ML20207S709

Insp Rept 50-112/87-01 on 870126-30.Violations Noted:Failure to Maintain Records in Proper Units,Failure to Provide Emergency Planning Training & Failure to Maintain Ltrs of Agreement

ML20207S709
Person / Time
Site:	05000112
Issue date:	02/26/1987
From:	Baer R, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20207S705	List: ML20207S704 ML20207S708 ML20207S709
References
50-112-87-01, 50-112-87-1, NUDOCS 8703200200
Download: ML20207S709 (8)

See also: IR 05000112/1987001

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APPENDIX C

U.S. NUCLEAR REGULATORY COMMISSION

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REGION IV,

~NRC Inspection Report:

50-112/87-01

License:

R-53

Docket: .50-112

Licensee:

University of Oklahoma

865 Asp Ave., Room 212

Norman, Oklahoma

73019

Facility Name:

AGN-211P, Research Reactor (100W)

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Inspection At:

University of Oklahoma, Norman, Oklahoma

Inspection Conducted: January 26-30, 198/

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Inspector:

2/I /

Rf E.

3aer, Radiation Specialist, Facilities

Date '

Radiological Protection Section

-Approved:

(llAdOl/l dAi(#1

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B. Murray, Chief,' Facilijties Radiological

Date

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Protection Section

Inspection Summary

Inspection Conducted January 26-30, 1987 (Report 50-112/87-01)

Areas Inspected:

Routine, unannounced inspection of the licensee's

organization and management controls, operations and maintenance logs, records,

operator requalification program, radiation protection, radioactivity releases,

transportation, emergency planning, physical security plan, nuclear material

safeguards, and an allegation.

Results: Within the areas inspected, three violations were identified (failure

to maintain records in proper units, paragraph 8; failure to provide emergency

planning training, and failure to maintain letters of agreement, paragraph 13).

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DETAILS

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1.

Persons Contacted

• D. M. Egle, Director, School of Aerospace, Mechanical and Nuclear

Engineering

• C. M. Jensen, Reactor Director and Senior Reactor Operator

• P. Skierkowski, Radiation Safety Officer

M. C. Smith, Radiation Safety Technician

K. A. Messana, Safety Inspector, Department of Public Safety

D. McGhee, Captain, Norman Fire Department

The NRC inspector also. interviewed other licensee and City of Norman

employees including police officers and firemen.

• Denotes those present during the exit interview on January 30, 1987.

2.

Status of Facility

The AGN-211P reactor was operated approximately 40 times between

January 11, 1985, and April 24, 1986.

The reactor has not been operated

since April 24, 1986.

The licensee no longer offers courses of

instruction in the School of Nuclear Engineering or performs research in

nuclear technology which would require the operation of the reactor.

The

licensee has discussed with the NRC procedures for "mothballing" the

reactor.

3.

Organization and Management Control

The NRC inspector reviewed the organization and management controls to

determine compliance with Technical Specification (TS) 6.1.

The current organization was verified to be consistent with TS Figure 4,

" Administrative Organization of University of Oklahoma Reactor AGN 211P"-

except for the positions of Reactor Supervisor and Reactor Staff.

The TS

allows the Reactor Director to also serve as the Reactor Supervisor. The

status of licensed operators, membership and meetings or the Reactor

Safety Committee (RSC), and other matters concerning supervision of the

reactor facility were examined. The NRC inspector noted that the position

of Reactor Director had been filled by the only qualified senior' reactor

operator presently on campus.

The NRC inspector reviewed the minutes of meetings conducted by the RSC

and verified that the committee had met quarterly since thelprevious

inspection and reviewed matters related to the reactor.

It was verified

that records reflected attendance by designated committee members.

The

following items were routinely reviewed by the committee:

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Reactor Surveillance. Logs

' Facilities Manual

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. Fuel Element _ Inspection and Inventory

Reactor Maintenance Log

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-Requalification Program-

Physical. Security Plan.

Emergency Plan .

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Reactor Operations and Sample-Irradiation Logs

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Reactor; Experiments

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No violations'or' deviations were identified.

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Operation and Maint$ nance' Logs

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.The NRC. inspector reviewed the following logs for the period January 1,

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.1985, through January 27, 1987, to determine compliance with'TS 3.1, 3.2,

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!3.3,3.4,4.2,-o.21(g),anoo.21(n).

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Reactor Operations Log

Reactor Maintenance Log

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-All maintenance and~ operations activities appeared to have been conducted

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in.a manner consistent 1with the TS requirements and administrative

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' procedures.

