ML20236A086

Proposed Tech Specs Exempting Facility from 10CFR50.54 (R) & from Maintaining Requalification Program

ML20236A086
Person / Time
Site:	05000112
Issue date:	10/15/1987
From:	OKLAHOMA, UNIV. OF, NORMAN, OK
To:
Shared Package
ML20235Z503	List: ML20235Z499 ML20236A086
References
NUDOCS 8710220007
Download: ML20236A086 (18)

Text

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' APPENDIX A i

LICENSE NO. R-53 TECHNICAL SPECIFICATIONS FOR THE UNIVERSITY OF OKLAHOHA REACTOR MODEL AGN-211P (S.N. 102)

August 31, 1987 t

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l TABLE OF' CONTENTS PAGE

! '1.0 DEFINITIONS. .- . . . . . . . .. . . . . . . . . .. . . 1 1

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTING .. .

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. . . . . . . . . . I 3.0 LIMITING CONDITIONS FOR OPERATION.

. .. . . . . . . . . . . . . 2 4.0 SURVEILLANCE REQUIREMENTS.

4.1 Facility Support and Protection System . . . . . . 2

. . . . . . . . . . . . . . . . .. .. 3

.5.0 DESIGN FEATURES 3

5.1 Mothball Status of the Reactor . . . . . . . . . .

3-5.2 Fuel Storage . . . . . . . . . . . . . . . . . . .

3 6.0 ADMINISTRATIVE CONTROLS. . . . . . . . . . . . . . . .

6.1 Organization . . . . . . . . . . . . . . . . . . . 3 6.2 Reactor Safety Committee . . . . . . . . . . . . . 5 1 I

7 6.3 Reportable Occurrences . . . . . . . . . . . . . .

6.4 Procedures . . . . . . . . . . . . . . . . . . . . 8 9 '

6.5 Records Retention. . . . . . . . . . . . . . . . .

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1'.0L DEFINITIONS Quarterly - .s' defined sa 3 months not to exceed 4 months.

i Semi-Annually --in defined as 6 months but not to exceed ?

months.

Annually - Annually is defined as 12 months but not to exceed 14 months.

Shutdown Margin - The shutdown margin is defined as the amount-of negative reactivity by which the reactor is shutdown with the most' reactive rod stuck out of the core.

Reactor Secured - The reactor shall be considered secured when:

(1) It'contains insufficient fissile material or moderator present in the reactor, adjacent experiments or control rods, to attain critically under optimum available I conditions of moderation and reflection, or j l

(2) No work is11n progress involving core fuel, control. c rods or control rod drives unless.they are physically decoupled from the reactor, and (3) The console key switch is in the off position and the ,

key is removed from the lock.

SAFSTOR or Mothball - The reactor. facility is considered to .

be in a SAFSTOR or mothballed condition when the-facility is {

in a state of protective. storage. The facility may be left intact except that.all fissionable materials shall be removed from the reactor pool. The reactor fuel shall be in storage containers located in a fuel storage area. Appropriate surveillance, radiation monitoring, and security procedures ..

are established under a possession-only license to ensure that the health and safety of.the public is not endangered.

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS I Not Applicable. The reactor shall remain secured and the facility shall be in mothball status.

i 3.0 LIMITING CONDITIONS FOR OPERATION Not Applicable. The reactor shall remain secured and the facility shall be in mothball status.

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' 4. 0 SURVEILLANCE REQUIREMENTS Actions specified in this section are applicable to the mothballed condition-of the facility and shall be performed within the specified' surveillance' period.

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' 4 .1 ~ Facility Support and Protection Systems Applicability 2.

JThim. specification applies to the facility support and protection" systems such as physical barriers, and radiation .

monitoring activities.

Objective To assure.that the public health and safety are not endangered as a result of physical degradation of the facility during the term of the possession-only license period.

Specification

-a. physical barriers to unauthorized entrance into the reactor facility and fuel storage area, e.g., building, rooms, doors,.and access openings,.shall be visually inspected at least once quarterly.

b. Fuel storage containers and container locking rings shall be visually inspected'at least quarterly.

c. A radiation survey of the reactor facility and fuel storage area shall be performed at least semi-annually Basis j The physical barriers, e.g. building, rooms doors, and access openings are inspected to assure that these barriers have not deteriorated and that locks and locking apparatus are intact.

