ML20215D390

Proposed Tech Specs Reflecting Administrative Changes Due to Formation of New Nuclear Engineering Dept & Restaffing of Nuclear Reactor Lab

ML20215D390
Person / Time
Site:	University of Illinois
Issue date:	05/29/1987
From:	ILLINOIS, UNIV. OF, URBANA, IL
To:
Shared Package
ML20215D342	List: ML20215D338 ML20215D390
References
NUDOCS 8706180503
Download: ML20215D390 (11)

Text

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31 6.0 ADMINISTRATIVE CONTROLS 6.1 Organization Amendment No.5

a. The reactor facility shall be an integral part of the Department of i Nuclear Engineering of the College of Engineering of the University of {j Illinois. The reactor shall be related to the University structure as shown in Chart I.

b. The reactor facility shall be under the supervision of the Reactor j Supervisor who shall have been qualified as a licensed senior operator for the reactor. He shall be responsible for assuring that all opera- {

i tions are conducted in a safe manner and within the limits prescribed by the facility license and the provisions of the Nuclear Reactor 3 Committee.

Amendmen No.5- i

c. There shall be a Reactor Health Physicist responsible for assuring the l day to day and routine radiological safety activities at the Nuclear -

Reactor Laboratory. The University of. Illinois Radiation Safety ]

Officer shall be responsible for monitoring, planning and promoting 1 radiological safety at the Nuclear Reactor Laboratory. He has the  !

responsibility and authority to stop, secure or otherwise control as )

necessary any operation or activity that poses an unacceptable j radiological hazard. l d

CHART I l Head of Department of Division of Environmental i Nuclear Engineering Health and. Safety l J

L_____,

, Radiation Safety Neclear Reactor Director of

' Officer  !

Committee -- Nuclear Reactor ,

8 Laboratory ,

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f t Reactor '

e . Reactor Health Supervisor -----

Physicist --- J Licensed Operators Reactor Operation ,

Chart I. Administrative organization of the reactor f acility. Dashed lines indicate reporting paths outside the operational chain of supervision, indicated by solid lines.

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I 32 6.2 Review 1

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, j

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

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1. Review and approval of experiments utilizing the reactor facili- ]

ties, 1

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

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

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

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

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

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

Amendment

c. The Committee shall be composed of at least five voting members, one No 5 of whom shall be a Health Physicist designated by the Health Physics Office of the University, and one whom shall be the Director of' the Reactor Laboratory. Three members shall be appointed by the Head of the Department of Nuclear Engineering, chosen from the faculty of Nuclear Engineering so as to maintain a balanced knowledge of reactor safety and regulation. The Reactor Supervisor and the Reactor Health Physicist shall be non-voting members.

d. The Committee shall have a written statement defining such matters as the authority of the Committee, the subjects within its purview, and other such administrative provisions as are required for effective functioning of the Committee. Minutes of all meetings of the Committee shall be kept. Amendment No.5

e. A quorum of the Committee shall be a majority of not less than one half of the members and the reactor operating staff shall not consti-tute a voting majority.

f. The Reactor committee shall meet at least quarterly with the interval between meetings not to exceed 5 months.

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L33 6.3; Operating Procedures 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.

b.- Installation or removal of fuel elements, control rods. experiments, .

and experimental facilities.

c. Actions to be taken to correct specific land foreseen potential malfunctions of systems or components, including responses t'o' alarms, suspected primary coolant systen leaks, and abnormal reactivity changes.

d. Emergency conditions involving potential ~or actual release'of. radio-activity, including provisions for evacuation, re-entry,. recovery, and .

medical support.

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

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-val of the Reactor Supervisor. All such temporary changes' to procedures shall be documented and subsequently reviewed by the Nuclear Reactor Committee.

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6.4 Action to be Taken in the Event a Safety ~ Limit is Exceeded In the event a safety limit Lis exceeded, or thought to have been exceeded:

Amendment

a. The reactor shall be shut down and reactor operation shall not' be. No.5 resumed until authorized by the USNRC.

b. . An immediate report of the occurrence shall be.made to the Chairman of the Nuclear Reactor Committee, and reports shall be made to the USNRC-in accordance with .Section 6.7 of these specifications.

c. A report.shall be made which shall include an: analysis of the causes' and extent of possible resultant damage, efficacy of corrective action, and recommendations for. measures to prevent or. reduce the pro -

bability of reoccurrence. . This report shall be submitted to the Nuclear Reactor Committee for review, and a ' suitable similar report submitted to the USNRC when authorization to resume' operation of the reactor is sought.

