IR 05000059/1998201
| ML20247J195 | |
| Person / Time | |
|---|---|
| Site: | Texas A&M University |
| Issue date: | 05/12/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20247J193 | List: |
| References | |
| 50-059-98-201, 50-59-98-201, NUDOCS 9805210359 | |
| Download: ML20247J195 (12) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No:
50-059 License No:
R-23 Report No:
50-059/98-201 Licensee:
Texas A&M University Facility:
AGN-201M Reactor Location:
Zachry Engineering Center, Texas A&M University College Station, Texas Dates:
April 6-9,1998 Inspector:
Stephen W. Holmes, Reactor Inspector Approved by:
Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation l
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EXECUTIVE SUMMARY This routine, announced inspection consisted of the review of selected conditions and records since the last inspection, verification of corrective actions previously committed to
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The reactor was being maintained and operated as required by the license and applicable regulations. The reactor license was under timely renewal. No reactor design changes had been made nor new experiments approved since the last inspection. The licensee made a number of commitments to enhance tracking of senior reactor operator hours, 50.59 change evaluations, and reviews / audits in the Reactor Safety Board minutes. Two previous violations for failure to perform required audits of reactor facility activities and to perform annual reviews of the physical security plan were closed.
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Report Details Summary of Plant Status i
With the license in timely renewal, operations were continuing to support the requirements of several nuclear engineering courses and reactor operator training as well as performing preventive maintenance and operational surveillance required by the Technical Specifications. At the time of this inspection the reactor was shutdown while undergoing repair to the 110 and 220 volt electrical power circuits following a loss of power to the engineering building. Repairs were being conducted as outlined in facility procedures. No safety concerns were noted.
1.
Operations
Conduct of Operations 01.1 Reactor Staffing a.
inspection Scope (Inspection Procedure 69001)
The inspector reviewed reactor staff qualifications, operations logs and records, selected events, and interviewed staff.
b.
Observations and Findings Licensed staff consisted of the Reactor Supervisor (RS), and one other Senior Reactor Operator (SRO). The reactor staff satisfied the training and experience required by the Technical Specifications (TS). Operation logs and records confirmed that shift staffing met the minimum requirements for duty and on-call personnel. Staffing has been constant for the past decade, c.
Conclusions j
The operations staffing of the research reactor satisfied TS requirements.
01.2 Control and Performance of Experiments a.
Inspection Scope (Inspection Procedure 69001)
The inspector reviewed the 10 approved reactor experiments, reactor logs, documentation of experiments performed, experimental data, Reactor Safety Board (RSB) minutes, and interviewed staff.
b.
Observations and Findings The inspector verified that each experiment procedure had been reviewed and approved as required by TS. It was noted that all 10 reactor experiments were approved in January 1976 and that the licensee had not approved any new experiments for the reactor since that tim _ _ _ - _ - _ _ _. _ _ _ _ _ _ _ _ _ __ _
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2-Review of the experiment data in the reactor log and interviews with staff verified that experiments were constrained as required by the TS and experiment authorization. The experiments were also installed, performed, and removed as outlined in the experiment authorization and licensee's procedures.
c.
Conclusions License control and performance of experiments met TS and licensee requirements.
01.3 Reactor Operations and Fuel Handling a.
Inspection Scope (Inspection Procedure 69001)
The inspector interviewed staff, reviewed reactor operations and fuel logs, and periodic checkout, start-up and shutdown checklists. The inspector also observed a walkthrough simulation of a start-up, steady state power operation, and shutdown.
b.
Observations and Findings Reactor operations were carried out following written procedures and TS.
j information on operational status was recorded in log books and checklists as
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required by procedures and TS. Use of maintenance and repair logs satisfied regulatory and licensee requirements.
Due to the design of the AGN fuel (uranium dioxide embedded in radiation stabilized polyethylene), movement and handling were extremely infrequent. The j
inspector determined that there was no change in the quantity of reactor fuel since the previous NRC inspection.
Based on the review of the reactor operations log, the inspector verified that the
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licensee did not exceed a thermal power level of 5 watts, and the reactor safety limits were not exceeded. The reactor control system instrument channels, safety circuits, and safety interlocks required by TS were tested and operable prior to each startup of the reactor.
c.
Conclusions Reactor operations conformed to TS and licensee procedural requirements. Fuel handling, record maintenance, and documentation were accomplished as required by TS and licensee procedures. No safety concerns were identified.
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Operations Procedures and Documentation a.
Inspection Scope (inspection Procedure 69001)
The inspector reviewed operating procedures and updates, reactor operating records and logs, and RSB minutes, b.
Observations and Findings Written procedures required by the TS were available and used by the staff. Use of and adherence to the procedures was acceptable. The procedures had been revised for submission with the license renewal and, in accordance with RSB direction, would become effective at issuance of the new operating license. The inspector verified that the reactor facility procedures had been reviewed and approved by the RS, Reactor Administrator (Head of the Nuclear Engineering Department), and the RSB as required by the TS.
