ML20246L807

Safety Evaluation Supporting Amend 5 to License R-123

ML20246L807
Person / Time
Site:	University of Virginia
Issue date:	03/15/1989
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20246L798	List: ML20246L794 ML20246L802 ML20246L807
References
NUDOCS 8903240281
Download: ML20246L807 (2)

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UNITED STATES ,

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n NUCLEAR REGULATORY COMMISSION l

, $p . . WASHINGTON, D. C. 20555

,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION  !

SUPPORTING AMENDMENT N0. 5 TO FACILITY OPERATING LICENSE N0. R-123 ,

UNIVERSITY OF VIRGINIA  :

DOCKET NO. 50-396 i i

1.0 INTRODUCTION

By letter dated Ncvember 22, 1988, as su pplemented on January 12, 1989, the University of Virginia (UVA) requested changes to the Technical Specifications (TS) of Facility Operating License No. R-123 for the University of Virginia CAVALIER Research Reactor. The requested changes would allow surveillance requirements falling due when the core is in an unloaded state to be postponed until such time as the core is reassembled. Those surveillance that do not  ;

require fuel on the gridplate shall be completed before fuel is returned to '

the gridplate. Surve111ances that require fuel to be on the grid plate shall be completed as per the individual specification. The reactor core shall not

, be left in a partially loaded condition for more than one calendar week.

2.0 EVALUATION The CAVALIER' reactor is currently shutdown and the reactor core has been completely unloaded and placed into dry storage in accordance with the facility technical specifications. The licensee is planning to decommission the facility at some point in the future. To prevent unnecessary operation of the reactor and activation of reactor components, UVA has requested that surveillance requirements that fall due when the reactor core is in an I unloaded state'be postponed until such time that the core is to be reassembled. Surveillance that are postponed that do not require fuel to be on the gridplate shall be completed before fuel is moved to reload the core.

Surveillance requiring fuel on the gridplate shall be completed in accordance with the existing individual specifications. The surveillance affected i involve shim rod dro channels (TS 4.2(3))p time (TS

, calibration 4.1(1)), monitoring of radiation calibrationequipment of reactor safety (TS 4.3), 4 determination of boron concentration in the solution contained in the alternative reactivity insertion system (ARIS) (TS 4.5(2)), flow test of the ARIS (TS 4.5(3)), and blowing out a section of pipe in the ARIS with air .

(TS4.5(4)). The other surveillance requirements are event dependent instead l of time dependent and are not affected by this amendment. Although not required by the amended technical specifications, calibration of certain radiation monitors will continue under the requirements of 10 CFR 70.24 concerning criticality accident requirements.

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Because this requested postponement in surveillance requirements is only i applicable when the reactor is unloaded, the licensee has proposed that the reactor core shall not be left in a partially loaded condition for more than one calendar week. If any fuel is on the gridplate, the surveillance require.aents shall be met.

Because these surveillance requirements can only be postponed while the i reactor. core is completely unloaded and the reactor is inoperable, the staff j concludes that this amendment does not change previously evaluated accidents 1 or create the possibility of a new or different kind of accident and does not  !

involve a significant reduction in any margin of safety. Therefore, the 4 changes are acceptable.

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3.0 ENVIRONMENTAL CONSIDERATION

j 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 l inspection and surveillance requirements. The staff has determined that the I amendment involves no significant increase in the amounts, and no significant I 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 l

. 51.22(b), no Environmental Impact Statement or Environmental Assessment need be l prepared in connection with the issuance of this amendment. l

4.0 CONCLUSION

The staff has concluded, based on the considerations discussed above, that:

(1) because the amendment does not involve a significant increase in the l 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 1 in compliance with the Commission's regulations and the issuance of this l amendment will not be inimical to the common defense and security or the I

, health and safety of the public. l Principal Contributor: Alexander Adams, Jr. l Dated: March 15, 1989 l

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