ML20005D903

Fuel Shipment QA Program

ML20005D903
Person / Time
Site:	07100689, 07105908
Issue date:	12/31/1989
From:	MANHATTAN COLLEGE, RIVERDALE, NY
To:
Shared Package
ML20005D899	List: ML20005D898 ML20005D903
References
26200, NUDOCS 9001020201
Download: ML20005D903 (35)

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,V-Manhattan College Quality Assurance Program FUEL SHIPMENT QUALITY ASSURANCE PROGRAM MANHATTAN COLLEGE ZERO POWER REACTOR REACTOR FACILITY RIVERDALE, NEW YORK, NEW YORK t

DECEMBER,1989 L

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i Table of Contents I

! INTRODUCTION 1

1.1 Purnose _

I 1.2 Anplienbility I

1.3 Ref erences.

I 2 PROGRAM REQUIREMENTS.

I 2.101ganizalinn.

I 2.2 ltesoonsibility 4

2.3 I)ocurnentation.....-

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4 2.4 Procturment Control.

5 2.5 hinte rial Contr ol...........<-

5 2.6 Process Control 5

2.7 Internal InsntcliDDI.

6 2.8 Test Control.- __

6 2.9 Mensurine and Test Eaulnatal...

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6 2.10 Nonconformine Material and Paris....

6 2.11 Corrective Action _....

6 2.12 0uality Assurance Records.

6 2.13 Audits.

7 3 FORMS..

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Table of Figures 2

1. MCZPR ORGANIZATION a

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r 1 INTRODUCTION 1.1 Eurpose The purpose of this document is to provide requirements for managing, conducting, and i

auditing the Fuel Shipment Quality Assurance Program at Manhattan College.

1.2 Applicabliity The Quality Assurance Program applies to those quality assurance activities related to transportation of irradiated fuel from the Manhattan College Zero Power Reactor (MCZPR) Facility.

t l.3 Reintacu American National Standard institute (ANSI) N4021976, Quality Assurance Program Requirements for Research Reactors.

~ ANSI /ANS 15.19, Shipment and Receipt of Special Nuclear Material (SNM) by Research Reactor Facilities.

Code of Federal Regulations, Title 10, Title 49.

2 PROGRAM RI'QUIREMENTS 2.1 Q1ganization 2.1.1 Refer to Figure I for the MCZPR table of organization.

'2.1.2 The Reactor Administrator has the responsibility for implementing the Quality Assurance requirements of this program.

s 2.2 Runonsibillix

-Tha Reactor Administrator is responsible for final policy decisions in establishing the facility's quality assurance goals, objectives, and requirements and administering the Quality Assurance Program. The Reactor Operations Committee (ROC) is responsible to the Reactor Administrator for the review and evaluation of quality assurance require-ments, policies, and procedures. The Chief Reactor Supervisor is responsible for the f

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. prepa.ation of operating schedules and procedures, and maintenance o equ pment.

2.2.1 R1 Actor Administrator The Reactor Administrator is responsible for the overall administration and super.

vision of the reactor facility inclusive of the administration of the Quality Assurance The Reactor Ad' inistrator approves all regulations, instructions, and Program.

m procedures governing the operation of the reactor facility.

2.2.2 Henctor Operations Committee (ROC) Char _ln The ROC is responsible for the review, evaluation of, and development of recom-mendations for all proposed operations and i)tocedures in order to assure that the reactor facility is operated in a safe and competent manner. They shall also make recommendations relating to quality assurance, and compliance with U.S. Nuclear Regulatory Commission regulations as well as other rules and regulations they deem appropriate. Recommendations are made to the Reactor Administrator, t

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DEAN OF SCliOOL OF ENGINEERING REACTOR ADMINISTRATOR RADIATION REACTOR SAFETY OFFICER OPERATIONS y

COMMITTEE HEALTH PHYSt.

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CillEF REACTOR SUPERVISOR

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f-FIGURE I Table of Organization MCZPR l.-

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The ROC meets semiannually, during the Spring and Fall academic semesters, and at other times if deemed necessary by the Reactor Administrator, or at the request of individual Committec members.

A formal agenda is. proposed by the Renetor Administrator and minutes are recorded and kept of each meeting, and are distributed to all committee members. The membership of the ROC include the Radiation Safety Officer, the Health Physicist, the Chief Reactor Supervisor, and other appointed personnel involved in operations or oversight of the MCZPR.

