ML20059H701

Proposed Tech Specs Reflecting Changes to Administrative Controls for Nuclear Reactor Lab

ML20059H701
Person / Time
Site:	University of Illinois
Issue date:	01/11/1994
From:	ILLINOIS, UNIV. OF, URBANA, IL
To:
Shared Package
ML20059H511	List: ML20059H507 ML20059H701
References
NUDOCS 9401310117
Download: ML20059H701 (26)

Text

.

~

6.0 ADMINISTRATIVE CONTROLS 6.1 Orminization 6.1.1 Structure and Responsibility

a. The reactor facility shall be an integral part of the Department of Nuclear Engineering of the University of 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 ReactoFSuperviser Reactor Administrator who l

shall have been qualified as a licensed senior operator for the reactor. He shall be responsible for assuring that all operations are conducted in a safe manner and within the limits prescribed by the facility licmse and the provisions of the Nuclear Reactor Committee.

l

c. There shall be a Reactor Health Physicist responsible for assuring the day to day and routine radiological safety activities at the Nuclear Reactor Laboratory. The University ofIllinois 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 control as necessary any operation or activity that poses an unacceptable radiological hazard.

CHARTI liend, Depetment of Divuine oflanironmental Nuclour Faq6eeming i

Rachneion Safety Otlker Reessor Conmartee Remtor Admmistrator Reactor Heulth Physicise Operstmns Supenient l op.,.,% se l

CHART 1: Administrative organization of the reactor facility. Dotted lines indicate reportingcommunication paths l

outside the operational diain of supervision, indicated by solid lines.

9401310117 940111 4

PDR ADOCK 05000151 [4

- P PDR l

~-.

t 6.1.2 StafHng

a. 'Ihe minimum staffing when the reactor is not shutdown shall be:

1. A licmsed reactor operator shall be in the control room.

2. A second designated person shall be present inside the reactor building able to shutdown the reactor in an emergency. Unexpected absence for as long as two hours to acconunodate a personal emergency may be -

acceptable provided immediate action is taken to obtain a replacement.

3. A Senior Reactor Operator shall be readily available on call as defined in the Nuclear Reactor Laboratory Rules and Regulations.

o. A list of reactor facility personnel by name and telephone number shall be readily available in the control -

room for use by the operator. The list shall include:

1. Reactor Operations Supervisor l

2. Director-ofWuclear-Reactor-Laboratory Reactor Administrator l

3. Head, Department of Nuclear Engineering

4. Reactor Health Physicist l.

5. Licensed operators

c. Events requiring the presence at the facility of a Scnior Reactor Operator:

1. Initial startup and approach to power.

2. All fuel or control rod relocations within the reactor core region.

3. Relocation of any in-core experiment with a reactivity woith greater than one dollar.

4. Recovery from unplanned or unscheduled shutdown or significant power reduction (in these instances, documented verbal concurrence from the Senior Reactor Operator is required).

6.1.3 Selection and Training of Personnel i

The Reactor-Superwser Reactor Administrator is responsible for the training and requalification of the facility l

l reactor operators and senior reactor operators. The selection, training, and requalification of operations personnel.

shall be consistent with all currcnt regulations and guidelines.

l i

6.2 Review and Audit 6.2.1 Charter and Rules i

a. He Reactor Comnsttee shall be composed of at least five voting members, one of whom shall be a Health Physicist designated by the Healtl@hysicsreffice+f-campus Radiation Safety Officerfor the University, and one whom shall be the Directoref4heNuclear-Reactor-Laboratory Reactor Administrator. 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 a non-voting members.

b. De Reactor Conunittee shall have a wntten statemmt defining such matters as the authority of the l

committee, the subjects within its purview, and other such administrative provisions as are required for the effective functioning of the Reactor Committee. Minutes of all meetings of the Reactor Committee shall be l

kept.

