ML20199G001

Amend 16 to License R-106,removing gender-specific Wording from TS 6.1.a,updating Organizational Titles in TS 6.1 & Removing References to Region V from TS Reporting Requirements

ML20199G001
Person / Time
Site:	Oregon State University
Issue date:	01/28/1998
From:	Weiss S NRC (Affiliation Not Assigned)
To:
Shared Package
ML20199F970	List: ML20199F967 ML20199G001 ML20199G033
References
R-106-A-016, R-106-A-16, NUDOCS 9802040190
Download: ML20199G001 (6)

Text

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NUCLEAR REGULATORY COMMISSION-WASHINGToM. D.C. 2066dL4001

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OREGON STATE UNIVERSITY DOCKET NO. 50-243 AMENDMENT TO AMENDED FACILITY OPERATING LICENSE Amendment No.16 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 November 25,1997, as '

supplemented on Decemt'er 19,1997, 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 FederalRegulations (10 CFR):

I B. The facility will operate in conformity with the application, the provisions of the Act, and ti.e 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 notice for this amendment is not required by 10 CFR 2.'iO6.

9802040190 980128 PDR P ADOCK 05000243 PDR

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2. According y, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C.(2) of Amended Facility Operating License No. R 106 is hereby amended to read as follows:

(2) Technical Soecifications Tne Technical Specifications contained in Appendix A, as revised through Amendment No.16, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

. 3. This licerse amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION W e Sey our H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation

Enclosure:

Appendix A Technical Specifications Changes Date of Issuance: January 28, 1998

4 ENCLOSURE TO LICENSE AMENDMENT NO.16 AMENDED FACILITY OPERATING LICENSE NO. R 106 DOCKET NO. 50-243 Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages. The reviseti pages are identified by ainendment number and contain verticallines indicating the areas of change .

Remove - jnggg 30 30 34- 34 35 35 e

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6. ADNINISTRATIVE CONTROLS 6.1 GIGnNIZATION

a. - The facility shall-be under the direct control of the Radiation Center Director or a licensed senior operator designated by the Director to be 1 y in direct control. The Radiation Center Director shall be responsible to 0;tgon State University's Vice Provost for Resem:h for the safe I operation and maintenance of the reactor and its associated equipment.

Tne Radiation Center Director, or an individual appointed by the Director, shall be responsible for assuring that all operations are conducted in a safe manner and within the limits prescribed by the facility license and the requirements of the Reactor Operations Committee. The Radiation Center Director shall enforce rules for the ,

protection of personnel assinst radiation.

-b. The safe operation of the OSTR shall be related to the University Administration as shown in the following chart:

President, Oregon State Univoredy Provost & Executive Vlos Proeident i I I -- I Vice Presidmt for R. nonce and Vice Provost for Roseveh Administration l

OSU l

me.to,. m.on Center neoctor A l o,,e,e,,one _.

Commbee I- 1 I Reactor Administrator I

Maeotor sneervisor I

OSTR Rettetton Center Operatione Health Physico staff ste*f Normel administrative reporting channel Technical sowtow feo et, esmmunioetione and teolotence 30 Amendment No. 16

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g. -Offsite environmental monitoring surveys.

h. Fuel inventories and transfers.

1. Facility radiation and contamination surveys.

J. Radiation exposures for all personel.

k, Updated, corrected, and as built drawings of the facility.

6.7 REPORTING RFOUIRIMENTS In addition to the requirements of applicable regulatio'is, and in no way substituting therefore, reports shall be made to the NRC as follows:

a. A report within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone or fax to the NRC Operations Center of:

1. Any accidental release of radioactivity above applicable limits in unrestricted areas, whether or not the release resulted in property damage, personal injury, or exposure:

2. Any violation of a safety limit:

3. Operation with a safety system setting less consereative than speci-  ;

fied in Section 2.2, Limiting Safety Syster Settings:

4. Operation in viciation of a Limiting Condition for Operation:

5. Failure of a required reactor or experiment safety system component I

which could render the system incapable of performing its intended s-fety function unless the failure is discovered during maintenance tests or periods of reactor shutdown:

6. Any unanticipated or uncontrolled change in reactivity greater than

$1.00:

7. An observed inadequacy in the implementation of either administrative or procedural controls, such that the inadequacy could have caused the existence or development of a condition which could result in operation of the reactor outside the specified safety limits: and

8. A measurable release of fission products from a fuel element.

b. A report within 14 days in writing to the NRC, Document Control Desk, ,

Washington, D.C. I

1. Any accidental release of radioactivity above permissible limits in unrestricted areas, whether or not the release resulted in property damage, personal injury, or exposure; the written report (and, to the extent possible, the preliminary telephone or fax report) shall l describe, analyze, and evaluate safety implications, and outline the corrective measures taken or planned to prevent reoccurrence of the event:

34- Amendment No. 16

, 2. Those svents reported as requireo by Sections 6.7.a.2 through 6.7.a.8.

c. A repet within 30 d3ys in writing to the NRC. Document Control Desk. Washing-ton, D.C. l 1.- Any significant variation of measured valtes from a corresponding pre-dicted or previously measured value of safety connected operating charac-teristics occurring during operation of the reactor:

2. Any significant change dn the transient or accident analyses as described in the Safety Analysis Report:

3. Any changes in facility organization or personnel: and

4. Any observed inadequacies in the implementation of administrative or procedural controis such that the inadequacy causes or could have caused the existence nr development of an unsafe condition with regard to reactor operations.

d. A report within 90 days after completion of starting testing of the reactor (in writing to the NRC. Document Control Desk, Washington, D.C.) upon receipt of a l new facility license, or an dinendment to the license authorizing an increase in reactor power level, describing the measured values of the operating conditions or characteristics of the reactor under the new conditions including:

1. An evaluation of facility perfomance to date in comparison with design predictions and specifications.

2. A reassessment of the safety analysis submitted with the license applica-tion in light of measured operating characteristics when such measurements indicato that there may be substantial variance from prior analysis.

e. An annual report by November 1 of each year (in writing to the NRC. Document Control Desk, Washington. D.C.). I

1. A brief summary of operating experience including experiments performed and changes in facility design, performance characteristics and operating procedures related to reactor safety occurring during the reporting period, and results of surveillance test and i_nspections.

2. A tabulation showing the energy generated by the reactor (in megawatt-hours), !ars reactor was critical, and the cumulative total energy output since 4:.itial criticality.

3. The number of emergency shutdowns and inadvertent scrams, including reasons therefore.

4. Discussion of the major maintenance operations performed during the period. ncluding the effect, if any, on the safety of the cperation of the reactor and the reasons for any corrective maintenance required.

Amendment No., 16