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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20198B2201997-12-18018 December 1997
Safety Evaluation Supporting Amend 17 to License R-52
1997-12-18
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20211G5341999-06-30030 June 1999
Submits Annual Rept, Covering Period 980701 Through 990630 for Activities of Triga Mark I Reactor.With
ML20209A7181999-06-22022 June 1999
Special Rept:On 990607,compliance with Spec 4.6 Was Not Enforced in Procedure Number Uarr 155,monthly Checklist, During Review of TS & Procedures.Caused by Omission of Item from Monthly Checklist.Prepared Revised Version of Uarr 155
ML20196B6021998-11-25025 November 1998
Ro:On 901206,950424 & 970512,deficiencies Occurred in Shipping & Receiving Special Nuclear Matl.Caused by Misunderstanding of Procedure Uarr 127.Committee Discussed Matter in 981103 Meeting & Matter Was Described in Training
ML20237C9921998-06-30030 June 1998
Annual Rept Covering Period 970101-980630 for Activities of Triga Mark I at Univ of Az,Tucson,Az.Supporting Documentation,Encl
ML20198B2201997-12-18018 December 1997
Safety Evaluation Supporting Amend 17 to License R-52
ML20199F1971997-11-13013 November 1997
Deficiency Rept Re Malfunction of Mode Selector Switch. Action Will Be Reviewed by Reactor Committee for Facility
ML20199B6341997-11-13013 November 1997
Ro:On 971104,malfunction of Mode Switch in Pulse Mode Occurred.Caused by Failure of Mode Switch to Reliably Switch Between Normal & High Range Signals.Removed Rear Casing of Mode Switch & Applied Switch Cleaning Fluid
ML20198P2541997-11-0505 November 1997
Ro:On 971104,change of Mode Switch from Manual to Pulse Positions Did Not Reliably Switch Between Normal & High Range Signals.Caused by Malfunction of Switch.Applied Switch Cleaning Fluid to Switch
ML20217D1681997-10-0101 October 1997
Ro:On 970930,discovered That Reactor Power Calibr Showed Safety Channels Reading Lower than Actual Power.Cause Indeterminate.Recalibr Power Channels & Issued Instructions to Set Scrams More Conservatively Pending Investigation
ML20216D4731997-08-13013 August 1997
Annual Rept Covering Period Jul 1996-June 1997,for Activities of Triga Mark I Reactor at Univ of Az,Tucson,Az
ML20128P6211996-10-16016 October 1996
Rs:On 960919,reactor Started Up & Operated by RO W/O SRO Supervision.Caused by Personnel Error & Misinterpretation of Procedural Requirements.Ro License Suspended.Procedure Uarr 163 Revised
ML20059E8061990-08-29029 August 1990
Annual Rept for License R-52 for Jul 1989 - June 1990
ML20248A9711989-09-15015 September 1989
Rev 1 to Operator & Senior Operator Requalification Program for Univ of Arizona Research Reactor
ML20246N7601989-08-31031 August 1989
Annual Rept Covering Period Jul 1988 - June 1989 for Activities of Triga Mark I Reactor
ML20204F5311988-10-19019 October 1988
SAR Univ of Arizona Triga Mark I Research Reactor
ML20204F4341988-10-17017 October 1988
Operator & Senior Operator Requalification Program
ML20209H5671986-08-27027 August 1986
Annual Rept for Triga Mark I Reactor at Univ of Arizona,Jul 1985 - June 1986
ML20135A9281985-08-26026 August 1985
Annual Rept for Jul 1984 - June 1985
1999-06-30
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Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.17 TO AMENDED FACILITY OPERATING l) CENSE NO. R 52 THE UNIVERSITY OF ARIZONA DOCKET NO. 50113
1.0 INTRODUCTION
By letter dated October 22,1997, the University of Arizcna (the licensee) submitted a request for amendment to the Technical Specifications (TSs) for the University of Arizona Research Reactor. The amendment updates the reporting requirements for a change in the NRC's organization and corrects a typographical error.
2.0 EVALUATION The changes to the reporting requirement replace the designation of the regional office with the Non Power Reactors and Decommissioning Project Directorate. This is consistent with the current NRC organization responsibility for inspections at non power reactors, such as the University of Arizona Research Reactor, Therefore, this change is acceptable.
The typogr9phical change replaces "officiency" with
- efficacy," does not change the intent of the TSs reporting, and, therefore,is acceptable.
3.0 ENVIRONMENTAL CONSIDERATIO This amendment involves changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection 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 chedent previously evaluated, and does not involve a significant reduction in a margin of safety, the amendment does not involve a significant 9901060234 971218 PDR ADOCK 05000113 P PDR _
l l
3-harard's 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: Marvin M. Mendonca Date: Decmiber 18, 1997
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