, the radiation surveys should be made from the outer surfaces of the 676 container.
If the 676 container will be shipped inside of an overpack, the radiation surveys should be made from the outer surfaces of the 676 container as well as the outer surface of the overpack with the 676 container packaged for shipment.
I l
When using an overpack, package labeling for transport is based on the radiation surveys from the outer surfaces of the overpack with the 676 packaged for shipment inside the overpack.
Revision 2 7-1 Feb 1997 l
7.
Return the container to Amersham Corporation according to proper procedures for transporting radioactive material as established in 49 CFR 171-178.
NOTE:
The U.S. Department of Transportation, in 49 CFR 173.22 e requires each shipper of Type B quantities of radioactive material to provide prior notification to the consignee of the dates of shipment and expected arrival.
l 7.2 Procedure for Unfoadino the Packaae The consignee of a package of radioactive material must make arrangements to t
receive the package when it is delivered. If the package is to be picked up at the carrier's terminal,10 CFR 20.205 requires that this be done expeditiously upon l
notification of its arrival.
Upon receipt, survey the 676 with a survey meter as soon as possible, preferably at the time of pickup and no more than three hours after it was received during normal working hours. Radiation levels should not exceed 200 milliroentgen per hour at the surface of the 676, nor 10 mitiroentgens per hour at a distance of 40 inches (1m) from the surface. Actual radiation levels should be recorded on the receiving report. If the radiation levels exceed these limits, the 676 should be secured in a Restricted Area, and the appropriate personnel notified in accordance with 10 CFR 20.
All components should be inspected for physical damage.
The radioisotope, activity, model number, and serial number of the source and the l
package model number and serial number should be recorded.
Opening and operation of the 676 will be performed in accordance with the operation manual supplied with the package in accordance with 10 CFR 71.89.
7.3 Preoaration of an Emotv Packaae for Transoort l
l 1.
For shipment of an empty Model 676, you must first assure there are no unauthorized source assemblies or cropped sources within the container, by performing the following procedure.
I a)
Remove the authorized source assembly from the Model 676 in accordance with the applicable operations manual for the storage l
device.
b)
After removing the source and disconnecting the source assembly, attach the jumper (dummy connector without a serial number) to the male connector of the drive cable.
l c)
Return the drive cable and connector to the Model 676 and disconnect the controis.
di insert dust cover cap, place selector ring in lock position, depress lock and remove the key. Insert the shipping plug and seal wire. Place an Revision 2 7-2 Feb 1997 t
1
_.m t
\\
)
i 1
1-
\\
EMPTY tag on the device.
2.
Assure that the levels of removable radioactive contamination on the outside surface of the outer package do not exceed 0.00001 microcurie per cm'.
i j
3.
. When you have assured the Model 676 is empty, survey the device and
)
prepare the package for transport depending upon the radiation levels
.l l
obtained, as given in 49 CFR 173.'
t l.
i i
l i
l-t i
i i
l
]
i j
l.i l-1 I
l l
l~
i i
i i
)
l i
Revision 2 7-3 Feb 1997
7 8.
Acceotance Tests and Maintenance Proaram i
8.1 Acceotence Tests i
1 8.1.1 Visual Insoection The package is visually examined to assure that the appropriate fasteners are properly safety wired. The package is inspected to assure that the proper marking and labeling is present.
i The seat weld of the radioactive source capsule is visually inspected for proper closure.
The package is inspected to assure it has been constructed and fabricated in accordance with drawing number R67690, Revision A; Sheet 1 of 5.
l The labels are inspected to assure they contain the required information and 4
are marked in accordence with 10 CFR 71.85(c) and 10 CFR 40.13 (c)(6)(i).
i l
8.1.2 Structural and Pressura Tests j
The swage coupling between the source capsule and cable is subjected to a static tensile test with a load of one hundred pounds.
8.1.3 Leak Testo The radioactive source capsule, which serves as the primary containment, is wipe tested for leakage of radioactive contamination, and must be less than 0.005 Ci of removeable contamination. The source capsule is subjected to a vacuum bubble leak test. Failure of either of these tests will prevent use of l
this source assembly.
8.1.4 Comoonent tests The lock assembly of the package is tested to assure that the security of the source will be maintained. A simulated (dummy) source assembly is installed in the radiographic exposure device and the lockbox locked. An attempt is made to pull the simulated source out through the lockbox. The shipping plugs are installed and checked to be sure they are attached securely to the device. Failure of either of these two tests will prevent use of the package I
until the cause of the failure is corrected and retested.