A quorum of the Reactor Committee shall be a majority of not less than one half of the members and the l

c.

reactor operating staff shall not constitute a voting majority.

d. The Reactor Committee shall meet at least quarterly with the interval between meetings not to exceed 5 i

months.

6.2.2 Review Function The review function of the Committee shall include, but is not linsted to the following:

Determinations that proposed changes in equipment, systems, tests, experiments, or procedures do not a.

involve an unreviewed safety question.

b. All new procedures and major revisions thereto having safety significance, proposed changes in reactor facility equipment, or systems having safdy significance.

c.

All new experiments or classes of experiments for determination that an unreviewed safety question does not exist.

d.

Proposed changes in the technical specifications or licmse.

e.

Violations of technical specifications or license.

f.

Operating abnormalities having safety sigtsficance.

g.

Reportable occurrmces as listed in 6.8-2.

.l h.

Audit reports A written report or nsnutes of the findings and recommendations of the Committee shall be submitted to the Head, Department of Nuclear Engineering, and the Reactor Comnsttee members in a timely manner after each meeting.

l t

e a g 4

- 6.2.2 Audit Function The audit function of the Reactor Committee shall include selective (but comprehensive) examination of operating l

records, logs, and other documents. Discussions with cognizant personnel and observation of operations should be uscxi also as appropriate. In no case shall the individual immediately responsible for the area perform an audit in that area. The following items shall be audited:

a. Facility operations for conformance to the technical specifications and license, at least once per calendar year (interval between audits not to exceed 15 months).

b. The requalification program for the operating staff, at least every other calendar year (interval between audits not to exceed 30 months).

c. The action taken to correct those deficiencies that may occur in the reactor facility equipment, systems, structures, or methods of operations that affect reactor safety, at least once per calendar year (interval baween audits not to exceed 15 months).

d. The reactor facility emergency plan, and implementing procedures at least once every other calendar year (interval between audits not to exceed 30 months).

Deficiencies uncovered that affect reactor safety shall immediately be reported to the Head, Department of Nuclear Engineering. A written report of the findings of the audit shall be submitted to the Reactor Committee within three l

months after the audit is compided and then forwarded to the Head, Departmcnt of Nuclear Engineering.

9

?

t l

i r

}

i e -

m--

--.-e e

-ye-

=m

,e-e-

y-y

k

6.3 Radiation Safay The Reactor Health Physicist shall be responsible for implementing the Radiation Protection Program at the reactor such that all regulatory requirements are met and guidelines followed as applicable.

'i l

)

e i

e b

t

-I i

.i h

6.4 ' ProcWures Writtm procedures shall be prepared, reviewed and approved prior to initiating any of the actisities listed in this section. The procedures shall be reviewed by the Reactor Committee and approved by the Reactor-Director-Reactor Administrator and such review and approval shall be documented in a timely manner. The procedures shall be adequate to assure the safety of the reactor, but should not preclude the use ofindependent 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 and foresmn potential malfunctions of systems or components, including responses to alanns, suspected primary coolant leaks, and abnormal reactisity changes.

d. Emergency conditions involving potential or actual release of radioactivity, including provisions for evacuation, reentry-entry, recovery, and medical support.

c. Maintenance procedures which could have an effect on reactor safety.

f. Periodic surveillance of reactor instrummtation and safety systems, area monitors and continuous air monitors.

g. Personnel radiation protection, consistent with applicable regulations or guidelines. The procedures shall include managemcnt commitment and programs to maintain exposures and releases a4s llow aAs is rReasonably a4chievable(ALARA).

h. Implementation of physical security plan.

