ML19347E891

QA Program

ML19347E891
Person / Time
Site:	07100440
Issue date:	04/08/1981
From:	Andresky E, Levelius W PROFESSIONAL SERVICE INDUSTRIES, INC. (FORMERLY PTL-I
To:
Shared Package
ML19347E890	List: ML19347E889 ML19347E891
References
19028, IR-QA-1, NUDOCS 8105140187
Download: ML19347E891 (16)

Text

.

b PITTSBUNGH TESTING LABORATORY

. m.m..

850 POPLAR STREET, PITTSBURGH, PA.15220 PROCEDURE: INDUSTRIAL RADIOGRAPHY QA PROGW1 i

PROCEDURE NO. :

Is ue I; ate :

4-8-81 Prepared by:

E. L. Andresky, Radiologica Safety Coordinator Reviewed & Accepted by:

'W.H.

Levelius, Vice President &

Liason Officer REVISION HISTORY AND APPROVAL

[hR REV.

DATE DESCRIPIION A

AC EPTA d_

0 4-8-81 Original Issue m

STATUS:

ISSUED FOR REVIEW AND COMMENT x ISSUED FOR USE i

X UNCONTROLLED CONTROLLED CDNTROLLEO COPY NO.

12:023 l

810514 0 Ilf]'

QUALITY CONTROL PROCEDURE REV.

NO.

0 1

i TITLE INDUSTRIAL RADIOGRAPHY OA PROGRAM j.3 CFR PART 71 OA PROGRAM)

REV.

DOCUMENT NO.

IR-OA-1 DATE 4-8-81 l.

Organization The final responsibility for the Quality Assurance (QA) Program

~

for Part 71 Requirements rests with Pittsburgh Testing Laboratory.

Design and Fabrication shall not be conducted under this QA Program. The QA Program is* implemented using the organizational chart shown in Appendix A.

The Liaison Officer is responsible for overall administration of the program, training and certification, document control, and auditing.

The Radiographers are responsible for handling, storing, shipping, inspection, test and operating status and recordkeeping.

2.

Quality Assurance Program The management of Pittsburgh Testing Laboratory establishes and implements this QA Program. Training, prior to engagement, for all CA functions is required according to written procedures.

QA Program revisions will be made according to written procedures with management approval. The QA Program will ensure that all defined QC procedures, engineering procedures, and specific provisions of the package design approval are satisfied.

The QA program will emphasize control of the characteristics of the package which are critical to safety.

The Radiological Safety Coordinator shall assure that all radioactive material sMpping packages are designed and manufactured under a QA Program approved by the Nuclear Regulatory Commission for all packages designed or fabricated after January 1, 1979.

This requirement will be satisfied by receiving a certification to this effect from the manufacturer.

3.

Document Control All documents related to a specific shipping package will be controlled through the use of written procedures. All document changes will be performed according to written procedures approved by management.

The Radiological Safety Coordinator shall insure that all QA functions are conducted in accordance with the latest applicable changes to these documents.

PITTSBURGH TESTING LABORATORY

,,gg 1 og 3

i QUALITY CONTROL PROCEDURE JEV.

NO.

O l

l TITLE INDUSTRIAL _ RADIOGRAPHY QA PROGRAM (10 CFR PART 71 QA PROGRAM)

REV.

DOCUMENT NO.

IR-OA.1 DATE 4-8-81 4.

Handlino, Storage, and Shipoing Written safety procedures concerning the handling, storage, and shipping of packages for certain special form radioactive material will be followed.

Shipments will not be made unless all tests, certifications, acceptances, and final inspections have been completed.

Work instructions will be provided for handling, storage, and shipping operations.

Radiography personnel shall perform the critical handling, storage, and shipping operations.

5.

Inspection. Test, and Operatino Status Inspection, :ast, and operating status of packages for certain special form radioactive material will be indicated and controlled by written procedures.

Status will be indicated by tag, label, marking, or log entry.

Status of nonconforming parts of packages will be positively maintained by written procedures.

Radiography personnel shall perform the regulatory required inspections and tests in accordance with written procedures.

The Radiological Safety Coordinator shal L ensure that these functions are performed.

6.

Quality Assurance Records Records of package approvals, procurement, 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.