8.1.5 Tests for Shieldina Intearity l
With the package containing a source assembly, the radiation levels at the surface of the package and at 40 inches (1m) from the surface of the l
package are measured using a small detector survey instrument. These l
radiation levels, when extrapolated to the rated capacity of the package, must not exceed 200 milliroentgens per hour at the surface of the package nor 10mR/hr at 40 inches (1m) from the surf ace.
Revision 2 8-1 Feb 1997 l
r
m i
s 8.1.6 Thermal Acceotance Tests Not applicable.
8.2 Malutenance Proaram i-8.2.1 Structural and Pressure Tests Not applicable.
j l
l 8.2.2 Leak Tests i
j As described in section 8.1.3, the radioactive source assembly is leak tested l
at manufacture and must be less than 0.005 Cl of removable contamination.
l-
~ contamination every six months by the user,.with the same acceptance i
Additionally, the source assembly is wipe tested for leakage of radioactive
]
i criteria.
1 8.2.3 Subsystem Maintenance The lockbox assembly is tested as described in section 8.1.4 prior to each use of the package. Additionally, the package is inspected for tightness of I
fasteners, proper safety wires, and general condition before each use. The device must be inspected at intervals not to exceed three (3) months as 1
stated in Section 8.2 Appendix A.
8.2.4 Valves. Ruoture Discs, and Gaskets on Containment Vessel j
Not applicable.
l 8.2.5 Shieldina Prior to each use, a radiation survey of the package is made to assure that the radiation levels do not exceed 200 milliroentgens per hour at the surface r -
nor 10 milliroentgens per hour at 40 inches (1m) from the surface.
l 8.2.6 Thermal '
I I
Not applicable, i
f
(-
8.2.7 Miscellaneous I
Inspections and tests designed for secondary users of this package under the general license provisions of 10 CFR 71.12(b) are included in Section 8.2 Appendix A.
1 4
Revision 2 8-2 Feb 1997 l
l
?
L N
14 7/8 S
N 16 B
p4 13 11/16
[
[
s
{
[
'NR y
t sN e 4',
7,
">g,,,,,,
e s
\\
PRIOR TO 1977)
B s
23
\\[
MODEL 676 A & AE RETROFIT f,{
MODEL 676 8 & BE NEW PRODUCTION U
A ALL SiONS ARE INCHES AND REFERENCE NE oescRierige ~
MAX. WEIGHT: 625 LBS e e g M#* tion DRAWING DDCO#9: ADDED SUPP. LEAD, MAX WGT. (SHT2) 5,h-23 eq m
SIZE OF RETA.INING BAR WAS 1/4 THK (SHT3)
E TITLE MODEL 676 PROJECTOR CHGD SHIELD APPROX WGT TO MAX WGT (SHT4)
DESCRIPTION APPROVALS DATE LTR SIZE DWG.NO.
R 67690 REV REVISIONS A
scitt: NoNE issetT, or 5 E
E f3/16 FILLET WELD
~
g:RE-CSIDE FRAME INSERT (1/4 LOW CARBON STEEL)
$/jj (PRIOR TO 1991) d SEE VIEW C ON SE 5 3/16 ALTERNATE CONSTRUCTIONS FILLET WELD SIDE FRAME INSERT (1/4 LOW CARB. STL.)
'S' TUBE EXTENSIONS (2) 1 1
2 (PRIOR TO 1979) d
[ SCREWS & LOCKWASHE SAFETY WIRED SIDE FRAME (REF 3
f
/
1/4-20 TAMPER PROOF BUTTON HD 18-8 STN STL), OR V[m,,s,,4?-~,,,-,,~,,~~,,-~nu~,,,,~,-,~~,~~,~,, L ~~ 9?-,n&l l h (1/4-20 HEX HD BOLTS GRA
/
x 37 g s x
.x g
g s
r
\\g
/
q
,/[
(STEEL) TORQUE AT 70 LB-IN l
\\I
\\
N s\\
N Y h
i 5 LB-IN x
x
\\/ /
/
/
~'
l y LOCK ASSEMBLY (REF)
- f 7
/
- / fj /
gg RADIOACTIVE SOURCE
?
j s / j/p /p/
-mp 7
7 N
gy SHIPPING PLATE (REF)
ASSEMBLY
\\
/
x
/
"S" TUBE FABRICATED FROM:
'(/
/.7 f
\\
/
i U
WHEN REQD
/
/
l A ZlRCALLOY, OR
/ /
/
MAX WGT: 50 LBS
- s f
/
/~s i
\\
A
/ /
/ !
/.