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.6.5' 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-specifications,.the following' action shall be taken:

a. . .The Reactor Supervisor shal1J be notifieci 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, efficacy of correctiveLaction and recommendations.for.

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measures:to prevent ~or. reduce the probability or reoccurrence. -This report shall be: submitted to the Nuclear Reactor Committee for review ,,,,,,,,,

c. . Where appropriate, a report shallbe submitted to the USNRC ' in- accor- "*

dance with Section 6.7 of these' specifications..

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-4 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 periodf off at. least .2 years' of the. following items, as.a ' minimum:

Normal plant operation;

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b.- Principal maintenance activities;-

.c. Abnormal. occurrences;

d. Equipment and component surveillance activities;- ,

e. Gaseous and J'aiquid radioactive effluents released to the environs;-

f. Off-site environmental monitoring surleys;

g. Feel 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.

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6.7J Reporting Requirements

In addition to the requirements of applicable- regulations,;and in no way substituting therefore, reports shall be made to the USNRC as'follows: Amendment

a. . An.immediate report (by telephone and telegraph to the Regional N .5)

Administrator,.USNRC,' Region III) of:

1. Any accidental off-site release of radioactivity above per-missible limits, whether or..not the release resulted in property damage, personal injury or exposure; and ~

2. Any violation of a' safety. limit.

Amendment-

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 telephone and telegraph'to the Regional No.S.

Administrator, USNRC, Region III) of: l

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-neered safety features as described in these-specifications; and

3. Any abnormal occurrences as defined in Section 1.14 of these specifications. Amendment.

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-neered safety features as described in these specifications; and.

3. Any abnormal occurrences as described in Section 1.14 of these specifications.

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. Amendment A report within 30 days (in writing to the Director, Office of "

d.

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. Amendment

e. A report within 60 days after criticality of the reactor (in writing 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;

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

4. Minimum shutdown margin both at room and operating temperatures. Amendment A routine report (in writing to the Director, Office of Nuclear No.5 f.

Reactor Regulation, Document Control Desk, USNRC Headquarters)- within  !

60 days after completing of the first six months of facility operation and at the end of each 12-month period thereafter, providing the i following information- i i

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;

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3. The numberJof emergency shutdowns and. inadvertent scrams,-

including the reasons therefore;

4. . Discussion of the major maintenance operations performed dur;ing 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 to the. facility or procedures,-tests, and experiments carried out under.the l conditions of Section 50'.59 '

of 10CFR550;

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

sures, and a summary of the results of radiation and con-tamination surveys performed within the facility.

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40-6L8 Review of Experiments

'a.z All .p'roposed experiments utilizing the reactor shall be e' valuated 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 Technical 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 1 -

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

4. Any radiation hazard that may result from the activation of materials or from external beams.

b. Prior to the performing of an experiment not previously performed in q the reactor, it shall be reviewed and ' approved in writing by the - '

Nuclear Reactor' Committee. . Their review shall consider the following information:

1. The purpose of the experiment;

2. A procedure for the performance of the' experiment; and

3. The evaluation approved by a licensed senior operator,

c. For the irradiation of materials, the applicant shall submit an

" Irradiation Request" to the Reactor Supervisor or Reactor Health Physicist. This request'shall contain information'on the' target material including the amount, chemical form, and ' packaging. For routine irradiations (which do not contain nuclear fuel or known.

explosive. materials and which do not constitute a significant threat to the integrity of the reactor or to the safety of individuals) .the approval for the Nuclear Reactor Committee may be made by the Reactor I Supervisor and Reactor Health Physicist.

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d. In evalu'ating experiments, the following assumptions shall be used for the purpose of determining whether. failure' of,.the' experiment would cause the1 appropriate limits of 10CFR 20'to be exceeded:

1. If the. possibility. exists. that' airborne concentrations of- radio - H

. active gases' or aerosols may be ' released within the' facility,100 percent of the gases or aerosols will escape; 1

2. If the' effluent exhausts through a' filter installation designed  :;

for greater than 99 percent. efficiency for 0.3 micron particles,- )

at least 10% of gases or. aerosols will escape; and )

3. For' a material whose boiling point is'above 130*F and-where vapors formed by boiling, this material could escape.only through a column of water above the core, at least 10 percent of.these vapors will escape.

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