ML20206Q137

Proposed Tech Specs,Reflecting Change of Nuclear Engineering Status from Program to Dept

ML20206Q137
Person / Time
Site:	05000356
Issue date:	04/14/1987
From:	ILLINOIS, UNIV. OF, URBANA, IL
To:
Shared Package
ML20206Q121	List: ML20206Q114 ML20206Q137
References
NUDOCS 8704210350
Download: ML20206Q137 (7)

Text

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IN .

6.0 : -ADMINISTRATIVE CONTROLS-6.1. Organization a '. The LOPRA facility shall be=an integral part of the Department of c Nuclear, Engineering of . the College of Engineering of - t.he University of Illinois. The LOPRA shall be related 'to the University structure.as  ;

shown in Chart I.

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b. The LOPRA facility _shall-be under the' supervision of the~ Reactor Supervisor who shall.have qualified as a licensed senior operator for the LOPRA. He shall be responsible for assuring that'a11~. operations

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

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c. There shall be a Reactor Health Physicist responsible for assuring the day to day and routine radiological; safety activities at the-Nuclear H Reactor Laboratory. The University of Illinois Radiation. Safety Officer.shall be responsible for monitoring, plannin.g.and promoting 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 radiological hazard.- _.

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

L. _ _ _ _ _ .) Radiation Safety Nuclear Reactor ~~

Director of I Officer

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Committee Nuclear Reactor l- '

I Laboratory  :

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I i i i e i L__ Reactor Reactor Heaith ,___g_

Supervisor Physicist.

Licensed Operators Reactor-Operation Chart I. 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 LOPRA 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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b .' - The responsibilities of the Committee include,:but'are not-limited to-the following: '

l. Review and approval of: experiments utilizing the.LOPRA facilities;

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 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 1 - anomalies; i

~ 6. Review of unusual ~ occurrences and incidents which are reportable under 10CFR$20 and 20CFR$50; and j 7. Approval of individuals for the supervision and operation of the

LOPRA.

c. The Committee shall be composed of at least five voting members, one 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 4 the Department of Nuclear Engineering, chosen from the faculty of-l Nuclear Engineering so as to maintain a balanced knowledge of reactor j safety and regulation. The Reactor Supervisor and the Reactor Health j Physicist shall be non-voting members.

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d. The' Committee shall have a written statement. defining such matters as 3 the authority of the Committee, the subjects within its purview,~ and other such administrative provisions as are required for effectiive functioning of the Committee. Minutes of a11' meetings of the  ;

a Committee shall be kept. '

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.

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f. The Reactor committee shall meet at least quarterly with the interval

between meetings not to exceed 5 months. .

l 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 LOPRA, but should not 1 preclude the use of independent judgment and action should the situation

, require such.

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'i 'a. Startup, operation, gud shutdown of the'LOPRA. ,

4 b.' Installation or removal 2 of fuel- elements, . control rods, experiments,

and experimental facilities.

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

tions of systems or components,' including responses to alarms-and.

l abnormal reactivity. changes.

d. Emergency conditions involving potential or actual reldas'e of? radio- :p

[i . activity, including provisions for evacuation,: re-entry, recovery, and l ' medical support.- _

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=e. Maintenance procedures which could have an effect on LOPRA safety. ,

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'f. Periodic' surveillance of'LOPRA instrumentation ~and safety systems,1 area:

) -monitors and continuous air monitors. ,

i Substantive changes to the above procedures-shall be made only with the approval of the Nuclear Reactor Connaittee. Te'aporary changes to the proca '

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dures that'do not change their original intent may.be made with the appro- -

val of the Reactor Supervisoc. All such temporary changes to-procedures T' shall be documented and subsequently reviewed by the Nuclear Reactor. '

}_ Committee.

6.4 Review and Approval of Experiments All proposed experiments utilizing the LOPRA shall be evaluated by the

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experimenter and a staff member approved by the_ Nuclear Reactor; Committee. The evaluation chall be reviewed by a licensed senior I operator of the facility (and the Reactor Health Physicist when

! appropriate) to assure compliance with the provisions of the utiliza--

j tion license, the Technical-Specifications, and 10CFRS20..

1 If, in his judgment, the experiment meets with the above provisions and

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does not constitute a threat to the integrity'of the LOPRA, the senior operator shall submit it to the Reactor Supervisor. for scheduling or "to ,

the Nuclear Reactor Committee for f.inal approval as; indicated in

! Section 6.2 above. When pertinent, the evaluation shall include

.i l 1. The reactivity worth of the experiment; i 2. Theintegrityoftheexperiment, including [theeffectsofchanges

in temperature, pressure, or chemical composition;

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j 3. Any physical or chemical interaction that could occur with the

! reactor components; and i 4. Any radiation hazard that may result from the activation of

! materials or from external beams.

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i b. Prior to the performing of an experiment, not previously performed in l the LOPRA, it shall be-reviewed and approved in writing by the Nuclear i Reactor Committee. Their review shall consider-the following '

I information:- . .

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-The.purposeoof the experiment; 1.

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 'explo-sive materials ~and which do not constitute.a significant threat'to the integrity of the LOPRA or to the safety.of individuals), the approval t~ for the N clear u Reactor Committee may be made by the Reactor Supervisor and Reactor Health Physicist.