These records will be maintained in acaordance with written procedures. The records will be identified and retrievable.

A list of these records, with their storage locations, will be maintained by the Radiological Safety Coordinator.

7.

Audits Established schedules of audits of the QA Program will be performed using written check lists. 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, but each activity will be audited at least once per year. Audit reports will be maintained as part of the quality assurance records. Members of the audit team shall have no responsibility in the activity being audited.

PITTSBURGH TESTING LABORATORY PAGE 2 OF 3 i

QUALITY CONTROL PROCEDURE REV.

NO.

O l

l TITLE INDUSTRIAL RADIOGRAPIN QA PROGRA*1 (10 CFR PART 71 QA PROGRAM)

REV.

DOCUMENT NO.

TR OA 1 OATE_a.E-81__._

8.

Refe-ence Documents Appendix B - Certificate of Compliance (Ga2r.ma Industries, Inc. )

Appendix C - NRC Certificate of Compliance Certificate No. 6717 Appendix D - IAEA Certificate of Competent Authority Certificate No. 6717-B Appendix E - IAEA Certificate of Competent Authority Certificate No. USA /0166/S Appendix F - Type A Packago Certificate Letter - Troxler Electronic Laboratory Dated 3-11-77 Appendix G. - NRC Certificate of Compliance Certificate No. 9056 Appendix H - NRC Certificate of Compliance Certificate No. 9036 PITTSBURGH TESTING LABORATORY PAGE 3 OF 3

ORGANIZATIONAL CHART r

3 W. H. Levelius Vice President &

Liason Officer L

i f

3 E. L. Andresky Radiological Safety Coordinator

(

r 3

e Radiation Safety Officer Radiation Safety Supervisor District Office District Office L

(

1 7

Radiographer i

J i

Assistant Radiographer L

r 3

Trainees Appendix A t

)

GAMMA INDUSTR 1 ES A Division ofNuclear Systems. Inc.

BATON ACUGE HOUSTON BAT RC G 21 TE P CNh 7 674 CERTIFICATE OF COMPLIANCE i

i i

TO:

Mr. Joe Nalapa p

Pittsburgh Testing Lab i

,5 l

O.

Box 1646 Pit.tsburgh, PA 15230 I

REFERENCE:

Ga=a Industries Models:

Gama 35, Gamma Century, Ga==a Pipeliner Model I, Gamma C Above devices meet the DOT Specification 7A This is to certify that the referenced device has been tested and complies with all requirements of DOT regulations pertaining to this device when used l

in accordance with DOT regulations. Documentation of all tests are on file at Gamma Industries, Baton Rouge, Louisiana.

4 s

i

\\ Don IUdde I;

Quality Assurance Manager I

l f

Apper. dix B

l

\\

a Frem NRC418 U.S. NUCLE AR REGULATORY CoMha331oN gg [733 CERTIFICATE OF COMPLIANCE

,g For Radioactive uaterM Pachaeos I.fal Certificats Nummer 1.!bl Revwion No.

1.fcl Packagni teentificaten Ns.

1.(d) Pages No. 1.fol Total No. Pages 6717 4

USA /6717/B 1

2

2. PRE AMSLE 2.tal Thes certificate is ensued to satisfy Sections 173.393a.173.394.173.395. and 173 ?J6 of the oeoertrnent of Transoorteten Hazaroovs Materiais Regulations 149 cFR 17o.189 and 14 Crf4103) and sections 146-19-104 and 146-19-10o of ins oeoartment of Treasportation aangerous cargoes Regulateau (46 CFR 126-149). as amended.

2.lb)

The sectageng and contents described in

• tem s be6cm, meets the safety !tandards set forth in Suboart C of Tide 10. code of Federal Regulations. Part 71 ** Packaging of Radeactive Materials for Transoort and Transportation of Red.oactive Material Under Certsen Conditens."

2.fc)

This certificato does not relieve the conssgnor from comodiance weth any requirement of the regulations of the U.s. oeoartment of Transportation or other acosicable regulatory agencies, incsuding the government of any country througfi or into wn n the oocasse e it be transponed.

