ML040720746

Revision to Safety Evaluation of Amendment No. 7 to Amended Facility Operating License No. R-130 - Regents of University of California

ML040720746
Person / Time
Site:	University of California-Davis
Issue date:	03/30/2004
From:	Eresian W NRC/NRR/DRIP/RNRP
To:	Klein B McClellan Nuclear Research Center
Eresian , W, NRC/NRR/DRIP/RNRP, 415-1833
References
TAC MB5598
Download: ML040720746 (8)

Text

March 30, 2004 Dr. Barry M. Klein Vice Chancellor for Research University of California, Davis One Shields Avenue Davis, CA 95616-8558

SUBJECT:

REVISION TO SAFETY EVALUATION OF AMENDMENT NO. 7 TO AMENDED FACILITY OPERATING LICENSE NO. R-130 - REGENTS OF THE UNIVERSITY OF CALIFORNIA (TAC NO. MB5598)

Dear Dr. Klein:

The U.S. Nuclear Regulatory Commission has issued the enclosed revision to the Safety Evaluation of Amendment No. 7 to Facility Operating License No. R-130 for the McClellan Nuclear Radiation Center (MNRC) TRIGA Research Reactor. Amendment No. 7 was issued on December 30, 2003 and is available on the Commissions ADAMS system, Accession Number ML033421339.

Sincerely,

/RA/

Warren J. Eresian, Project Manager Research and Test Reactors Section New, Research and Test Reactors Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-607

Enclosure:

Revision to Amendment No. 7 Safety Evaluation Report cc w/enclosure: Please see next page

University of California - Davis/McClellan MNRC Docket No. 50-607 cc:

Mr. Jeff Ching 5335 Price Avenue, Bldg. 258 McClellan AFB, CA 95652-2504 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

March 30, 2004 Dr. Barry M. Klein Vice Chancellor for Research University of California, Davis One Shields Avenue Davis, CA 95616-8558

SUBJECT:

REVISION TO SAFETY EVALUATION OF AMENDMENT NO. 7 TO AMENDED FACILITY OPERATING LICENSE NO. R-130 - REGENTS OF THE UNIVERSITY OF CALIFORNIA (TAC NO. MB5598)

Dear Dr. Klein:

The U.S. Nuclear Regulatory Commission has issued the enclosed revision to the Safety Evaluation of Amendment No. 7 to Facility Operating License No. R-130 for the McClellan Nuclear Radiation Center (MNRC) TRIGA Research Reactor. Amendment No. 7 was issued on December 30, 2003 and is available on the Commissions ADAMS system, Accession Number ML033421339.

Sincerely,

/RA/

Warren J. Eresian, Project Manager Research and Test Reactors Section New, Research and Test Reactors Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-607

Enclosure:

Revision to Amendment No. 7 Safety Evaluation Report cc w/enclosure: Please see next page DISTRIBUTION:

PUBLIC RNRP\R&TR r/f SHolmes OGC MMendonca WEresian TDragoun PMadden AAdams PDoyle CBassett DMatthews EHylton PIsaac DHughes JLyons KWitt PYoung GHill (2) (T5-C3)

ADAMS ACCESSION NO: ML040720746 TEMPLATE No.: NRR-106 OFFICE RNRP:PM RNRP:LA OGC RNRP:SC NAME WEresian:rdr EHylton SUttal PMadden DATE 03/ 15 /2004 03/ 15 /2004 03/ 29 /2004 03/ 15 /2004

OFFICIAL RECORD COPY REVISION TO SAFETY EVALUATION REPORT SUPPORTING AMENDMENT NO. 7 TO AMENDED FACILITY OPERATING LICENSE NO. R-130 REGENTS OF THE UNIVERSITY OF CALIFORNIA AT McCLELLAN NUCLEAR RADIATION CENTER DOCKET NO. 50-607

1.0 INTRODUCTION

By letter dated October 21, 2003, the Regents of the University of California (the licensee) submitted a request for amendment of the Facility Operating License No. R-130 for the McClellan Nuclear Radiation Center (MNRC) TRIGA research reactor. The request provided for the allowance of radioactive materials not produced by the reactor to be received, possessed and used on the facility site. In particular, it was requested that Section 2.B of the Facility Operating License be amended to include an additional section 2.B.(4) as follows:

2.B.(4) In addition to those items specified in 2.B.(1), 2.B.(2) and 2.B.(3) the following radioactive materials may be received, possessed, and used at the facility.

Radioactive Material Chemical and/or Maximum Quantity Licensee May (element and mass number) Physical Form Possess at Any One Time A. Any radioactive material A. Any A. 20 Curies (1 Curie each, except as between atomic number 1 through provided below) 83, inclusive B. Any radioactive material with A. Any A. 4 Curies (100 millicuries each, atomic numbers 84 and above except as provided below) or up to 20 micrograms C. Iodine-125 C. Iodide/Liquid C. 40 Curies D. Source material (but only trace D. Any D. 4 grams per radionuclide, not to amounts of Th-234) exceed 10 grams total E. Special nuclear material E. Any E. 2 grams per radionuclide, not to exceed 5 grams total This amendment request was approved and issued on December 30, 2003.

2.0 EVALUATION The previous safety evaluation assumed that all of the radioactive materials to be received, possessed and handled in accordance with this amendment request would be located in the reactor room glove box. The significance of this assumption is related to the ability of the reactor room glove box and its associated exhaust system to mitigate the consequences associated with the complete volatilization of the maximum radioactive material inventory contained in the box, a total of 64.4 curies. (The total activity in categories A, B, and C in the above table is 64 curies. The maximum activity in category D is about 0.1 curie, while the maximum activity in category E is about 0.3 curie.). The staff concluded that the consequences of the complete volatilization of 64.4 curies are much less than the consequences of the bounding MHA, and the amendment request was approved.

Instead of locating all of the radioactive materials shown in above table in the reactor room glove box, some of the materials will be located in the restricted area of the McClellan Nuclear Radiation Center. Non-volatile material will be handled in accordance with approved procedures. Any unsealed volatile material, such as Iodine-125 (the majority of the radioactive materials), will continue to be handled in areas with filtered ventilation to mitigate the consequences of complete volatilization of the unsealed material (e.g., the reactor room glove box and reactor room fume hood), as previously analyzed.

The staff has reviewed the proposed change to the Facility Operating License and concluded that it does not impact the licensees ability to continue to meet the relevant requirements of 10 CFR Part 50.36.

3.0 ENVIRONMENTAL CONSIDERATION

This amendment does not involve changes in the installation or use of a facility component located within the restricted area as defined ion 10 CFR Part 20 or changes in inspection and 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 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 with the issuance of this amendment.

4.0 CONCLUSION

The staff has concluded, on the basis of 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 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 changes; and (3) such changes are in compliance with the Commissions 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: Warren J. Eresian Date: March 30, 2004