ML20202B561

Proposed Tech Specs 6.1 Re Administrative Controls

ML20202B561
Person / Time
Site:	Oregon State University
Issue date:	11/25/1997
From:	Oregon State University, CORVALLIS, OR
To:
Shared Package
ML20202B513	List: ML20202B507 ML20202B561
References
NUDOCS 9712030119
Download: ML20202B561 (3)

Text

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6. ADMINISTRATIVE CONTROLS 6.1 ORGANIZATION

a. The facility shall be under the direct control of the Radiation Center Director or a licensed senior operator designated by the Dire: tor to be in direct control. The Radiation Center Director shall be responsible to Oregon State University's Vice Provost for Research for the safe oxration and maintenance of the reactor and its associated equipment.

Tw 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 against radiation.

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

Pro.mns, o,e on St.i. univ.rony Provost & Enocutive Vice President I I I l vice Pro.mnt for F6nence end Vice Provost for Research Adtninistration l

g

--- Safety Reactor CMuse Director, Mediation Center - Opwations ***

Committee l I Reactor Hoeith

^## Physicist I _. _ . .

Rextor Supervisor I _

OSTR Rasation Center Operetions Hootth Physice .

Stati Staff Normal admin 6strative reporting channel

,, Technica reytow (as Pawl, commun6cet6cne end assistance 30 Amendment No. 16 9712030119 971125 PDR ADOCK 05000243 P PM .

g. Offsite environmental monnoring surveys,

h. fuel inventories and transfers.

1. Facility radiation and contamination surveys. g j, Radiation exposures for all personnel.

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

6.7 P2 PORTING Rt00lREMEN1-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 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. Operatio1 with a safety system setting less conservative than speci.

fied in Section 2.2, Limiting Safety System httings: ,

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

5. Failure of a recuired reactor or experiment safety system component which could rencer the system incapable of performing its intended safety function unless the failure is discovered during maintenance tests or periods of reactcr stutdown:

6. Any un6nticipated or uncontrolled change in reactivity greater than

$1.00;

7. An obstrved inadequacy in the implementation of either administrative or pro:edural controls, such that the inadequacy could have caused the existence or development of a condition which could result in operatic, of the reactor outside the specified safety limits; and -

8. A mea';urable 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.

1. Any accidental release of radioactivity above permissible limits in unrestricted areas, whether or not the release resulted in property damtge, personal injury, or exposure: the written report (and, to tra extent possible, the preliminary telephone or telegraph report) shall describe, analyze, and evaluate safety implications, and outline the 4

corrective measures taken or planned to prevent reoccurrence of the event:

34- Amendment No. 16

2. Those events reported as required by Sections 6.7.a.2 through 6.7.a.8.

c. A report within 30 days in writing to the NRC, Document Control Desk Washing-ton, D.C.

1. Any significant variation of measured values 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 in the transient or accident analyses as described in the Safety Analysis Report:

3. Any charges in facility organization or personnel: and

4. Any observea inadequacier in the implementation of edministrative or procedural controls such that the inadequacy causes or could have caused the existence or 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 new facility license, 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:

1. An evaluation of facility performance 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 indicate that there may be substantial variance from prior analysis,

e. An annual report by k.a.tcr 1 of each year (in writing to the NRC, Document Control Desk 1shington, D.C.)

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 uf surveillance test and inspections.

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

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 corrective maintenance required.

35- Amendment No. 16

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