3. This evtificate is issued on the basis of a safety analyses rooort of the package desegn or apodicaten-3.lal Prepared by (Name and address):

3.!b)

Title and centification of report or acoticaten:

Gimma Industries Nuclear Packaging, Inc. application dated P.O. Box 2543 June 20, 1975, as supplemented Baton Rouge, LA 70821 3.ici ooc,et No. 73_g737

4. CO No4TioNS This 6 08 cate is conditenal woon the *ulfilling of the requirements of Suboart o of 10 CFR 71, as soolicable, and the conditions specfied in iters 5 beli..

5. oeser.ot on of Packag'ng are Autnorised Contents. Modet Numoer. Fisade Cass. Ctn r Conditens. and References.

e (a) Packagine, (1) Model No.:

6717-B (2) Descrip'. ion Radiographic device within a protective overpack.

The overpack consists of an outer container which is a 10 gallon open head r, teel drum having a minimum 20-gauge body and cover, welded seams and a clamp-ring type head closure.

The. void space between the inner and outer container is filled with 1-1/2" thick molded asbestos free liner on sides, top and bottom, plus molded polyurethane filler to position and secure the radiographic device within the drum.

Maximum gross weight of the package not to exceed 75 l

pounds.

(3) Drawing The packaging is construr:ted in accordance with Nuclear Packaging Inc.

Drawing No. SK-D-1, Rev. 2.

Apper. dix c

?00R ORHL

e Pag 2 2 - C rtificate No. 6717 - Revision No. 4 - Docket No. 71-6717 l

S.

(b) Contents (1) Type and form of material 1ridium-192 as sealed sources which meet the requirements of special form as defined in 10 CFR 571.4(o).

(2) Maximum quantity of material per package 200 curies.

6.

The contents must be secured in a single snug-fitting inner radiographic device which has a metal outer wall and meets the requirements of 49 CFR 5178.350 (00T Specification 7A).

7.

The source shall be secured in the shielded position of the radiographic device by the shipping plug, source assembly, and locking device.

Theshippingplugandsource assembly used must be fabricated of materials capable of resisting a 1475 F fira environment for one-half hour and ' maintaining thuir positioning function.

The ball stop of the source assembly must engage the locking device.

The flexible cable of the source assembly and shipping plug must be of sufficient length and diameter to provide positive positioning of the source in the shielded position.

8.

The packaging at:thorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).

9.

Expiration date:

July 31, 1985.

REFERENCES Nuclear Packaging, Inc. application dated June 20, 1975.

Supplements dated:

August 8, 1975; and February 26, 1980.

FOR THE U.S. NUCLEAR REGULA10RY COMMISSION f

Charles E. MacDonald, Cnief Transporation Certification Branch Division of Fuel Cycle and Material Safety AUG 0 41980 D:te:

Appendix C

DEPARTMENT OF TRANSPORTATION RESEARCH AND SPECIAL PROGRAMS ADMlNISTRATION W ASHINGTON. O C.

20590 IAEA CERTIFICATE OF COMPETENT AUTHORITY Type B Radioactive Material Package Desien Certificate Number USA /6717/B (Revision 3)

This establishes tl.at the packaging design described herein, when loaded with the authorized radioactive contents, has been certified by the National Competent Authority of the United States, as meeting the regula-tory requirements for Type B packaging for radioactive materials as pre-scribed in IAEA If Regulations and $$ 49 CFR 173.393a and 173.394(b)(3) of the USA 2/ Regulations for the transport of radioactive materials.

I.

Package Identification - Model No. 6717-3.

II. Packaging Description - Packaging authorized by this certificate consists of an outer 10-gallon steel drum with an inner container which is a metal-walled container meeting the requirements of DOT Specification 7A, surrounded by polyurethane filler and a 1-1/2" asbestos liner. Gross weight is approximately 75 pounds.

I;I. Authorized Radioactive Contents - The authorized contents consist of radioactive materials, n.o.s. as not more than 200 curies of iridium-192 as sealed sources which must meet the requirements for special form as set forth in 49 CFR 173.389(g).

IV. General Conditions -

a. Each user of this certificate must have in his possession a copy of this certificate.

b. Each user of this certificate, other than Ca=ma Industries, Baton Rouge, Louisiana, shall register his identity in writing to :he Office of Hazardous Materials Regulation, U.S. Depart. ment of Transportation, Washington, D.C.