In-evaluating experiments, the following assumptions shall be/used = for 'N

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the purpose of determining whether failure- of the experiment' wouldl cause the appropriate limits of ~ 10CFR520 to be exceeded:

l l 1. If the possibility exists that' airborne concentrations"cf radio-active gases or aerosols may be released within the facility, 100 percent of theLgases or aerosols will escape; i ,

2. If the effluent exhausts through a filter installation designed for greater than 99 percent efficiency for 0.3 micron particles, i j at least 10% of the particulates will escape; an'd

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.

i 6.5 Action to be Taken in the Event a Safety Limit is Exceeded In the event a safety limit is exceeded, or thought to have been exceeded:

a. The LOPRA e '1' be shut down and.LOPRA operation shall not be resumed until authorita by the USNRC. j l b. An immediate report of the occurrence shall be made to the Chairman'of ll

. the Nuclear Reactor Committee and reports shall be made to the~USNRC in -1 l accordance with Section 6.7 of these specifications.

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.. 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 probability 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 LOPRA is sought.

t 6.6 Action to be Taken in the Event of a Reportable Occurrence 1

In the event of a reportable occurrence, as defined in Section 1.12 of the l specifications, the following actions shall be taken.

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The Reactor Supervisor shall be notified and corrective action taken'

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-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 corrective action, and recommendations for;. '

measures.to prevent er reduce the probability of reoccurrence. This '

report shal1~be submitted to the Nuclear Reactor Committee for review.

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

9, 6.7 -Reporting Requirements  ;

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

a. An immediate report (by telephone'and= telegraph ~to the Regional- ,

Administrator, USNRC, Region III) oft y ~

1. Any accidental off-site release.of radioactivity above: permissible limits,'whether or not the release resulted in property damage, personal injury or exposure; 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 telephone and' telegraph to the Regional' q '

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 LOPRA;

2. < In'cidents or conditions relating tio operation of the facility- -

which prevented or could have prevented the performance of engi- i

neered safety features as described in these specifications; and i 3. Any reportable occurrences as defined in Section 1.12 of these [

specifications.

c. A report within 14 days (in writing to the Director, Office of. Nuclear 4 Reactor Regulation, Document Control Desk,'USNRC Headquarters) of:

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

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

3. Any' reportable occurrences as defined in Section 1.12 of'these 'l specifications.  :

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d A report within 30 days (in writing to the Director, Office of Nuclear Reactor Regulation, Document Control Desk, USNRC Headquarters) of:

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.1. Any substantial variance from performance specifications contained in these specifications;;

2. - Any.significant change in'the transient or accident analyses as -,

' described in the-Safety Analysis Report;

3. Any changes in facility organization; and

4. 'Any observed inadequacies in the implementation of administrative or procedural controls.

e. A report within 60 days af ter criticality of the LOPRA (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 LOPRA power level or the installation of_a new core, describing the measured values of the operating conditions or characteristics of_the LOPRA under the new conditions, including:

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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 LOPRA; and j 4. Minimum snutdown margin both at room and operating temperatures.

f. A routine report (in writing to the Director, Office of Nuclear Reactor Regulation, Document Control Desk, USNRC Headquarters) within 60 days after completion of the first six months of facility operation and at the end of each 12-month period thereafter, providing the following.

information:

1. A narrative summary of operating experience (including experiments performed) and of changes in facility design, performance charac-teristics and operating procedures _related to LOPRA safety occurring during the reporting period;

2. A tabulation showing the energy generated by the LOPRA (in megawatt-hours), the amount of pulse operation, the number of hours the LOPRA was critical.

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 LOPRA, 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 conditions of.Section 50.59 of

. 10CFR$50; O

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6. .A' summary of_the nature and~ amount of radioactive effluents released or discharged to the environs beyond the effective

' control of the licensee.as measured at or prior to the point of' l

such' release or discharge;.

7. A description of any environmental' surveys performed outside the facility; and A summary of radiation exposures-received by facility; personnel-

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-and visitors, including the dates and times of significant expo-sures,:and a summary of the results of radiation and contamination surveys performed within the facility.

16.8 Records Records to be Retained for a Period of at Least Five Years:

. Normal reactor facility operations-(including scheduled and unscheduled

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shutdowns)

b. Principal maintenance operations

c. Reportable occurrences

d. Surveillance activities required by Technical Specifications-

e. Facility radiation and contamination surveys

f. Experiments performed with the reactor

g. Approved changes to operating procedures

h. Records of meetings of the Nuclear Reactor Committee Records to be Retained for the Life of the Facility:

a. Records of gaseous and liquid radioactive effluents released to the environment

b. Appropriate off-site environmental monitoring surveys

c. Fuel inventories and fuel transfers

d. ~ Radiation exposures for all personnel e._ Updated as-built drawings of the facility

f. Records of transient or operational cycles for those' components designed for a limited number of transients or cycles-

g. Records of training and qualification for' members of the facility staff.

h. Records and reviews performed for changes made to procedures or' equip-ment or reviews of tests and experiments pursuant to'10CFR550.59 These records may be coordinated for both the LOPRA and Advanced TRIGA Reactor facilities.

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