IR 05000116/1997201
| ML20210M814 | |
| Person / Time | |
|---|---|
| Site: | University of Iowa |
| Issue date: | 08/18/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20210M799 | List: |
| References | |
| 50-116-97-201, NUDOCS 9708220228 | |
| Download: ML20210M814 (16) | |
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U.S. NUCLEAR REGULATORY COMMISSION Docket No: 50 116 i
License No: R 059
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Report No: 50110/97201 (DRPM)
l Licensee: lowa State University
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Facility Name: UTR 10 Argonaut Reactor Location: Ames, Iowa l Dates: July 2125,1997 I Inspector: T. M. Burdick Approved by: Marvin Mendonca, Acting Director Non Power Reactor and Decommissioning Project Directorate i
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9708220220 970s1e gDR ADOCK 05000116 PDR
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Executive Summary UTR 10 Argonaut Reactor Report No. 50116/97201(DRPM)
This routine, announced inspection included aspects of organization, periodic and special reports, operations, maintenance and procedures; requalification training; surveillance; experiments; radiation controls; environmental protection; design change, audit, and review; emergency preparedness; fuel handling activities (69001); and review of licensee reports (90713).
QIganization and Staffino (69001)
- The UTR 10 Reactor staffing has declined since the last inspection. Only one permanent staff member, the Reactor Manager (RM), remained to hold a senior reactor operator's (SRO) licence. Four other SROs were available only on a very limited basi (Section 1.0)
Ocarations and Maintenance. Proceduras. Ranualification Prooram. Exoeriments. Radiation Control and Envitonmental Protection. Emeroencv Plan. and Fuel Handlino (69001), and Estladic and Snecial Ranorts(90713)
e No concerns were identifie (Sections 2.0, 3.0, 4.0, 6.0, 7.0,10.0,11.0, and 12.0) '
I Surveillance and Limitino Conditions for Ocaration (69001)
e The inspector identified a violation in which the licensee operated the reactor prior to completing required surveillance on safety related system *
One Non cited Violation was identified when the licensee discovered that the safety related power supply batteries had not undergone the required 3 year surveillanc (Section 5.0)
Design Control (69001) -
e The reactor lab building underwent modification to interior walls and doors to meet fire safety codes that affected radiation monitoring and alarms. -
e The licensee installed a new replacement linear power wide-range channel due to a recurring failure of the installed unit's recorder pens. (Section 8.0)
Audits and Reviews (69001) .
e A second Non Cited Violation was identified when the licensee discovered that they had failed to audit their fuel shipping progra Fuel Handlino e The licensee had been planning a High Enriched Uranium (HEU) fuel shipment that has since been delayed. (Section 9.0)
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DETAILS ElAQLSummary The University of lows UTR 10 reactor at Ames has been very inactive during the past two years. Qualified operator staffing availability has been a problem. Operations conducted were primarily for operator license maintenance and reactor surveillance. Occasional demonstration irradiation experiments for undergraduates were conducted. The reactor hos l
been out of service for most of 1997 due to problems with the linear power wide range channel and the resulting incomplete surveillance. A similar outage occurred in 1996 for the same reasons. The licensee has been attempting to complete surveillance this summer and hoped to be operational by late July, I
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' Organization
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a. Insnection Scone (69001) l l
The inspector reviewed Technical Specifications (T.S.) and the Safety Analysis l'
Report (SAR) related to organization and staffing and cornpared the requirements with current conditions.
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b Qbservations and Findinos The inspector determined that the organizational structure and assignment of responsibilities had been as specified in T.S. 6.0. Graduation and departure of student employees and the previous RM had left the staff with only one permanent SRO and four other part time SROs whose availability was limite The abrupt resignation of the Chair has recently affected membership of the Reactor Use Committee (RUC) while retirement is approaching for another member. The Reactor Use Committee (RUC) has recommended replacement members to the Radiation Safety Committee (RSC).
The licensee has conducted meetings more frequently than require The inspector verified that reactor staffing met requirements. However, the RM said that the limited availability of qualified staff has inhibited the ability to meet all required surveillance in a timely manner. The inspector identifico a violation of surveillance requirements detailed in section The lengthy outages that occurred in 1996 and 1997 Interfered with the required operating hours needed to keep the staff qualified as well, c. Conclusions The licensee's staffing difficulties have affected their ability to meet requirement ..