- Substantive changes to the above procedures shall be made only after documented review by the Reactor Committee and approval by the. Reactor DirectorAdministrator. Minor modifications to the original procedures which do not change their original intent may be made by the Reactoroperations Supervisor but the modifications must be.

approved by the Reactor DirectorAdministrator within 14 days. Temporary deviations from the procedures may be made by the responsible Smior Reactor Operator or higher individual present, in order to deal with special or.

unusual circumstances or conditions. Such deviations shall be documented and reported to the Reactor DirectorAdministrator:

l i

4 s

J s

n-------

n

..s

+

s.-

Experiments Review and Approval 6.5 x

a. All new experiments or class of experiments utilizing the reactor shall be evaluated by the experimmter and a staff member approved by the Nuclear Reactor Committee. The evaluation shall be reviewed by a licensed l

smior reactor operator of the facility and the Reactor Health Physicist to assure compliance with the provisions of the utilization license, the Technical Specifications and 10CFR20. If, in theirjudgment, the experiment meets with the above provisions and does not constitute a threat to the integrity of the reactor, they shall submit it to the ReactorOperations Supervisor for review, if the ReactorOperations Supervisor l

agrees with the evaluation by the senior reactor operator and the Reactor Health Physicist he shall submit the experiment to the Reactor Committee for review as indicated in Section 6.2. The experiment shall be approved in writing by the Reactor DirectorAdministrator prior to initiation. When pettinent, the evaluation shall include the following:

1. The reactivity worth of the experiment.

2. The integrity of the experimmt, including the effects of changes in temperature, pressure, or chemical composition.

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

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

b. The Reactor Committee review of an experiment shall be performedprior to thejirst experiment and shall l'

be documented in writing and shall consider at a minimum the following:

1. The purpose of the experiment.

2. A procedure for the performance of the experiment.

3. The evaluation approved by a licensed senior reactor operator.

4. Determination that the experiment does not involve an unreviewed safety question.

t Substantive changes to previously approved experiments shall be made only after review by the Reactor c.

Committee and approved in writing by the Reactor Director. Administrator Minor changes that do not significantly alter the safety analysis of the experiment may be approved by the Reactoroperations i

Supervisor or Reactor DirectorAdministrator.

d. For the irradiation of materials, the applicant shall submit a request to the Reactor Health Physicist and ReadorOperations Supenisor. This request shall contain at a minimum infonnation on thetarget material including the amount, chemical form, and expected radiological hazard for the desired irradiation period. 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 ofindividuals), the approval for the Reactor Committee may be made by the Reactor Health Physicist and the ReactorOperations l

Supenisor.

t I

_ -~-

j

+

e. In evaluating experiments the following assumptions shall be used for the purpose of determining whether failure of the experiment would cause the appropriate limits of 10CFR20 to be exceeded:

1.

If the possibility exists that airborne conceitrations of radioactive gases or aerosols may be released within the facility,100 percent of the gases or aerosols will escape.

If the effluent exhausts through a filter installation designed for gr 2.

for 0.3 micron particles, at least 10% of gases +r aerosols will escape.

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 those j

vapors will escape.

.L i

i t

e 5

h i

I P

1

.l q

--?

=

~..

6.6 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 reactor shall be shut down and reactor operation shall not resume until authorized by the USNRC.

b. The safety violation shall be promptly reported to the Reactor DirectorAdministrator and reposts shall be l

made to the USNRC in accordance with Section 6.8 of these specifications.

c. A safety limit violation report shall be prepared. The report shall describe the following:

1. Applicable circumstances leading to the violation including, when known, the cause and centributing factors.

2. Effect of the violation upon reactor facility components, systems, or structures and on the health and safety of personnel and the public.

3. Corrective action to be takm to prevent recurrence.

The report shall be reviewed by the Reactor Conunittee and any follow up report shall be submitted to the USNRC ' j when authorization is sought to resume operation of the reactor.

f i

'l

~

6.7 Action to be takm in the Event of an Abnormal Occurrence in the event of an abnormal occurrence, as defmed in Section 1.14 of the specifications, the following action shall be taken:

a. The reactor shall be shutdown and the ReactorOperations Supervisor and Reactor Administrator shall be notified and corrective action taken prior to resumption of operations. 'Ibe Reactor DirectorAdministrator shall authorize resumption of operations.