Storage containers and container locking rings are inspected to assure. integrity of the containers. This inspection, in I conjunction with the annual fuel inventory and radiation survey'of the fuel storage area will verify that radioactive material has not been removed from the containers or is not escaping or being transported through the containment barriers. In addition, the radiation survey provides assurance that radiation doses to facility personnel and to o

the public are maintained at a level below 10 CFR 20 limits.

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i 5.0 ' DESIGN' FEATURES

. 5 .1 ' Mothball Status-of the Reactor l

During a mothballed state of protective storage

a. .The' reactor fuel'is removed from the pool.

b. All fissionable material used in connection with j operation of:the reactor is stored in approved storage l

' containers.with k<0.8, containing less than 200 grams of 1

U-235 each, and is located in a designated, controlled-fuel storage' area in accordance with paragraph 5.2 of these technical specifications.  !

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j5. 2 Fuel Storage.

Fuel, including fueled experiments and fuel devices, shall be stored in locked rooms in the reactor building. The  :

storage array shall be such that K is no greater than 0.8 I for all conditions of moderation ankIreflection.

6.0 ADMINISTRATIVE CONTROLS l 1

6.1 Organization of Responsibility for the University of Oklahoma Nuclear Reactor - Administrative control'of the q reactor is diagrammed in Figure 1. 1 I

6.1.1 President - Chief Executive Officer of the University l l

6.1.2 Provost - Chief Academic Officer 6.1.3 V.P. for Administrative Affairs - Chief Administrative Officer  ;

.i 6.1.4 Dean of Engineering - Administrative Officer in charge of the College of Engineering 6.1.5 Director. School of Aerospace. Mechanical and Nuclear Engineering (AMNE) - The Director is the head of the three degree programs, Aerospace, Mechanical and Nuclear

' Engineering. The Director will provide proper financial and technical support to ensure the mothball status of the facility is maintained in accordance with all requirements.

6.1.6 Reactor Director - Responsible for the general administra- l tion of the facility. In this capacity the Director shall have the authority and responsibility for the facility and, within the limitations set forth by the facility license, l shall make policy decisions on all matters concerning the '

safety of the mothball status of the fuel and is advised by i the Reactor Safety Committee, the Radiation Safety Committee and the University Radiation Safety Officer.

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.6[1'7. Reactor Supervisor -l Position not needed during time-the reactor is in a mothbal1~ status.

6.1.8 University Radiation Safety Officer (RSO) Has over-all- a

-responsibility for radiological safetylat the-University and

,shall assure that necessary radiation surveys are conducted in.the Reactor, fuel storage, and other associated labora-tories )

The Radiation Safety OfficerLsh'all review the radio-logical' safety aspects of!the fuel storage and shall advise i the Reactor Director in all matters ~ relative to radiologi-. j cal safety. The.RSO will be a member'of the Reactor Safety 1 Committee.and the Radiation Safety Committee.

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6.1.9: Reactor Staff Qualifications - The Reactor Director shall have. sufficient qualifications to ensure parts 4.0 -

and 5.0 of these technical specifications are met.

6.2-. Reactor Safety Committee - H 6.2.1. 'The Reactor. Safety Committee (RSC) shall be composed of not-less'than four members appointed by the Vice-President for Administrative Affairs, two of whom will be the Radiation Safety Officer and the Reactor i Director.

.6.2.2. A minimum of fifty percent (50%) of the membership ]

shall cotatitute a quorum. A minimum quorum shall not I be constituted with more than two committee members from the operating staff.

6.2.3. 'The committee shall have a maximum of three members l appointed from the reactor operating staff. j

6. 2. 4. . Minutes of the meeting shall be taken and submitted to j each member of the committee along.with reports ,

presented the committee.

6.2.5. Ad hoc subcommittees may be convened at the request of the chair and will report'their findings to the .

committee.

6.2.6. The chair shall be appointed by the Vice-President for i Administrative Affairs. The chair shall be responsible l to call the committee into session at least semi- I annually and shall make assignments as necessary to the l members of the. committee. The chair will be responsible i for the recording of the minutes and the dissemination of. committee reports and minutes. The chair or chair's designate shall have signature authority for the committee.

I 6.2.7. Committee members shall ave duties and authority as assigned by the chair.

