ML20207S709
| 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: |
| References | |
| 50-112-87-01, 50-112-87-1, NUDOCS 8703200200 | |
| Download: ML20207S709 (8) | |
See also: IR 05000112/1987001
Text
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APPENDIX C
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV,
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~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
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Inspection Conducted: January 26-30, 198/ I
Inspector:
Rf E. 3aer, Radiation Specialist, Facilities
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Radiological Protection Section
-Approved: (llAdOl/l dAi(#1 8[b[b7
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B. Murray, Chief,' Facilijties Radiological
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 *
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' Facilities Manual .
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. Fuel Element _ Inspection and Inventory
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Reactor Maintenance Log
-Requalification Program-
Physical. Security Plan.
Emergency Plan . .
Reactor Operations and Sample-Irradiation Logs
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Reactor; Experiments
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No violations'or' deviations were identified.
?_ 14; 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,
!3.3,3.4,4.2,-o.21(g),anoo.21(n).
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- Reactor Operations Log
Reactor Maintenance Log
-All maintenance and~ operations activities appeared to have been conducted
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in.a manner consistent 1with the TS requirements and administrative
{ ' procedures.
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No'violationshar deviations were identified.
- 5. -Procedures
e EThe NRC inspector reviewed operating and surveillance procedures to
, . determine compliance with the requirements of TS 3.4, 4.1, 4.2,-and 6.12.
L'- 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:
I Low Water Level Switch Interlock Test
Temperatcre Interlock ~
ll Circulation Pump Interlock
- ' ' Water Conductivity-Meter Calibration
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l Air-Water Monitor. Adjustment
High Voltage'DC: Power Supplies Calibration
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Low Power and Period Meter Calibration
! Linear Power Channel Calibration
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Neutronic Power Calibration
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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 ,
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
- 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 s
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
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University of Oklahoma reactor had: (a) received radiation overexposures
during the past 10-20 years, (b) radiation exposures in adjacent rooms
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were above the regulatory limits, and (c) the reactor staff failed to lock -
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',
, environmental radiation dosimeter results, person'el n radiation exposure
- histories, and reactor operation logs for the period' July 1971 through
December 1986: #
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Allegation, Part (a) , I
, The NRC inspector's review of radiation exposure histories and
li environmental radiation dosimeter results indicated the. highest
recorded exposure was less than 750 millirem / year for personnel
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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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room The NRC'(inspcctor's,y(view of reactor logs . indicated tLe
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inspe'ctor was' jat able to Yubstantiate this portjoi of the
allegation.
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