ML20205D806
| ML20205D806 | |
| Person / Time | |
|---|---|
| Issue date: | 09/30/1985 |
| From: | Felton J NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Swiger J ENVIROCARE, INC. |
| Shared Package | |
| ML20205D814 | List: |
| References | |
| FOIA-85-317 NUDOCS 8510170095 | |
| Download: ML20205D806 (6) | |
See also: IR 05000115/2005017
Text
, ,k UNITED STATES l
~
8 o NUCLEAR REGULATORY COMMISSION
$ E WASHINGTON, D. C. 20555
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Mr. Joseph L. Swiger
Envirocare, Inc.
Suite 3-8
Professional Building, Heritage Valley
Southbury, CT 06488 IN RESPONSE REFER
TO F01A-85-317
Dear Mr. Swiger:
This is in response to your letter dated April 29, 1985, as modified by
Ms. Reed's letter dated May 7,1985, in which you requested, pursuant to
the Freedom of Information Act (F0IA), records regarding the International
Nutronics
through May Facility in Dover, New Jersey, for the period January 15, 1985,
7, 1985.
The records listed on the enclosed Appendix A are available for public
NW, Washington, DC. inspection and copying in the NRC Public Document Room
the PDR accession numbers indicated beside the document The
descrip
remaining records will be filed in PDR folder F01A-85-317 under your name.
Appendix
name. B are also being placed in the PDR folder F01A-
The stated enclosures to documents two and three are not provided since
you provided them to NRC and we assume that you already have copies of them.
We are enclosing a copy of a notice that provides charges and procedures for
obtaining copies of records from the PDR.
The remaining portions of document
one of Appendix B contain information which
is confidential business (proprietary) information that is being withheld from
public disclosure pursuant to Exemption 4 of the FOIA (5 U.S.C. 552(b)(4)) and
10 CFR 9.5(a)(4) of the Commission's regulations.
Pursuant to 10 CFR 9.9 of the Corraission's regulations, it has been determined
that the information withheld is exempt from production or disclosure, and
that its production or disclosure is contrary to the public interest. The
Murley, Regional Administrator, Region I. persons responsible for this den
8510170095 850930
hGE -317 PDR
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Mr. Joseph L. Swiger -2-
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This denial may be appealep to the Commission's Executive Director for
Operations within 30 day!8fr,om the receipt of this letter. As provided in
10 CFR 9.11, any such ap>eal must be in writing, addressed to the Executive
Director for Operations, U.S. Nuclear Regulatory Commission, Washington, DC
20555, and should clearly state on the envelope and in the letter that it is
an " Appeal from an Initial FOIA Decision."
Sincerely,
AL () -
c
.4-
J. M. Felton, Director
Division of Rules and Records
Office of Administration
Enclosures: As stated
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Re: F01A-85-317
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APPENDIX A
s
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- 1. 01/15/85 Letter from.NRC to International Nutronics, Inc. (INI) re:
Inspection Report 84-35. (2 pages) - Accession No. 8501210120
,
- 2. 01/15/85 Letter from NRC to INI re: Inspection Report 84-37. (2 pages) -
Accession No. 8501210193
3. 01/18/85 Letter from NUS to NRC re: BCL-4 Radioactive Materials
Package, Certificate of Compliance 5950, Docket 71-5950.