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No'violationshar deviations were identified.

5.

-Procedures

EThe NRC inspector reviewed operating and surveillance procedures to

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. determine compliance with the requirements of TS 3.4, 4.1, 4.2,-and 6.12.

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The reactor operations manual contained procedures for:

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" Normal Startup, Operation and Shutdown of the AGN-211 Reactor

Reactor Startup,-Operation and Shutdown L'og

Completion of the-Irradiation Request Form

Experiment Request

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iProcedure for Core Rearrangement

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.The surveillance activities log contained the procedures and logs for:

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Low Water Level Switch Interlock Test

Temperatcre Interlock ~

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Circulation Pump Interlock

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' Water Conductivity-Meter Calibration

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Air-Water Monitor. Adjustment

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High Voltage'DC: Power Supplies Calibration

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Linear Power Channel Calibration

Low Power and Period Meter Calibration

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Neutronic Power Calibration

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4

Safety and Control Rod Surveillance

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Emergency Evaluation Horn Test

Security Alarm System Test

The NRC inspector verified that limits regarding excess reactivity,

control and safety rod worths, scram capabilities, and safety systems were

not exceeded.

The records of surveillance test results did not indicate

any unusual conditions.

No violations or deviations were identified.

6.

Records

The NRC inspector reviewed the licensee's records 'for ' reactor operations,

reactor component changes /replecement, and calibrations. The licensee had

replaced the four control rod drive motors in .lulv 1985, in acenrdance

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with an. approved procedure.

The licensee had not made any facility

modifications during the inspection period.

No violations or deviations were identified.

7.

Operator Requalification Program

The NRC inspector reviewed the licensee's reactor operator requalification

training program for compliance with 10 CFR.Part 55, Appendix A. The NRC

inspector reviewed training documents for the currently licensed operator

and previously licensed individuals to determine agreement with the

requalification program approved by the NRC on February 23, 1933.

The NRC inspector noted the last training session was held on April 25,

1986, at which time the three licensed reactor operators were in

attendance.

Since April 25, 1986, the 1icensee has lost the services of

two of these reactor operators.

Records indicate the reactor was last

operated on April 24, 1986.

No violations or deviations were identified.

8.

Radiation Protection

The NRC inspector reviewed the licensee's radiation protection program to

determine compliance with 10 CFR Parts, 19.11, 19.12, 19.13,'20.101,

20.104, 20.201, 20.202, 20.203, 20.207, 20.401, 20.403, 20.405, 20.408,

and 20.409 and 50.54(q).

The NRC inspector reviewed records, interviewed personnel, made

observations, and performed independent surveys.

10 CFR Part 20.401(b) requires that each licensee shall maintain records

in the same units used in this part, showing the results of surveys

required by 20.201(b), . . . ."

10 CFR Part 20.5(a) states that

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radioactivity is commonly, and for purposes of the regulations in this

part shall be, measured in terms of disintegrations per unit time or in

curies.

The NRC inspector reviewed radiation and contamination survey records of

surveys performed to satisfy the requirements of 10 CFR Part 20.201(b),

during the period January 1,1985, through December 31, 1986, in rooms 106

and 107 of the Nuclear Engineering Laboratory (NEL) building.

The NRC

inspector determined that smear surveys taken to detect removable

contamination were recorded in counts per minute.

It was also noted that

the licensee's procedures did not include a method for converting counts

per minute into disintegrations per minute.

The NRC inspector stated that failure to maintain records in the same

units used in 10 CFR Part 20.5 was considered an apparent violation of 10 CFR Part 20.401(b).

(112/8701-01)

The NRC inspector reviewed the course outline, lesson plans, and viewed

video tapes of the training program, " Radiation Safety for Laboratory

,

Personnel." The NRC inspector verified that individuals were receiving

the training required in-10 CFR Part 19.12 and recommended by Regulatory

Guide 8.13.

9.

Radioactive Releases

The licensee does not maintain a detailed environmental surveillance

program (e.g. collection and analysis of water, soil, and vegetation

samples). There are no specific license requirements that such a program

be maintained.

A licensee representative stated that no liquid effluent releasas have

been made since the last inspection.

The licensee's operation records

indicate that gaseous releases are within 10 CFR Part 20 limits.

No violations or deviations were identified.

10.

Transportation (Fuel Shipments)

The NRC inspector verified that there had been no fuel shipments since the

previous operational inspection.

No violations or deviations were identified.

11.

