ML19275A561

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QA Plan for Shipment of R-3 Fuel.
ML19275A561
Person / Time
Site: Duane Arnold, North Carolina State University
Issue date: 09/11/1979
From:
North Carolina State University, RALEIGH, NC
To:
Shared Package
ML19275A560 List:
References
NUDOCS 7910040645
Download: ML19275A561 (10)


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QUALTIY ASSURANCE PLAN FOR SHIPMENT OF THE R-3 FUEL HORTH CAROLINA STATE 'JNIVERSITY AT RALEIGH P.O. BOX 5636 RALEIGH, h.C. 27650 DEPARTMENT OF NUCLEAR ENGINEERIf!G BURLINGT0ft ENGINEERING LABORATORIES ROOM 1110 i N ISSUED BY: N /b Jk [7f QA ADMINISTRATOR 'DATE 1101 215 1910040 g y 1c^ 2.3

9 Revision Sheet Revision Date Reviewed and Signed and Inserted Numt.er Approved by Distributed RPC by QA Admin.

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TABLE OF CONTENTS Revision Sheet i Table of Contents 11

1. Quality Assurance Plan 1 1.1 Purpose 1 1.2 Applicability 1 1.3 Organization and Training 1 TABLE I Quality Assurance Organization 3 1.4 Reference 4 1.5 Procedures and Implementation 4 1.6 Document Control 5 1.7 Inspection, Handling, Loading and Shipping 6 1.8 Maintenance. Test and Operating Status 6 1.9 Quality Assurance Records 6 1.10 Audits 7 i

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R-3 RESEARCH REACTOR SHIPMENT OF SPENT FUEL

1. Quality Assurance Plan 1.1. Purpose The Department of Nuclear Engineering, North Carolina State University at Raleigh (NCSU) establishes this Quality Assurance (QA) Plan to conform with the requirements of 10CFR 71.51 as it applies to the shipment of the R-3 Research Reactor irradiated fuel. The objective of the QA Plan is to formulate the procedure for implementing a functional QA pro-gram and to assign responsibility for its accomplishment and for evaluating (auditing) its effectiveness.

In establishing this QA Plan, NCSU commits itself to the conscientious implementation of the QA plan described.

1.2. Applicability The QA Plan applies to containers owned by another party and utilized by NCSU to ship the R-3 spent fuel. Design, fab-rication, testing, and maintenance of shipping packages shall i not be conducted under this QA Plan. These functions shall be performed by the owners of the shipping packages under their applicable QA programs. Furthermore, this NCSU QA Plan applies only to shipping packages which have been reviewed, licensed, and certified by the U.S. Nuclear Regulatory Commission, per applicable regulations. i 1.3. Organization and Training i

This QA Plan is implemented through the organization shown in Table 1, which is licensed to possess but not to operate the R-3 research reactor facility (License No. R-63). The React-or Health Physicist is designated as the QA Plan Administrator, the person specifically responsible for the overall implementa-tion of the QA Plan, including assignment of personnel, training and certification of personnel, and initiation and control of documentation.

The NCSU Radiation Protection Council has the responsiblity to develop and irplement procedures for auditing the QA program.

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I The QA Administrator for the R-3 fuel shipment reports I directly to the Head, Department of Nuclear Engineering, NCSU l for the purposes of this shipment. In this capacity, he is authorized, and is organizationally free, to identify quality and safety problems; to initiate, recommend or provide sol"* ions to the identified problems; and to verify the implementation of such solutions.

The Nuclear Operations Administrator (NOA), in addition ,

to his principal responsibilities regarding the PULSTAR reactor, :i has cognizance of the R-3 Facility to assure compliance with l the R-63 license "to possess but not to operate" this facility.

The Reactor Supervisor (RS), who reports directly to the NOA, f

mainta2ns routine surveillance of the R-3 Facility in addition to his principal duties which relate to the PULSTAR reactor. The Reactor Health Physicist, in addition to his duties concerning I the PULSTAR reactor, maintains the health physics instrumentation on the R-3 Facility.

The Radiation Protection Council (RPC), NCSU, currently i provides a review and audit of all nuclear activities on Campus.

The NCSU Administration will expect this Council to provide i similar (review and audit) services of the QA Program for the shipment of the R-3 fuel.

The Reactor Safeguards Advisory Committee serves as a  !

permanent committee to the RPC for the purpose of conducting in-  !

dependent appraisals of reacter precedures. This Committee may be designated by the RPC as the "QA Audit Group" for the R-3 fuel shipment.

The quallfication of the individual organizational positions are discussed below:

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a. The NOA, as a minimum, must have at least five years  ;

of reactor operating experience, including two years of super- l visory reactor ex>erience. The incumbent NOA has been a senior i reactor operator on the )ULSTAR reacter for six years and prior -

I to the PULSTAR he was A and senior --rator on the R-3 reactor. I i

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. i TABLE I l

QUALITY ASSURANCE ORGANIZATION for the R-3 REACTOR Chancellor, NCSU  ;

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Dea'n of Radia' tion  !

Engineering Protection l Council l

l Head, Reactor Radiation Qual ty Nuclear f

Safeguards Protection Assurance Engineering Advisory Office Audit

  • Dept. Group Group Quality Nucl' ear ' #

' "E'"

t Assurance Operations .