Records of power level, operating periods, unusual events, calibration and maintenance procedures, installed experiments, and start-up and shutdown checks were Deing kept. The licensee's logs and records were clear, concise, and legible. The inspector determined that the annual reactor operating reports, logs, and records acceptably documented reactor operations activities. Reactor operations and testing were documented in accordance with the TS.
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Conclusions Facility operational procedures satisfied TS requirements. Reactor operating records and logs were being maintained as required by TS.
05 Operator Training and Qualification Program a.
Inspection Scope (Inspection Procedure 69001)
-The inspector reviewed requalification program records, NRC licenses, training records and interviewed staff.
b.
Observations and Findings
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Currently licensed operators were participating in the ongoing training as required by the NRC-approved requalification plan. Lectures were conducted as required.
l The lecture outline for the reactor operator requalification program included appropriate subject material and a comprehensive written examination, which had been given and successfully passed by the senior reactor operators.
i Requalification training records contained the documentation required by the approved operator requalification program. Biennial medical exams had been I
performed as required.
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Although required quarterly operational hours were being performed and l
recorded, the inspector could not easily determine those hours comprising SRO l
duties. The licensee stated that SRO hours would be annotated separately on their present tracking documents. This will be reviewed during a future l
inspection as an Ir.spection Follow-up item (IFl 059-98-201-01).
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Conclusions The reactor operator requalification training program was being conducted and documented in accordance with the NRC approved program. Reactor operator requalification training records were being acceptably maintained. TS and NRC-approved requalification plan requirements were met.
Organization and Administration a.
Inspection Scope (Inspection Procedure 69001)
The inspector reviewed organization, staffing and administrative controls and interviewed management and staff.
b.
Observations and Findings Since the last inspection no functional changes in the management organization or administrative controls had been made.
c.
Conclusions Organizational and administrative controls remain consistent with TS and license requirements and commitments.
07 Quality Assurance in Operations
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Inspection Scope (Inspection Procedure 69001)
The inspector reviewed RSB minutes, annual reviews, audits, verified licensee corrective action for violations 9601-01 and 9601-03 and interviewed staff.
The inspector met with the new Dean of the College of Engineering who also chaired the RSI'
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. Observations and Findings RSB membership satisfied TS requirements and the Committee's procedural rules. Review of the minutes showed that the committee provided guidance, direction and oversight, and ensured suitable use of the reactor. Agendas and
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-5-minutes of the RSB meetings included entries concerning the AGN-201M reactor facility. The meeting minutes provided a record of the safety oversight of reactor operations. The inspector noted that the Reactor Safety Board had responsibility for both the AGN-201M (Docket No.50-059) and TRIGA (Docket No. 50-128) reactor facilities located at Texas A&M University.
i The inspector verified that licensee corrective action for violations 9601-01 and
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9601-03 involving quarterly audits and biennial reviews had been accomplished.
Audit checklist had been developed to ensure that all the items were reviewed l
and audited annually as required by TS. Since the last inspection all required
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quarterly audits of reactor facility activities and reviews of procedures, l
equipment changes, proposed tests or experiments, had been performed and j
documented in the RSB minutes. Additionally the biennial reviews of the emergency and security plans had been conducted and acceptably documented.
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Conclusions The RSB met at least annually. Quarterly audits were conducted as required.
The RSB carried out its safety duties as required by license, TS, and administrative criteria.
l Violations 9601-01 and 9601-03 involving quarterly audits and biennial reviews were closed based on the implementation of licensee corrective actions..
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ll. Maintenance M1 Conduct of Maintenance M 1.1 Surveillance and Limiting Conditions for Operation a.
inspection Scope (Inspection Procedure 69001)
The inspector reviewed selected surveillance records, data sheets and records of tests, licensee procedures, reactor logs, checklists, periodic reports, and interviewed staff.
b.
Observations and Findings Daily and other periodic checks, tests, and verifications for TS required limiting conditions for operations (LCO) were completed as required. Surveillance and LCO verifications were completed on schedule as required by TS and following licensee procedures. All were within prescribed TS and procedure parameters and in close agreement with the previous surveillance results.
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Conclusions
. The facility's program for surveillance and LCO confirmations satisfied TS requirements.
M2 Maintenance and Material Condition of Facilities and Nuioment a.
Inspection Scope (Inspection Procedure 69001)
The inspector reviewed maintenance and reactor logs, RSB minutes, repair records, and observed facility and equipment during an accompanied tour.
b.
Observations and Findings Routine / preventative maintenance was controlled and documented.
Unscheduled maintenance or repairs were informally evaluated to decide that it was not a facility change. The RS stated that they would evaluate the need for formal written guidance to ensure that any facility change would be done under 50.59 or license amendment as required by TS. This will be reviewed during a
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future inspection as an Inspection Follow-up item (IFl 059-98-201-02).
