ML20207K305

Proposed Tech Spec Section 6,revising Administrative Controls

ML20207K305
Person / Time
Site:	University of Illinois
Issue date:	01/06/1987
From:	ILLINOIS, UNIV. OF, URBANA, IL
To:
Shared Package
ML20207K289	List: ML20207K285 ML20207K305
References
NUDOCS 8701090386
Download: ML20207K305 (6)

Text

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6.0 ADMINISTRATIVE CONTROLS l

6.1 Organization l

a. The reactor facility shall be an integral part of the Department of Nuclear Engineering of the College of Engineering of the University of Illinois. The reactor shall be related to the University structure as

, shown in Chart !.

b. The reactor facility shall be under the supervision of the Reactor Supervisor who shall have been qualified as a Ifcensed senior operator for the reactor. He shall be responsible for assuring that all opera-tions are conducted in a safe manner and within the limits prescribed by the facility license and the provisions of the Nuclear Reactor Conmittee.

l c. There shall be a Reactor Health Physicist responsible for assuring the I safety of the reactor from the standpoint of radiation protection, and l for assuming compilance with the University of Illinois' broad license as administered by the Health Physics Of fice. The Health Physicist may report directly to the Head of the Department of Nor' ear Engineering or to the Health Physics Office in the event of safety or regulatory concerns.

CIART I Head of Department of Division of Environmental Nuclear Engincoring Health and Safoty I

L7 Health Physics I "Tu" clear Reactor ,,,,, Director of l Office C$nnitten Nuclear Reactor i Laboratory I I I 1 l

l l I L. Reactor . Reactor Health , _J Supervisor Physicist

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ticensed Operstars Reactor Operation Chart 1. Administrative organization of the reactor facility. Dashed lines indicate reporting paths outside the operational chain of supervision, indicated by solid lines.

6.2 Review

a. There shall be a Nuclear Reactor Committee which shall review reactor operations to assure that the facility is operated in a manner con-sistent with public safety and within the terms of the facility license.

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PDH l

b. The responsibilities of the Committee include, but are not limited to, the following:

1. Review and approval of experiments utilizing the reactor facill-ties;

2. Review and approval of all proposed changes to the facility, pro-cedures, and Technical Specifications;

3. Determination of whether a proposed change, test, or experiment would constitute an unroviewed safety question or a cnonge in the Technical Specifications;

4. Review of the operation and operational records of the facility; t

5. Review of abnormal performance of plant equipment and operating anomalies;

6. Review of unusual or abnormal occurrences and incidents which are reportable under 10CFR 20 and 10CFR 50; and a

7. Approval of individuals for the supervision and operation of the i reactor.

c. The Committee shall be composed of at least five voting members, one of whom shall be a Health Physt.ist designated by the Health Physics 2

Office of the University, and one whom shall be the Director of the Reactor Laboratory. Three members shall be appointed by the Head of che Department of Nuclear Engineering, chosen from the faculty of Nuclear Engineering so as to maintain a balanced knowledge of reactor ,

i safety and regulation. The Reactor Supervisor and the Reactor Health

, Physicist shall be non-voting members.

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d. The Conmittee shall have a written statement defining such matters as the authority of the Committee, the subjects within its purview, and i

other such administrative provisions as are required for effective functioning of the Committee. Minutes of all neetings of the Committee shall be kept.

e. A quorum of the Committee shall consist of three voting cembers, one of whom shall be the chairman or his designeo.

f. The Committee shall meet at least every 112 days.

6.3 Oporatino Proceduros Written procedures, reviewed and approved by the Nuclear Reactor Committee, shall be in effect and followed for the following items. The procedures shall be adequate to assure the safety of the reactor, but should not preclude the use of Independent judgment and action should the situation require such.

! a. Startup, operation, and shutdown of the reactor.

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l b. Installation or removal of fuel elemencs, control rods, experiments, l and experimental facilities.

c. Actions to be taken to correct specific and foreseen potential

• i malfunctions of systems or components, including responses to alarms.

l suspected primary coolant system leaks, and abnormal reactivity changes.

d. Emergency conditions involving potential or actual release of radio-activity, including provisions for evacuation, ee-entry, recovery, and medical support. j

e. Maintenance procedures which could have an effect on reactor safety. >

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f. Periodic surveillance of reactor instrumentation and safety systems, '

area monitors and continuous air monitors.

Substantive changes to the above procedures shall be made only with the approval of the Nuclear Reactor Committee. Temporary changes to the proce-dures that do not change their original intent may be made with the appro- l val of the Reactor Supervisor. All such temporary changes to procedures l shall be documented and subsequently reviewed by the Nuclear Reactor i Comnittee. j 6.4 _ Action to be Taken in the Event a Safety Limit is Exceeded f In the event a safety limit is exceeded, or thought to have been exceeded:

a. The reactor shall be shut down and reactor operation shall not be resumed until authorized by the USNRC.

b. An immediate report of the occurrence shall be made to the Chairman of <

the Nuclear Reactor Connittee, and reports shall be made to the USNRC l in accordance with Section 6.7 of those specifications.  !

c. A report shall be made which shall include an analysis of the causes f and extent of possible resultant damage, efficacy of corrective I action, and recommendations for measures to prevent or reduce the pro- j bability of reoccurrence. This report shall be submitted to the -

Nuclear Reactor Conntttee for review, and a suitable similar report i submitted to the USNRC when authorization to resume operation of the reactor is sought.  !

l 6.S Action to be Taken in the Event of_an Abnormal Occurrence  ;

In the event of an abnormal occurrence, as defined in Section 1.14 of the i specifications, the following action shall be taken i

a. The Reactor Supervisor shall be notifled and corrective action taken ,

prior to resumption of the operation involved.

b. A report shall be made which shall include an analysis of the cause of the occurrence, ef ficacy of corrective action and recommendations for measures to prevent or reduce the probability or reoccurrence. This report shall be submitted to the Nuclear Reactor Committee for review. i e

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c. Where appropriate, a report shall be submitted to the USNRC in accor-dance with Section 6.7 of these specifications.

