ML20148F987
| ML20148F987 | |
| Person / Time | |
|---|---|
| Site: | 07109033 |
| Issue date: | 05/28/1997 |
| From: | Roughan C AMERSHAM CORP. |
| To: | Osgood N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9706050112 | |
| Download: ML20148F987 (12) | |
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e SENTINEL Amersham Corporation 40 North Avenue l
Burlington, MA 01803 Ms. Nancy Osgood Package Certification Section tel (617) 272-2000 Spent Fuel Project Office tel (800) 815-1383 NMSS fax (617) 273-2216 U. S. Nuclear Regulatory Commission Washington, DC 20555 l
1 PAmersham 28 May 1997 QSA Docket Number 71-9033
Dear Ms. Osgood:
This letter is in response to your letter dated 19 Aug 1996, and the questions are answered in the i
same order as in your letter.
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1a)
The drawings for new construction include the the welding standard, Mil Spec 6858C, which is the seine standard provided in 1990, i
1b)
The foam density for new construction is specified on the drawings.
1 For older construction the drawings referenced on the certificate are historical as those versions are no longer manufactureo, as a result the changes referenced above can not be added to the drawing.
We can confirm the following information for older construction:
i The foam density is a minimum of 7.5 pounds per cubic foot The welds made after 1990 are in accordance with MIL SPEC - 6858C.
l 2)
Tungsten ie not used as supplemental shielding and the drawings have been revised to delete this reference.
i 3)
The operating procedures have been updated in Section 7 to clarify the terminology used. As j
this section was written in a generic manner in order to cover all packages, it has resulted in
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l the different terms used for the package. We have made a similar change to the model 820 package, section 7 and will continue to update this section to reference the specific model number instead of generic terms.
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Section 8 has been updated to reflect the reference to applicable marking requirements.
j in addition to the changes to the drawing described above, we have updated the drawings to the new format on the CAD system for clarity and included some minor revisions. The changes include:
Incorporating drawing number 66030 Rev D into drawing number 66025 Rev H as the g
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9706050112 970528
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packages are identical except for the capacity and the outer shell material. We have put both options on the drawing, le capacity of 120 Ci for 660A and 140 Ci for 660B and the outer
' housing is described as either steel or stainless steel.
On sheet 1 the thickness of the bolt cover has been revised to read 0.04 as it is not critical to safety.
On sheet 1, the option of removable feet is included to clearly depict the optional repair that is authorized under the current certificate in Section 8 of the SAR.
On sheet 2 the references for the stainless steel have been modified to list the series of steel as 300 series.
On sheet 2 an option for stainless steel for the locking slide and sleeve materialis included.
1 On sheet 2 have removed the detail on the cable assembly as it is not critical to safety, it only serves as an attachment to prevent the cover from being lost.
On sheet 3 section B-B shows a repair of the S-tube.
The enclosed engineering analysis demonstrates that these minor changes have no effect on the -
' package's ability to meet the Type B(U) requirements.
We appreciate your assistance with this request. If you require any additional information, please contact us.
Sincerely, NV\\ )
Cathleen Roughan Regulatory Affairs Manager i
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Engineering Analysis Change to drawing -
Stainless steel lock slide as an option The use of stainless steel will enhance corrosion resistance. Other mechanical properties when considered within the operating and transport condition limits (io thermal test of 800 C) will be equivalent to those of locking slides and sleeves made from steel. Therefore this change will have no impact on the package's ability to continue to meet the Type B(U) requirements.
Optional feet on bottom of the device This change is necessary to ensure that the earlier authorized repair of wear through on the bottom
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of the package (Section 8, revision dated 31 March 1994) is clearly depicted on the drawings as an option. The feet are an add on feature and do not impact the structuralintegrity of the container.
Section 8 has been revised to remove the reference to foot pad drawing number and the method of attachment.
Repair of S-tube Section B-B of drawing number R66025 Rev H shows the repair of an S-tube that has been bent due to an excessive impact from a drop, Prior to performing this repair the package would be thoroughly inspected to ensure that the package continues to meet all of the requirements in the Type B certificate and the Sealed Source and Device Registry.
The repair consists of cutting out the damaged section of tube and press fitting a short section of tube the same dimensions of the S-tube into the sleeve and securing with permanent lock tite. The other end of the tube would fit into the endplate fitting, thereby securing both ends of the tube.
This repair was performed in the past but was discontinued several years ago as the drawings for the model 660 series did not clearly show the repair.
The shield is supported within the container by foam. Previous testing has shown that the S-tube does not function as e structural element supporting the shield. The rearplate assembly containing the lock assembly, the foam and the teleflex cable of the source serve as the components that keep the source in a secured position. For example during the 30 foot drop tests the tube was bent but the source romained shielded because the foam and the teleflex cable supported the shield. In addition through all previous 1esting the endplates remained attached to the device and continued to secure the source thrcugh tne locking assembly on the rear plate.
As the S-tube does not serve as a component that keeps the source in the secured position, the repair does not adversely affect any of the Type B (U) package tests. A unit with a repaired S-tube would continue to meet all of the Type B(U) requirements.
Reference to 300 series of Stainless Steel All stainless steels in the 300 series have the appropriate mechanical properties for the components to meet Type B tests.
CAST HANDLE
- 1/4-20 FLAT HD CONNECTING RODS STORAGE TUB"c X4 (12L14 STL)
SHELL (.06 (ALUM. ALLOY)
SCR X8 (STL, ZINC OR CAD PLTD)
//10-32 FtAT HD RECEPTACLE CARBON STL OR
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END PLATES SCR X4 (STL, ZlNC
(.12 THK LOW
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SEE SHT 2 i
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SOURCE IDENT (pgg,0yy y g(p
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RIGID (SEE SHT 2)
S TUBE -
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POLYURETHANE SEE SHT 3 STN STL) y RElNFORCEMENT FOAM, 7.5 MIN RADIOACTIVE s
SLEEVE -
SHIELD -
LBS/CU FT SOURCE (IN STORED MODEL No 660A-120 Ci MAX CAPACITY.
SEE SHT 3 j
SEE SHT 3 f
POSITION) 9f MODEL No 6608: 140 Ci MAX CAPACITY.
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nf 2g ALL DIMENSIONS ARE INCHES AND REFERENCE 7
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OPTIONA*_, REMOVABLE MAXIMUM TOTAL WEIGHT = 56 LBS.
5 h INDICATES COMPONENT MATERIAL:
300 SERIES STN STL Amersham Corporation DRAWING 40 NORTH AVE, BURUNGTON, MA 01803 SEE DDC0 # 14
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TITLE MODEL 660 PRO.JECTOR g
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DESCRIPTION APPROVALS DATE LTR SIZE DWG. NO.
R 66025 REV SCAtE: none l SHEET 3 Or 3 H
REVISIONS A
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END PLATE REF
- 10-32 SOC h
LOCK LOCK RETAINER h COMPRESSION SLEEVE (HARDENED SPRING (LEE #
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OR HARDENED X4 (STN STL p f'///ffjj STN STL) b W/ LOCTITE) h
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RETAINER PROTECTIVE 1
LUGS ( t BUMPER X2 (RUBBER)
COMPRESSION SELECTOR RING 1 SPRING)
CABLE AS$Y LOCK ASSEMBLY h INDICATES COMPONENT MATERIAL:
300 SERIES STN STL
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BACKING PLATE (.06 THK SHELL (REF)
X1 WIDE STN STL)
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SPOTWELD: WELDED AND INSPECTED IN SECTION A-A QC SPE W 58C.
MSS OmERWISE SPECIF!ED: ALL DluENSIONS ARE REFERENCE FROM SHT 1 SIZE = 1/8 MIN DIA SIZE DWG. NO R
66025 REV SCALE: 1/1 SPACING = 1 INCH.
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STUBE SLEEVE X2
(.550 OD X.030 WALL OR (ZlRCALLOY OR
.562 OD X.035 WALL.