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Conclusions Maintenance logs, records, performance, and maintenance reviews satisfied TS e
and procedure requirements.
Ill. Engineering E1 Conduct of Engineering, Design Changes a.
Inspection Scope (Inspection Procedure 69001)
The inspector reviewed procedures, logs, records, and RSB files. The inspector also interviewed staff.
b.
Observations and Findings No design changes had been r. lade since the last inspection.
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Conclusions
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Design continued to satisfy TS and tegulatory requirements.
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IV. Plant Support R1 Radiological Protection and Chemistry Controls R1.1 Radiation Protection Postings a.
Scope (Inspection Procedure 69001)
The inspector reviewed radiological signs and postings, routire radiation surveys and observed the facility and equipment during accompanied tours, b.
Observations and Findings Postings were acceptable for the hazards involved. The facility and radioactive material storage were secured and properly posted. No unmarked or unsecured radioactive materials were evident. NRC Forms-3 were posted in appropriate areas in the facility as were current notices to workers required by 10 CFR 19.
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Conclusions Radiological postings satisfied regulatory requirements.
R1.2 Radiation Protection Surveys a.
Scope (Inspection Procedure 69001)
The inspector reviewed procedures and survey records, and interviewed staff.
b.
Observations and Findings Annual and other periodic contamination or radiation surveys were done by reactor and HP staffs as required by TS and licensee procedures. Results were acceptably evaluated, c.
Conclusions Surveys were conducted and documented as required by 10 CFR 20, TS, and licensee procedures.
R1.3 Personnel Dosimetry a.
Scope (Inspection Procedure 69001)
The inspector reviewed dosimetry records, licensee procedures, and interviewed staf _ _ _ _ _ _ _. _ _ _ _ - _ _ _ _ _ _ _ _ -
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Observations and Findings The licensee used a National Voluntary Laboratory Accreditation Program-accredited vendor to process personnel thermoluminescent dosimetry. An examination of records for the past two years showed that all exposures were within NRC limits, with most having no exposure above background.
c.
Conclusions Doses were in conformance with licensee and 10 CFR 20 limits.
R2 Status of Radiation Protection and Control (RP&C) Facilities and Equipment a.
Scope (Inspection Procedure 69001)
The inspector reviewed the licensee's inventory, calibration, and periodic checks of portable radiation survey instruments, and interviewed HP staff.
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Observations and Findings Calibrated instruments were available at the time of inspection. Calibrations of the instruments used to perform radiation surveys were performed with i
radioactive sources traceable to national standards. All instruments checked were in calibration. Calibration records were in order.
c.
Conclusions RP&C equipment was being maintained according to industry and equipment manufacturer standards. Calibrations satisfied TS requirements.
R6 RP&C Organization and Administration a.
Scope (Inspection Procedure 69001)
l The inspector reviewed radiation protection program documentation, and interviewed staff.
b.
Observations and Findings The Radiation Safety Office provided support to the reactor as well for being responsible for the state license. Coordination of HP activities between the HP and reactor staffs was acceptable.
The inspector determined, while performing an in-office review of the licensee's audit and review program, that annual review of the radiation protection program, in accordance with 10 CFR 20.1101(c), had been performed.
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Conclusions HP staffing and radiation protection program documentation met TS, regulatory requirements and licensee commitments.
V. Management Meetings X1 Exit Meeting Summary
'The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on April 9,1998. The licensee acknowledged the findings presented.
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PARTIAL LIST OF PERSONS CONTACTED Licensee
"R. Berry Reactor Supervisor C. Meyer Radiation Safety Officer, Environmental Health and Safety
"J. Poston Reactor Administrator, Head, Nuclear Engineering Department l
D. Russell, Jr.
Dean, College of Engineering, Chairman Reactor Safety Board
" Attended Out Briefing INSPECTION PROCEDURE (IP) USED IP 69001:
CLASS 11 NON-POWER REACTORS ITEMS OPENED, CLOSED, AND DISCUSSED Opened IFl 50-059-98-201-01 The licensee would annotated SRO hours separately on their present tracking documents.
l IFl 50-059-98-201-02 Licensee to evaluate the need for formal written guidance to
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insure that any facility change would be done under 50.59 or license amendment as required by TS.
Closed NOV 50-059 96-201-01 Failure to ensure that quarterly audits of facility activities and reactor operations were performed and failure to ensure that biennial audits of the emergency plan and implementing
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I procedures were performed and by an individual who was not responsible for the audited item NCV 50-059-96-201-03 Failure to ensure that biennial audits of the security plan and implementing procedures were performed and by an individual who was not responsible for the audited item PARTIAL LIST OF ANACHRONISMS USED HP Health Physics LCO Limiting Conditions for Operations
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l NRC Nuclear Regulatory Commission RS Reactor Supervisor RSB Reactor Safety Board i
SRO Senior Reactor Operator TS Technical Specifications i
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