(11 pages)
4. 01/21/85 Letter from INI to NRC re: Request of Approval to Apply INI's
QA Plan Approved Under 10 CFR Part 50, Appendix 8, to
Transportation of Radioactive Materials. (12 pages)
5. 01/24/85 Memo from NRC to NRC re: Inspection 85-01 Notes. (22 pages)
6. 01/30/85 Letter from INI to NRC re: Letter Submitting QA Manual for
Shipment of Radioactive Materials. (38 pages)
- 7. 02/04/85 Letter from NRC to INI re: Inspection Report 85-01. (2 pages) -
Accession No. 850?l10299
8. Undated Memo from NRC to NRC re: Inspection 85-03 Notes. (2 pages)
- 9. 02/07/85 Letter from NRC to INI re: Inspection Report 85-03. (2 pages)
Accession No. 8502130171
10. 02/13/85 Letter from Envirocare, Inc. to NRC re: Fax Item - Procedure
No. 57. (4 pages)
11. 02/22/85 Letter from NRC to Envirocare, Inc re: Allegation Against
INI. (2 pages)
12. Undated Memo from NRC to NRC re: Inspection 85-02 Notes. (13 pages)
- 13. 02/25/85 Letter from NRC to INI re: Inspection Report 85-02. (2 pages)
Accession No. 8503050210
14. 03/11/85 Memo from NRC to NRC re: Inspection 85-05 Notes. (2 pages)
15. 03/13/85 Letter from INI to NRC re: Request for Extension of Completion
Date for Decommissioning of INI's Dover Facility. (2 pages)
16. 03/13/85 Memo from NRC to NRC re: Inspection 85-04 Notes. (2 pages)
- 17. 03/14/85 Letter from NRC to INI re: Inspection Report 85-05. (2 pages)
Accession No. 8503280658
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Re: F01A-85-317
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APPENDIX A
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(CONTINI)ED)
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18. 03/19/85 Letter from INI to NRC re: Request to be added to Cask User's
List for Package Nupac 7-100, Certificate of Compliance
- USA /9080/A. (2 pages)
- 19. 03/20/85 Letter from NRC to INI re: Inspection Report 85'-04. (2 pages)
Accession No. 8503260518
20. 03/22/85 Memo from NRC to NRC re: Inspection 85-06 Notes. (18 pages)
21. 03/22/85 Memo from NRC to NRC re: Inspection 85-07 Notes. (10 pages)
- 22. 03/25/85 Letter from NRC to INI re: Inspection Report 85-06. (2 pages)
Accession No. 8503280438
- 23. 03/25/85 Letter from NRC tc INI re: Inspection Report 85-07. (2 pages)
Accession No. 8504050074
24. 03/29/85 Letter from NRC to Envirocare re: Telephone Record - Subject:
INI Decontamination Operations. (1page)
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25. 04/02/85 Letter from INI to NRC re: Transfer of Personnel Qualifications
and Procedures No. 63. (18 pages)
26. 04/08/85 Memo from NRC to NRC re: Inspection 85-08 Notes. (9 pages)
27. 04/09/85 Letter from Envirocare to NRC re: Fax Item - Procedure No. 62.
,
(3pages)
28. 04/12/85 Letter from NRC to INI re: Inspection Report 85-08. (2 pages)
29. Undated Memo from NRC to NRC re: Inspection 85-09 Notes. (19 pages)
30. 04/16/85 Letter from NRC to INI re: Inspection Report 85-09. (2 pages)
i 31. 04/19/85 Letter from NRC to INI re: Request for Information to
(2 pages)
'
Determine Whether Extension of Time Should be Granted.
32. 04/22/85 Memo from NRC to NRC re: Inspection 85-10 Notes. (25pages)
33. Undated Memo from NRC to NRC re: Inspection 85-11 Notes. (2 pages)
1
34. 04/21/85 Letter from Envirocare to NRC re: Western Union Mailgram.
(1page)
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APPENDIX A i
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35. 04/24/85 Letter from NRC to INI re: Inspection Report 85-10. (2 pages)
36. 05/07/85 Letter from INI to NRC re: Response to NRC Letter 04/19/85.
j (15 pages)
37. 05/07/85 Letter from Regional counsel, RI to File re: Memo, Subject:
,
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Telephone Conversation with John Keith of Envirocare, Inc. and
Greg Parker of INI. (1 page)
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- NOTE: THE DOCUMENTS WITH THE IDENTIFIED ACCESSION NUMBERS CAN BE LOCATED
AT THE NRC PUBLIC DOCUMENT ROOM .
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Re: F0!A-85-317
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APPENDIX B
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1. 03/12/85 Affidavit ay R. E. Voit, NUS (3 pages) w/ attachments (1) No.