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-2-2.0 Operations and Maintenance Activities a. Insnaction Scona (69001)
The inspector reviewed the reactor operations and maintenance logs to determine compliance with Operating 1.lconse Condition 2. b, Observations and Findinos l No reactor operation occurred during the inspectio The licenses had operated the reactor intermittently at various thermal power ;
levels in accordance with Operating License Condition 2. l The inspector identified that the licensee operated the reactor on December 31, l 1996 in violation of T.S. requirements detailed in Section 5.0.
l The inspector reviewed the records for repair of the linear wide range nuclear i channelin 1996. Linear channel recorder problems for two extended periods had interrupted reactor operations in the last 18 month Other maintenance and operationL activity records reviewed by the inspector revealed no significant concerns, c. Conclusions Operations were conducted, with one exception, in accordance with the reactor's license conditions, safety limits and limiting conditlo; s for operation. The licensee's logs and records documented reactor operations and maintenance activitie .0 Procedures a. insoection Scone (69001)
The inspector reviewed the licensee's written procedures for operating and maintaining the reactor, performing surveillance activities, and conducting experiments to determine compliance with the requirements in T.S. b. Observations and Findinos The inspector verified that the licensee reviewed procedures as required. The licensee developed new procedures for fuel segregation and shipment and the new linear wide range nuclear channel, c. Conclusions The licensee had approved procedures to acceptably conduct reactor operations, maintenance, experiments, surveillance testing, and instrument calibrations according to T.S. requirement _ _
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-3- Requalification Training a. insoection Scone (69001)
The inspector reviewed the reactor operators' requalification training program to determine compilance with the requirements in 10 CFR 19.12 and 10 CFR 55.5 b. Observations and Findinos The licensee's last two written exams were acceptable. Each licensed operator had a current license and physical examinatio The inspector noted that the licensee did not renew one license in a timely manner. The Individual had not operated the reactor meanwhile while waiting for the NRC to dispodtion his application for a license. The licensee has set up a better tracking system for license renewal l c. Conclusions l
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The licensee is acceptably conducting a training program and maintaining training record .0. Surveillance and Limiting Conditions for Operation a insoection Scone (69001)
The inspector reviewed selected surveillance test documentation to determine compliance with the requirements in T.S. b. Observations and Findinos The inspector identified a violation of T.S. requirements. T.S. 4.0 requires that all surveillance be complete prior to operation of the reactor. Contrary to this, the licensee operated the reactor at full power on December 31,1996 when annual surveillance of 12 M 5, Moderator Level; 12 M 9, Rod Position Indication; and 12 M 10, Rod Responses (drop, withdrawal, and delay times) were not complet This is a violation (50116/9720101)
The licensee had conducted each of these surveillance in late December 1995 and all were due prior to December 31,1996. The RM had assumed that all surveillance were provided with a 10% grace period based upon informal and unwritten guidance he had received from his predecessor. Nolther the licensee's T.S. nor their implementing procedures provide any authorization regarding grace period for surveillanc The RM stated that he felt he had to operate the reactor to accomplish the 12 M-6, Thermal Power Calibration (calorimetric) although the inspector noted it was not due until January 11,1997. He stated that the staff necessary to accomplish the power calibration was available on December 31,1996 and that
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~4-the assumed 10% grace period would allow delaying tno other surveillance that required fewer people. The inspector noted that the three missed surveillance could have been done without reactor operatio The licensee preliminarily indicated that the cause for the violation appears to have been twofold; a limited availability of qualified staffing to ensure reactor surveillance were completed within the required time limits and a licensee j assumption that they could apply an informal 10% grace period to the prescribed l time limi )
The licensee completed the required surveillance satisfactorily in January 199 To prevent recurrence, the licenses had proposed multiple approaches; no application of grace periods to the requirements and shifting part of the surveillance schedule to the Summer months which would reduce classes and
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other conflicts with staffing. The licensee may also consider making staffing addition The licensee identified on January 10,1997 that the required surveillance, 3 36 M 1. T.S. 4.6.3.B battery discharge testing, was overdue. The licensee's '