20590.

c. This certificate does not re'.ieve any consignor or carrier from compliance with any requirement of the Government of any councry through or into which the package is to be transported.

V.

Maykina and Labeling - The package must bear the marking USA /6717/B as wel.1 as the other marking and labels prescribed by the USA Regulations,.

1 1

l Appendix D

Certificate Nunb2r USA /6717/B (R2v. 3)

Page 2 VI.

Eoiration Date - This certificate, unless renewed, expires on July 31, 1985.

This certificate is issued in accordance with the requirements of the IAEA and USA Regulations and in response to the March 10, 1975, petition by Nuclear Systems. Inc., Baton Rouge, Louisiana, and revised in response to~

the August-12, 1980, petitien by Gansna Industries, Baton Rouge, Louisiana sud in consideration of the associated infnrmation provided in U.S. Nuclear Regulatory Connaission Certificate No. 6717 (Appendix A).

Certified by:

AArk/7MTO 3

(Date)

Richard R. Rawl Chief, Radioactive & terials Branch Office of Hazardous Materials Reguistion Materials Transportation Bureau 1/ " Safety Series No. 6, Regulations for the Safe Transport of Radioactivu Materials," 1967 Edition published by the International Atomic Energy Agency (IAEA), Vienna, Austria.

2/ Title 49, Code of Federal Regulations, Parts 100-199, USA, i

Revision 1 issued to incorporate USNRC Certificate No. 6717. Revision 1.

Revision 2 issued to incorporate USNRC Certificate No. 6717, Revision 2 and to extend e'zpiration date.

Revision 3 issued to incorporate USNRC Certificate No. 6717, Revision 3 and to extend expiration date.

Appendix D

e DEPARTMENT OF TRANSPORTATION

),

SPECIAL PROGRAMS ADMINISTRATION 1

}; RESEARCH AND j

WASHINGTON. D.C 2o590 i

f IAEA CERTIFICATE OF COMPETENT AUTHORITY s.e e er R EFE R TOs Special Form Radioactive Material Encapsulation Certificate Number USA /0166/S (Revision 1)

This certifies that' the encapsulated sources, as described, when loaded with the authorized radioactive contents, have been deconstrated to meet the regulatory regjirements for special form radioactive material as 2

prescribed in IAEA and USA Regulations for the transport of radioactive materials.

Source Description - The sources described by this certificate are I.identified as the following Ca==a Industries models which are constructed according to the listed drawing numbers:

Drawine Nc.

.Model No.

602-7001-004 VD and VD(HT) 602-7001-005 NB, NBC and NB(HP) ~

602-7001-006 Single Encapsulation Universal Sot ree Double Encapsulation Universal Sourca 602-7001-007 602-7001-008 Single Encapsulation S$de k' eld All models" are velded en' apsulations constructed of 300 'stries stainless c

s steel.

II.

Radicactive Contents

.,The authorized radioactive contents of these sources consist of.not more than:

Contents Model No.

VD and VD(HP) 300 curies of:.

Bariu=-131 Manganese-54 Cadmium-109 *lPhosphorus-32 Calcium-45. Rubidfum-86 Calcium-47 Selenium-75 Cesiu=-137 Strontium-85 Chlorine-36

'Thalliu=-204 Chromium-51 Thulium-170 Iridium-192 Tin-113 Cobalt-60 Ytterbium-169 Iron-59 Zinc-65 O

9

TYPE A PACKAGE CERTIFICATION Troxler Electrcnic Laboratories, Inc. certifies that their models 1255, 1257, 1351, 1352, 2226, 2376, 2401, 2402, 2451, 2452, 3401, and 3411 contain Type A quantities of special form radioactive materials and are packed for shipment in Specification 7A Type A (general parkaging) containers (US Titic 49 CFR 178.350).

These containers meet the requirements of CFR 173.24 and are designed and constructed to meet the star.dards as specified in CFR 173.389(j) and 173.398(b).

They are marked ' 3A DOT 7A TYPE A, RADIOACTIVE MATERIALS in conformanca with CFR 173.24 These regulations are in conformance with the requirements (Marginal C-6) of the International Atomic Energy Agency's " Regulations for the Safe Transport of Radioactive Materials", Safety Series No. 6, 1973, revision edition. These regulations do not require competent authority for international shipment as covered in Sectica VIII, paragraph 801.