SS-008, Revision D dated 03/11/85, (2) No. SS-014, Revision 8
dated 03/12/85, (3) Enclosure (10), NUS Process Services
Organization Chart dated 02/15/85. (96 pages)
2. 04/01/85 Letter to Friedman from Swiger w/ title page (2 pages); and with
NUS0SC Procedure No. 7071-07, Revision 1 dated 04/01/85.
(12 pages)
3. 04/02/85 Letter to Friedman from Swiger w/ Attached 1.N.1/E-Care Health
Physics Procedure No. 62, covering N US0SC Procedure No.
7071-08(10 pages); and Procedure No. 62 and NUS0SC Procedure
No. 7071-08 dated 03/21/85 and 03/028/85. (59pages)
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OPERATING SERVICES
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NUSCORPORATION January 18, 1985 _
253G COUNTAYSIDE BOULEVAAD PPD-FS-85-002 ed.
CLE AAWATE A, FLOAID A 33575-2094 W'
(8131796-2264
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Director, Of fice of Nuclear Material Safety y
U.S. Nuclear Regulatory Commission
Washington. D.C. 20555 h
Attention: Mr. Charles E. MacDonald, Chief
Transportation Branch
b
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Subject: BCL-4 Radioactive Materials Package
Certificate of Compliance 5950
Docket No. 71-5950
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Re: NRC Memo FCTC: RHO 71-5950 from R.H. Odegaarden
dated 1/7/85
Dear Mr. MacDonald:
The following information is provided in'accordance with
reference (a) in support of a one-time exemption to ship Cobalt-
60 sources f rom International Nutronics. Inc., Dover, New Jersey,
.
facility. The Dover, New Jersey, facility is being de-
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commissioned and the conditions at the site restrict the method
of loading the type of radioactive material packagec that can be
accommodated at this facility. This request for exemption
involves 1) the modification of the inner can assembly to the
, BCL-4 package to enable the loading of the cannister underwater
and 2) relief from the requirement in the Certificate of
Conformance limiting the radiation level at one meter from the
package to 10 mrem /hr for exclusive use shipment.
On January 4, 1985, we met with members of your staff to discuss
!
the shipment of the CO-60, reference (a), in the BCL-4 cask. The
following information is intended to address the commission's
,
concerns identified in reference (a).
1. International Nutronics, Inc., must submit a Quality
Assurance Program in accordance with 10CFR71. subpart H.
INI is submitting under separate cover INI Quality
Assurance Program Plan supplementing their Quality
Assurance Program which meets the requirement of
. 2. The modifications to the inner cannister assembly are
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s, all contained on NUSOSC Drawing 7071-M-008, entitled
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JN Inner Can Cover Modification and Tool Details, enclosure
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14r. ChnrlOO E. MacDc .ld
Jcnunry 18, 1985
PPD-FS-002
Page Two -
3. The residual water in the inner can assembly under normal
and accident conditions was evaluated by Battelle Columbus
- Laboratories and the results of thair analysis are presented
} in a letter to NUSOSC dated December 27, 1984, Enclosure (2).
l The BCL analysis was based on the following conditions:
(1) 400 watt contents heat load. This is the maximum per-
mitted in the BCL-4 cask.
(2) The inner can assembly is as shown on NUSOSC Drawing
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No. 7071-M-008.
l (3) The void volume of the inner can assembly of 0.303 cubic
feet takes into consideration the maximum source loadings
) and the volume of the baskets designed to hold the sources.
li
The basket design is shown on NUSOSC Drawing 7071-M-009,
entitled BCL-4 Cask Inner Scaled Cannister Baskets, enclo-
sure (3).
l (4) A residual water content of 5 cc. This is the amount
j of water that was left in the inner cannister assembly after
I a mockup demonstration was performed at our NUSOSC Clearwater
{ facility.
I
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(5) The temperatures in the inner can assembly are as pre-
sented in the Safety Analysis Report for Packaging for the
BCL-4 shipping cask.
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4. The initial acceptance test for the cannister is defined
in Section 8 of the SAR. The Acceptance Test includes a
visual examination and a 15 psi Soap Bubble Leak Test to
establish that the seal of the inner can assembly has been
accomplished. The modifications to the inner cannister lid,
which are the only modifications to the cannister, were
pressure tested to 100 psig and inspected fsr leaks during
the mockup demonstration. No leakage was observed.