annual RUC operations auditors reported the missed requirement to the RUC during the audit review on January 17,1997. The RM immediately began the discharge surveillance. However, the lengthy surveillance was not completed
) until January 27,199 T.S. required this surveillance be completed though the reactor was not operational. The RM had misunderstood the requirement for completion of the surveillanc This licensee identified and corrected violation is being treated as a Non Cited Violation, consistent with Section Vll.B.1. of the NRC Enforcement Polie (50 116/97201 02)
c. Conclusions The inspector cited a violation of T.S. requirement .0 Experiments a. Insoection Scone (69001)
The inspector reviewed the licensee's program to control and conduct experiments performed in the reactor to determine compliance with the requirements in T.S. 3.1.3.C, 3.8 and b. Observations and Findinos The inspector reviewed a sarnpling of experiments. Only a few irradiation demonstrations were conducted during the period. No items of concern were note ___
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--5-c.- Conclusions Those reactor experiments reviewed by the' inspector were conducted in accordance with properly reviewed and approved procedures and satisfactorily documented in the reactor operations log. -
7.0 - Radiation Control
'a. inanaction Econa (89001)
- The inspector reviewed the radiation protection program and records and-interviewed personnel to determiria compliance with the requirements in 10 CFR -
Part 20 and T.S. 3.7, and >
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The inspector also reviewed the licensee's program for the discharge or removal of radioactive liquid, gases, and solids from the reactor laboratory, b. Observations and Findinos The lit.easse acceptably posted and illuminated the reactor room, and stored and '
marked potentially contaminated tools and equipmen The licensee had recorded no exposure since the last inspection including the period last year whan they removed the HEU fuel from the storage pit for -
inspection and identification. The licensee issued finger rings during the fuel .
handling activit Reactor operation was so limited that release to the atmosphere was negligibl They have not produced liquid waste since the last inspection. Solid waste was also minimal and had been transferred to the campus license for disposal,
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- All badged reactor personnel exposures were less than detectabl Reactor operations resulted in no radiation exposure and no or insignifican . production of effluent and waste during the perio . Design Change Control
' a. -- Insnaction Scone (69001)
The inspector reviewed licensee system modification activities to verify proper
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50.59 evaluation) installation and operation; pror.edure change and operator treinin .-
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-6-b. Ohsarvations and Findinas The lab building underwent modification rd t 'dition of interior walls and doors for fire safety code compliance. The licens, unntified that the radiation j monitoring (RAM) and alarm system was affected and took the nacessary steps !
to ensure the system remained operable during and following the construction, j The only modification to the RAM system was connecting the building .
evacuation alarm system to the RAM alarm system to assure it was audible to lab occupant Following two prolonged interruptions to reactor operWilty the licensee installed a new linear power wide range channel. The inspectos verified that the licensee acceptably did a 50.59 review; modified procedures; installed the system; l
. completed terir.3; and trained the operators on the new equipmen '
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c, conclusions -
The licensee activities involving system modifications were acceptabl .0 - Audits and Reviews-a. Insoection Scone (69001)
- The inspector reviewed the RUC meetings, audits, and reviews to determine compliance with the requirements in T.S. b. -- Observations and Findinas The licensee held RUC meetings more frequently than the required semiannual sessions. - The RM presented relative matters to the committee for review as requira The licensee prepared and presented one 50.59 review to the RUC for approva It appeared to be acceptabl The licensee recently discovered that they had not audited their fuel shipping
. quality assurance (QA) program as required since its inception in 1995. The V
licensee conducted an immediate audit and they resolved minor documentation =
findings acceptably. The licensee had never shipped fuel under the progra This licensee-identified and corrected violation is being treated as e Non-Cited -
. Violation, consistent with Section Vll.B.1. of the NRC Enforcement Polic (50 ?16/97201 03)-
The RUC members t'hemselves conducted the required T.S. operations safety audits. The audits appeared comprehensive and detaile Annual HP audits were conducted by the RSO or his delegates as require ~ . . . . . . . . . . . . . ..
