ML20154D801
| ML20154D801 | |
| Person / Time | |
|---|---|
| Site: | 05000157 |
| Issue date: | 05/13/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20154D793 | List: |
| References | |
| NUDOCS 8805190350 | |
| Download: ML20154D801 (2) | |
Text
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- UNITED STATES r[g NUCLEAR REGULATORY COMMISSION
.[35 7, gb /l WASHINGTON, D. C. 20555
\N..ljf SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 9 TO FACILITY GPERATING LICENSE NO. R-80 CORNELL UNIVERSITY DOCKET NO. 50-157
1.0 INTRODUCTION
By letter dated May 4, 1988, Cornell University (licensee) requested an amendment to their Technical Specifications (TS) for the Cornell University TRIGA Reactor. The amendment would permit operating the reactor in a normal and a restricted mode. In the normal mode of operation the fuel element containing thernocouples would be a stainless-steel-clad high-hydride fuel element. In the restricted mode of operation the fuel element containing thermocouples would be an aluminum-clad low-hydride fuel element. The restricted mode of operation also limits power to 200 kW and does not allow pulse mode operation.
The amendment request was developed because of an apparent leak in the two stainless-steel-clad fuel elements containing thermocouples and the desire of the licensee to continue operation until new stainless-steel-clad fuel elements with thercocouples are delivered. The licensee has aluminum-clad fuel elements with thermocouples on hand.
- In a telecon of May 5, 1988, Theodore Michaels (NRR) to David Clark (licensee), the licensee further agreed to TS changes to Sections 3.1 (Specifications) and 3.3 (Specifications and Bases). !
i 2.0 EVALUATION The licensee has adjusted the TS limits for the power level, the excess j reactivity and maximum positive experirrent worth to preclude failure of '
the aluminum-clad fuel, which occurs at 530'C. Analyses for operation with aluminum-clad fuel are available and can be found in references 1 and 2. Experience with regard to operation with mixed cores of stainless-steel and aluminum-clad fuel is available with the Michigan State University TRIGA, which was licensed to operate in this configuration from 1974 to ;
1984 at 250 kW and up to 2$ pulses. Additionally, tests taken by Cornell i in February-March 1984 showed that the thermocouple measurements in the l B-ring for the all stainless-steel-clad high-hydride core was 160'C at l 100 kW. The safety limit setting for operation at 200 KW will be set for 230*C which is well below the failure tenperature of the fuel (530*C).
The scram protection of the reactor in the restricted mode is identical to the norrral mode of operation except that the power level scram will be set at 200 kW. The fuel temperature scram will be set to provide protection to 8805190350 880513 PDR ADOCK 05000157 P PDR
ensure that if a condition results in which the limiting safety system setting is exceeded in the restricted mode an immediate shutdown will occur.
Therefore, since the power and excess reactivity levels have been adjusted to account for the aluminum-clad fuel element and scram functions in the restricted mode are identical to those in the normal mode, except for settings, the staff finds that the reactor can be operated as proposed by the licensee.
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 and changes in inspection and surveillance requirements. 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 in-dividual 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 environ-mental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that: (1) because the amenoment 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, (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 will be conducted in compliance with the Commission's regulatiors and the issuance of this amendrant will not be inimical to the common defense and security or the health and safety of the public.
5.0 References
- 1. "Technical Four.dations of TRIGA," GA-471 (1958), pp. 63-72.
- 2. "Hazards Analysis for the Oregon State University 250 kW TRIGA Mark II Reactor," (June 1965), Section 4.7.
Principal Contributor: Theodore S. Michaels Dated: May 13,1998 l
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