ML20246D101
| ML20246D101 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 08/15/1989 |
| From: | Weiss S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246D098 | List: |
| References | |
| R-106-A-010, R-106-A-10, NUDOCS 8908250252 | |
| Download: ML20246D101 (5) | |
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c OREG0H STATE UNIVERSITY-DOCKET NO. 50-243 1.
AMENDMENT TO FACILITY OPERATING LI,ENSE C
Amendment No. '10 License No. R-106 c
1..
The Nuclea'r. Regulatory Commission (the Commission) has found that:
A '.
The application for amendment to Facility. Operating License
- No. R IO6 filed by Oregon State University (the licensee), dated June 14, 1989, complies with the standards and requirements of-
'the Atomic Energy Act of 1954, as amended (the Act). and the Commission's regulations as set forth in'.10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions'of the Act, and the regulations of the Commission;
.C.
There is reasonableL assurance:
(1)thattheactivities. authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted inl compliance with the Commission's regulations set forth
.in 10 CFR Chapter I;-
L 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;.
I E.
The issuance of this amendment is in accordance with 10 CFR Part 51 h
of the Conraission's regulations and 'all applicable requirements have L
been satisfied; and F.
Publication of notice of this amendment is not required since it does r
not involve a significant hazards consideration not amendment of a license of the type described in 10 CFR Section 2.106(a)(2).
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- 2. ' Accordingly, 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 License No. R-106 is hereby_
amended to' read as follows:
(2)'TechnicalSpecifications The Technical Specifications contained:in Appendix A, as revised through Amendment No..10, are hereby incorporated in the license.
The licensee.shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of its date of issuance.
- 3. -
FOR THE NUCLEAR REGULATORY COMMISSION
.Os Seymour H. Weiss, Director Non-Power Reactor, Decommissioning and Environmental Project Directorate Division of Reactor _ Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation-
Enclosure:
Appendix A Technical Specifications Changes-
.Date of: Issuance: August 15,-1989 a
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-ENCLOSURE TO LICENSE AMENDMENT NO. 10 y
FACILITY OPERATING LICENSE,NO. R-106 l
DOCKETNO.50-29 Replace the following pages of the Appendix A Technical Specifications with
. the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of. change.
Remove Pages Insert _Pages 34 34 35 35 I
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Offsite environmental monitoring surveys.
h.
Fuel inventories ar.d transfers.
1.
Facility radiation and contamination surveys.
l j.
Radiatien exposures for all personnel.
k.
Updated, corrected, und as-built drawings of the facility.
6.7 REPORTING REQUIREMENTS In addition to the requirements of applicable regulations, 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 telegraph to the NRC, Region V, of:
l 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 conservative than specified in Section 2.2, Limiting Safety System Settings; 4.
Operation in violation of a Limiting Condition for Operation; 5.
Failure of a required reactor or experiment safety system com-
-ponent which could render the system incapable of performing its intended safety 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 adminis-trative or procedural controls, such that the inadequacy could have caused the existence or development of a condition which could resul+ in operation of the reactor outside the specified safety limics; 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., with a copy to the NRC, Region V.
1.
Any accidental release of radioactivity above permissible limits in unrestricted areas, whether or not the release resulted in roperty damage, personal injury, or exposure; the written report p(and, to the extent possible, the preliminary telephone or telegraph report) shall describe, analyze, and evaluate safety implications, and outline the corrective measures taken or planned to prevent reoccurrence of the event; Amendment No. 10
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Those events reported as required by Sections 6.7.a.2 through.
q ij 6.7.a.8.
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A report within 30 days. in' writing to the NRC, Document Control. Desk, Washington, D.C.,: with a copy-to the NRC, Region V.
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1.
Any significant variation of measured values' from.a corresponding predicted or previously measured value of safety-connected-L '
operating characteristics occurring ~during operation of the reactor;.
1 1
2.
Any significant change in the transient'or accident analyses as described in.the Safety Analysis' Report;-
l 3.
' Any changes in facility organization or personnel; and l
4.
- Any observed-inadequacies in the implementation of. administrative or procedural controls such that the inadequacy causes or could have caused the. existence or development of an unsafe condition j
with' regard to. reactor operations, d.
A.repcrt within 90 days after completion of starting ' testing of the reactor (in writing to the NRC, Document Control Desk, Washington, D.C.
and a copy;to NRC, Region V) upon receipt'of a:new facilityL11 cense, or an amendment 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:
a 1.
An. evaluation of facility performance'to date in comparison with design predictions and' specifications.
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2.
.A reassessment of the safety analysis submitted with the i
license application in light of measured operating charac-1 teristics when such measurements indicate that there may.
1 be substantial variance from prior analysis.
j e.
An annual report within 75 days following the 30th of June of each j
year (in writing to the NRC, Document Control Desk, Washington, j
D.C. and a copy to the NRC, Region V).
j i
1.
A brief summary of operating experience including experiments performed and changes in facility design, performance charac-teristics and operating procedures related to reactor safety occurring during the reporting period, and results of sur-veillance test and inspections.
2.
A tabulation showing the energy generated by the reactor (in megawatt-hours), hours reactor was critical, and the cum-ulative total energy output since initial criticality.
a 3.
The number of emergency shutdowns and inadvertent scrams, including reasons therefore.
4.
Discussion of the major maintenance operations performed during the period, including the effect, if any, on the safety of the operation of the reactor and the reasons for any cor-rective maintenance required.
35 -
Amendment No. 10
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