ML20205B349
| ML20205B349 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 10/20/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205B227 | List: |
| References | |
| NUDOCS 8810260226 | |
| Download: ML20205B349 (5) | |
Text
,
- "go UNITED STATES
!' g NUCLEAR REGULATORY COMMISSION 5 WA$HINGTON, D. C. 20555
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'S, e . . . . ,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 16 TO FA_CILITY OPERATING LICENSE NO. R-103 UNIVERSITY OF MISSOURI - COLUMBIA DOCKET N0. 50-186
1.0 INTRODUCTION
By letters dated February 26, 1982, November 22, 1985, and May 20, 1988 the University of Missourt at Columbia requested changes to Facility Operating License No. R-103 and to Appendix A of the License, Technical Specifications for the University of Missouri Research Reactor (MURR). The requested changes would (1) authorize an increase in the amount of depleted uranium that may be received, possessed, and used from 20 kg. to 50 kg., (2) authorize the receipt, p(3) remove the requirement that the pool cooling system pumps operate inosse parallel, (4) update the facility organizational structure, and (5) correct ,
a typographical error and replace references to the AEC with NRC.
4 2.0 EVALVATION 2.1 Changes in the MURR Organizational Structure
, The University of Missouri at Columbia has eliminated the position of Associate Vice President for Academic Affairs. The Vice President of '
Academic Affairs has assumed the duties of the associate vice president. The Reactor Advisory Connittee and the Radiation Safety Officer will now report to the Vice President of Academic Affairs. This action does not affect the day-to-day operation of the facility and will increase the effectiveness of university management by allowing responsibility and oversight for the facility to rest with one vice president where before three people (university president, vice president, and associate vice president) were involved.
2.2 Administrative Changes Amendment No. 4 to the license dated September 7,1976 changed the title of "Reactor Supervisor" to "Reactor Manager." This was a change in title only.
The title of Reactor Supervisor was inadvertently not changed to Reactor
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Manager in Technical Specification 4.2.d. This oversight is corrected. Due to a typographica error, the bases for Technical Specification 5.1, which concerns containment building leak rate, incorrectly references Technical o2g2g$3 s g$6 0
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. Specification 4.2.a instead of Technical Specification 4.2.c which is the correct reference to building leak rate design limits. This error is corrected. Technical Specification 6.1.e, 6.1.f, and 6.1.h refer to the AEC. This is updated to read NRC. Each of these changes is administrative in nature and has no effect on the operation of the facility.
2.3 Changes in Lineup of pool System Pumps The reactor has two major cooling systems; a pressurized primary system which cools the reactor core and a pool cooling system which cools the pool in which the reactor pressure vessel is located. The pool cooling system has two Worthington 6-CNG-104 centrifugal pumps that are arranged in parallel.
The requirement that both pumps operate simultaneously was placed in the technical specifications in 1974 when the pool heat exchangers were rearranged and a second pump was added to the system in connection with doubling the facility power level to the current 10 Mw(t). There was a question as to whether one pump alone had the capacity to meet the increased technical t specifications minimum pool cooling flow requirement. Testing has shown that pump capacity is such that either pump functioning alone could provide the minimum technical specification flow through each pool heat exchanger of 425 gpm (850 gpm total minimum pool cooling system flow) and meet the requirements for differential pressure across the reactor reflector. This change will not affect the tech 11 cal specifications' scram set points. This change will not affect the ability to cool the reactor core because core cooling is an independent system. The pool cooling system is not required to provide cooling in the event of a primary pump failure or loss of coolant accident.
This change will increase operational flexibility by allowing the reactor to remain in operation if one pump needs to be removed from service for maintenance. l l
2.4 Addition to License of Sealed Plutonium Rod '
The licensee has proposed to receive, possess, and use up to 40 grams of plutonium enriched to 90% plutonium-242 (nonfissile isotope) in the form.of a rod sealed in a stainless steel can for use in connection with the reactor.
The rod is to be used for studies with neutron diffraction of the crystal structure and magnetic phases of plutonium in the temperature range 20 to 650 degrees K. The rod will be used external to the biological shield and will have no reactivity affect on the reactor. When not in use, the rod will be kept in a Controlled Access Area (CAA). The material will be used in accord-
! ance with the Special Nuclear Material provisions of MURR's NRC-approved physical security plan. The material will be used in accordance with HURR health physics procedures. We conclude, therefore, that the use of the
>1utonium as described above will not affect the safety of the facility or the i sealth and safety of the public. !
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2 Specification 4.2.a instead of Technical Specification 4.2.c which is the correct reference to building leak rate design limi+s. This error is corrected. Technical Specification 6.1.e. 6.1.f, and 6.1.h refer to the AEC. This is updated to read NRC. Each of these changes is administrative in nature and has no effect on the operation of the facility.