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 reoccurrmee.

c. The occurrence shall be reviewed by the Reactor Committee at the next scheduled meeting.

[

d. A report shall be submitted to the USNRC in accordance with Section 6.8 of these specifications.

a f

3 E

5

6.8 R_eporting Requirements I

In addition to the requirenents of applicable regulations, and in no way substituting therefore, reports shall be made -

to the USNRC as follows:

a. There shall be a report not later than the following working day by telephone and confirmed in writing by facsimile or similar conveyance to the Regional Administrator, USNRC, Region 111 and the USNRC headquarters operations center to be followed by a written report that describes the circumstances of the -

event that describes the event within 14 days to the Document Control Desk, USNRC Headquarters, and a copy to the Regional Administrator, USNRC, Region III of any of the following:

1 Release of radioactivity from the site above allowed limi,

2. Violation of safety limits.

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

4. Incidents or conditions relating to operation of the facility which prevented or could have prevented the performance of engineered safety features as described in these specifications,

5. Any abnormal occurrences as defmaiin Section 1.14 of these specifications.

b. A report within 30 days (in writing to the Document Control Desk, USNRC Headquarters) of;

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

2. Significant changes in the transient or accident analysis as described in the Safety Analysis Report.

3. Permanent changes in the facility organizaticn involving the ReactorOpemtions Supervisor, Reactor DirectorAdministrator or Department Head.

c.

A report within 60 days after criticality of the reactor (in writing to the Document Control Desk, USNRC Headquaners) 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 woith.

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

4. Minimum shutdown margin both at room and operating temperatures.

1

^\\

m

~

w

d. A routine report (in writing to the 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 reactor operating experimce including the energy produced by the reactor, hours critical, and amount of pulsing operation.

2. 'Ihe unscheduled shutdowns including, where applicable, corrective action taken to preclude recurrmce.

3. Tabulation of major preventive and corrective maintenance operations having safety sigmficance.

4. Tabulation of major changes in the reactor facility and procedures, and tabulation of new tests, experimmts or both, that are significantly differmt from those performed previously and are not -

j described in the Safety Analysis Report, including a summary of safety evaluation leading to the.

I conclusions that no unreviewed safety questions were involved. {Per 10 CFR 50.59 (b)(2)}

5. A sununary of the nature and amount of radioactive effluents released or discharged to emirons beyond the effective control of the licensee as measured at or prior to the point of such release or discharge, The summary shall include to the extent practicable an estimate ofindividual radionuclides presmt in the effluent. If the estimated average release after dilution or diffusion is less than 25 percent of the concentration allowed or recommended, a statement to this effect is sufficient.

6. A summarized result of environmental surveys performed outside the facility.

7. A summary of exposures received by facility personnel and visitors where such exposures are greater than 25 percmt of that allowed or recommended.

l 1

I l

l R__________

l

... ~.

l

'6.9 ' Plant Opera.tingR_ecords In addition to the requirements of applicable regulations, and in no way substituting therefore, records and logs shall be prepared and raained as follows:

a. Records to be retained for a period of at least five years or for the life of the component involved ifless than i

five years:

1. Normal reactor facility operation (but not including supporting documents such as checklists, log sheets, etc., which shall be maintained for a period of at least one year).

l

2. Principle maintenance operations

3. Rgortable occurrences l

4. Surveillance activities required by the Technical Specifications j

5. Reactor facility radiation and contamination surveys 1

6. Experimmts perfonned with the reactor

7. Fuel inventories, receipts, and shipments j

8. Approved changes in operatingprocedures

9. Records of meeting and audit reports of the Committee 1

b. Records to be retained for at least one certification cycle:

i

1. Record of retraining and requalification of certified operations personnel shall be maintained at all times j

the individual is employed or until the certification is renewed.

i

c. Records to be retained for the lifetime of the reaccor facility:

1. Gaseous and liquid radioactive effluents released to the mvirons

2. Off-site mvironmental monitoring surveys

3. Radiation exposure for all personnel monitored

4. Drawings of the reactor facility i

f a

1

i i

Technical Specification Revisions as they will appear.when inserted.

t i

a 3

h i

u

.- 31

-i

' 6.0 A_DMINISTRATIVE CONTROLS 6,1 Orcanization'-

I 6.1.1 Structure and Responsibility

a. The reactor facility shall be an integral part of the Department of Nuclear Engineering of the University of Illinois. He reactor shall be related to the University stru.ture as shown in Chart I.

i

b. The reactor facility shall be under the superi.sion of the Reactor Administrator who shall have becn qualified as a licensed senior operator for the reactor. He 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 prosisions of -

the Reactor Committee.

c. There shall be a Reactor Health Physicist responsible for assuring the day to day and routine radiological safety activities at the Nuclear Reactor Laboratory. He University of Illinois Radiation Safety Officer shall be responsible for monitoring, planning and promoting radiological safety at the Nuclear Reactor l

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.

i CHARTI

+

Ilead. Dopertnwnt of ihmirm of fiawironnental lisalth and Safuty g, g.

l a.a.i s.r,y os.r l

l Re. con.n.o Rmw Adnmawrsw 5._..--

Randor Houlth Phyescist l oPwWins hpnier l

loP=ota l

f CHART I: Administrative organization of the reactor facility. Dotted lines indicate communication paths outside the operational chain of supervision, indicated by solid lines.

i l.

t I

e

l 6.1.2 Stafing

a. The minimum staffmg whm the reactor is not shutdown shall be:

i

1. A licensed reactor operator shall be in the control room.

2. A second designated person shall be present inside the reactor building able to shutdown the reactor in an emergency. Unexpected absence for as long as two hours to accommodate a personal emergmcy may be.

acceptable provided immediate action is taken to obtain a rcplacement.

l

3. A Smior Reactor Operator shall be readily available on call as defined in the Nuclear Reactor Laboratory Rules and Regulations.

1

b. A list of reactor facility personnel by name and telephone number shall be readily available in the control room for use by the operator. The list shall include:

,t

1. Operations Supervisor

2. Reactor Administrator

3. Head, Department of Nuclear Engineering

4. Reactor Health Physicist i

5. Licensed operators

c. Events requiring the presmee at the facility of a Smior Reactor Operator:

1. Initial startup and approach to power.

2. All fuel or control rod relocations within the reactor core region.

3. Relocation of any in-core experiment with a reactivity worth greater than one dollar.

4. Recovery from unplanned or unscheduled shutdown or significant power reduction (In theseinstances,.

l documented verbal concurrmcc from the Senior Reactor Operator is required).

6.13 Selection and Trainine of Personnel

{

. The Reactor Administrator is responsible for the training and requalification of the facility reactor operators and I

smior reactor operators. 'the selection, training, and requalification of operations personnel shall be consistmt with all currmt regulations and guidelines.

l i

l t

~

6.2 Review and Audit 6.2.1 Giarter and Rules

a. The Reactor Committee shall be composed of at least five voting members, one of whom shall be a Health.

Physicist designated by the campus Radiation Safety Officer for the University, and one whom shall be the l

Reador Administrator. Three members shall be appointed by the Head of the Departmmt of Nuclear.

i Engineering, chosen from the faculty of Nuclear Engineering so as to maintain a balanced knowledge of reactor safety and regulation. The Reactor Health Physicist shall be a non-voting member.

l t

b. The. Reactor Committee shall have a writtm statement defining such matters as the authority of the committee, the subjects within its purview, and other such administrative provisions as are required for the effective functioning of the Reactor Committee. Mimites of all meetings of the Reactor Committee shall be kept.

A quorum of the Reactor Conunittee shall be a majority of not less than one half of the members and the c.

reactor operating staff shall not constitute a voting majority.

j i

d. The Reactor Committee shall med at least quarterly with the interval between meetings not to exceed 5 l

months.

