ML20215D182

Proposed Tech Specs Changing Status of Nuclear Engineering from Program to Dept & Changing Staffing of Nuclear Reactor Lab

ML20215D182
Person / Time
Site:	05000356
Issue date:	05/29/1987
From:	ILLINOIS, UNIV. OF, URBANA, IL
To:
Shared Package
ML20215D174	List: ML20215D172 ML20215D182
References
NUDOCS 8706180428
Download: ML20215D182 (9)

Text

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.. 'l Bases

. In order that the movement ~of air can be controlled : the building contains ; l no windows.that can be opened.. The room air is exhausted through absolute l filters and discharged through a stack-to provide dilution. d l

5.3 Fuel Storage ~ '1 Applicability

-.This specification applies to the storage of reactor fuel at; times when it is not in the reactor core.' 1 Objective The objective is to assure that fuel which is being st'ored will' not beco'me.

supercritical and will not reach an unsafe temperature.

Specifications

a. All' fuel elements shall be stored in a. geometrical array. where the keff ' 3" is less than 0.8 for all conditions of moderation. - -

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b. Irradiated fuel elements and fueled devices shall be stored'in an array _

..which will permit sufficient natural convection cooling by water or air such that the fuel element of fueled. device temperature will not exceed 800 C for the stainless steel clad LOPRA fuel. and 500*C for the aluminum clad LOPRA fuel.

Bases New fuel is stored in its shipping containers or in a ~15-position rack in a locked storage room. Hot fuel-is stored 'in pits described in Section. IX of -

the SAR for the Advanced TRIGA reactor. These pits are designed to hold 24 elements, an amount which cannot~ form a critical ar' ray.- Very hot _ fuel is stored in racks in the main tank or the bulk shielding tank where' cooling .

water is provided.

6.0 ADMINISTRATIVE CONTROLS 6.1 Organization Amendment-No.4

a. The LOPRA facility shall be an integral part -of _ the Department of Nuclear Engineering of the Colic:ge of Engineering' of the 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 f be unde'r the supervision of the Reactor -

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-Supervisor who shall have qualified as a licensed senior" operator for the LOPRA.. .He shall_ be responsible'for assuring that all. operations .l are conducted in a safe manner and within the' limits prescribed by the: j facility license and the provisions' of the' Nuclear Reactor Committee.' Amendmen

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

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Reactor Laboratory. The. University of Illinois Radiation; Safety -]

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

responsibility and' authority to stop, secure or otherwise contro11as-necessary any operation or activity that poses an unacceptable I radiological hazard.

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

~----9 Radiation Safety Nuclear Reactor Director of l. Officer Committee Nuclear Reactor i l q 8

Laboratory [  ;

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t--~ Reactor ~~~~~~~

Reactor Health --~~;

Supervisor Physicist l i Licensed j Operators 1 Reactor l Operation .j i

Chart 1. Administrative organization of the reactor facility. Dashed ~ I lines indicate reporting paths outside the operational chain.of supervision, '

indicated by solid lines.  ;

6.2 Review 's

a. There shall be a Nuclear React'or Committee which shall review LOPRA - i operations to assure that the facility is operated.in a manner con- i 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 1 the following:

1. 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 anomalies; 16- )

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- 6. Review of-unusual occurrences and incidents which are reportable .

under 10CFR 20 and 20CFRE50;.and

7. Approval of individuals for the supervision and ope' ration of the LOPRA. Amendment' No.4

c. The Committee shall b.e 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 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.4

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.

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 preclude the use of independent judgment and action should the situation' require such.

a. Startup, operation, and' shutdown of the LOPRA.

b. Installation or removal 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 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 LOPRA safety,

f. Periodic surveillance of LOPRA instrumentation and safety systems, area lj monitors and continuous air monitors.

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Substantive changes to the"above procedures shall. be made only with the approval of the _ Nuclear _ Reactor Committee.. Temporary changes to the proce- -i

-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 q shall be documented and subsequently reviewed by the Nuclear Reactor Committee.