5. The operating procedures used in the loading and unloading
of BCL-4 cask are included as Enclosure (4). These pro-
cedures are abbreviated versions of NUSOSC detailed Proce-
dures 7071-03 and 7071-04, submitted to INI and Region I.
The abbreviated procedures follow the format submitted by
BCL in Section 7 of the Safety Analysis report.
6. The certificate of Compliance, USA /5950/B( )P, paragraph
7.0 (2) contains a restriction' limiting the donc rate to
NUS8t;famir#,;%"=
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Mr. Chrrles E. MacDi .ld
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l Jcnuary 18, 1985
PPD-FS-85-002
l Page Three -
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l, 10 millirem per hour at three (3) feet from the external
j! surface of the package. This is a self-imposed restric-
'
i tion by BCL. For the transport of the Co-60 sources from
il INI we propose using the external radiation standards in
i; paragraph 71.47 of 10CFR71 for exclusive use shipment. In
fg loading approximately 10,500 ci of CO-60 in the BCL-4 cask
'l the measured dose rate at one meter was approximately
14 mrem /hr and 90 mrem /hr on contact. We would anticipate
j similar or slightly higher dose rates for the INI CO-60
il shipments.
Il
- . 7. The CO-60 sources are loaded in baskets as shown in NUSOSC
,l Drawing 7071-M-009. These baskets are designed to main-
lg tain the sources in their respective positions during trans-
- port. The 1 3/4 inch diameter tubes are designed to store .
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tuptured sources contained in a 1 inch diameter pipe plugged
at both ends. The end play between the source and the cannis- '
li ter is 4 inches in the upper basket and 1 inch in the lower
i basket. The clearance between the basket and the inner can !
l assembly is 3/8 inch,
i We believe the above satisfactorily addresses the concerns of
4 the Commission for loading of the INI CO-60 sources underwater and
l transporting the CO-60 sources in the BCL-4 shipping package. t
!I
l There is the matter of requesting.the following waiver on the
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first shipment from INI in the BCL-4 which has already been loaded
at INI. The conditions are:
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!i 1. The radiation dose rate at one meter from the surface of the
l' cask reads 14 mrem /hr and the Certificate of Conformance
!! restricts the dose rate to 10 mrem /hr. This item should ;
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be* resolved if item 6.0 above is accepted.
!
l 2. The 5/16" inlet port, reference NUSOSC Drawing 7071-M-008,
! is not provided with a gasketed cap. The valve sealing this
2
port is designed similar to the valve on the tire. Because
j the seal increases with internal pressure and the clearance
to install a cap was small, NUSOSC did not recommend a cap.
l
NUSOSC has subsequently designed a cap to seal the inlet port.
!
i 3. NUSOSC earlier procedure called for removal of the 7/16 inch
! diameter plug in the outlet port to depressurize the inner
l can assembly after the pressure test. The plug was then
replaced. This procedure invalidated the test on the plug.
The procedure has been revised'to correct this point,
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N U S M;we w,W," = a i
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na . +.a .- - ., as . n--w ., -- .+----._a . -a- . - - - . _ _ + - . - - . . x.- _. _ _ > ~ ,
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Mr. Charles E. MacDonald
January 18, 1985 _
PPD-FS-85-002
- Page Four
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' NUSOSC believes a waiver of the above points is warranted
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inasmuch as dbily checks since December 4, 1984, of the cask
i cavity which is provided with a pressure gauge have not indicated
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any increase in pressure which indicates that the inner can assembly i
seal is adequate or that there is no pressure increase in the cask !
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cavity - thus, no mechanism for radioactive material to escape.
We trust the above information is sufficient to allow the
shipment of the CO-60 at INI to proceed. If the Commission needs
any further information, or if there is a fee involved with the
submittal of this exemption, please advise me at the earliest.