6.2.2 Review Function The review function of the Committee shall include, but is not limited to the following:

Determinations that proposed changes in equipment, systems, tests, experiments, or procedures do not

{

a.

involve an unreviewed safety question.

b. All new procaiures and major revisions therdo having safety significance, proposed changes in reactor facility equipment, or systems having safety significance.

c. All new experiments or classes of experiments for determination that an unreviewed safety question does not exist.

d.

Proposed changes in the technical specifications or licmse.

i e.

Violations of technical specifications or license.

4

-i f.

Operating abnormalities having safety significance.

g.

Reportable occurrences as listed in 6.8.

h.

Audit reports i

A written report or minutes of the findings and recommendations of the Committee shall be submitted tc the Head,.

l Departmmt of Nuclear Engineering, and the Reactor Committee members in a timely manner after each meeting.

l

4

.6.2.2 Audit Fun _gionl o

t ne audit function of the Reactor Committee shall include selective (but comprehensive) examination of operating records, logs, and other documents. Discussions with cognizant personnel and observation of operations should be used also as appropriate. In no case shall the individual immediately responsible for the area perform an audit in that area. The following items shall be audited:

4 Facil' ty operations for conformance to the technical specifications and license, at least once per calendar year i

a.

(interval between audits not to exceed 15 months).

1

b. He requalification program for the operating staff, at least every other calendar year (interval between audits not to exceed 30 months).

c. The action taken to correct those deficiencies that may occur in the reactor facility equipment, systems, l

structures, or methods of operations that affect reactor safety, at least once per calendar year (interval between audits not to exceed 15 months).

d. The reactor facility emergmcy plan, and implementing procedures at least once every other calendar year (interval between audits not to exceed 30 months).

Deficiencies uncovered that affect reactor safety shall immediately be reported to the Head, Department of Nuclear -

Engineering. A written report of the findings of the audit shall be submitted to the Reactor Committee within three i

months after the audit is completed and then fonvarded to the Head, Departmmt of Nuclear Engineering.

i L

s

?

t r

i Il i

1

-1 I

i i

w -

W 5

.35 1

.' 6.3 Radiation _Safgy De Reactor Health Physicist shall be responsible for implenunting the Radiation Protection Program at the reactor such that all regulatory requirements are met and guidelines followed as applicable.

j I

i t

i f

6 f

t t

9 s'l s

r l

i

.i 5

s a

.w

. > - +

6.4 Procedures s

Writtm procedures shall be prepared, reviewed and approved prior to initiating any of the activities listed in this section. The procedures shall be reviewed by the Reactor Committee and approved by the Reactor Administrator

- and such review and approval shall be docummted in a timely manner. The procedures shall be adaluate to assure the safety of the reactor, but should not preclude the use ofindependent 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 expenmental facilities.

c.

Actions to be taken to correct specific and foreseen potential malfunctions of systems or components,.

including responses to alarms, suspected primary coolant leaks, and abnormal reactisity changes.

d. Emergency conditions involving potential or actual release of radioactivity, including provisions for evacuation, reentry-entry, recovery, and medical support.

c.

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.

g. Personnel radiation protection, consistent with.pplicable regulations or guidelines. The procedures shall include management commitment and progran s to maintain exposures and releases As Low As is Reasonably Achievable (ALARA).

h. hnplementation of physical security plan.