The ROC is responsible for the examination of new and untried operations and L

procedures, and for taking action on all new experimental plans. The Committec

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reviews and evaluates all proposed changes in the experimental plans which involve changes in the reactor system. The ROC also advises on any problems relative to the safe operation of the reactor facility,and audits the current and proposed uses of the MCZPR facility.

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2.2.3 Chief Reactot_SEPfuh01.

The Chief Reactor Supervisor is responsible for the promulgation and enforcement of administrative rules, regulations and operating procedures relative to the MCZPR.

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l lic has prime responsibility for the day to day operations within the facility and

_ i preparation and storage of all prescribed logs and operating records.

2.2.4 Quality Assutann.Approsal/Respansibility i !

i 2.2.4.1 This Quality Assurance Program and any future revisions shall be approved by the ROC.

2.2.4.2 Activitics as outlined in this Quality Assurance Program may be delegated or subcontracted, however the responsibility for these activitics remain that of the Reactor Administrator.

.2.2.4.3 Individual responsibility and activities for the Quality Assurance Program are as follows:

Etactor Administrator The Reactor Administrator is responsible for:

Approving Q.A. procedures, designs, and standards.

Assigning Quality Assuranec/ Quality Control personnel.

. j Scheduling reactor activitics, including quality inspections and audits.

l Assigning drawing and document numbers as tequired.

Submitting procedures, safety analysis and project design modifications to the ROC for review as required.

Submitting license and technical specification amendments to the NRC as required.

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Maintaining a project file that contains copics of all records associated the project.

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The Chief Reactor Supervitor is responsible for:

Maintaining properly calibrated measuring and test equipment.

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Preparing fuel removal and loading procedures.

Conducting the approved f uel replacement operations 2.2.5 QualIiv' Aslu.tAnce Au.ctl1 The Quality Assurance Audit will be performed at the end of the shipping process.

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2.3 pocumentalian All activities affecting fuel transportation will be formally identified and documented.

Documentation willinclude the applicable procedures, reviews, and other measures to be l

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2.4 fanttment Control l

Applicable codes, standards, and regulatory requirements will be included in procurement documents. Procurement documents will require contractors or subcontractors to provide appropriate quality assurance controls, which may include, but are not limited to, functions such as inspections, tests, and controls over materials, processes, and nonconformances.

2.4.1 Procedures will be established on a project basis that clearly delinente the sequence of actions to be accomplished in the preparation, review,and control

. of procurement documents.

2.4.2 A review and concurrence of the adequacy of quality and requirements stated in procurement documents will be conducted by the Reactor Administrator.

The review will; determine that quality requirements are correctly stated, inspectable, and controllable; there are adequate acceptance and rejection criteria; and the procurement do M nent has been prepared, reviewed and approved in accordance with Quainty Assurance Program requirements.

2.4.3 -

The review and approval by the Reactor Administrator of procurement

' documents will be documented prior to release.

2.4.4 Procurement documents will identify the applicable 10 CFR and 49 CFR requirements which must be complied with and described in the supplicr's

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quality assurance program. The supplier's quality assurance program or applicable portions thereof will be reviewed and concurred with by the Reactor Administrator prior to initiation of activitics affected by the program.

2.4.5 Procurement documents will contain or reference the design basis technical requirements including the applicable regulatory requirements, material and component identification requirements, drawings, specifications, codes and industrial standards, test and inspection requirements, and special process instructions.

2.4.6 Procurement documents will identify the documentation (e.g., drawings, specifications, procedures, inspection and fabrication plans, inspection and test records, personnel and procedure qualifications, and chemical and physical test results of rnaterial) to be prepared, maintained, and submitted to the Reactor Administrator for review and approval.

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i 2.4.7 Procurement documents will identify those records to be retained, controlled, and maintained by the supplict, aad those delivered to the facility prior to use or installation of the hardware.

2.5 Malerini Corttrol Control of the identification, handling, storage, shipping, cleaning, and preservation of material will be established as deemed necessary by the Reactor Administrator.

2.5.1 Non conforming material or parts will be identified, segregated, and eval.

unted.' Evaluation will be acceptance, repair, rework, or rejection.

2.5.2 Special handling, preservation, storage, cleaning, packaging, and shipping requirements will be established and accomplished by reactor facility per-i sonnel in accordance with predetermined work and inspection instructions.

2.5.3 All necessary shipping will be prepared as required, y

2.5.4 All conditions of the Nuclear Regulatory Commission package approval requirements and the United States Department of Transportation shipping requirements will be satisfied prior to shipment.