6.6 Plant Operating Records In addition to the requirements of applicable regulations, and in no way substituting therefore, records and logs shall be prepared and retained for a pe'riod of ~at least 2 years of the following items, as a 11nimum:

a. Normal plant operation;,

b. Principal maintenance activities;

c. Abnormal occurrences;

d. Equipment and component surveillance activities;

e. Gaseous and liquid radioactive effluents released to the environs;

f. Off-site environmental monitoring surveys;

g. Fuel inventories and transfers;

h. Facility radiation and contamination surveys;

, i. Radiation exposures for all personnel; J. Experiments performed with the reactor; and

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

6.7 Reporting Requirements In addition to the requirements of applicable regulations, and in no way substituting therefore, repcets shall be made to the USNRC as follows:

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l a. An immediate report (by telephone and telegraph to the Regional Administrator, USNRC, Region !!!) of:

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1. Any accidental release of radioactivity above permissible limits, whether or not the release resulted in property damage, personal injury or exposuro; and

2. Any violation of a safety limit.

b. A report within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (by tolophone and telegraph to the Regional Administrator, USNRC, Region !!!) of:

1. Any significant variation of measured values from a corresponding predicted or previously measured value of safety-connected operating characteristics occurring during operation of the reactor;

2. Incidents or conditions relating to operation of the facility which prevented or could have prevented the performance of engi-neored safety features as described in these specifications; and

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3. Any abnormal occurrences as defi'ned in Section 1.14 of these specifications.

c. A report within 10 days (in writing to the Director, Office of Nuclear Reactor Regulation, Document Control Desk, USNRC Head-quarters, and a copy to the Regional Administrator, USNRC, Region ,

, III) of:

1. Any significant variation of measured values from a corresponding predicted or previously measured value of safety-connected operating characteristics occurring during operation of the  !

reactor;  ;

2. Incidents or conditions relating to operating of the facility which prevented or could have prevented the performance of engi- l neered safety features as described in these specifications; and  !

3. Any abnormal occurrences as described in Section 1.14 of + ese 4 specifications.

d. A report within 30 days (in writing to the Director, Office of Nuclear Reactor Regulation, Document Control Desk, USNRC Head ,  ;

quarters)of:

1. Any substantial variance from performance specifications con-  !

tained in these specifications; '

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

3. Any changes in facility organization. >

e. A report within 60 days after criticality of the reactor (in writing t to the Director, Office of Nuclear Reactor Regulation Document Control Desk, USNRC Headquarters) upon receipt of a new facility license or an amendment to the license authorizing an increase in reactor power level or the installation of a new core, describing the measured values of the operating conditions or characteristics of the reactor under the new conditions, including; l

1. Total control rod reactivity worth; ,

2. Reactivity worth of the single control rod of highest reactivity -

worth; ,

3. Total and individual reactivity worths of any experiments inserted in the reactor; and i

l 4. Minimum shutdown margin bo'th at room and operating temperatures.

f. A routine report (in writing to the Director. Office of Nuciear l Reactor Regulation Document Control Desk, USNRC Headquarters) within l 60 days after completing of the first six months of facility operation ,

and at the end of each 12-month period thereafter, providing the ,

following information: ,

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1. A narrative summary of operating experience (including experi-

, ments performed) and of changes in facility design, performance l characteristics and operating procedures related to reactor safety occurring during the reporting period;

2. A tabulation showing the energy generated by the reactor (in megawatt-hours), the amount of pulse operation, the number of hours the reactor was critical; l 3. The number of emergency shutdowns and inadvertent scrams, ,

! including the reasons therefore;

4. Discussion of the major maintenance operations performed during the period, including the effect, if any, on the safe operation of the reactor, and the reasons for any corrective maintenance required; ,

5. A summary of each change toI the facility or procedures, tests, and experiments carried out under the conditions of Section 50.59 of 10CFR 50;

6. A summary of the nature and amount of radioactive affluents released or discharged to the environs beyond the effective control of the licenses as measured at or prior to the point of such release or discharge;

7. A description of any environmental surveys performed outside the facility; and

8. A summary of radiation exposures received by facility personnel I

and visitors, including the dates and time of significant expo- ,

sures, and a summary of the results of radiation and con- -

i tanination surveys performed within the facility.

6.8 Review of Experiments ,

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a. All proposed experiments utilizing the reactor shall be evaluated by the experimenter and a staff member approved by the Nuclear Reactor Committee. The evaluation shall be reviewed by a licensed senior operator of the facility (and the Reactor Health Physicist when-appropriate) to assure compliance with the provisions of the utiliza-tion license, the fechnical Specifications, and 10CFR 20. If, in his judgment, the experiment meets with the above provisions and does not constitute a threat to the integrity of the reactor, he shall submit it to the Reactor Supervisor for scheduling or to the Nuclear Reactor Committee for final approval as indicated in Section 6.2 above. When pertinent, the evaluation shall include:

1. The reactivity worth of the experiment;

2. The integrity of the experiment, including the effects of changes

, in temperature, pressure, or chemical composition;

3. Any physical or chemical interaction that could occur with the reactor components; and

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