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Very truly yours,
,
m
Thomas A. Russ 11
.fL46^*
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- j Manager, Field Services
<; TAR /lg
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! Enclosures: 4
al
cc: Bruce Thomas, INI
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J. Swiger, E-Care
M. Swiger, E-Care
! T. Emswiler, DCL
R. Voit, NUSOSC
- L. Friedman, USNRC, Region I
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Enclosure (2)
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OBallelle ~
Columbu> taboratories
50i kent; Avenue
Columbus, Ohio 4120 t
Telephone- ((,14i 4244424
December 27, 1984 1*' 24 m4
i
Mr. Tom Russel l
NUS Operating Services Corporation
2536 Countryside Blvd
Clearwater, Florida 33575
Dear Mr. Russel: i
In response to your verbal authorization, we have calculated the pres- *
sures in a modified BCL-4 canister. The following assumed conditions
were used in the analyses:
1. 400 watt contents heat load (maximum permitted) ,
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in the BCL-4
2. Canister configuration as shown in NUS Drawing '
No. 7071-M-008
3. Contents of canister as shown on attached sketches
prepared by T. R. Emswiler of Battelle
. 4. Five cc of residual water in the canister
5. Temperature of the canister and contents as
presented in the Safety Analysis Report for 1
Packaging for the BCL-4 shipping cask (SARP).
The results of our analyses indicate that the canister internal free l
volume is 0.303 cu. ft. For the volume and the contents temperatures ;
- hown in the SARP, the following internal pressures were calculated:
Total Pressure
Condition Partial Pressure, Psia Psig
Air Water Vapor
Normal Transport 21.4 17.2 23.9
Accident 27.8 22.3 35.4 ;
If you require any other help, please ca1T either Tom Emswiler or myself.
Very Truly Yours,
t4 /* f
Richard J. Burian
Principal Research Engineer
Nuclear Systems Section
' Enclosure (4) ,
OPERATING PROCEDURE FOR BCL-4 SUIPPING CASK _
(UNDERWATER LOADING)
The procedures outlined in this section are applicable for han-
dling the BCL-4 Cask during underwater loading of the package
at International Nutronics, Inc., Dover, New Jersey, and for
unloading in the BCL Hot Cell in Ohio.
I. PRELOADING OPERATIONS
Prior to each use, the following operations shall be performed:
1. Verify that the license is current and applicable.
2. Verify that the CO-60 sources to be shipped are
loaded in their respective loading baskets and that
the curie content and location are in accordance with
the loading plan.
3. Verify that the contents meet the license require-
ments of the package.
II. PROCEDURE FOR LOADING THE SOURCES INTO THE INNER
CAN ASSEMBLY
The CO-60 sources are normally loaded into their respective
basket prior to this step and are ready to be loaded into the
BCL-4 Inner Can Assembly.
1. Inspect the inner can assembly and perform pre-
requisite check per NUSOSC Procedure 7071-03.
2. Remove the cover from the inner can and lower inner
can into the pool.
3. Using long-handled tools, load first the bottom
source basket into the inner can, then the top basket.
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NUSEurAtat; mig"~ s
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4. Parivrm o pre-use insp;ction et the inner can
cover per Section 4.3 of the BCL Document HS-COM-4.
5. Using long-handled tools, lower the cover in piace '
determined by the aligning pins.
6. Bolt down the cover in place by torquing the bolts
to 60i10 inch pounds.
7. Attach the 80-100 psig air line to the inlet pene-
tration and pressurize the cannister for a minimum
of one (1) minute af ter air bubbles start coming
out of the dewatering penetration.
.
8. Install plug into the dewatering penetration using
teflon tape on the threads.
9. Pressurize the inner can assembly to 45 psig mini-
, mum and hold pressure for 15 minutes minimum while
observing for bubbles.
Note: The acceptance criterion is that there will
be no evidence of bubbles indicative of a leak.
Failure to meet this criterion constitutes a failure
of the pressure test and requires that the cognizant
personnel be notified and corrective action taken.
10. Upon acceptance of the pressure test, depressurize
the cannister by climinating air through the inlet
penetration.
11. Using long-handled tools, cap the inlet penetration.
The inner can assembly is now ready for loading in
the cask and shipping offsite.
III.
