ML19324B624
| ML19324B624 | |
| Person / Time | |
|---|---|
| Site: | 05000262 |
| Issue date: | 11/01/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19324B621 | List: |
| References | |
| NUDOCS 8911070198 | |
| Download: ML19324B624 (5) | |
Text
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h SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPp0RTING AMENDMENT L 2_TO j
FACILITY LICENSE,ij0n d O9
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R BRIGHAM YOUNG UN!YERSITY DOCKELN0.50y62 j
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1.0 INTRODUCTION
Brigham Young University (BYU) submitted an application, pursuant to 10 CFR I
50.90, for a change of status of their Facility License from operating to possession-only for the Atomics International Type L.77 homogeneous solution i
research reactor on May 22, 1987, as supplemented on September 29 1987, March 17, 1988, April 24, 1989, and June 12, 1989. The application included a i
description of the current facility status and revised technical specifications, i
The licensee has requested an exemption from the req)uirement to maintain in effect an emergency plan pursuant to 10 CFR 50.54(q.
The licensee has also requested that the requirement for maintaining a Physical Security Plan be i
deleted from the license.
The basis of the requests is that the reactor feel has been removed from the site.
2.0 TACILITY STATUS i
The uranyl sulfate fuel has been unloaded from the reactor and returned to its owner, the Department of Energy. An 0.5 curie plutonium-teryllium (Pu-Be)
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neutron source remains on site. This source will either be returned to the i
Department of Energy or transferred to a Special Nuclear Material license at a later date. Until that date, the source will be stored in the reactor. The reactor will normally have all access covers and ports closed and locked.
The reactor may be opened for maintenance, to meet surveillance requirements, i
or to perform measurements to develop a decossnissioning plan.
The reactor configuration during possession-only status will be as follows:
the empty stainless steel core tank, gas recombiner, three solic shield l
regions, reactor shield tank, exposure facilities, instrumentation thimbles and two uncompensated ionization chambers, safety-control rods, and rod drive mechanismsshallremaininstalled(Seefigures1and2). The control console remains on site but has been disconnected from the reactor.
To reduce the l
potential for corrcsion, the water in the reactor shield tank will be disposed of in accordance with 10 CFR 20.303 after the Pu-Be source is removed from the reactor.
l 891107019e e921or r
PDR ADOCK 05000262 P
PDC.
The license, including the technical specifications, has been nodifiec to reflect the possession only status. Technical spe:ifications addressing perfortnance, softty, surveillance end reporting related to reactor operation have been deleted. Technical specifications addressing monitoring and surveillance, staff ano public safety, organization, and related reporting requirerents have been retained.
3 0 EVALUATION 1
Removal and shipment off site of the reactor fuel assures that the reactor cannot be operated. Access covers and ports shall remin closed and lockoo when unattended by the facility staff. The three solid shields that surround the reactor tank and the water in the reactor shield tank will provide adequate shielcing for the Pu-Be source and provide a containment barrier for any trace radioactivity present.
Residue contamination levels and radiation fields are very low and present no hazard to the steff or the public.
The rtactor roem shall remain locked at any time authorized personnel are not present. The revised technical specifications reflect the possession-only status of the reactor facility and will continue to assure the health and safety of the reactor staff, the public and the environment. The amended technicalspecificationsincluderadiatIonmonitoring,surveillanceofthe shutdown reactor, and administrative functions.
The staff concludes that the atenced license and technical specifications will continue to assure that the various activities permitted under the possession-only license status will be conducted without significant risk to the health and safety of onsite i
personnel or the public or to the environment.
The licensee has requested to be relievtd from the requirement of maintaining l
4 physical security plan. The only Special Nuclear Material remaining in the I
reactor building is a Pu-Be source which has seven grams of contained pursuant to 10 CFR 73.67(b) plutonium is exempt from physical protection plutonium. This amount of i
(1)(11). Therefore, the staff concludes that the Itcenset is not required to maintain a physical security plan in accordance with the provisions of 10 CFR 50.34(c). Access control to tht facility shall be governed by the technical specifications.
The licensee has requested pursuant to 10 CFR 50.12(a)(2)(11) that a spectfic exemption be grantee to 10 CFR 50.54(q) which requires that a non-power reactor shall follow and maintain in effect an energency plan. The radioactive material remaining at the reactor f acility consists of small amounts of activated byproduct material and the Pu-Be source. The remaining radioactive material is in solid form and there is no credible scenario in which radioactive material could be dispersed into the air. This assures that the radiological emergencies addressed by the Emergency Plan can not occur. The technical specifications require that emergency procedures be in effect for the facilit. The staff finds that granting a specific exemption under 10 CFR 50.12(a)(2)y(11)isacceptable. This special exemption is authorized by law, will not present an undue risk to the public health and safety, and is consistent with the conenon defense and security ano the special circumstance of 10 CFR 50.12(a)(2)(11) exists, i.e. application of the reguletion in the particular circunistance is not necessary to achieve the unoerlaying purpose of the rule.
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l l 4.0 [Ny!RONMENTAl. CONSIDERATION f
This amendment involves changes in the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and changes in inspection and surveillance requirements.
The staff has detemined l
that the amendment involves no significant hazards consideration (as discussed below), no significant change in the types or significant increase in any effluents that may be released offsite and there is no significant increase in individual or cumulative occupational radiation exposure. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in i
10CFR51.22(c)(g). Pursuant to 10 CTR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
l 5.0 CONCLU$10N
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The staff concludes, that amending this license to a possession-only status is f
appropriate.
The staff has further concluded, based on the considerations discussed above, that:
(1) because the amendment does not involve a significant s
in. crease in the probability or consequences of an accident previously evaluated, or create the possibility of a new or different kind of accident from any j
accident previously evaluated, br involved a significant reduction in a mergin i
of safety, the amendment does not involve a si nificant harards consideration (2) there is reasonable assurance that the het th and safety of the public will i
not be endangered by the proposed activities, cnd (3) such activities will be conducted in compliance with the Comission's regvlations and the issuance of this amendment will not be inimical to the common defense and security nor to the health and safety of the public, i
i' Principal Contributor: Alexander Adams, Jr.
Dated:
November 1, 1989 l
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