For re-shipment, the shipper must maintain a copy of this Certification on file for a period of cne year in accordarce with CFR 173.394 (a) (1). Note that 173.393(b) requires that "Each package must incorperate a feature such as a seal, which is not readily breakable and which, while intact, will be evidence that the package has not been illicitly opened.

TROXLE?. ELECTRONIC LAEORATORIES, INC.

)

?

'.M,M Q k.L. Berry,hicePresident Research and Develeprent March 11, 1977 RLS/td t

Appendix F P001 BRME

~ '..

/

Femsse fuRC4U U.S. NUCLE AR REcuLATORY CoVMIS$1CN

((,38 CERTIFICATE OF COMPLIANCE n

For Radioactive Materials P3ctages 1.la) Cerensste feweeer 1.14 ) Revisen No.

1.(c) Package ident'afication' No.

1.(d) Pages No-1.lel Total No. Pages 9056 0

USA /9056/B 1

2

2. PMAaf9LE llal This cwtificate is cause to satisfy 5enens 173.393a 173.394.173.395. and 173.396 of t'io Decertment of Transoor arion Maz-re: s Mansraels Renwietens (49 CFR 170189 and 14 CrR 103) anc Sections 1a6-19-10a mas 146-19-100 of the Cecartment of Teamemortat.un Dangerous Cargoes Regudatens 146 CFR 146-149). as amencec.

2.bul The amuseW and contenta desent,sd in item 5 below, meets the safety standares set forth in Subpart C of T;tre 10. C::e cf Feeured ReWatees. Part 71. Pactaging of Radioactive Meterials for Transport and Transportation of Rarsicactive P.*ateoal under Certant Condsten6.**

2.5sl Thes eartificate does not reiseve the consegnor from compliance witis any requirement of the regulations of the U S. Desar-e t :f Trancartation or other acol. cable regulatory agencies. enclucing toe government of any country througn or into wmn the sac = e

=ds he tronaswrted.

1 This surWacare in issues on the basis of a safety analyses report of the package des.gn or aposicaten-1(al Prm by (Name and addrear):

3.(b)

Tide ano usentification of recort or soplication:

Source Production & Equipment Source Production & Equipment Comoany apolication Company dated July 23, 1975, as suoplemented.

625 0xlev Street Kenner, Lou 1 stana 70062 3.(c) ooc =e no. 71-9056

4. Ccv.on Cus Tem est.fscate es conditenas en the fulfilius of the requireements of Subpart D of 10 cFR 71, as acolicable, and the cerc.troms s:<=W2

• si isonn S twelow.

E Des:r.pnen or s e' wng aM Autnoritec Coe. tents. Mocei Nar=cer. Fissile Clas:.. Ciner Ocec.t: oms, ard Atf t:e*:c-m=

(a) Packaging (1) Model No. - SPEC 2-T (2)

Description A steel encased, uranium shielded Gamma Ray Projector.

Prima ry components corsist of an outer steel shell, internal bracing, depleted uranium shield, a..d a Zircalloy "S" tube.

The contents are securali positioned in the Zircalloy "S" tube by a source cable lockine device and shipping plug. The unit resembles a rectangular box 12.5" long by 4.4" high by 4.4" wide with a gross weight of 40 pounds.

(3) Drawings The packaging is constructed in accordance with Source Production &

Equipment Cocoany drawing of the Model SPEC 2-T submitted in the January 8,1976 supplement.

Appendix G P00RORBNi

Page 2 - Certificate No. 9056 - Revision No. 0 - Docket No. 71-9056 5.

(b) Contents (1) Type and fann of material Iridium-192 as sealed sources which meet the requirements of special form as defined in i 71.4(o) of 10 CFR Part 71.

(2) Maximum quantity of material per package 200 Curies (Nominal) 6.

The source shall be secured in the shielded position of the pack-aging by the shipping plug, source assembly, and locking device.

The shipping plug and source assembly used must be fabricated of materials capable of resisting a 14750F fire environment for one-half hour and maintaining their positioning function.

The source assembly ball stop must engage tne locking device.

The flexible cable of the source assembly and shipping plug must be of sufficient length and diameter to provide positive positioning of the source in the shielded position.