PROCEDURE FOR LOADING THE INNER CAN ASSEMBLY INTO THE
BCL-4 CASK FOR SHIPMENT
1. Lift the cask off the transport vehicle with clings
around two trunnions. Move to enclosure.
2. Inspect the cask and remove any road dirt.
3. Remove cap from cask drain valve housing.
4. Remove the plug from the drain valve.
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5. Inepsct the drain valve. Notify cognizent per-
sonnel if any damage or deficiency is noted.
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6. Remove all cask lid bolts.
7. Insert lifting eyes on the cask lid.
8. ' Attach the lid lifting sling to the cask lid lift-
ing eyes.
9. Using the cask lid lifting sling, remove the cask
lid with continuous monitoring by Health Physics.
10. Perform the pre-use inspection per NUSOSC Procedure
7071-04 and perform any required corrective main-
i
tenance as described in the procedure.
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11. Ensure that the cask 0-ring is properly seated in
the cover groove, and place the cover back on the
cask.
12. Open the drain valve.
4 13. Move cask to the storage pool.
4 14. Attach cask to chain falls using slings around the
two trunnions.
15. Attach a third sling to the cask cover.
16. Lower the cask in the storage pool to the desired
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depth.
17. Remove the cask cover and move the lid out of the
way.
18. Lift canister by bail and insert slowly in cask.
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19. Place cover on cask.
20. Remove cask from storage pool and drain water from
cask cavity.
21. Perform a complete radiation survey of the cask.
Fill out the Radioactive Shipment form. Limits
are as follows:
.
a. Dose rate not to exceed 200 mR/hr at cask surface
or personnel barrier and not to exceed a trans-
port index of 10 for, nonexclusive use of a vehicle. ;
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31. Instruct the driver os to the disposition of the
above forms. _
32. Review any Emergency Instructions with the driver
and be sure they are clearly understood by him.
33. Ensure that all trailer lights and brakes are
operating properly and that the tires are in satis-
factory condition.
34. Release equipment. '
IV. PROCEDURE FOR UNLOADING THE PACKAGE.
2
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- The Sources are scheduled to be shipped to the BCL Hot Labora-
tory at Went Jefferson, Ohio, and the procedure for unloading
the radioactive sources in BCL's Hot Cell is attached.
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7.2 Procedures for Unloading the Package
For the following unloading procedures, it will be assumed that the
cask has arrived at the BCL Hot Laboratory at West Jefferson, Ohio, and
contains radioactive material.
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Procedure
(1) Move transport vehicle to unloading area. Secure trailer prior
. .
to removing tractor.
(2) Survey and smear tractor, trailer, and barriers. Remove
barrier.
(3) Perform radiation and smear surveys on external surfaces
of cask and record results.
(4) Notify operating supervisor of results cf survey and obtain
his authorization and instructions to unload cask f rom
trailer and move to designated area.
(5) Remove all tiedowns and remove cask using the lifting yoke
(supplied) or by lifting cask by properly using the pallet.
(6) Survey trailer area where cask was located.
(7) Move cask to designated area.
(8) Clean road dirt from cask if required.
(9) Check seal identification and intactness. Notify cognizant
supervisor of any apparent security violation and await
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his instructions.
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(10) Inspect external cask components for apparent damage or
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deficiencies and report these to cognizant supervisor.
(11) Move cask to Hot Lab unloading area.
(12) Review unloading instructions and any special handling, safety,
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and security procedures.
(13) Remove lid bolts. Insert lifting eyes in lid.
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(14) . Lift lid from cask.
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(15) Remove containment canister from cask cavity using bail on top
of canister.
4 (16) Replace cask lid and lid bolts.
(17) Remove cask from unloading area and take to work area.
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(18) Remove lid bolts and lid.
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. (19) Flush and clean cavity.
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- (20) Drain all liquid from cavity, close drain, place cap on drain
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i housing, replace, lid and secure lid bolts.
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(21) Decontaminate exterior surface as required.
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(22) Label cask " Empty" and remove cask to storage area.