6.4 Review and Approval of Experiments 1

a. All proposed experiments utilizing the LOPRA~ shall be evaluated by the il experimenter and a staff member approved by the Nuclear ReactorL J 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. t If, in his judgment,' the- experiment meets with the' above provisions ~ and 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 Conmittee for final approval as indicated.in 1 Section 6.2.above. When pertinent, the evaluation shall-include- -d

1. The reactivity worth of the experiment;

2. The integrity of the experiment, including the effects of changes' l in temperature, pressure, or chemical composition; '

3. Any physical or chemical interaction that'could occur with the reactor components; and i 1

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

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

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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 explo-- l sive materials and which do not constitute a significant

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- threat to the integrity.of- the LOPRA or to the safety.'.of: individuals),

the approval for the Nuclear Reactor Committee may be made by the Reactor. Supervisor'and Reactor-Health Physicist.

d. .In evaluating experiments', the'.following assumptions shall be used for the purpose of determining whether failure of.the experiment would

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cause the appropriate limits of:10CFR 20 to be exceeded:

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

2. If the effluent- exhausts through a- filter' instal _lation.' designed -

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

at least 10% of the particulates will escape; and

3. For a material whose b' oiling ~ 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.

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:

Amendment

a. The LOPRA shall be shut down and LOPRA operation shall-not be' resumed No.4 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 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.

6.6 Action to be Taken in the Event of, a Reportable Occurrence ' i In the event of a reportable occurrence, as defined in Section 1.12 of the specifications, the following actions shall be taken.

a. The Reactor Supervisor shall be notified and corrective action taken prior to resumption of the operation involved. ,

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.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 ~or reduce the probability of reoccurrence. . This

. report shall be submitted.to the Nuclear Reactor Committee for review.

Amendment-c.- Where appropriate, a report shall-be submitted to the USNRC in accor-No.4' dance with Section 6.7 of these specifications.: I 6.7 Reporting Requirements In addition to the' requirements of applicable regulations, and in no way No.4 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);of:

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. Amendment-

'No.4

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 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. 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 reportable occurrences as defined in.Section 1.12 of these specifications. Amendment-

c. A report within 14 days (in writing to the Director, Office'of. Nuclear Reactor Regulation, Document Control Desk, USNRC Headquarters) 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. 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 20 l

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3. . Any , reportable. occurrences:as . defined in Section 1.12 of these i specifications. 4,, g,, ,[

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

Any substantial variance from performance specifications contained- ~I 1.

-in these specifications;

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

3. Any changes _in facility organization;'and-1

4. Any observed inadequacies in the imp 1'ementation of administrative

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or. procedural controls. - Amendment-

e. A report within 60 days' after 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.- -i 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:

1. Total control rod reactivity worth;- I l

.2.. Reactivity worth of the single control ro'd of highest reactivity; j worth; R

3. Total and individual reactivity worths -of any experiments inserted in the LOPRA; and 1

4. Minimum shutdown margin both 'at room and operating temperatures'. LAmen'dment No.4

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.

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3. :The number of ~ emergency shutdowns and . inadvertent iscrams',-

including the. reasons therefore;

4. Discussion of the major maintenance' operations performed.du' ring the period, . including the effect, if- any, on-the safe. operation-of .

the LOPRA, and the. reasons.for any corrective maintenance' required; A summary of.each change to the facility or procedures, tests, and

5. . . experiments - ca rried s out: under the conditions of Section 50.59 of.

L10CFR 50;

6. A summary of the nature and amount of radioactive' effluents released or discharged to the environs beyond the effective 1 control of the licensee as measured at or prion to the point of such release or discharge;- ,

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

8. A summary of radiation exposures received-by facility. personnel and visitors, including the dates and times of .significant expo-sures, and a summary of the results of radiation andLeontamination surveys performed within the facility.

6.8 Records-Records to be Retained for a Period of at least Five Years: .

a. Normal reactor facility operations (including scheduled' and unscheduled j 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 i

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a Records to'be Retained for the Life of the Facility:

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

b. Appropriate off-site environmental monitoring surveys j

c. Fuel inventories and fuel transfers- l 1

d. Radiation exposures for all personnel

e. Updated as-built drawings of the facility

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

g. Records of training and qualification for members of the facility. staff 1

h. Records and reviews performed for changes made to procedures or equip- i ment or reviews of tests and experiments pursuant to 10CFR@50.59 These records may be coordinated for both the LOPRA and Advanced TRIGA Reactor facilities. i l

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