ML052500635
| ML052500635 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 09/26/2005 |
| From: | Lyon C NRC/NRR/DRIP/RNRP |
| To: | Reese S Oregon State University |
| Lyon C, NRR/DRIP/RNRP, 415-2296 | |
| Shared Package | |
| ML052510684 | List: |
| References | |
| TAC MC6737 | |
| Download: ML052500635 (8) | |
Text
September 26, 2005 Mr. Steven R. Reese Director, Radiation Center Oregon State University 100 Radiation Center Corvalis, OR 97331-5903
SUBJECT:
OREGON STATE UNIVERSITY - ISSUANCE OF AMENDMENT RE:
ADMINISTRATIVE CHANGE TO TECHNICAL SPECIFICATIONS (TAC NO. MC6737)
Dear Mr. Reese:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 20 to Amended Facility Operating License No. R-106 for the Oregon State University TRIGA Research Reactor. This amendment revises the Technical Specifications in response to your application dated April 7, 2005.
The amendment revises the title of Vice Provost for Research to Vice President for Research.
A copy of the Safety Evaluation is also enclosed.
Sincerely,
/RA/
Carl F. Lyon, 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. 50-243
Enclosures:
- 1. Amendment No. 20 to License No. R-106
- 2. Safety Evaluation cc w/encls: See next page
September 26, 2005 Mr. Steven R. Reese Director, Radiation Center Oregon State University 100 Radiation Center Corvalis, OR 97331-5903
SUBJECT:
OREGON STATE UNIVERSITY - ISSUANCE OF AMENDMENT RE:
ADMINISTRATIVE CHANGE TO TECHNICAL SPECIFICATIONS (TAC NO. MC6737)
Dear Mr. Reese:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 20 to Amended Facility Operating License No. R-106 for the Oregon State University TRIGA Research Reactor. This amendment revises the Technical Specifications in response to your application dated April 7, 2005.
The amendment revises the title of Vice Provost for Research to Vice President for Research.
A copy of the Safety Evaluation is also enclosed.
Sincerely,
/RA/
Carl F. Lyon, 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. 50-243
Enclosures:
- 1. Amendment No. 20 to License No. R-106
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC RNRP/R&TR r/f MVoth WKennedy BThomas TDragoun MMendonca AAdams CLyon DHughes WBeckner OGC EHylton FGillespie KWitt CBassett DMatthews DHarrison WSchuster PYoung WEresian PIsaac GHill (2)
PDoyle PACKAGE ACCESSION NO.: ML052510684 ADAMS ACCESSION NO.: ML052500635 TECH SPEC ACCESSION NO.: ML052510577 TEMPLATE No.: NRR-106 OFFICE RNRP:PM RNRP:LA OGC RNRP:SC NAME AAdams EHylton BThomas DATE 9/15 /05 9/15 /05 9/22 /05 9/23 /05 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY
Oregon State University Docket No. 50-243 cc:
Mayor of the City of Corvallis Corvallis, OR 97331 David Stewart-Smith Oregon Office of Energy 625 Marion Street, N.E.
Salem, OR 97310 John Cassady, Vice President for Research Oregon State University 312 Kerr Administration Building Corvallis, OR 97331-5904 Todd Keller Reactor Administrator Oregon State University 100 Radiation Center Corvallis, OR 97331-5904 Dr. John Ringle, Chairman Reactor Operations Committee Oregon State University 100 Radiation Center Corvallis, OR 97331-5904 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611
OREGON STATE UNIVERSITY DOCKET NO. 50-243 AMENDMENT TO AMENDED FACILITY OPERATING LICENSE Amendment No. 20 License No. R-106 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for an amendment to Amended Facility Operating License No. R-106 filed by Oregon State University (the licensee) on April 7, 2005, conforms to the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the Commission as stated in Chapter I of Title 10 of the Code of Federal Regulations (10 CFR);
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance that (i) the activities authorized by this amendment can be conducted without endangering the health and safety of the public and (ii) such activities will be conducted in compliance with the regulations of the Commission; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
This amendment is issued in accordance with the regulations of the Commission as stated in 10 CFR Part 51, and all applicable requirements have been satisfied; and F.
Prior notice of this amendment was not required by 10 CFR 2.105 and publication of a notice for this amendment is not required by 10 CFR 2.106.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. R-106 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 20, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Brian E. Thomas, Section Chief Research and Test Reactors Section New, Research and Test Reactors Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
ATTACHMENT TO LICENSE AMENDMENT NO. 20 AMENDED FACILITY OPERATING LICENSE NO. R-106 DOCKET NO. 50-243 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
REMOVE INSERT 30 30
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO AMENDMENT NO. 20 TO AMENDED FACILITY OPERATING LICENSE NO. R-106 OREGON STATE UNIVERSITY DOCKET NO. 50-243
1.0 INTRODUCTION
By application to the U.S. Nuclear Regulatory Commission (NRC or the Commission) dated April 7, 2005 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML051040245), Oregon State University (the licensee) requested an amendment to the Operating License for the TRIGA Research Reactor. The proposed change would revise the Technical Specifications (TSs) to reflect the change in title of the Vice Provost for Research to Vice President for Research. Specifically, the change in title would be reflected in the organizational description in TS 6.1.a and in the organizational chart in TS 6.1.b.
2.0 EVALUATION Oregon State University stated that it has recently changed its administrative structure to elevate the title of Vice Provost for Research to Vice President for Research. The licensee states that the responsibilities and obligations of the position have not been changed. The licensee proposes to change the position title as reflected in the organizational description in TS 6.1.a and in the organizational chart in TS 6.1.b. No changes are proposed to the reporting relationships of the positions.
Since the proposed change involves only an update of the position title to reflect the current organization and no changes to the responsibilities and obligations of the position, the staff finds the proposed change acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment changes recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the 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 NRC staff has concluded, based on the considerations discussed above, that the proposed amendment does not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) result in a significant reduction in a margin of safety. Therefore, the amendment does not involve a significant hazards consideration.
The NRC staff has also concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: F. Lyon Date: