ML20046C617
| ML20046C617 | |
| Person / Time | |
|---|---|
| Site: | Kansas State University |
| Issue date: | 07/20/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20046C606 | List: |
| References | |
| NUDOCS 9308110229 | |
| Download: ML20046C617 (3) | |
Text
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/p mcg'o, UNITED STATES
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i SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 9 TO FACILITY OPERATING LICENSE NO. R-88 r
KANSAS STATE UNIVERSITY DOCKET N0. 50-188 I.0 INTRODUCTION i
By letter dated July 14, 1993, Kansas State University (the licensee) requested that their Technical Specifications (TS) be revised to reflect a different interlocking arrangement for transient rod operation in the steady state mode. The licensee is installing an operating console that was previously in service at the U.S. Geological Survey TRIGA reactor in Denver, Colorado and this console has a different interlocking scheme than previously used at Kansas State, but achieves the same system control.
2.0 EVALUATION The present TS in Table II, page 9, item 3, stipulates that, while in the steady state mode of operation the transient rod will not be supplied with compressed air unless the regulating rod and shim rods (2) are fully inserted.
This interlocking arrangement precludes an inadvertent fast withdrawal of the transient rod with the regulating and shim rods withdrawn.
The new console interlocking arrangement achieves the same result but with a different interlocking arrangement. The new console operates as follows when the steady state mode of operation is switched on. Compressed air cannot be applied to the transient rod unless the following actions have taken place. A shock absorber, located on the bridge above the reactor tank, is moved t
4 vertically, by motor, to a fully down position. Compressed air is applied to hold a piston, connected to the control rod, in contact with the shock absorber. When the shock absorber is down, application of air does not move the rod and there is no reactivity effect. The shock absorber is then moved i
upward, by motor, thus moving the control rod itself to some position determined by the reactor operator. Therefore, the transient rod, while in the steady state mode of operation, cannot be pulsed _by compressed air to give an inadvertent fast withdrawal of the transient rod with the regulating rod and shim rods withdrawn.
The ' ff finds this interlock arrangement acceptable and notes that it t previously been used at the U.S. Geological Survey.
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3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves changes in the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20, i
The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of 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 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 t
of this amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
l (1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously evaluated, or create the possibility of a new or different kind of accident from any accident previously evaluated, and does not involve a significant reduction in a margin of safety, the amendment does not involve a significant hazards consideration, t
(2) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed activities, and (3) such activities 3
will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or the health and safety of the public.
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Principal Contributor: Theodore S. Michaels Date: July 20, 1993 I
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July 20, 1993 l
Docket No. 50- 188 Dr. Richard E. Faw, Director-l Nuclear Reactor Facility 3
Department of Nuclear Engineering Ward Hall Kansas State University Manhattan, Kansas 66506
Dear Dr. Faw:
SUBJECT:
ISSUANCE OF AMENDMENT N0. 8 TO FACILITY OPERATING LICENSE NO. R KANSAS STATE UNIVERSITY RESEARCH REACTOR The Commission has issued-the enclosed Amendment No. 8 to Facility Operating License No. R-88 for the Kansas State University Research Reactor. The amendment consists of changes to the Technical Specifications (TS) in response i
to your submittal dated July 14, 1993.
% TS to restate the interlock requirements for the i
The amendment rev d transient rod in a
-Ady state mode due to the installation of the t
U.S. Geological Survey control console.
l A copy of the related Safety Evaluation supporting Amendment No. 8 is enclosed.
Sincerely, Original signed by:
I Theodore S. Michaels, Sr. Project Manager-Non-Power Reactors and Decommissioning 1
Project Directorate Division of Operating Reactor Support j
Office of Nuclear Reactor Regulation l
Enclosures:
1.
Amendment No. 8 2.
Safety Evaluation cc w/ enclosures:
See next page l
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