TITAN 1UM, OR TYPE 304L STN STL SAME MATERIAL AS STUBE COATED WITH 50-100uu NiAL AND CAST INTO SHIELD) 400-500 uM AL203)
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SHIELD ASSEMBLY DU SHIELD (REF)
SUPPORT SLEEVE (REF)
SHIELD ASSEMBLY WE!GHT APPROX. 34 LBS OR AS NEEDED TO PASS RADIATION PROFILE. MAX WEtGHT = 40 LOS.
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NEW TUBE SECTION.
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- = -m gM>p ADDITIONAL LEAD SHIELDING NOT TO EXCEED 3 LBS, MAX
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TICHT FITTING EXISTING S-TUBr 3: E THICKNESS = 1/4 INCH.
. INSTALLATION WITH UNBROKEN SECTIbN PERMANENT LOCKTITE TO SECURE.
SECTION B-B SHow:NG REPAfR OF S-TUBE SIZE DWG.NO.
R 66025 REV SCALE: NONE l SHEET 3 Or 3 H
REPAIR APPLIES TO BOTH ENDS A
l 7.
Oneratina Procedure 7.1 Procedure for Loadina the Packaae 1.
Ensure that the source is locked into place in its storage position. To check this, the dust cover should be in place, l
the lock should be in the down position, the key removed, and the selector ring should be immobile.
2.
The storage plug shocid be properly inserted. (attach a tamper proof security seal with an identification mark to the storage plug).
3.
Assure all the conditions of the Certificate of Compliance are met and the 660 has all the required markings.
4.
If the 660 is to be packaged in a crate or other outer i
packaging, the outer packaging must be strong enough to withstand the normal conditions of transport.
These requirements are outlined in 10 CFR 71.
The 660 should be j
put in the outer package with sufficient blocking to prevent shifting during transportation.
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5.
Perform a radioactive contamination wipe test of the 660.
This consists of rubbing filter paper or other absorbent material, using heavy finger pressure, over an area of 46 in.'
(300 cm ) of the package surface. The activity on the 2
filter paper should not exceed 0.00001 uCi per em8 of removable contamination. Also wipe test the outer packaging if used.
6.
Survey the 660 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 660 as required by 49 CFR 172.403.
If radiation levels above 200 l
mR/hr at the surface or 10 mR/hr at 40 inches (1m) from the surface are measured, the 660 must not be shipped. Also survey the outer packaging if used.
7.
Return the 660 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 l
173.22 (c) requires each shipper of Type B l
quantities of radioactive material to provide prior notification to the consignee of the dates of shipment and expected arrival.
7-1 REV. 2 May 1997 l
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7.'2 Procedure for Unloadina the Packace The consignee of a package of radioactive material must make arrangements to 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 notification of its arrival.
Upon receipt, survey the package 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 package, nor 10 milliroentgens 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 container 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 660 model number and serial number should be recorded.
Opening and operation of the device will be performed in accordance with the operation manual supplied with the 660 in accordance with 10 CFR 71.89.
7.3 Prenaration of an Emnty Packace for Transnort 1
1.
For shipment of an empty Model 660, you must first assure there are no unauthorized source assemblies or cropped sources within.the container, by performing the following procedure, a)
Remove the authorized source assembly from the Model 660 in accordance with the applicable operations manual for the storage 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.
c)
Return the drive cable and connector to the Model 660 and disconnect the controls.
d)
Insert dust cover cap, place selector ring in lock position, depress lock and remove the key.
Insert the l
shipping plug and seal wire.
Place an EMPTY tag on the i
device.
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7-2 i
REV. 2 l
hay 1997
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L 2.
Assure that the levels of removable radioactive contamination l
on the outside surface of the outer package do not exceed 0.00001 microcurie per 1 cm8 3.
When you have assured the Model 660 is empty, survey the device and prepare'the package for transport depending upon the radiation levels obtained, as given in 49 CFR 173.
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8.
A centance Tests and Maintenance Procram E
.I 8.1 Accentance Tests 8.1.1 Visual Insnection The package is visually examined to assure that the i
appropriate fasteners are properly seal wired. The package
-is inspected to assure that the required marking and labeling l
is securely attached to the package. The labels must-include the information given.in'10 CFR 71.85(c) and 10 CFR
'f 40.13 (c) (6) (i).
i The seal weld.of the radioactive source capsule is visually i
inspected for proper closure.