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6. 2; 8.L .The committee shall' review and approve the-

~ comprehensive. safety aspects.of the fuel _ storage.

n Review and approval by7 the RSC will include's

. determination that any.previously-unreviewed safety Bi . question does.not pone aLhazard to the' reactor,' reactor. l l personnel,'or the~ environment as defined in 10CFR 50.

.Its' duties lshall. include, but not be limited to.the

.following:

1 A) Review and' approve safety standards. associated.

with the mothballed status.of the reactor facility which are consistent with the' technical y specifications-of the reactor. .

4 B) Review and approve procedures'as required by the .;

technical specification for rearrangement of fuel, l surveillance,' and security of the fuel.

l C) Review and approve procedures for the modification j' and/or testing-of replacement components associated with the radiation monitoring and fuel storage security systems. ,

D) Review and approve standard procedures for audit j

and review of the surveillance procedures required j

1 by the technical specifications and security plan.

Audit performance at-least annually of the reactor E) 1 staff in the areas facilities manual (procedures), ')

maintenance logs and test procedures, surveillance l tests, and physical security plan.

F) Review all abnormal occurrences and violations of )

the technical specifications, evaluating the causes of such events, the corrective action taken and recommending measures to prevent the recurrence of the incident. Report their findings.  !

to all authorities as required by the technical l specifications and University authority.

1 6.3' Reporting Requirements 6.3.1 Annual Report. An annual report describing the status of the facility, the.results of environmental and facility radiation survyes, an evaluation of the performance of security and surveillance measures, personnel exposures to radiation, and any abnormal occurrences during the previous calendar year shall be submitted to the Director of Nuclear 6

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Reactor Regulation prior to MayL31, of each calendar. year.

16.3.2 ' Reportable Occurrences. Reportable occurrences shall be

' reported as; expeditiously as possible by telephone and

. confirmed by telegraph, mailgram or facsimile transmission-to.the NRC. Operations Center (202) 951-0550,- no later than.

.the:first work day following the event. A written followup report describing the reportable occurrance including causes, probable consequences, corrective actions,,and measures to prevent recurrence shall be submitted within 14 days. 'Information provided shall contain narrative material for'a complete explanation of the circumstances surrounding the event. The following events shall be reported:

a. Discovery of significant, unexplained increase in.

radiation or. contamination levels within or around the reactor facility or. fuel storage area..

b. Abnormal degradation discovered.in protective barriers  ;

for-the reactor facility or fuel storage area which.

would~ compromise the physical security established for protective' storage of the reactor and reactor fuel.

6~.3.3 -Special' Reports., Special reports which may be required by the Nuclear Regulatory Commission shall be submitted to the Director of the appropriate NRC Regional Office within the time period specified for each report.

E.4 Peppgdurgn, There shall be written procedures for the following.

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1. Surveillance and testing of equipment and systems I required for protective storage of'the reactor and l reactor fuel.

2. Personnel radiation protection consistent with 10 CFR 20.

3. Access control to the reactor facility and fuel and storage area. l

4. Implementation of the security plan.

5. Notification of the proper authorities in the event of ,

significant changes in the radiation or contamination i levels within the facility. l 6.5 Record Retention 6.5.1 SAFSTOR Records. Retention records or logs relative to the following items shall be kept and retained until the 7

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. license l's terminated, unless otherwise specified by the

^NRC:

a. ' Facility: radiation surveys.-

, b. . Inspections of physical barriers.

'c. Abnormal occurrences.

d. . Environmental Surveys

'6.5.2. Prior Facility Operation Records.

Records"or logs relative to the following items shall e 'be retained for a' period of at least ten years:

a. Operating logs'or-data which shall identify: (

1. Completion of. pre-startup checkout, start-up, power changes, and shutdown of the reactor.-  !

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2. Installation or removal of fuel elements, control rods, or experiments that could

affect core reactivity.

3. Installation or removal of jumpers, special Ltags or notices,.or other temporary changes to reactor safety circuitry.

4. Rod worth measurements and other reactivity measurements.

b. principal < maintenance operations. l

c. Reportable occurrences,

d. Surveillance activities required by technical specifications.

e. Facility radiation and contamination surveys.

f. Experiments performed with the reactor.

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g. . Changes to operating procedures.