2.5.5 Departure time, arrival time and destination of a package will be established and monitored to a degree consistent with safe transportation of the p'ackage.

2.6 Process Control Processing of fuel and containers will be accomplished under controlled conditions in accordance with applicable codes, standards,and specifications. Procedures will be written for those special processes not covered by existing codes or standards.

2,6.1 Special processes such as nondestructive testing, and cleaning will be con-trolled through compliance with written procedures and inspections.

2.6.2 Identification of the inspection, test and status of fuel and containers will be controlled through compliance with written procedures.

2.6.3 Application and removal of status indicators such as tags, labels, and stamps will be controlled through compliance with written procedures.

2.7 Internal Inspections inspection requirements apply to procurement, container, load'ng and vehicle loading and will include, to the applicable extent, the following:

a) Inspection procedures, specifying the characteristics to be inspected, sampling plans, and acceptance criteria.

b) Description of process monitoring action for those situations in which inspection is impossible or disadvantageous.

c) Specification of mandatory points of inspection.

d) Procedures for identifying inspection and test status, so that only items that have passed the required inspections and tests are used. Nonconforming items will be clearly identified.

2.7.1 Inspection program which certifies conformance of quality affecting acti-vities with requirements will be established, documented, and accomplished in accordance with written procedurcs.

2.7.2 Measures will be taken and documented to determine the validity of previous L

inspections performed when measuring or test equipment is found to be out of calibration.

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2.8 Test Control The test program will cover required tests.

Test procedures will specify appropriate prerequisite and monitoring requirements, equipment to be used, personnel training requirements, suitable environmental conditions and provisions for documer.tation as applicable.

2.9 Measuring and Test rnulpment Tools, gages, instruments, and other measuring and testing devices used in fuel shipping activities will be available, and properly calibrated, or adjusted as appropriate at the required intervals.

2.10 Enntsnforming Mattilal and Parts All non conforming fuel shipping material, shall be identified, and segregated from acceptable material.

2.11 Conttilic_.Acilon Significant conditions detrimental to quality of fuel shipping items, such as failure, malfunctions, and deficiencies, shall be promptly identified, the cause determined, and corrective action taken to preclude repetition.

2.12 Quality Assurance _ Records The Quality Assurance Program is based upon (ucumentary evidence of all activities affecting quality of fuel transportation related items.

Records maintained shall include as minimum: Inspection and Test results, results of Quality Assurance reviews, Monitoring actions, Audits, Material analyses, Procedures used in Quality Assurance Program Records.

2.12.1 All records shall be identified and retrievable.

2.12.2 The Reactor Administrator shall maintain the quality assurance records.

2.12.3 The retention period for fuel shipping records shall be for three years following the end of the f act shipping process.

2.13 Andhi Audits shall be performed at the end of the fuel shipping process by a designated independent member or members of the ROC. The audit results shall be reported on the Audit Report form. The report shall be forwarded to the Reactor Administrator, with copics to the Reactor Operations Committec.

2.13.1 Deficient areas will be noted and corrective action taken. Deficient areas will be reaudited on a timely basis to verify implementation or corrective action taken to minimize reoccurrence of deficiencies.

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3 FORMS

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The following forms (QA 1,2,and 3) will be utilized in performance of the Quality Assurance i

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F Procedures for IIEU Shipping from Manhattan College Nuclear Reactor Facility using a DOT 6M type Container Container Procurement Notation is made on form QA 1 that the procurement documentation contains a Certificate of Compliance for the container, and quality assorance program is given for the container, identifying the 10 CFR and 49 CFR compliance requirements, and that record Leeping requirements are specified. Any nonconforming items should be noted on form QA 2.

Shioment Notifiention Reouirements AT least seven days before the shipment is scheduled, the organizations listed below will be notified in writing with the following information: Route of shipment, time and date that shipment will arrive in the area (as exact as possible), truck identification (license number, etc.) material identification (chemical form, weight, description, etc.), destination, identi-fication of Manhattan College as shippers, and emergency numbers to contact. All of the information must be marked " Safeguards Information" on an inside envelope. Any changes in information should be made as soon as possible, with telephonc notification acceptable with changes being only referenced to the original date (i.e. " days before" or

• days after").

