ML20215H898
| ML20215H898 | |
| Person / Time | |
|---|---|
| Site: | 07100396, 07100369 |
| Issue date: | 10/31/1986 |
| From: | RENSSELAER POLYTECHNIC INSTITUTE, TROY, NY |
| To: | |
| Shared Package | |
| ML20215H896 | List: |
| References | |
| NUDOCS 8610240217 | |
| Download: ML20215H898 (7) | |
Text
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t RPI QUALITY ASSURANCE PROGRAM J
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Submitted in Accordance with 10CFR 71.12(B) i NRC License No. CX-22 Docket No. 50-225 1
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October 1986 i
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Rensselaer Polytechnic Institute i
Critical Experiments Facility Troy, New York, 12180 8610240217 861 FDR ADOCK 07100 C
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CONTENTS NUMBER SECTION INTRODUCTION 1.
ORGANIZATION 2.
QUALITY ASSURANCE PROGRAM 3.
DESIGN CONTROL 4.
PROCUREMENT CONTROL 5.
INSTRUCTIONS, PROCEDURES, AND DRAWINGS 6.
DOCUMENT' CONTROL 7.
CONTROL OF PURCHASED HATERIAL, EQUIPMENT, AND SERVICES 8.
IDENTIFICATION AND CONTROL OF MATERIALS, PARTS, MfPONENTS 9.
SPECIAL PROCESSES 10.
INSPECTION CONTROL ll.
TEST CONTROL 12.
CONTROL OF MEASURING AND TEST EQUIPMENT 13.
HANDLING, STORAGE, AND SHIPPING 14.
INSPECTION, TEST, AND OPERATING STATUS 15.
CONTROL OF-NONCONFORMING MATERIALS, PARTS, OR COMPONENTS 16.
CORRECTIVE ACTIONS 17.
QUALITY ASSURANCE RECORDS 18.
AUDITS FIGURE I
RPI QUALITY ASSURANCE PROGRAM INTRODUCTION In order to comply with NRC rule of conversion to low enriched uranium (LEU) fuel from highly enriched uranium (HEU) fuel, RPI is now arranging to have the HEU fuel on site, returned to the US Department of Energy (DOE).
The Quality Assurance (QA) Program submitted here is to assist in handling the shipment of SM1-Core 2 MTR fuel plates using DOT-6M 110 gallon drum containers provided by the DOE.
The program under which these containers will be used is based on the following considerations:
(1) RPI possesses 188 HEU f rradiated fuel plates with loadings of 26.62 gm or 25.07 gm of Uranium-235 per plate.
(2) RPI wishes to return these fuel plates to the DOE.
(3) Each plate produces a radiation field of 1 to 4.5 millf rem per. hour at a distance of I cm, without intervening shielding.
(4) This program is limited to the objective (2), the quantity indicated in (1), with the characteristics indicated in (3).
(5) RPI does not design, fabricate, assemble, or test containers, and does not Intend to nrocure any container for ownership or lease to others. This QA Program.is limited to the use of containers provided by the DOE, to accomplish (2). RPI does not intend to rework, repair, maintain or modify the DOE containers.
(6) Transportation will be handled by a DOE SST (transport truck with guards).
The QA Program is submitted pursuant to 10CFR Part 71, paragraphs 71.12 and subpart H.
The Program outline follows Regulatory Guide 7.10 (June 1986) in those parts of Annex 2.that are applicable to use of type B( )F containers.
1.
ORGANIZATION The final responsibility for the Quality Assurance (QA) Program for 10CFR
- Part 71 requirements rests with Rensselaer Polytechnic Institute.
Responsibility for the safe operation of the RPI Reactor Facility is vested
.within the chain of command shown in Figure 1.
The QA Program will be performed within the operating organization.
The Eacility Director is responsible for the overall administration of the program, training and certification, document control and auditing.
The Eacility Supervisor is responsible for handling, storing, shipping, inspection, operating status and record keeping.,_
The Of fice of Radiation and Nuclear Safety (ORNS) will have primary responsibility for monitoring all packaging, and shipping activities with regard to radiation protection.
The Nuclear Safety Review Board (NSRB) is responsible for the audit control of the QA Program.
2.
QUALITY ASSURANCE PROGRAM The scope of the program includes handling, loading, and delivering to a carrier for transport; DOE owned containers for return of irradiated HEU fuel plates to the DOE.
The containers are DOT-6M 110 gallon drums, NRC approved B( )F containers. The quantity of material to be shipped is fixed (188 plates), and the active period of the program will span no nore than a few months.
Quality control will be exercised primarily through the use of written procedures constructed from:
(a) Federal regulatory requirements; (b)
Instructions, procedures, and drawings; and (c) Appilcable partions of the RPI Critical Facility Radiation Protection Procedures. Quality assurance will be ef fected by formatting these procedures as check-lists to be used by the individuals or their designates who are responsible for quality assurance.
3.
DESIGN CONTROL Design activities related to the shipping package are not to be performed by RPl.
The proper design control has been performed by the DOE, owner of the shipping package.
4.
PROCUREMENT CONTROL Procurement activities related to the shipping package are not to be performed by RPI.
The proper procurement document control is the responsibility of the DOE, owner of the shipping package.
5.
INSTRUCTIONS, PROCEDURES, AND DRAWINGS 5.1 Preparation of packaging for use.
The routine detenninations of 10CFR 71.87, where applicable, will be subject to check-list assurance.
5.2 Repairs, rework, and maintenance. The ac tivi t ies repai r, rework, or maintenance are.not to be performed.
Servicing, such as gasket replacement, shall be in accordance with package specifications.