Adninistrator' s Administrator f

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.- - -Reactor Reactor Applications Health .

Engineer Physicist' I l

NOTE: The R-63 license is "to possess but not to operate" the R-3, 10 KW research reactor. The " solid" lines indicate the positions having responsibilities concerning the shipment of the R-3 fuel; and the

" dashed lines" show positions in the current PULSTAR organi::stion having respos'sibilities for compliance with the R-63 license conditions.

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b. The Reactor Supervisor shall be a licensed senior reactor operator. The incumbent Reactor Supervisor has been in this position since PULSTAR start-up in September 1973 (six years) and immediately prior to his current position, he was senior reactor operator and reactor supervisor on the R-3 reactor.
c. The Reactor Health Physicist (RHP) shall be able to satisfy the qualifications of a Certified Health Physicist or j is equivalently qualified. The incumbent RHP has been in this position the past six years; and was a Senior Health Physicist at Goddard Space Flight Center, Beltsville, Md.
d. The members (10) of the Radiation Protection Council are members of the general faculty, NCSU, and represent a broad spectrum of scientific disciplines representing the field of nuclear science and the related fields of physical and biologi-cal sciences. The individual members are actively engaged in teaching and research involving the use of radiuactive materials and/or ionizing radia+, ion producing devices.

' e. The members (3) of the Reactor Safeguards Advisory Group (RSAG) are appointed by the Chancellor, NCSU, upon re-commendation of the RPC. The qualification for RSAG membership are comparable to "d" above.

1.4 References

a. 10CFR 71
b. ANSI N 402-1976 (15.8)
c. QA Programs for Package Owners Facilities (BMI-1, Battelle Columbus Laboratories)
d. NRC Docket No. 50-111, License R-63 1.5 Procedures and Imolementation j The objective of this QA Plan is to assure that the packaging and shipment of the R-3 reactor spent fuel is safely accomplished according to all applicable regulations, and in a t

manner intended,to preclude any excessive or unauthorized radia- i tion exposure of the personnel involved, or of the general public.

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I These objectives shall be achieved through the following:

a. Written procedures to assure that the shipping packages to be used have been designed, fabricated, tested, and maintained according to the engineering and quality control procedures of the approved designs.
b. Written procedures which describe the loading of fuel into the packages.
c. Written procedures which define and list the required radiation surveys and surveillanca of the loaded shipping packages.
d. Written procedures which outline the training and certification of personnel required to implement the QA program adequately.
e. Written procedures which describe and define the audit-ing required to determine that the QA Plan is being implemented fully, and to determine the effectiveness of the QA Plan, and to prseide NCSU Administration with advice and recommendations for improving the pecgram, or for correcting deficiencies in the program.

1.6 ~ Document Control All documents (written procedures, checklists, drawings, i

etc.) related or pertaining to the shipment of the R-3 fuel will be controlled through the use of written procedures. Certain documents may be originated by and obtained from the owner of the shipping package; others may be prepared at NCSU. Whatever the original source of the subject document, it shall be approved by the procedures of the originating organization; and any changes, alterations or modificatiens thereto shall be reviewed and approved by the process and/or procedures of the criginating organization. In regards to documents originating at NCSU, the QA Administrator shall initiate the document and changes thereto and the NCSU Radiation Protection Council shall review and approve the document and/or subsequent changes.

The Quality Assurance Administrator will insure that all QA functions are accomplished in accordance with the current editions of these documents, including all approved modifications and amendments.

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1.7 Inspection. Handling, Loading and Shioping Upon receipt of the shipping package, initially and for subsequent reuse, an inspection of the packsge will be made to conclusively identify the item as the one described in the owner's prepared documents and approved / licensed for the use intended; that the package is sound, undamaged and complies with the licensed conditions, and that the package is radio'.ogically acceptable for use.

Writt n procedures for safe handling, loading, and shipping of packages for certain special nuclear material will be followed.

Shipments will be made only if all tests, certifications, accept-ances, final inspections, and radiation surveys have been com-pleted and documented. Test and survey instrumentation will be operated and calibrated according to specifications. Written instructions will be provided for all of the above operations.

1.8 Maintenance, Test and coeratine status Written procedures will be maintained by the owner of the i

shipping package by which he accomplishes both preventative and corrective maintenance, testing, and certification to the user of the operational status of the package. These procedures will include the specifications of the operating parameters, error limits, and celibration of test instrumentation. Status and disposition of any non-conforming components, packages, cr com-ponent functions will be maintained currently by written proced-ures and documentation.

1.9 Quality Assurance Records Records will be maintained of package approvals and cert-ifications (including references and drawings), inspections or tests, logs of utilization, training and qualifications of person-nel, and contents of shipments. Written descriptions and draw-ings of auxiliary equipment, and applicable procedores also will be maintained. These records will be maintained for at lea =t 2 years following fuel shipment.

All records will be maintained according to written pro-cedures, and will be identifiable and retrievable. A list of records with their storage locations, will be maintained by the

p. QA Program Administrator.

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1.10 Audits Management will establish schedules and procedures for auditing the QA program using written check sheets. Results of audits -tll be reported to management in writing. Audit reports will be evaluated and deficiencies discussed and corrected. A ,

written record of each audit will be maintained as part of the QA files.

Members of the audit team will have no line responsibility for the activity being audited.

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