6.5.3 Other Records l 1

Records or logs relative to the following items shall

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be retained for the life of the facility, unless otherwise specified by the NRC:

a. Gaseous and liquid radioactive effluents released j to the environment.  !

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b. Appropriate off-site environmental monitoring l l

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c. Fuel inventories-and fuel transfers.

d. Radiation exposures for all personnel.

e .- Updated as-built drawingu 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 qualifications.for members of the facility staff.

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'h. Records of reviews' performed for changes made to j procedures'or equipment or reviews of tests and-experiments pursuant to 10 CFR 50.59.

1. Records of meetings of the Reactor Safety Committee.

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ENVIRONMENTAL IMPACT APPRAISAL-4 UNIVERSITY OF OKLAHOMA AGN-211P LICENSE R-53 DOCKET 50-112 August' 31,.1987

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' ENVIRONMENTAL IMPACT APPRAISAL (EIA)

I. INTRODUCTION

.This section~ discusses the environmental effects of t

mothballing the University of Oklahoma AGN-211P, swimming pool type reactor. ;The reactor was originally licensed in 1958 and  ;

began operation in 1959. The core consisted of a rectangular parallelepiped made up of a maximum of 20 fuel elements surroundediby a graphite reflector and positioned near the bottom of an 800 gallon pool of distilled water. The reactor has operated at a maximum licensed power of 100 watts. The reactor has not operated since April '1986.

The. reactor served to support the Nuclear Engineering Program which offered the B.S., M.S., and'Ph.D. degrees-in

- Nuclear Engineering.

II. FACILITY The reactor was purchased from the Aerojet General Nucleonics Corporation in 1958 and was installed by Aerojet personnel. The reactor is housed on the first floor of the Nuclear Engineering f I

Laboratory Building (NHL). The second floor houses the University's. Personnel Department. Installation of the reactor in i

1958 had no obvious impact on the environment or the immediate terrain. No pipelines, electrical or mechanical structures or any other form of device connects the reactor to the outside environment. The reactor needs no external cooling and emits no effluents, liquids or gas. The flux was too low to produce a i

measurable amount of Ar-41. Any liquid or solid wastes from experiments are appropriately packaged and disposed of through the l

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! University's regular' radioactive waste program.

Finally, no changes in the' building or the area.immediately-external'to the building are required or are planned as a result h- of'mothballing the reactor.

III. ENVIRONMENTAL EFFECTS FROM OPERATIONS Operation'of the reactor at 100 watts in the past has had no discernible impact on the environment. In 28 years of operation, no member of the-staff has received a radiation dose which exceeds regulatory limit. We note also that the neutron flux in water was too low to produce any tritium through neutron capture by deuterium in'the. water.

t IV. ENVIRONMENTAL EFFECTS DUE TO /.CCIDENTS We see no credible accident that can have an impact on the environment due to the mothball status of the reactor.

V. COSTS AND BENEFITS OF THE FACULTY Several hundred thousand dollars has been invested in the. j reactor and the section of the building in which the reactor is j housed over a period of years. The entire reactor and

'1 associated nuclear labs'have recently undergone a major j l

renovation. There are currently no plans to move or otherwise 1 i

substantively revise the reactor or fuel storage facility. 3 )

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l REQUALIFICATION PROGRAM

.FOR t

' UNIVERSITY OF OKLAHOMA

.AGN-211P REACTOR

'", LICENSE R-53 DOCKET 50-112 August' 31,.1987 I

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j During that period'of time where the' reactor is in a mothballed status,'the requalification program will be

' i nope ra t.i ve .

- Basis: . . Operator qualification is not necessary for the storage of. fuel..as-no operations with a' critical configuration are allowed.

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EMERGENCY PLANNING FOR UNIVERSITY OF OKLAHOMA AGN-211P REACTOR LICENSE R-53 DOCKET 50-112 August 31, 1987 i

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During that period of time when the reactor is in a mothballed status, the emergency plan will be inoperative and an exemption from 50.54(R)-is requested. i Basis': The reactor fuel will be maintained with K < 0.8 for any j combinations of fuel or moderator. Therefore, no critically accident can happen. Further, as of July 1987, radiation levels at the surface of the fuel storage containers were less than 2 ]

i ar/hr and less than 0.5 ar/hr at one meter from the fuel.

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