ML20202C222

QA Program for Areco Upgrade & Mod of Irradiator for Cs-137 Wesf Capsule Use

ML20202C222
Person / Time
Site:	07100602
Issue date:	06/11/1986
From:	Myron J APPLIED RADIANT ENERGY CORP. (FORMERLY AMERICAN NOVAW
To:
Shared Package
ML20202C201	List: ML20202C199 ML20202C222
References
NUDOCS 8607110153
Download: ML20202C222 (4)

Text

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THE APPLIEp RADIANT ENERGY CORP.

2432 LAKESIDE DRIVE LYNCHBURG, VIRGINIA 24501 (804) 525-5252 JUNE 11, 1986 QUALITY ASSURANCE PROGRAM FOR ARECO'S UPGRADE AND MODIFICATION OF IRRADIATOR FOR CESIUM-137 WESF CAPSULE USE.

1) ORGANIZATION

• THE FINAL RESPONSIBILITY FOR THE QUALITY ASSURANCE (QA) PROGRAM FOR PART 71 REoUIREMENTS RESTS WITH THE APPLIED RADI ANT ENERGY CORP.

(ARECO) DESIGN AND FABRICATION SHALL NOT BE CONDUCTED UNDER THIS QA PROGRAM. THE QA PROGRAM IS DRAWN UP AND IMPLEMENTED BY THE FOLLOWING ARECO PERSONNELI LAWRENCE G. BARRETT, PRESIDENT JAMES J. MYRON PH.D, DIRECTOR OF RADIATION AND TECHNICAL SERVICES BOTH BARRETT AND MYRON ARE RADI ATION PROTECTION OFFICERS UNDER ARECO'S NRC MATERIALS l! CENSE.

RODNEY W. RELL, B.S. MANAGER, CONVERSION AND IRRADIATION (C&I) DEPT WILL BE AN ALTERNATE RADI ATION PROTECTION OFFICER BY AN AMENDMENT OF THE LICENSE TO BE RECEIVED VERY SHORTLY FROM THE NRC.

THE ABOvE RADIATION SAFETY OFFICERS ARE RESPONSIBLE FOR OVERALL ADMIN!=

STRATION OF THE PROGRAM, TRAINING AND CERTIFICATION OF SPECIFIED USERS (RADI ATION TECHNICI ANS ) OF THE LICENSED MATERIAL, DOCUMEN T CONTROL,

RADIOACTIVE SHIPMENT RECEIVAL, INSPECTION, STORING, AND SHIPPING.

TRAINED AND CERTIFIED RADI ATION TECHNICI ANS ARE RESPONSIBLE FOR HANDLING, TESTING, OPERATING STATUS AND RECORDS KEEPING.

AUDITING IS BY A NON ARECO AGENT (SEE SECTION 7)

2) QUALITY ASSURANCE PROGRAM THE MANAGEMENT OF ARECO'S UPGRADE AND MODIFICATION OF IRRADIATOR FOR CESIUM-137 WESF CAPSULE USE PROGRAM ESTABLISHES AND IMPLEMENTS THIS QA PROGRAM. TRAINING, PRIOR TO ENGAGEMENTS, FOR ALL QA FUNCTIONS IS REQUIRED ACCORDING TO WRITTEN PROCEDURES. QA PROGRAM REVISIONS WILL BE MADE ACCORD-8607110153 860611 PDR ADOCK 07100602 C

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ING TO WRITTEN PROCEDURES AND MUST BE UNANIMOUSLY APPROVED BY THE THREE RADIATION SAFETY OFFICERS NAMED IN SECTION 1). THE GA PROGRAM WILL INSURE THAT ALL DEFINED QC PROCEDURES, ENGINEERING PROCEDURES AND SPECIFIC PROVISIONS OF THE PACKAGE ARE SATISFIED. THIS PROGRAM IS CONFINED TO THE PACKAGE: GENERAL ELECTRIC RADIOACTIVE MATERI AL SHIPP-ING CONTAINER MODEL 700 CONTAINING RADIOACTIVE MATERI AL. THE GA PROGRAM WILL EMPHASIZE CONTROL OF THE CHARACTFRISTICS OF THE GE 700 CASK CONTAINING CES!UM 137 WESF CAPSULES WHICH ARE CRITICAL TO SAFETY, THE REGUIREMENT THAT THE GE 700 CASK HAS REEN DESIGNED AND MANUFACTURED UNDER A GA PROGRAM APPROVED BY THE NUCLEAR REGULATORY COMMISSION IS MET BY A NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADI-ACTIVE MATERIALS PACKAGES. GE MODEL 700 CASK HAS BEEN ISSUED CERTIFICATE NUMBER 5942 ON SEPT. 18, 1985. A COPY OF THIS CERTIFICATE AND A DRAWING OF THE CASK COMPRISE TWO ATTACHMENTS TO THIS QA PROGRAM.

3) DOCUMENT CONTROL ALL DOCUMENTS RELATING TO A GE 700 SHIPPING CASK CONTAINING RADIOACTIVE MATERI AL WILL BE CONTROLLED THROUGH THE USE OF WRITTEN PROCEDURES. ALL DOCUMENT CHANGES WILL BE PERFORMED ACCORDING TO WRITTEN PROCEDURES APPROVED BY THE THREE INDIVIDUALS NAMEDIN SECTION 1).

THE RADIATION SAFETY OFFICER (S) SHALL INSURE THAT ALL QA FUNCTIONS ARE CONDUCTED IN ACCORDANCE WITH THE LATEST CHANGES TO THESE DOCUMENTS.

4) HANDLING, STORAGE, AND SHIPPING WRITTEN SAFETY PROCEDURES CONCERNT*

'HE HANDLING, STORAGE AND SHIPMENT 700 SHIPPING CASK WILL BE FOLLOWED.

OF SEALED RADIOACTIVE MATERIAL IN SHIPMENTS OR ACCEPTANCE OF SHIPMENTS WILL NOT BE MADE UNLESS ALL TESTS, CERTIFICATIONS, AND FINAL INSPECTIONS HAVE BEEN COMPLETED. WORK INSTRUC-TIONS WILL BE PROVIDED FOR HANDLING, STORAGE AND SHIPPING OPFRATIONS.

RADIATION SAFETY OFFICERS AND TRAINED CERTIFIED RADrATION TECHNICIANS SHALL PERFORM THE CRITICAL HANDLING, STORAGE AND SHIPPING OPERATIONS.

5)

INSPECTION, TEST, AND OPERATING STATUS l

INSPECTION AND TESTING OF THE GE 700 CASK AND CONTENTS WILL BE CARRIED OUT FOLLOWING WRITTEN PROCEDURES.

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RADIArrON SAFETY OFFICERS AND TRAINED CERTIFIED RADIATION TECHNICIANS i

l SHALL PERFORM THE REQUIRED INSPECTIONS AND TESTS IN ACCORDANCE WITH I

WRITTEN PROCEDURES. THE RESPONSIBILITY OF THE PERFORMANCE OF THESE FUNCTIONS RESTS WITH A RADm TION SAFETY OFFICER (J. MYRON).

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6) QUALITY ASSURANCE RECORDS RECORCS OF PACKAGE APPROVALS (INCLUDING REFERENCES AND DRAWINGS). PRO-CUREMENT, INSPECTIONS, TESTS, OPERATING LOGS, AUDIT RESULTS, PERSONNEL TRAINING AND QUALIFICATIONS AND RECORDS OF SHIPMENTS WILL BE MAINTAINED.

DESCRIPTIONS OF EQUIPMENT AND WRITTEN PROCEDURES WILL ALSO BE MAINTAINED.

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. THESE RECORDS WIL'L BE MAINTAINED IN ACCORDANCE WITH WRITTEN PROCEDURES.

THE RECORDS WILL BE IDENTIFIED AND RETRIEVABLE. A LIST OF THESE RECORDS, WITH THEIR STORAGE LOCATIONS, WILL BE MAINTAINED BY A RADM TION SAFETY OFFICER. (J. MYRON)

7) AUDITS AUDITS OF RADIOACTIVE MATERIAL AT ARECO'S IRRADIATION FACILITY WILL BE CARRIED OUT AT 6 MONTH INTERVALS BY HEALTH PHYSICS CONSULATION, AN NRC CERTIFIED COMPANY, WHICH HAS BEEN CONTRACTED BY ARECO TO PERFORM AUDITS OF NRC LICENSE MATERIAL FOR THE PAST THREE YEARS. RESULTS OF AUDITS WILL BE MAINTAINED AND REPORTED TO MANAGEMENT. AUDIT REPORTS WILL BE EVALUATED AND DEFICIENT AREAS CORRECTED. THE AUDITS WILL BE DEPENDENT ON THE SAFETY SIGNIFICANCE OF THE ACTIVITY BEING AUDITED. AUDIT REPORTS WILL BE MAIN-TAINED AS PART OF THE QUALITY ASSURANCE RECORDS. HEALTH PHYSICS CONSUL-ATION HAS NO RESPONSIBILITY IN ARECO ACTIVITIES.

JAMES J. MYRON PH.D.