2.3 Changes in Lineup of Pool System Pcmps The reactor has two major cooling systees; a pressurized primary system which cools the reactor core and a pool cooling system which cools the pool in i which the reactor pressure vessel is located. The pool cooling system has two Worthington 6-CNG-104 centrifugal pumps that are arranged in parallel. l (he requirement that both pumps operate simultaneously was placed in the technical specifications in 1974 when the pool heat exchargers were rearranged and a second pump was added to the system in connection with doubling the facility power level to the current 10 Mw(t). There was a question as to whether one pump alone had the capacity to meet the increased tecnnical specificationsXminimum pool cooling flow requirement. Testing has shown that pump cdpacity is such that either pump functioning alone could provide the minimum technical specification flow through each pool heat exchanger of 425 gpm (850 gpm total minimum pool cooling system flow) cnd meet the requirements for differential pressure across the reactor reflector. This change will not affect the technical specifications' scram set points. This change will not -
affect the ability to cool the reactor core because core cooling is an ;
independent system. The pool cooling system is not required to provide cooling in the event of a primary pump failure or loss of coolant accident.
This change will increase operational flexibility by allowing the reactor tc remain in operation if one pump needs to be removed from service for maintenance.
2.4 Addition to License of Sealed Plutonium Rod The licensee has proposed to receive, possess, and use up to 40 grams of plutonium enriched to 90% plutonium-242 (nonfissile isotope) in the form of a rod sealed in a stainless steel can for use in connection with the reactor.
The rod is to be used for studies with neutron diffraction of the crystal structure and magnetic phases of plutonium in the temperature range 20.to 650 degrees K. The rod will be used external to the biological shield and will have no reactivity affect on the reactor. When not in use, the rod will be kept in a Controlled Access Area (CAA). The material will be used in accord-ence with the Special Nuclear Material provisions of MURR's NRC-approved physical security plan. The material will be used in accordance with MURR health physics procedures. We conclude, therefore, that the use of the plutonium as described above will not affect the safety of the facility or the health and safety uf the public.
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2.5 Increase in Depleted Uranium The licensee has proposed to receive, possess, and use up to 50 kilograms of depleted uranium for instructional and experimental purposes. This J represents an increase of 30 k'lograms over the current limit of 20 !
kilograms. The depleted uranium is used in connection with filtered beam ;
research for neutron capture therapy. The licensee is approaching the .
4 current 20 kilogram limit and desires to obtain additional filter pieces in !
the future. This material is to be used outside the reactor biological shield and will have no affect on the reactivity of the reactor. The material will be used in accordance with MURR health physics procedures. We conclude, therefore, that increasing the amount of depleted uranium to be used as described above to 50 kilograms will not affect the safety of the i facility or the health and safety of the public.
3.0 ENVIRONMENTAL CONSIDERATION
3.1 Changes in the MURR Organizational Structure and Administrative Changes i This section of the amendment involves changes in the category of record- !
keeping, reporting, and administrative procedures and requirements. ;
1 Accordingly, this section of the amendment meets the eligibility criteria for i categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR l 51.22(b),noenvironmentalimpactstatementorenvironmentalassessmentneed !
be prepared in connection wit 1 the issuance of this section of the amendment. I i
3.2 Changes in Lineup of Pool System Pumps, Addition to License of Seale.1 !
Plutonium Rod and Increase in Depleted Uranium l
This section of the amendment involves changes in the installation or use of !
facility components located within the restricted area aa, defined in 10 CFR Part 20 and changes in inspection and surveillance requirements. The staff has determined that the amendment involves (1) no significant hazards
' consideration, (2) no significant increase in the amounts, and no significant ,
change in the types, of any effluents that may be released offsite, and (3) l there is no significant increase in individual or cumulative occupational l
^ radiation exposure. Accordingly, this amendment meets the eligibility l criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant :
to 10 CFR 51.22(b), no environmental impact statement or environmental !
assessment need be prepared in connection with the issuance of this amendment. ,
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4.0 CONCLUSION
4 The staff has concluded, based on the considerations discussed above, !
that: (1) because the amendment does not involve a significant increase *
- in the probability or consequences of accidents previously evaluated, or i
create the possibility of a new or different kind of accident from any
- accident previously evaluated, and does not involve a significant !
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4- l reduct',on in a margin of safety, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the proposed activities, and (3) public will not be such activities willendangered by the be conducted fr.
compliance with the Commission's regulations and the issuarce of this amendment will not be inimical to the common defense and security or the health and safety of the public.
Principal Contributor: Alexander Adams, Jr. ,
Dated: October 20, 1988 1