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INTERNATION Al. NUTRONICS, INC. _ @ O
January 21,1985
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U.S. Nuclear Regulatory Commission
Charles E. MacDonald d, g' \
Chief Transportation Certification Branch ' ,7)3
Washington. D. C. 20555
[) /
RE: Submission of International Nutronics' previously approved
10 CFR Part 50 Appendix B Quality Assurance Plan to be
applied to Transport of Radioactive Materials under Part
71 Subpart H.
Mr. MacDonald:
This letter and enclosed information is in request of approv _
al to apply INI's Quality Assurance Plan approved under 10 CPR
Part 50 Appendix B to transportation of radioactive materials.
Delegation of quality assurance functions are stipulated in
the enclosed documentation to NUS Operating Service Corporation
and Battelle Columbus Laboratories for utilization of the BCL-4
Cask to transport Cobalt-60 sources. The functional organiza-
tion. chart-for this program is'inclodedtas well as INI's
organizational chart.
INI's Quality Assurance Program was reviewed by U.S. Nuclear
Regulatory Commission personnel from Region IV on October *4-6/83
and documented in Report No. 99900928/83-01 published in the
quarterly report October 1983 - December 1983, Nureg-0040,
Vol. 7, No. 4, " Licensee Contractor And Vendor Inspection
Status Report ".
Should you have any questions regarding this submission please
direct them to my attention at telephone 201-361-6990. I wish
to thank you for your timely consideration regarding this
request. The necessary review fee is included.
Sin rely,
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U.S. HIGHWAY 46 AND SCHLEY STREET, DOVER, NEW JERSEY 07801
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INTERNATIONAL NUTRONICS INC.
DOVER, NEW JERSEY
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QUALITY ASSURANCE PLAN
for
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TRANSPORT OF RADIOACTIVE MATERIALS
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REVISED O
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Prepared by: Date
, Manager, Quality Assurance
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Approved by: @ M Date ///I/h
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President
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I. Purpose
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II. Changes
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j IV. References
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V. Scope of Work ;
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t VI. Project Organization
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I. PURPOSE
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This plan documents the quality applicable requirements of 10CFR71
for the Design, Fabrication, Procurement, Use, Maintenance, and
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Repair of packaging used in the transport of radioactive materials.
International Nutronics Inc. is in the process of decommissioning
its Dover, New Jersey facility and in the course of decommission-
ing, must dispose of some 50,000 curies of CO-60 obtained in
1970 and 1974. INI has contracted with Envirocare Inc. for the
decommissioning of the facility. E-CARE in turn, subcontracted
.
the disposal of the sources to NUS Operating Services Corporation
who intends to ship the CO-60 sources to Battelle Columbus Lab- .
oratory who will take title to the cobalt. The shipments of
!
radioactive materials will be made in an approved shipping cask.
This plan complies with the requirements of 10CFR71, Appendix
H, " Quality Assurance Criteria for Shipping Packages for Radio-
active Materials" to the extent consistent with their importance
to safety. The QA plan identifies the procedures necessary to
'
assure that shipping packages are designed, fabricated, procured,
used, maintained and repaired in accordance with 10CFR71.
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II. CHANGES
Changes to this plan shall be documented, reviewed, approved,
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and controlled at the same organizational levels of reponsibility
as applied to the current INI Quality Assurance Manual, which
meets the requirements of 10CFR50, Appendix B.
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III. DEFINITIONS
1. INI - International Nutronics Inc. is the Licensee
of the cobalt material.
.
2. E-CARE - ENVIROCARE INC. is the contractor for decommis- i
sioning.
3. NUSOSC - NUS Operating Services Corporation is a sub-
contractor to E-CARE for the packaging, transportation,
and disposal of the radioactive materials.
4. BCL - Battelle Columbus Laboratory is the owner of ,
BCL-4 Cask and Licensee for the receipt of the CO-60.
5. NUSPSC - NUS Process Service Corporation, a subsidary
of NUSOSC which specializes in transport of radiactive
material.
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IV. REFERENCES
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International Nutronics Incorporated Quality Assurance Manual
dated July 1, 1983 with current revisions issued through the
life of this project shall be used as a guide in the preparation of
this plan.
