ML20198J243

Safety Evaluation Supporting Amend 24 to License R-66

ML20198J243
Person / Time
Site:	University of Virginia
Issue date:	12/21/1998
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20198J227	List: ML20198J222 ML20198J229 ML20198J243
References
NUDOCS 9812300120
Download: ML20198J243 (2)

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3066dH201

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SAFETY EVALUATION BY THE OFFICE OF NUCl FAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 24 TO AMENDED FACILITY OPERATING LICENSE NO. R-66 THE UNIVERSITY OF V!RGlNIA DOCKET NO. 50-62

1.0 INTRODUCTION

By letter dated December 3,1998, as supplemented on December 10,1998, the University of Virginia (UVA or licensee) submitted a request for amendment to Appendix A of Amended Facility Operating License No. R-66 for the UVA Researc5 Reactor (UVARR), " Technical Specifications for the University of Virginia Reactor." The esquested changes would remove surveillance requirements for rod drop measurements and primary coolant flow calibration.

2.0 EVALUATION The licensee has requested that technical specification (TS) 4.1.1 concerning shim rod drop time rneasurements be deleted from the TSs. The TS currently reads:

Dron-time Measurements Shim rod drop times shall be measured semiannually. Shim rod drop times shall also ;

be measured if the control assembly is moved to a new position in the core or if I maintenance is performed on the mechanism. l The purpose of this TS is to help ensure that the shim rods will operate properly if needed to f shut down the reactor by a scram. The UVARR was permanently shut down on June 30,1998, l and all fuel elements have been removed from the reactor grid plate to storage. In addition, the l specially designed fuel elements that the control rods pass through have been shipped off the site. Because the reactor will never be operated again and the control rods will never be i needed to control the reactivity of the reactor, and deletion of this TS is acceptable to the staff.  !

1 TSs 4.2.3 and 4.2.5 conceming reactor safety system surveillances read as follows:

4.2.3 Channel Calibrations A channel calibration of the reactor safety measuring channels shall be performed semiannually.

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4 4.2.5 Ranctor Rafatv Channels Checks The above specifications (4.2.1 through 4.2.4) do not apply to the following l reactor safety channels: power to primary coolant pump, manual button, '

header air pressure, and pool water level monitor. Operation of these i sefety channels will be checked before each day's operation or before each operation extending more than one day.

i i The reactor safety measuring channels are presented in Table 3.1 of the TSs. One of these channels is the primary coolant flow measuring channel. The licensee wants to eliminate the ,

j requirement to perform semiannual calibrations of the primary coolant flow measuring channel.

i To accomplish this, the licensee has proposed that primary coolant flow be added to the list of l reactor safety channels in TS 4.2.5. to which TS 4.2.3 is not applicable. The licensee's i proposed change in wording to TS 4.2.5 would also result in TS 4.2.1,4.2.2, and 4.2.4, not  ;

applying to the primary coolant flow measuring channel. . Because these three TSs are l i

applicable only upon operation of the reactor the licensee's proposed wording does not affect 4 these TSs because the reactor has been permanently shut down. Because the reactor will no j longer be operated, calibrated primary coolant flow measurements are not needed, and the l 1 deletion of this calibration requirement is acceptable to the staff. I j -!

3.0 ENVIRONMENTAL CONSIDERATION

! This amendment involves changes in the installation or use of a facility component located )

l within the restricted area as defined in 10 CFR Part 20 or changes in inspection and i surveillance requirements. The staff has determined that this amendment involves no

! significant increase in the amounts, and no significant change in the types, of any effluents that

may be released off site, and no significant increase in Individual or cumulative occupational i radiation exposure. Accordingly, this amendment meets it:: eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 OFR 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

l The staff has concluded, on the basis of the considerations discussed above, that (1) because l the amendment does not involve a significant increase in the probability or consequences of j accidents previously evaluated, or create the possibility of a new or different kind of accident i 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 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.

Principal Contributor: A. Adams, Jr.

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