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V DIRECTOR OF RADIATION & IECHNICAL SERVICES ATTACHMENTS:

1) DRAWING OF GENERAL ELECTRIC-MODEL 700 SHIELDED CONTAINER

2) NRC CERTIFICATE OF COMPLIANCE FOR GE-700 SHIELDED CONTAINER

100 Series Ceehlication Ne 5942 ( A I A E A. Certified )

Casa Assembly Weigne 2 3.310 lbs. - 10.595 Kg s Assembly Weight 3 3.585 lbs. 15.265 Kos Assembly Drawing No. 289E642G2 Modes of Transporterien. Yessel. Moser Vehicle and Rail Fisste Classification Ill A E.C. License $NM-960 71-46 WettLead 6500 D'y Ses Section Oveer Jocket 661/2 in.

1500 Wer Ses section Inner Jacket 621/4 in.

Cask Lifting Eers 59-l/4 in.

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Inner Jochet i.d. 57-9/16 in.

PRV & Filter I

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l Deein O.,e, p 10-3/8 in. Lead

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anner Jocket 79 5/8 in.

Cesk 60-1/8 in.

^ NFill tube

. - Cevit y 15 in. diem.

l u 40 in.

100 5/16

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' 1/4 in.

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- 12 5 /8 in.

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o Cash 36-7/8 in. diem.

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Pellet 661/2 in. m 51-1/2 in.

GENER AL ELECTRIC - MODit 100 5HifLDED CONT AlHit (WiTHOUT CASK EXTENSION)

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CERTIFICATE OF COMPLIANCE 1

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io cm' FOR RADIOACTIVE MATERIALS PACKAGES b REYissON NUMBER c PACS (AGE IDENTIFeCATsON NUMBER e PAGE NUMBER e Tor AL NUM8ER PAG ($

e CE;,TiFiCATE NUusER 5942 10 USA /5942/B( )F 1

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2 PREAMBLE l

C. Thes certificate es issued to cert.fy that the packagmg and contents described in item 5 bekyo. meets the applicable safety standards set forth in Title 10. Code of Federal Regulations. Part 71. Packaging and Transportation of Radeoactive Material" b This certsfacate does not releeve the consignor from compliance with any requirement of the regulations of the U S. Department of Transportation or other I

l applicab8e regulatory agencies, encluding the govemment of any country through or ento which the pacatage will be transported il l

f317scy s issvEo o~ 1,.E s* sis or a sartTv anausis,aEgigtggEgsy ic4A,o~

General Electric Application dated May 30, 1985, f'

General Electric Company P.O. Box 460 as supplemented.

Pleasanton, CA 94566 g

i coocurEeER 71-5942

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This certificate is conditional upon fulf 11*ng the requirements of 10 CFR Part 71. as applacable. and the conditions specified below l{i h*

(a)

Packagi ng i

1l (1) Model No.:

700 f'

(2) Description p

l 11 A-steel encased lead shielded shipping cask enclosed by a double-1

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walled protective jacket 'of/the'same shape with a rectangular baseplate.

I The cask is a double-walled steel circular cylinder, 37-inch-diameter f:

by 65-inch high with a central jcavity'15-inch-diameter by 40-inch g

high. Approximately-J0.25 inches;Af lea _d surround the central cavity.

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The cask '.is equippe'd with eccavity d' rain lirieg pressu're relief valve J

jl set at 100,psig, and lif ting : device. Closure is accomplished by a silicone riubber gasketedia'nd tolted steel Llead filled plug.

The d

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I maximum gross. weight Jof thekpackage 1 contents, cask assembly, protective D

f jacket and base) is 35,500 pounds.K.l P

The cask may be modified with a 14-ipch high cavity extension with an f[

f addi tional silicone rubber.' gasket.

The' modified cask is 79 inches high. The caximum gross weight of the package (contents, modified g

(p cask assembly, protective jacket and base)is 40,200 pounds.

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f The packaging is constructed in accordance with the following General g

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Electric Company Drawing Nos.:

129D4768, Rev. 3; 129D4769, Rev. 4; g

y and 129D4770, Rev. 5.

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Lif ting and/or tie-down devices which are a structural part of the g

package rust be in accordance with the above drawings.