Orcanirntions j'

New York State Emergency Management Office Donald A. DeVito, Director State Campus Public Security Building #22 Albany, NY 12226-5000 contact: Mike Trier (518) 457 9972 Pennsylvania Einergency Management Agency P.O. Box 3321 Ilarrisburg, PA 17105 Atta: George M. Johnson, Director (717) 783 3150

$ 1000.00 required for escort Maryland State Police 1201 Reistertown Road Pikesville, MD 21208 3899 Attn: Lt. Col. J.A. Jones (301) 631 4212 Department of Public Safety West Virginia State Police 725 Jefferson Road South Charleston, WV 25309 Attn: Col. W.F, Donohue, Superintendent contact: Gary Morris, Office of Emergency Services (304) 348-5380 Commonwealth of Virginia Department of Emergency Services 310 Turner Road Richmond, VA Attn: Harry Broadas (804) 674 2416 1

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Tennessee Emergency Management Agency

~ 3041 Sideo Drive Nashville, TN _37204

-(615).252 3300-Chief ~

Materials Transfer SG Licensing Branch g.

-Division of Safeguards NMSS U.S. Nuclear Regulatory Commission g

~ Washington, DC 20555

.U.S. Nuclear Regulatory Commission Region i p

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King _ of Prussia, PA 19406 L

(215) 337 5000 O.S. Nuclear Regulatory Commission Region II

-101 Marietta Street, Northwest Suite 2900 Atlanta, G A 30323 (404) 221-4503

References:

10CFR 71.97 Container Acceipt:

Each container will be brought into the Reactor Facility to a predetermined location. The 4

container number will be noted and the container will be visually inspected to be free of non superficial defects and the container closures will be verified to be properly installed, b

Noted on Form A.

EAn exterior and interior wipe of not less than 100 cm2 will be taken and a counts will be-verified to be less than 200 dpm. A 3 count will be verified to be less than 2000 dpm.- Both counts will be entered on Form A.

References:

10 CFR 71.85 Lagdinn of Contai.Du

- A fuel element will be raised from the reactor pool (or alternatively, from the storage container-if the c!cments have been previously removed from the reactor) and the element number verified. The element will be suspended to allow it to dry, placed into a plastic bag, and lowered into the 6M container. All fuel transferrals will be made as reasonably achievable.

E An interior wipe will be taken and the container will then be closed and scaled. All surveys will be made using a monitor which has been verified to have been properly calibrated within the last calendar quarter. A survey of the container sides, top, and bottom will then

-be made and the maximum reading will be noted and verified to be less than 200 mR/hr.

A survey _ of the levels at a radius of 1 meter from the container shall be taken by and verified to be less than 10 mrem /hr, maximum. An external wipe sample will be made. The container will then be moved to a separate location so as not to interfere with the measurements of a different container. All data will be entered on Form B.

Under no circumstances is

- any loaded container to be left unattended or prior to loading onto the truck. All loaded containers are to be stored in a designated and clearly marked area in the reactor facility.

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References:

10 CFR 71.87 10 CFR 71.47 10 CFR 73.67 Prenaration for Shinment The container will be visually inspected and the seals verified, it will be verified that the nut on the securing bolt is against the right hand ring. The container will then be verified to have markings of " Type B" and " USA" as well as the gross container weight (if over 110 lbs.). The container will be verified to have a Radioactive Yellow 111 label on opposite sides of the container, with the activity as calculated and transport index (maximum radiation -

L level at I meter, or 1.0, whichever is larger) marked on the container, Any labels with contrary information present on the container (i.e. " empty" labels) are to be removed or defaced. All labeling is noted on Form D.

References:

_49 CFR 172 Subpart D (marking) 49 CFR 172.403 (labeling) 49 CFR 172.403 (bb)

(transport index) 10 CFR 73.67el (iii)

(visual inspection)

' Y. chicle Loading The truck must first be given a preliminary survey to assure that no radioactive material is present from a previous shipment. Manhattan College Security personnel will be present during all fuel movement from the reactor facility to the truck. One security officer will be stationed at the truck and another wi!! accompany all fuel movements outside of the

-.rcactor.:The truck will be loaded with the scaled containcts secured against any movement

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with the proper tic downs, capable of withstanding at least two (2) times the container weight in vertical force and ten (10) times the weight in horizontal force. The truck will be verified y

to be placarded on four sides with Radioactive" with the piacards verified secured. Noted on Form E.

A survey will be made of the truck using Form F to verify the following radiation levcis:

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<2 mrem /hr maximum in cab or sleeper 10 mrcta/hr maximum 2 meters from surface of truck

< 200 mrem /hr on surface of truck-The driver of the vehicle will then be given the following documents (noted on Form G),

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signed by an officer of the college: Radioactive Shipment and Rcccipt Record, Bill of Lading (Radioactive material Fissile III, N.O.S.), Shipper's declaration of Dangerous Goods, and Shipping and Emergency Instructions, listed below. The liiver's survey meter will be verified to be properly calibrated and in working order. Additionally, the driver's two way com-munication device will be verified to operable.