Substantive changes to the above procedures shall be made only after documented review by the Reactor Committee and approval by the Reactor Administrator. Minor modifications to the original procedures which do not change their original intent may be made by the Operations Supervisor but the modifications must be approved by the Reactor Administrator within 14 days. Temporary deviations from the procedures may be made by the responsible Senior Reactor Operator or higher individual present, in order to deal with special or unusual circumstances or i

conditions. Such deviations shall be documenteri and reported to the Reactor Administrator

-l i

8 l

t i

5 t

=

6:5 E_xperimmts Review and Approval

a. All new experimmts or class of experiments utilizing the reactor shall be evaluatal by the experimenter and a staff member approved by the Reactor Committee. He evaluation shall be reviewedby a licmsed senior reactor operator of the facility and the Reactor Health Physicist to assure compliance with the provisions of the utilization licmse, the Technical Specifications and 10CFR20. If, in theirjudgment, the experiment meets with the above provisions and does not constitute a threat to the integrity of the reactor, they shall submit it to the Operations Supervisor for review. If the Operations Supervisor agrees with the evahtation i

by the smior reactor operator and the Reactor Health Physicist he shall submit the experimait to the Reactor Committee for review as indicated in Section 6.2. The experiment shall be approved in writing by the Reactor Administrator prior to initiation. When pettinent, the evaluation shall include the following:

1. He reactivity worth of the experiment.

2. he integrity of the experimmt, including the effects of changes in temperature, pressure, or chemical composition.

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

4. Any radiation hazard that may res

• Sm the activation of materials or from external beams.

s

b. He Reactor Committee review of an experimmt shall be performal prior to the first experiment and shall be documented in writing and shall consider at a minimum the following:

. j

1. The purpose of the experir.ent.

2. A procedure for the performance of the experimmt.

3. The evaluation approved by a licensed smior reactor operator.

4. Determination that the experiment does not involve an unreviewed safety question.

c.

Substantive changes to previously approved experimmts shall be made only after review by the Reactor Committee and approved in writing by the Reactor Administrator Minor changes that do not significantly alter the safety analysis of the experiment may be approved by the Operations Supervisor or Reactor Administrator.

d. For the irradiation of materials, the applicant shall submit a request to the Reactor Health Physicist and Operations Supervisor. This request shall contain at a minimum information on the target material including the amount, chemical fonn, and expected radiological hazard for the desired irradiation period. 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 ofindividuals), the approval for the Reactor Committee may be made by the Reactor Health Physicist and the Operations Supervisor.

i i

__m,'

t 1

l

• l

e. In evaluating experimmts the following assumptions shall be used for the purpose of determining whether j

failure of the experiment would cause the appropriate limits of 10CFR20 to be exceeded:

1.

If the possibility exists that airbome concentrations of radioactive gases or aerosols may be released within the facility,100 percent of the gases or aerosols will escape.

2.

If the efflumt exhausts through a filter installation designed for greater than 99 perca t efficiency '

for 0.3 micron particles, at least 10% of aerosols will escape.

j 3.

For a material whose boiling point is above 130 F and where vapors fomied by boiling this l

material could escape only through a cohunn of water above the core, at least 10 percent of those.

j vapors will escape.

t

.- t

?-i k

t h

i I

s i

s i

{

t e

i a

e a

6.6. 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 reactor shall be shut down and reactor operation shall not resume until authorized by the USNRC.

b. The safety violation shall be promptly reported to the Reactor Administrator and reports shall be made to the USNRC in accordance with Section 6.8 of these specifications.

c. A safety limit violation report shall be prepared. The report shall describe the following:

1, Applicable circumstances leading to the violation including, when known, the cause and contributing factors.

2. Effect of the violation upon reactor facility components, systems, or structures and on the health and l

safety of personnel and the public.

3. Corrective action to be taken to prevent recurrence.

The report shall be reviewed by the Reactor Committee and any follow up report shall be submitted to the USNRC when authorization is sought to resume operation of the reactor.

+

C I

1 1:

L t

t l

I

~

6.7 Action to be taken in the Event of an Abnonnal Occurrence In the event of an abnonnal occurrence, as defined in Section 1.14 of the specifications, the following action shall be taken:

a. The reactor shall be shutdown and the Operations Supervisor and. Reactor Administrator shall be notified and

. corrective action taken prior to resumption of operations. The Reactor Administrator shall authorize -

l resmnption of operations.