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-7-c. Conclusions RUC meetings and atdits were conducted as required by T.S.. The licensee made objective evaluations of the findings and implemented acceptable change .0 Emergency Preparedness a. insoection Scoce (69001)
The inspector reviewed the emergency plan and the last two drills for the reactor laboratory; interviewed licensee emp;oyees; and inventoried a storage locker to determine compliance with the requirements in 10 CFR 50.54(q) and (r),
b. Observations and Findinos Self-evaluations were objective. The licensee made and implemented recommendations for improvemen The licensee recently obtained two portable disposable decontamination shower The inspector verified that the licensee could use the equipinent as intended at j the designated location. The licensee has placed one unit permanently whereas i
the second designated location has been undergoing reconstruction.
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c. Conclusions The licensee maintained their emergency program in an acceptable stat .0 Fuel Handling a. -Insoection Scone (69001)
The inspector reviewed the new fuel handling procedures and records at the reactor laboratory, and interviewed employees to assess fuel shipment activitie b. Observations and Findings The licensee had developed procedures ic: fusi shipment and performed preparations for shipment. The licensee conducted practice sessions with special tools and jigs used to load fuel plates into special adaptor cylinders to f acilitate loading the shipping cask. However, the licensee learned that others superseded the priority on their two shipments. The licensee delayed the project when they had to return the cask to the Department of Energy (DOE).
c. Conclusions The licensee's procedures and documentation for fuel movement were acceptabl ._ __ _ _ _ _ _ _ _ _ _ _ _
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-8-12.0 Review of Periodic and Special Reports a. Insoection Scotte (90713)
The inspector reviewec the licensee's submittal of reports and notifications to the NRC to determine compliance with the requirements in T.S. 6. b. Observations and Findinos The inspector found that the last two annual reports reflected actual conditions and status of the reactor laboratory, c. Conclusions l The licensee had submitted accurately and timely reports to the NRC in accordance with T.S. requirements.
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13.0 Persons Contacted l lowa State University f
l Warren R. Madden Vice President for Business and Finance L
'Dr. Daniel D. Bullen Facility Director
" Scott Wendt Reactor Manager Ken Kerns Radiation Safety Officer Dr. Eric Bartlett Former RUC Chair Tom Zimmerman Health Physicist The inspector also co'itected other technical and administrative staff personnel during the inspectio * Denotes those attending the exit meeting on July 25,1997, 14.0 Exit Interview (30703)
The inspector presented the inspection results to members of the licensee management at an exit meeting on July 25,1997. The licensee acknowledged the findings presented. The inspector asked the licensee whether any material examined during the inspection should be considered proprietary. The licensee identified no proprietary information, insoection Procedures Used IP 69001 Class ll Non-Power Reactors IP 90713 Review of Periodic and Special Reports F
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llama Onaned and Flamad-Q08n 50 116/97201-01 VIO Operation of the reactor without the completion of required surveillance :
50 116/97201-0 NCV Failure to conduct battery surveillance in the prescribed period -
50 116/97201 03-. NCV- Failure to audit the fuel shipping QA program-
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-10-List of Documents Reviewed
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Safety Analysis Report -
Safety Evaluation Report; Reactor Operating Uconse-Tschnical Specifications j-Administrative Procedures .
- Operating Procedur3s
~ Maintenance Procedures Surveillance Procedures Shipping records and procedures-Maintenance and Surveillance Records -
, Emergency procedures
!- Tralning Program
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' Emergency Plan '
-j Dosimetry Records "
-Training Records- '
' Various Reports 4
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List of Acronvms used j
, ALARA As Low as Reasonably Achievable CFR - Code of Federal Regulations l
DOE : Department of Energy DRPM Division of Reactor Project Management HEU High-Enriched Uranium HP' Health Physicist NRC -_ Nuclear Regulatory Commission POR Public Document Room-i QA -~ Quality hssurance-RA- Reactor Administrator -
RAM ; Radiation Monitoring
'RM Reactor Manager RUL" - Reactor Use Committee iRSC Reactor Safety Committee
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.RSO,
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Radiation Safety Officer SA ; Safety Analysis Report SRO: -Senior Reactor Operator Technical Specifications
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