References:

10 CFR 71.45 (tic downs) 10 CFR 71.45 (rad, levels) t 3

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.f Shipping Instructions to Carriers j

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' Notification in the Event of Delav or Reouired Channes in Route lThe time scheduled for this shipment from departure to arrivalis _

hours. If it becomes' apparent that delays for any reason will increase this time by five (5) hours or more, advise

.j the Manhattan College Nuclear Reactor Facility by phone (212)920 0147,of the new estimated l

l time of arrival and the cause of delay. Any change in route must be cleared with the L-Manhattan College Nuclear Facility before making the change.

r Insneetlon by Authorized Officials en route lThis shipment is proceeding under the full compliance of all known regulations and with the authorization of all cognizant authorities. At each port of entry, this Record and Receipt and the Bill of Lading should be presented for the inspection of the responsible authorities and they are to be permitted access to' the truck and its load for their inspection purposes, f

Under no conditions should anyone except the censignee be permitted to release tic downs, break seals,~ or open containers without having written authorization from the Manhattan College Nuclear Reactor Facility. -

Notification in the Event of Emerecnev Involvine the Shioment

'In the event of emergency involving this shipment, notify:

1.: Local fire and police departments

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2. The Manhattan College Nuclear Reactor Facility i

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(212) 920 0147 or (212) 920 0294 l

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(914) 351 2880, (914) 362 1629 Measures to Taken in Case of Fire or Accident

1. There is no explosion harard from the shipment.

2.- There is reasonable time to take action to avold any radiological hazard in the event of fire.

3. Keep sightsects back from the shipment - 50 yards.

4. Treat as petroleum fire - use foam type blanketing agent of COs extinguishers for

- small fires. Avoid direct water streams that might tend to spread any solid radioactive partiNes.

5. Use gamma radiation survey meters while approaching - not to exceed 10 mR/hr.

Route Log The carrier agrees to stop at a sr.fe stopping place (at least 100 yards away from any building) i periodically.to check tire conditions and other mechanical conditions of the truck and to log time, place, and results of this inspection. Additionally, the carrier is to periodically inspect the general condition of the shipment and tic downs.

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The condition of the tie downs and other data are to be logged. A copy of the log is to be sent on arrival to the Manhattan College Nuclear Reactor Facility,Corlear Avenue,Riverdale, NY 10471.

Additional Reagirements Fissile Class 111 shipments must be kept at least six (6) meters from any other packages bearing Radioactive Material labels.

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NOTE: THIS IS TO BE USED WITH SURVEY MAP A.

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'A - Below box B - Middle of box C-Roof of box I

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COMMENTS:

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Reactor Administrator

Mr c.. y l9tcy ",.:

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_ Radioactive': s hi pment and receipt record

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, Shippers; declaration'_of dangerous goods p

7 Shipping and-emergency: instructions L

Route 1 verified:with driver-s r

p, 1.ccetify that 1 have. received:all the above materials.

m-f i S

1I Drivers Signature g

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D:tbidriver'_s survey meter calibrated:

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4. Driver.'s'._ two-way' communucation opera ble i

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Reactor Administrator s---

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~

,477AddHW7 2 Q,wwxxxxxxxxx.ucxxxxxx.u: crxx.ux.c2xxxxr1Exxxxxxxxxxxx4 i I U.S. NUCLEAR nEGULAToRY COMMISSION neic posies sis CERTIFICATE OF COMPLIANCE h

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FOR RADIOACliVE M ATERIAL.S PACKAGES ff l.

--ctat.eigatt~vusta

, D af vision NQWhea 4fACSAGtTsh 3 tCAIsoN HVWtR S P AGt NUWSta e 101 AL Nywstm e&GE:

5908 12 USA /5908/B( )F 1

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2. P*tausti l

a. Thea certifecate is esswee to cenity that the packaging anc contents coscrit,ec :n item s below. ms.is the arpheaoie safety stancares set fortn in Tive 10.Coce g

St Feoeral Aegutations. Part 71.* Packaging and Transponation of Racicactive Materiat

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I

b. This cenificate se'ss not rehers tne tona'9nor trom comphance with any reoverement of the requistions of tna U.S. Depenment of Transponstion or otner N

E cpoi.canie fe,viatory agencies. incivoing tne go ornm.ni or any cow iry throvsn or into nien ine pactase -in de iranspones.

n I

i l

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tesis ctatie cast is iss.uto o~, t t sisis os a saestv *~*tvsis ataoat or t=t eacmact etsic~ en aerocatio~o titta awo ict~tiricatio~ os aceoat ca ***ucatio~

g a issvio to m.,.w m.