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.

i

c. The occurrence shall be reviewed by the Reactor Committee at the next scheduled meeting.

d. A report shall be submitted to the USNRC in accordance with Section 6.8 of these specifications.

b a

r r

b E

6.8 R_eportinz Requirements In addition to the requirements of applicable regulations, and in no way substituting therefore, reports shall be made to the USNRC as follows:

a. Here shall be a report not later than the following working day by telephone and confinned in writing by facsimile or similar conveyance to the Regional Administrator, USNRC, Region III and the USNRC headquarters operations center to be followed by a written report that describes the circumstances of the event that describes the event within 14 days to the Document Control Desk, USNRC Headquarters, and a copy to the Regional Administrator, USNRC, Region 111 of any of the following:

l

1. Release of radioactivity from the site above allowed limits.

2. Violation of safetylimits.

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

I

4. Incidents or conditions relating to operation of the facility which prevented or could have prevented the perfonnance of cngineered safety features as described in these specifications.

i

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

b. A report within 30 days (in writing to the Document Control Desk, USNRC Headquarters) of i

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

2. Significant changes in the transient or accident analysis as described in the Safety Analysis Rcport.

3..Pennanent changes in the facility organization involving the Operations Supervisor, Reactor Administrator or Department Head.

A report within 60 days after criticality of the reactor (in writing to the Document Control Desk, USNRC c.

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.

4. Minimum shutdown margin both at room and operatingtemperatures.

• d. A routine report (in writing to the Document Control Desk, USNRC Headquarte s) within 60 days after completion of the first six months of facility operation and at the aid of each 12 month period thereafter, providing the following infonnation:

1. A narrative summary of reactor operating experiaice including the energy produced by the reactor, hours critical, and amount of pulsing operation.

2. The unscheduled shutdowns including, where applicable, corrective action taken to preclude recurrence.

3. Tabulation of major preymtive and corrective maintenance operations having safety significance.

4. Tabulation cf major changes in the reactor facility and procedures, and tabulation of new tests, experiments or both, that are significantly different from those performed previously and are not described in the Safety Analysis Report, including a summary of safety evaluation leading to the -

conclusions that no unreviewed safety questions were involved. {Per 10 CFR 50.59 (b)(2)}

5. A summary of the nature and amount of radioactive effluents released or discharged to msirons beyond the effective control of the licensee as measured at or prior to the point of such release or discharge. The summary shall include to the extent practicable an estimate ofindividual radionuclides present in the effluent. If the estimated average release after dihrtion or diffusion is less than 75 percait of the concmtration allowed or recommended, a statement to this effect is sufficient.

6. A summarized result of environmmtal surveys performed outside the facility.

7. A summary of exposures received by facility personnel and visitors where such exposures are greater than 25 percent of that allowed or recommended.

P i

r r

i 4

4 4 6.9 Elant Operatinz Records i

In addition to the requirements of applicable regulations, and in no way substituting therefore, records and logs shall be prepared and retained as follows:

a. Records to be retained for a period of at least five years or for the life of the component involved ifless than five years:

1. Normal reactor facility operation (but not including supporting documents such as checklists, log sheas, ac., which shall be maintained for a period of at least one year).

2. Principle maintmance operations

3. Reportable occurrmees

4. Surveillance activities required by the Technical Specifications

5. Reactor facility radiation and contamination surveys

6. Experiments performed with the reactor

7. Fuel inventories, receipts, and shipments

8. Approved changes in operating procedures

9. Records of meeting and audit reports of the Conunittee

b. Records to be retained for at least one certification cycle:

1. Record of retraining and requalification of certified operations personnel shall be maintained at all times the individual is employed or until the certification is renewed.

c. Records to be retained for the lifaime of the reactor facility:

l. Gaseous and liquid radioactive efiluents released to the mvirons

2. Off-site environmental monitoring surveys

3. Radiation exposure for all personnel monitored

4. Drawings of the reactor facility

.