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V. SCOPE OF WORK
The Quality Assurance Plan defines ^the quality requirements con-
tained within the contract between ENVIROCARE INC. including its
subcontractors and INI for the packaging, and transport of approx-
imately 50,000 curies of CO-60. The scope of work is broken
down in the following tasks for the purpose of defining quality
requirements covered by this plan:
I. DESIGN AND FABRICATION
1. Provide engineering, design,-fabrication and testing
assistance to modify the inner can assembly to the
.
BCL-4 cask to provide for loading the sources under-
water. This work will be perfo med by NUSOSC, in accord-
ance with their existing Quality Assurance Program,which
meets the requirements of 10CFR50, Appendix 8.
The quality requirements for this work are as follows:
a. Provide design and fabrication ^ drawings of the inner
can assembly for INI approval and review by NRC Material
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Transportation Branch and Region I.
b. Perform acceptance testing of the cannicter modifica-
tion to verify design and provide certification that
inner can assembly meets the design requirements.
c. Provide certification that modification to the inner
can assembly meets fabricati,on and material require-
ments,
d. Provide procedures for loading of the sources in the
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inner can assembly in the storage pool for INI approval
and review by NRC Material Transportation Branch and
Region I.
e. Provide analysis that residual water does not compro-
mise the design of the inner can assembly.
II. USE
Provide assistance in unloading the shipping cask from the transport
vehicle, loading the inner can assemblies in the shipping cask
underwater, and preparing the cask for shipment. This work will
be performed by NUSPSC in accordance with NUSPSC Quality Assurance
Program which meets the requirements of 10CFR71. The quality :
requirements for this work are as follows:
a. Perform the work in accordance with procedures approved
by INI and review by NRC Region I.
b. Submit letter notifying NRC Material Transportation
Branch NUSPSC is user of the BCL-4 Cask.
c. Verify that the loading of the cask is performed in
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accordance with the C of C and any exemption granted
by the NRCMT8.
III. PROCUREMENT
There is no cask procurement in this plan.
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VI. MAINTENANCE AND REPAIR OF PACKAGING
Provide assistance in maintaining and repairing the BCL-4 cask.
This work will be performed by Battelle Columbus Laboratory in
accordance with their existing Quality Assurance Program which
meets the requirements of 10CFR71, Appendix H. The quality require-
ments for this work is as follows:
a. INI will perform an incoming inspection of the cask
and transport vehicle each time it is used and notify
BCL of any damage to the cask that requires repair.
b. The BCL-4 cask will be inspected at BCL after each
use and any repair will be performed by BCL.
c.
BCL will submit certification that all current maintenance
requirements have been performed and the Certificate
,
of Conformance is current.
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INI PROJECT FUNCTIONAL ORGANIZATION CHART
PRESIDENT
QUALITY
ASSURANCE
MANAGER
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INI SITE
INSPECTOR
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NUSOSC/NUSPSC BCL E-CARE
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FIGURE 1. INTERNATIONAL NUTRONICS ORGANIZATION (n o
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President YC
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Jim Parker n <>
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Executive Committee -
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Jim Parker 5 z2
Greg Parker O8 5
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Gene O'Sullivan jO
Al Gunby *
lgd 8N
Pat Burns o-
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Irvine Palo Alto Dover Corporate
Staff .
Pl1
Plant Manager Plant Manager Plant Manager Gene O'Sullivan:
Bob Baldwin Tom Rensel Bruce Thomas
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VP-Technical,
Cor.porate RSO
Rad. Safety & Rad. Safety &: l Rad. Safety & Greg Parker: l l
Qua1.' Control Qual. Control tOual. Control. General
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Kevin O'Sullivan Tom Rensel ,
tBruce Thomas Coun , Dir. ,
Production Production
Al Gunby: p n ,
John O'Sullivan Tom Rensel Principal Engr., g ,,l,
8-
QA-10CFR50,21 ]
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Bob Baldwin:
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Marketing Dir. g y fg
Tom Rensel: D.
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QA-Traceability fa .$*' o
Bruce Thomas: ' '
,
QA-10CFR70,49CFR ' -
Patrick Burns: A
CFO, Treasurer %'
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