I Babcock & Wilcox Company Nuclear Materials and Eouipment Corporation f

l P.O. Box 785 application dated May 3,1974s as supplemented.

g 1.ynchbu rg s VA 24505 I

I

..ooe st uvuota 71-5908 4

e CoNottiows O

This certificate is concitional upon futfilhng tne reoverements of 10 CFR Pan 71. as apphcabie and the con 0itions specified teiow I

ik s

s.

j (a)

Packaging j

f l

(1) Model No.:

DOT-6M Type B lis s

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(2) Description lt 1

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Metal packaging as described and constructed in accordance with DOT f

l l Specification 6M.

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(b) Contents

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I (1)

Type and fom of matarial il I

I l

f (i)

Solid radioactive materials Wnich will not decompose at temperatures up to 250'F.

Carbide compounds are not authorized; or h) e I

d (ii)

U0 or U0 mixtures in the fom of powder or. compact pellets; or 2

2 I

(iii)

Plutonium nitrate or uranyl nitrate solution in flame sealed

.[

l glass ampoules or screw top plastic vials, each within one or j

more additional plastic viais with taped lids: and within a i

g h)b sealed product can or polyethylene bottle containing a sufficient i

I amount of vemi:ulite to absorb twice the liquid contents present; I

or

k l

!)b I

I I

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it 11 i

8 il

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4 5

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=

J, u_m -

=merAw uKr mmrxxrCACWAX13:rXA An?I*MMATX^ XArrCecer - cer,d]

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i

. ConD1TioNs (continued) i l e-71-5908 j

lp 'ge' 2 - Certificate No. 5908 - Revision flo.12 - Docket No.

Pa

i 4

l, B'

- l (b)

Contents (continued) j (iv)

Plutoniun sources in excess of 20 curies per package must be at p'

least double encapsulated in a metal capsule such that the sources i

'g meet the requirements for special fonn radioactive material.

F i

k Inner and outer capsul'es are individually leak tested during ji fabrication per ANSI N542-1977, procedure A2.2.3 (He pressure h

-bubble test), or equivalent, p

(2) Maximum quantity of material per package and fissile class

!j b

(i)

For the material described in 5.(b)(1)(i), the maximum fissile i

material and maximun hydrogen per package for Fissile Class 1 is

gg, j

as follows:

b i

Maximum fissile material Hydrogen l'aterial p

Fissile per package, per package, Mg Material kiloarams arams f

i U-235 1.6 20 9@

131 Pu 0.9*

11 U-233' O.5 6.4 lR,i-W N

S.

Tecause of the 10 watt thennal decay heat limitation, the limit for per package rust be in the form of metal, metal alloy or reactor

-f j

Pu-238 is 0.02 kilograms.

Plutonium in excess of 20 curies p

.;g-fuel elements.

Q g

B, 4

(ii)

For the material described in 5.(b)(1)(i) the maximec U-235 N

minimum transport index :o be assigned to each pacliage for Fissile

-f loading for uranium bearing materials with an H/X 4 3 and the

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g Class II is as follows:

q g

Idi Ej Maximun

!iinimun ih, 31}.

l Kas U-235 Transoort Index b

3

t.. ;-

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(iii)

For tha interial ocscribed in 5.(b)(1)(ii) the maximum quantity

{

of U-233 is 500 grams at an H/U ratio not to exceed 20 contained g

within a package size of at least 55 gallons.

Each shipment rust g.

be limited as follows:

F The minimum transport index for Fissile 21 ass II.is 2.5 W

The maximum number of pact. ages for Fissile Clas; III is 51.

. y,...

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E

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mg-.ar Ior.srs2a.anauxa.xxA.arxxxxxs:1:s@?xxxxxxxMxxxx.a52MAKK2xxsm m.Djg.

f lI CoNDtTIONS (continued) p l

'n I,.f Page 3 - Certificate No. 5908 - Revision No.12 - Docket No. 71-5908 I.

.5 5.