I The package is inspected to assure it was manufactured in l
accordance with drawing 66025 or 66030, see' Appendix.1.3.
t 8.1.2 Structural and Pressure Tests The swage coupling between the source capsule and cable of l'
the source assembly is subjected to a static tensile test with a load of 100 lbs. (445N).
8.1.3 Leak Tests i
l 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 microcuries of l-removable contamination. The source 1 capsule is subjected to l
a vacuum bubble leak test.
Failure of either.of these tests will prevent use of this source assembly.
8.1.4 Comoonent tests
'i Il 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 j
exposure device and the lockbox locked.
An attempt is made to pull the simulated source out through the lockbox. The j
shipping plugs are installed and checked to be sure they are l-attached securely to the device. Failure of either of these l
two tests will prevent use of the package until the cause of the failure is corrected and retested.
8.1.5 Tests for Shieldina Inteority 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 package are measured using a small l
8-1 REV.2 I
May 1997 l
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detector survey instrument. These radiation levels, when extrapolated to the rated capacity of the package, must not
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exceed 200 milliroentgens per hour at the surface of the package nor 10mR/hr at 40 inches (1m) from the surface, j
l 8.1.6 Thermal Accentance Tests Not applicable.
8.2 Maintenance Procram J
8.2.1 Structural and Pressure Tests Not applicable.
8,2.2 Leak Tests As described in section 8.1.3, the radioactive source j
assembly is leak tested at manufacture and must be less then 0.005 microcuries of removable contamination. Additionally, the source assembly is wipe tested for leakage of radioactive i
contamination every six months with the same acceptance criteria.
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 fasteners, proper seal wires, and genera) condition before each use.
The device must be j
l inspected at intervals not to exceed-three months as given in i
Section 8.2.7.
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8.2.4 Valves, Runture Discs, and Gaskets on Containment Vessel i
Not applicable.
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 nor 10 milliroentgens per hour at 40 inches (1m) from the surface.
B.2.6 Thermal Not applicable.
B.2.7 Miscellaneous i
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Inspections and tests designed for secondary users of this package under the general license provisions of 10 CFR 71.12 (b) are included in Appendix A.
B-2 REV. 2 May 1997
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E Sliding the product on abrasive surfaces, can, over a period of time, cause wear-through of the extended feet on the bottom of the j
unit.
l This wear characteristic, has no adverse affect on the structural I
integrity, functionality or safety standards of the product.
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If and when, wear through of the feet occurs, repair procedures should be considered in order to prevent any damage occurring to the end plates. -The, product can be returned to Amersham Corporation for repair. This repair can occur in two ways.
a)
Additional foot pads can be secured over the existing foot pad locations, or b)
The outer shell is removed and a new outer shell is installed.
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Devices with Automatic Lockina Mechanisms /Model 660B. 660BE. 660A. and 660AE I
(a) Cover Plate Removal l
1.
Remove the Danger. Tag (secured with rivets) from the bottom of the rear plate.
I 2.
Remove the rear plate by unscrewing the six phillips head screws j
securing it to the exposure device body.
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(b) Refer to Figure 2 and dismantle the selector ausembly taking care not to l
lose the spring loaded parts.
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Remove the lock (2) from ~ the lock retainer (3).by undoing screw (4) and turning the key through 90 degrees.
1 (c) " Remove 4 screws securing the front end plate.
Remove the guide tube connector nut (17) and retaining ring (18),
a (d) Clean all parts with mineral' spirits or equivalent and inspect fe.r wear.
Replace as necessary.
(e) Lightly grease the inside surfaces of the selector ring (10) and the lock 1
retainer (3) using type MIL-G-23827 B grease.
Reassemble the lock by placing the return springs and spring guides into the lock, depressing the internal plunger (5), inserting the lock into the retainer (3) and securing the lock with the cap screw (4).
1 Attach the lock assembly to the mounting plate with two socket screws (1).
8-6 REV. 1 May 1997 1
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