Nuclear Materials Safeguards

The NRC inspector reviewed the nuclear materials inventory program to

determine compliance with 10 CFR Part 70.53.

The NRC inspector reviewed

the accountability procedures and practices, records and material status

reports.

The procedures, practices, and records were found to be well

implemented.

Responsibilities and response requirements were defined

clearly and understood, and appropriate test procedures were being used.

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The licensee had not received or shipped any radioactive materials s_ince

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the previous inspection.

No violations or deviations were identified.

- 12.

Physical Security Plan

The NRC inspector reviewed the implementation of the licensee's physical

security program through visual examinations, review of records, and

~ discussions with appropriate faculty and campus security, personnel.

The

review indicated that the physical security plan was being implemented,

responsibilities and response requirements were defined clearly and

understood, and the required tests were being performed.

-No violations or deviations were identified.

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13.

Emergency Planning

.The NRC inspector reviewed the emergency preparedness program to determine

agreement with commitments made in the Emergency Preparedness Plan.

The licensee fully implemented,the Emergency Preparedness Plan in

November 1984 and the emergency notification list was updated on March 7,

1986.

10 CFR Part 50.54(q) requires that a licensee authorized to operate a

research reactor shall follow and maintain in effect an' emergency plan.

Section 10.4, of the Emergency Preparedness Plan states, '.'The' Emergency

Plan shall be revised and updated as required based on drill results or

changes in the. facility and shall be reviewed annually by the reactor as

required based on drill results or changes in the facility and shall be

reviewed annually by the reactor staff to ensure the plan is adequate and

up to date." Section 3.1 addresses assistance from offsite organizations

and states " Written agreements with-these organizations are included in

Appendix A to this plan."

The NRC inspector determined on January 28, 1987, that the letter of

agreement with the Norman Municipal Hospital dated November 15, 1983,

expired on October 1, 1984.

The NRC inspector stated that failure to

review and update the letter of-agreement with the Norman Municipal-

Hospital was an apparent violation of requirements of 10 CFR Part 50.54(q).

(112/8701-02)

Section 10.1, of the Emergency Preparedness Plan addresses training that

will be provided to individuals with emergency response-responsibilities

and states that the University Police and Norman Fire Department shall be

trained on an annual basis in radiation safety and NEL facility emergency

procedures.

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.The NRC inspector reviewed the video tape prepared by the licensee which

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addresses the facility emergency procedures.

The NRC inspector also-

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discussed with representatives of the University _ Police and the Norman

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Fire Department the-training being received. The NRC inspector determined ~

on January 29,.1987 that training in radiation safety and the NEL facility

emergency procedures were not being received by all individuals from the

University Police and Norman Fire Department who would respond to an

emergency at the NEL facility.

The NRC inspector discussed with licensee

representatives the training _ requirements contained in the Emergency

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Preparedness Plan.

The licensee stated that training.had been provided

to selected individuals in the' police and fire departments.

However,

other individuals who might be-required to respond to emergency.

situations had not received the required training.

The failure to

provide the required training to all personnel is an apparent violation-

of-10 CFR Part 50.54(q).

(112/8701-03)

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14. - dllegation (4-86-A-109)

The NRC h'ad received a copy- of the Oklahoma Observer newspaper article

from the' licensee which' had alleged that personnel working near the

University of Oklahoma reactor had:

(a) received radiation overexposures

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during the past 10-20 years, (b) radiation exposures in adjacent rooms

were above the regulatory limits, and (c) the reactor staff failed to lock -

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a room directly above the reactor while the reactor was in _ operation.

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The NRC inspector reviewed selected reports, radiation survey records',

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environmental radiation dosimeter results, person'el radiation exposure

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histories, and reactor operation logs for the period' July 1971 through

December 1986:

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Allegation, Part (a)

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The NRC inspector's review of radiation exposure histories and

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environmental radiation dosimeter results indicated the. highest

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recorded exposure was less than 750 millirem / year for personnel

assigned to wear radiation dosimetry, and less than 120 millirem / year

for areas monitored by environmental radiation dosimeters.

The NRC

inspector was not able to substantiate this portion of the

allegation.

Allegation, Part (b)

The AGN-211P reactor is located below grade level in the NEL

building. The NRC inspector's review of facility records indicated

that rooms adjacent to the reactor facility did not increase in

radiation levels as a result of reactor operations.

The NRC

inspector was not able to substantiate this portion of the

allegation.

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the inspection on January 30, 1987.

The' NRC inspector' summarized ,the

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scope and findings of the inspection.

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