C TYPE 304L STAINLESS STEEL
/[/
/
/ /
SHIPPING PLUG ASSEMBLY s
s
/ / !/
/ //
h Q
COATED WITH 50-100 um NI AL
\\ }*
g 6
(SEAL-WIRED) h\\
/
/
/
x
~./ 7//
/ / - /
5 AND 400-500 um AL 0
/
-N 2 3 1 1/8 HEX
\\
N
/
/ // /y
/
5 SHELL WELDMENT
- , /
/ /
/
7
/ /
\\
~
N
/
/
\\
LO WA E (4)
[
'i
,//
/ /
/
l RIGID POLYURETHANE FOAM (STEEL), SAFETY WIRED
-j Ty/
7 N
\\ ks (14 LBS PER CUBIC FT MIN)
\\
,/
-- s N
\\
[//
h CONNECTOR PLATE
=
x -
i taa n/
2 SLEEVE (ZlRCALLOY OR TITANIUM)
CAST INTO SHIELD SECTION A-A COPPER SLEEVE (REF)
RETAINING BAR (REF)
ADJUSTING SCREW (REF)
NAMEPLATE UNLESS OTHERWISE SPECIFIED: ALL DIMENSIONS ARE REFERENCE (2 MINIMUM)
SIZE DWG.NO.
R 67690 REV ScitE: none issEET 2 or 5 E
A
)
R SEE VIEW D SIDE FRAME (2)
ON SHEET 5 (1 IN. THK LOW CARBON STEEL) f'.
,T
""e; xQ
\\l! -}
676......... REF C67692
\\'
\\
l \\
\\
g N
\\
b hN LOCK ASSEMBLY N
\\
\\,
's $N
\\
l
\\
\\
9
\\N
\\
N
\\
g A 676 E....... REF C67691 b
l\\
N
\\
g g
\\ -jipi.
/
676 A & B.. REF A85790
\\
I
[A s
N N
676 AE & BE REF A85791
-fal
\\
\\
\\,!
\\
S N 7E :
EYs\\
1
\\
N \\
j H s
~"~lNN g. _i
+gW A%
~
l k\\
DN SHIPPING PLATE l
N x
N gs Imi :
Im i, N,
\\ is N
b N
' l!h i
'l,!f N
g N-N NCONNECTOR PLATE N
g N
?rh (1/4 THK LOW CARBON STEEL) g N-s N
es N
g x
imi d _,2memmm_~~~m
'Mmmm 1M 3/8-24 HEX HD BOLT
(<
w/ /
\\'
- j gO KWASHER (6 EACH) mm t
f RETAINING BAR (4)
(1 X 8 X 1/4 THK LOW CARBON STEEL)
/
SECTION B-B LEVELING PLATE
~
SHIELD (REF)j (1/8 THK LOW CARBON STEEL)
UNt.ESS OTHERWISE SPECIFlED: ALL DIMENSIONS ARE REFERENCE sizo owc. no.
R 67690 REV A
scatt: noNE isneer 3 or 5 E
)
W.A,a Ja 4
-= -
3-m.
S s
b
+
c m
e 5 0 5
~
$ Q
.. D N
@ N g
c O z
$ % 0 i
$ N h
-@E_________t_____-$P g g a
g G<-
s a n
~
1 s
j
$ 10 i
v
' A xN s
N
=
+
/
h f
SIDE FRAME (REF) 7/16-20 X 1 LG (STEEL)
CLEAT (8) WELDED TO SHELL K AS (8) 1/8 /
TORQUE AT 30 LBS.- FT.
(PER ASME B+PV j
ADJUSTING SCREW (4)
~
CODE. SEC II, l
1/2-13 THREAD (STEEL)
K g
AFTER OCT 1996)
A JAM NUT (20) 1/2-13 THREAD m
i 2
STEEL SIDE FRAME (REF)
RETAINING BAR (4)
I MAX. GAP 1/8 IN*
NQl 1/4 THK LOW CARBON STEEL (REF) a 5/8 OD X.120 WALL (STEEL)
N TUBE, TAPPED 7/16-20
+
t X1 1/4 DEEP,
[Rl BOTH ENDS. (4) i,
VIEW C ADJUSTING NUT (4) 3/4 HEX LOW CARBON STEEL wxxx xxxv
{
NOTE:
ALL URANIUM STEEL INTERFACES HAVE
~
~
l BEEN SHIMMED WITH COPPER.
VIEW D UNLESS OTHERWISE SPECIRED: ALL DlWENSIONS ARE REFERENCE SIZE DWG. NO.
R 67690 REV A
scitt: none isster 5 or 5 E
)
-