IR 05000112/1987001
| 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) | |
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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 2/I Date '
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Radiological Protection Section-Approved: (llAdOl/l dAi(#1 8[b[b7 Date '
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 allegatio 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).
8703200200 870316 2 PDR ADOCK 0500
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DETAILS l~ Persons Contacted
- 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 fireme * Denotes those present during the exit interview on January 30, 198 . 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 reacto . Organization and Management Control The NRC inspector reviewed the organization and management controls to determine compliance with Technical Specification (TS) 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 campu 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 member 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 Pla Emergency Plan . .
Reactor Operations and Sample-Irradiation Logs
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Reactor; Experiments
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No violations'or' deviations were identifie ?_ 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
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I No'violationshar deviations were identified.
- 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 i
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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 l
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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 condition No violations or deviations were identifie . 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 perio No violations or deviations were identifie . 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, 193 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 operator Records indicate the reactor was last operated on April 24, 198 No violations or deviations were identifie . 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 survey 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 h si -
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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 curie 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 minut 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 8.1 . 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 maintaine 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 limit No violations or deviations were identifie . Transportation (Fuel Shipments)
The NRC inspector verified that there had been no fuel shipments since the previous operational inspectio No violations or deviations were identifie . 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 report 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 inspectio No violations or deviations were identifie . 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 performe No violations or deviations were identified.
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1 Emergency Planning
.The NRC inspector reviewed the emergency preparedness program to determine agreement with commitments made in the Emergency Preparedness Pla The licensee fully implemented,the Emergency Preparedness Plan in November 1984 and the emergency notification list was updated on March 7, 198 CFR Part 50.54(q) requires that a licensee authorized to operate a research reactor shall follow and maintain in effect an' emergency pla 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 procedure _
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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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q 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 Pla 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 emergenc 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: #
p 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 allegatio 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 allegatio e
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t The licensee had includsd 'in th- reactor startup, . operation,/anh ' '
shutdownlog'acheckoffline$em"storageroom(NEL-214) locked"and
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. the reactor ope *ator had the oaly key which allows access irito .this
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room The NRC'(inspcctor's,y(view of reactor logs . indicated tLe s
storige room.hid been lock!d prior to reactor operations. The NRC r inspe'ctor was' jat able to Yubstantiate this portjoi of the allegatio Q,
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the inspection on January 30, 1987. The' NRC inspector' summarized ,the 3 }:
scope and findings of the inspectio s A , 4
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