7. The nameplates shall be fabricat j of materia's c. pable of resisting the fire test of 10 C.

Part 71 and maintaining their legibility.

8.

The packaging authorized by tnis Certificate ef Compliance is hereby approved for use under the general license provisions of Paragraph 71.12(b) of 10 CFR Part 71.

9.

Expiration date: February 28, 1981.

REFERENCES Source Production & Equipment Company application dated July 28, 1975.

Sgplement dated January 8,1976.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION Wk$L Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety FEB 4 1976 Dak l

y-e P00R,mR1BELI Appendix G J

l

US. ATOMIC ENERGY COMMISSION

' 'E Uf CERTIFICATE OF COMPUANCE Me$'3[,j For Radioactivo Materials Packages

13. Cerlifecats Num:ser Ib. Reves on No.

Ic. Pacuage Identification No.

Id. Page No.

le. Total No. Par,.

9036 0

USA /9036/B 1

2

2. PREAMitLE 2a.

This certificate is issued to satisfy Sections 173.3934,173E4.173.395, and 173.396 of the De:urtment of,Transporvotion Hararcous Materials Regulations (49 CFR 170-189 and 14 CF R 103) and Sectens 146-10-104 and 146-19-100 of the Deportrnent of Transportat oa Dangerous Cargoes Regulations (46 CF R 146-149), os amended.

2b.

The packaging and contents described in item 3 below, rneets the safety stardarcs set forth in Subrurt C of Titre 10. Coca of Fecerat Regulations.Part 71," Pas-msg.ng of Radioactive Materet for Trenaport and Transoortation of Radioactive Materal Under Certam Conchtions."i 2c.

Tfue certificate does not relieve the consignor from comphance weith any requirement of the regulations of the US. Department of Transportation or other aposicable requietory agencies, including the powenment of any country through or into which tr.e pact age unit be transported.

3. Thes certificate s essued on the basis of e esfety anefysis report of the package dessen or oppi cation-(Il Propered by (Name and acWressh (2) Title and identificateen of report or oppficatlon:

Source Producticn & Equipment Co.

Source Production & Equipment Company application 625 0xley Street dated January 23, 1975, as supplemented.

Kenner, Louisiana 70062 (3) Docket No. 71-9036

4. CONDtTIONS Thes certificate is conditional upon the futfittirwJ of the requirements t

• Subpart D of 10 CFR 71, as applicable,and the con <titions spec.f *J in item S below.

5. Description of Packwng and Authorired Contents.Modet Number, F stile Class. Other Cond. tens and Heterences.

(a) Packaging (1) itodel No.: C-1 (2) Description A uranium shielded radiographic source changer. Configuration is that of a rectangular box 9" high x 7.5" wide x 7" deep. All fittings and source locking conponents are protected and enclosed v.ithin a 1/8" carben steel outer shell. The inner recentacle consists of a uraniun shield equipped with two closed botten Zircalny "J" tubes, each of vmich nay housc. one""p'igtail type" special form source, llaximum gross weight is 45 lbs.

(3) Drawings The package is constructed in accordance with the Source Production &

Equipmeat Company drawings as submitted in the applicat1on and supplement j

dated January 23, 1975 and liay 7,1975, respectively.

l l

y Appendix H P00RBR M

[

Page 2 - Certificate No. 9036 - Revision No. 0 - Docket No. 71-9036 5.

(b)

Contents (1) Type and form of material Iridium-192 as sealed sources that meet the requirements

-~

of special form as defined in 571.4(o) of 10 CFR Part 71.

(2) Maximum quantity of material per package Two sealed sources with a combined activity not to exceed 200 curies.

6.

The nameplate shall be fabricated of materials capable of resisting the fire test of 10 CFR Part 71 and maintaining its legibility.

7.

The package authorized by this certificate is hereby approved for use under the general license provisions of Paragraph 71.12(b) of 10 CFR Part 71.

8.

Expiration.cate: June 30, 1980.

REFERENCES Source Production & Equipment Company applicatien dated January 23, 1975.

Supplement dated liay 7, 1975.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION Y =As Y& O-- N Charles E. MacDonald, Chief Transportation Branch Division of liaterials and Fuel Cycle Facility Licensing Date June 26. 1975

\\

19C23 Appendix H

^

.