5.3 Loading.
Loading shall be conducted under a plan of suf ficient specificity to identify and account for fuel plates and quantitles conforming to shipping papers and inventory change reports.
Surveys of radiation fields and surface contamination of the package shall be made and recorded.
5.4 Transport of package. Upon delivery of packages to a nae SST (transport truck with guards) for transport, the condition of the pic' cage as evidenced by visual inspection will be noted, the seals and labels vril be recorded with the package identification by model and IIcense 1
re3 steation number.
A check-list procedure will be used.
6.
DOCUMENT CONTROL
-Control shall be exercised over the following documents:
(1) Document check-list (2) Operating procedures (3) Inspection procedures (4) Loading plans (5) Documents relating to package certification, QC, and QA (6) Radiation survey results
. (7) Shipping papers Procedures and check-lists, and changes thereto are to be approved by either the Reactor Supervisor or the Chairman of the NSRB, or their respective designates.
7.
CONTROL OF PURCHASED HATERIAL, EQUIPMENT AND SERVICES No special purpose materials or equipment are to be purchased for this activity.
Services such as container off-loading, on-loading, and carrier transport will be procured via normal RPI procedures. -
8.'
IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND COMPONErffS No materials, parts or components are to be identified or controlled for this activity, except those ' mentioned ~1n Section 5.2.
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SPECIAL PROCESSES No special processes are to be undertaken under this program.
i 10.
INSPECTION CONTROL 10.1 Receipt Inspection.
Inadequacely identified packaging, or packaging which deviates significantly from. certifications, drawings, or specifications, will not be used unless or until corrected.
10.2 Maintenance. Maintenance other than prescribed servicing will not be performed by RPI.
j 10.3 Final Inspection.
Check-lists will be established to ensure that:
(1) Packages are properly assembled.
(2) Moderators and/or neutron absorbers are present if required.
(3) Shipping papers are properly completed.
(4) Packages and transport vehicle are conspicuously and durably nacked as required by DOT.
(5) Pre-loading and post-loading surveys have been coupleted.
f Inspection is to be certified by the Reactor Supervisor or the Radiation Safety Officer or their designated alternate.
11.
TEST CONTROL 11.1 Use of packages. Tests permitted, recommendel, or specified by package licensee will be used to establish a QA check-list. ;
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f 11.2 Radiation survey.
Radiation survey results are to be cotapiled and records maintained by the RPI Radiation Safety Office.
12.
CONTROL OF MEASURING AND TEST EQUIPMENT As a user, RPI does not expect to use gauges, fixtures, reference standards, or other devices used to measure product (container) j.
characteristics.
Radiation survey equipment shall be maintained and calibrated in accordance with normal procedures of the RPI Radiation Safety Office.
13.
HANDLING. STORAGE. AND SHIPPING 13.1 Handling and storage.
Special handling and lif ting e<gulpment will be used in accordance with equipment specified or provided by the package IIcensee, and according to conditions identified in a certificate of compliance as well as instructions provided by the package licensee.
See Sections 4, 5, and 6.
Containers will be used promptly and returned to package licensee; they will not be placed in storage.
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13.2 Preparation for release and shipment. Measures will be instituted 4
to ensure that:
(1) Cavities are dry.
(2) Specified operations, inspections, and tests are to be arified
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by check-list.
i (3) The Reactor Supervisor is responsible for the observation of NRC and DOT requirements, and for the preparation of the shi pping ' papers.
l (4) Quality assurance will be performed with check-lists.
14.
INSPECTION TEST. AND OPERATING STATUS l
Status is to be tracked by a master check-list that acknowledges check off of Individual check-list completion.
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CONTROL OF NONCONFORMING MATERIALS. PARTS OR COMPONENTS J
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No applicable.
Rework, repair, maintenance, or modification are not to be undertaken by RPI.
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CORRECTIVE ACTIONS 16.1 Re por ting.
It is the responsibility of the RPI QC/QA to report conditions detrimental to quality to the package licensee.
16.2 Closeout.
RPI as a user will deem closeout completed upon (a) correction or the condition by the package licensee, or (b) package licensee's withdrawal of the container from service.
17.
QUALITY ASSURANCE RECORDS i
Records, showing evidence of delivery of packages to a DOE SST (transport j
truck with guards) under NRC and DOT requirements shall be retained for. a I
j minimum of one year, except for SNM transfer and inventory records retained j
for the duration of NRC licensing authority over the RPI Critical M*periments Facility. Records are to be retained by the RPI Radiation Safety Office, i
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I which is also responsible for maintaining all RPI records related to personnel exposures, radioactive material releases and shipment, and radiation protection matters related to the RPI Critical Facility.
18.
AUDITS The activity covered by this QA Program is a short-term effort. The Nuclear Safety Review Board (NSRB) will perform an audit at the end of the fuel transfer effort, to determine the adequacy of the records generated under this program.
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PROVOST RADIATION AND VICE PROVOST NUCLEAR SAFETY COMMITTEE I
DEAN, SCHOOL OF F"
ENGINEERING DIRECTOR
,d OFFICE OF RADIATION AND NUCLEAR SAFETY "]
CHAIRMAN, DEPT.
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OF NUCLEAR l
ENGINEERING l
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DIRECTOR, RPI f ~ ~ ~ ~ ""
CRITICAL FACILITY I
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SUPERVISOR OF b_____
CRITICAL FACILITY NUCLEAR SAFETY AND RADIATION REVIEW BOARD SAFETY OFFICE i
LICENSED SENIOR OPERATOR LICENSED OPERATOR j
l Figure 1 Rensselaer Polytechnic Institute critical facility organization
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