'F

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(b) Contents (continued)

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1 II (iv)

For the material described in 5.(b)(1)(iii) the maxinum quantity

',N I

of material is not to exceed 20 curies radicactivity and 40 mi of I

'l s olu ti on, Fissile material rust not exceed 10 grams.

i

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y-(v)

For the material described in 5.(bl(1)(iv) the naximun quantity

't

'tl is, of plutonium is 100 curies.

ih lui 6.

Two steel through bolts may be installed between the lid and bottom of the steel

'[

['

drums.

h.y 7.

' Venting may be orovided by a 1-inch diameter hole in the drum lid backed by a T

i

. l A){

minimum 1/2-inch thick Cerafelt refractory pad.

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8.

Maximum decay heat per package nust not exceed 10 watts, j

1 9.

.The package authorized by this certificate is hereby approved for use under the ig general license provisions of 10 CFR 671.12.

b, i>;

10.

Expiration date:

Februa ry 28, 1991.

g

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/

REFERENCES

)

%g l

g Nuclear l'aterials and Equipment Corporation application dated l'ay 3,1974.

Westinghouse Electric Corporation supplement (WAPD-RS(CC)-620) dated tiay 8,1973.

[$

DOE, NR supplements dated: ita rch 28, 1979; and July 19, 1982.

f Allied Chemical Corporation, Report No. ICP-1061 December 1974.

igi Monsanto Research Corooration application dated January 10, 1980.

ig;

_ g FOR THE U.S. NUCLEAR REGULATORY COMt11SSION

E:

)

'E

~'

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Charles E. flac onald, Chief f

n 4'W Transportation Certification Branch F,

%(

.lR Division of Fuel Cycle and j

Material Safety, NiiSS 1

l if l-id s" -

Date:

D O 5 MAS i{N

. )9l 1 1 i i If w. x..... x m =c.,.m m u

...,...w w a. _,.a w n. _ a m m,n. _ _ m a. m. g m L

?

' ;, ;.* d

[ 6R RE0g' UNITED STATES i!.

'n NUCLEAR REGULATORY COMMISSION-

,f,( --

,1 WASHINGTON. D. C. 20555

/

Transportation Certification Branch Acoroval Record

~

Model No. DOT-6ft Type B Packaainc Docket No. 71-5908 Certificate of Compliance No. 5908 has been revised to correct the incomplete "eaual to or less than" sign in Condition 5.(b)(2)(ii) of the c erti fica te.

Yg -

l Charles E. FacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS MAR 0 51986 Date:

,e.

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87TMS/f@7~5'

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MEOHANICAL ENotNEERIHo DEPARTMENT M*an n. sMen

. MANHATTAN COLLEot PARKWAY mvEnoAtt. NEW YORK 10471

, [, h 7Co, D ege

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-._s September 14,1989 U.S. Department of Energy Oak Ridge Operations.-

- Oak Ridge, TN 37831 ATTN: John H. Miller

SUBJECT:

Shipment of Uranium Scrap to Oak Ridge Operations /CSMO (your memo of 8/24/89)

Dear Mr. Miller:

I am providing the following information in response to the questions forwarded with your memo of August 24, 1989:

1-5 We are proposing to send as scrap 15 full fuel elements and I partial fuel element containing high enriched uranium (HEU) fuel that will be removed from the Manhattan College Zero Power Reactor (MCZPR) as part of the DOE's program to replace HEU fuel with LEU fuel in research reactors. Each fuel element consists of 6 concentric cylinders formed by joining 18 curved fuel plates within the grooves of 3 aluminum spacer webs (see attached figure) that are located within an aluminum support cylinder.

The fuel is 92 percent enriched U-235 (8 percent U-238) in a U-Al alloy matrix, with

.a total of 3024 gmt of enriched U-235 in all the fuel elements. The f uct clad is 1100 A1. Uranium density is 0.7 gm/cc. The fissile loading / cylinder, in grams U 235, for each cylinder in a full fuel element is:

Cylinder 1

16.8 gms.

24.0 gms.

2 29.4 gms.

3 36.9 gms.

4 5

43.2 gms.

6 49.7 gms.

Total Loading / element 200 gms.

There are no other metallic, chemical, or organic constituents present within or on the surface of the fuel elements. As described above, the elements are metallic; there will be no liquids present in the shipment.

6.

The fuel elements are being removed from a research reactor that has been made critical for short periods, since March 24,1964, as an educational tool at Manhattan College. In this regard:

3-A.