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lif{mma.wwww.m_vnvera rrsss s.-www-wma:mwwww.m CONDITIONS (continued) i Page 2 - Certificate No. 5942 Revision No.10 - Docket No. 71-5942 h

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(b) Contents L

(1) Type and form of material y

Byproduct, source, and special nuclear material contained in solid oxide or metal fom and in special form.

j (2) Maximum quantity of material per package Not to exceed 700 pounds (including shoring), and a

(i) 740 gm U-235, provided that the maximum U-235 enrichment does not g

exceed 6 weight percent; or g

M (ii) 1,200 gm U-235, {provided that the ' fuel material is in the fom of MTR-type fuel.' elements with a minimum active fuel length of 23 inches;pr'~

h (iii) 220 gm fissile material; or

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(iv) li650 g'm U-235, provided that the maximun U-235 enrichment does not excesd J'.5 weight percent and the fuel material is in the a

fom of 88 rods' loaded with 0.376-inch-diameter pellets with a i

minimum active. fuel length of '37 inches; or l

(v) those values esented-in Figure'l,-U0,, Weighthimits for Model 700

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1 Shipping Container,e of Exhibit 'A :to this application, applicable 1

to fuel _ material;in"the~ fonn of. rods with a minimum pellet diameter of 0.40 inch;,oF'* J 4

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(vi) 5,100 gm U-235, provided the fuel 'is in the -fam of ETR-type fuel I

l elements (GETRJuel)-with each' element containing no more than i

510 gm U-235 and inserted in the spaced stainless steel fuel shipping basket described in GE Drawing No.106D4150, Rev. 0.; or N.

(vii) 6,200 gm U-235, provided the fuel is it the fom of MURR TRTR

' j type elements containing not more than 775 gm U-235 per element; loaded and spaced in the stainless steel fuel shipping basket as N

L, described in MURR Orawing No.1228, Sheets 1 thru 5, Revision 0.

I'f Fuel elements shall have at least 150 days cooling time since last reactor operation; or 1

(viii) 3.510 gm U-235 provided the fuel is in the form of MTR-type fuel h

i j elements with each element containing no nore than 351 gm U-235 N

I 1 and inserted in a spaced stainless steel fuel shipping basket D

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described in GE Drawing No. 10604150, Rev.1 for GETR fuel. A l

l 1 shoring device to limit vertical motion of the fuel elements nust j

be included.

(ix) 7,020 gm U-235 provided the fuel is in the fonn of MTR-type fuel i

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elements with each element containing no more than 351 gn U-235

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inserted in a spaced stainless steel fuel shipping basket described i

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in GE Drawing No.106D4150, Rev.1, for 24-inch length fuel.

l Each shipment nust contain 20 fuel elements in 2 fuel baskets l

3 with the spacer plate shown on GE Drawing No. 218B6061, Rev. O, if 3

i located between the baskets,

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conotirons (continued) i

. 5942 - Revision No. 10 - Docket No. 71-5942 ll' i

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5.

(b) Contents (continued) l N

(3) Maximum quantity of radioactive decay heat per package 1

lI (1) 6,500 watts for dry shipments, or I'l (ii) 1,500 watts for wet shipments, provided that the cavity shall I

contain at least a 1,000 cu in air void (at standard temperature and pressure) at the time of delivery to a carrier for transport.

h (c) Fissile Class III ill I

Maximum number of pac,kages 'pe'r shipment' i-2 g.

Ei 6.

The radioactive material-5ust oe in the fom of fuel rods, or plates, fuel assemblies, or meeting >the requirements of special fom radioactive material.

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Shoring must be prp/vided 40, minimize movement of contents during accident conditions l

of transport.

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Prior to each shipment (excepb for contents meeting the requirements of special f

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fom radioactivhnaterial) fee' pack of detemining \\ hat a leakage}of 10~gge musg/s ht.. standard temperature and'ti g.)

pressure is not+ exceeded.

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4 This gasket (s) must be' replace,1 cone pu;berilid ' gasket (s) nustte I

9.

Prior to each shipment;T.he.sil b

I d ifainspection. shows any defects or every twelve h

(12) months, whi'heyer 'occUrif first.aCa'vityJrainfline nust be sealed with c

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appropriate sealant -applied -to fhYeads of pipe plug.

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10. The applicant rust conf.irm annually that the pressure relief valve is operable at 100 psig.

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11. When needed, sufficient antifreeze in the cask J:Ust be used to prevent damage of g-any component of the package due t,o freezing.

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12.

Fabrication of additional packagings is not authorized.

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13. The package authorized.by this certificate is hereby approved for use under the g!

general license provisions of 10 CFR 671.12.

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Expiration date: July 31, 1990.

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l CbNoiTioNS (continued) i lj )Page 4 - Certificate No. 5942 - Revision No.10 - Docket No.

71-5942 I

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l REFERENCES I

General Electric application dated May 30, 1985.

l Supplements dated:

June 5 and 7, August 7, and September 16,.1985.

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University of Missouri letter dated March 20, 1980.

g Appendix 6-A regarding University of Missouri's quality assurance program is not considered part of this application.

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r. Y._OR THE U.S2 UCLEAR REGULATORY COMMISSION i,l j.

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Charles

. MacDona d, Ch.ief lll Transportation Certification Branch l

Division of Fupl'fycle and '--

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