The material was first irradiated and made critical in the MCZPR on March 24, 1964 for an initial period of 40 minutes. Our records indicate that at maximum the reactor has had an average of I criticality sequence per week within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period since that time. We will conservatively estimate that the reactor was critical at its maximum power of 0.1 watt for the I hr. period, giving a maximum

- burnup/ core of 132.6 w hr (0.0055 MWD) or 8.8 w-hr (0.0004 MWD) average burnup/ element.

Prior to its installation at Manhattan College, the reactor core had been used since 1961 by AMF Atomics to perform short term critical exoeriments in the Pressurized Tube Reactor at the Industrial Reactor Laboratory in Plainsboro, NJ.

There are no records available on the operating history during this 3 year period.

B.

The reactor currently is used in a nuclear engineering course. If the core conversion occurs during the school year it will be made critical for the last time 1-2 weeks prior to conversion; during the school break this period would be 1-12 weeks.

This period is flexible. It will remain critical about I hour.

C.

The neutron fluence rate is approximately 10* ncutrons/cm2 3ee, D.

The maximum beta radiation level (vertical midpoint on surface of fuel) on a fuel element in the region of highest burnup (number 33) in the core is:

Surface 6.0%

1 foot from Surface - 1.25 The maximum gamma radiation level from the same locations is Surface - 4.35 I foot from surface - 0.975 E.

Based on extremely low fuel burnup and surface radiation levels the fuel elements would have only trace (negligible) quantities of fission products and transuranics.

i F.

The fuel elements.do not possess any abnormal or unique radioactive charac-teristics. We have safely handled them, during maintenance operations, in close proximity because of the low radiation levels.

Please let me know if there is any additional information we can provide. We are looking forward to working with you in arranging for the shipment of our material to ORNL.

Sincerely, d

G

/ b %, 6,, $ d ic Robert E. berlin Reactor Administrator ec:

. K. Brown,100 M. Bower,100 i

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. MANHATTAN COLLEGE PARXWAY MECHANICAL ENGINEERING DEPARTMENT L'

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AlVERDALE. NEW YORK 10471 (212: 97H145 November 10,1989 Susan S. Waddle, Chief

.Y-12 Program Management Branch, Y-12 Site Office Department of Energy Oak Ridge Operation P.O. Box 2001 Oak Ridge, TN 37831

SUBJECT:

Reauest For Shipment of Urard n: Scan T',ni M n) artt - C Ilege 1 ank Ridg>:

Operations

Dear Ms. Waddie:

In response to sour letter of '.ctobe N,19F9, we t.rc roviding

e - 7.a3.aformation relative to the transuranic ontent cf thu t.a.al.

Post irradation PU-239 cm.teu f uel :

un* '4WD = 499 p., A f l.'D (1)

Average Burn-up per core (15 f t it ana 1 nart.as fur' element) = 0.005: NWri (2)

Post irradation PU-239 content of 15 full and 1 "arFai fuel alements =

2.; ug(0.oc27 mg )

total (1)1See attachment for supporting calculations (2) See our letter of September 14,1989 Please let me know if any additional information is required. We are looking forward to completing arrangements to ship our scrap fuel elements to ORO.

Sincerely, 1

/

3 h

.)Llb Robert E. Berlin Reactor Administrator

cc:

K. Brown,100 M. Brower bec:

V. Antonetti J.Hu M. Vaillancourt J. Lestingi o

. ~.....

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Calculation of PU-239 Content of Irridusd Birl The following was used to calculate the transuranic (PU-239) content of the Manhattan College spent fuel.

PU 239 content of irradated fuel /MMD =

f gm U238 h oos,- a h f

f r

aas, - o, %

f aas, - a,

aas,- a, %

f

\\ Mis /D >

q

oas, jy,,,

q o

os, j u,,, y a as, j g,23, q

oas, j,,23, absorption cross section (including o,)

where o..,

fission cross section or

=

i..

,f:

residue after step in transformation o...

=

)

and (U ae)p,,-(U23e ) p.3, gms of U ae, gms of U 2

2 238 9a[

(U nas ) pr, - ( U23s)p,,,

1 gm of U as 1 MWD 2

.,l p' qig }

since 1 Atl/D~ l gm u consumption v,

an substituting in (1)

(o... )yn, - 7.68

( o, ),,, - 4.18 (o...),y, - 22 (o,)y,,, - 12 (0 es)ng22, - M (a,)y,,,,-3 (0...),,,3, - 101 1

( o, ),,,,, - 7 4 2 given Pu,3, content / All/ D - 499 p g /, Afi/ D O.

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...w.,.

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DATEld 2R 87 INITIAM

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