IR 05000131/1999201
| ML20205L144 | |
| Person / Time | |
|---|---|
| Site: | 05000131 |
| Issue date: | 04/07/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20205L135 | List: |
| References | |
| 50-131-99-201, NUDOCS 9904140154 | |
| Download: ML20205L144 (13) | |
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U.S. NUCLEAR REGULATORY COMMISSl3N Docket No: 50-131 License No: R-57
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Report No: 50-131/99201 (DRIP)
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Licensee: Omaha Veteran's Affairs Medical Center Facility Name: Veteran's Affairs Medical Center Research Reactor Location: Omaha, Nebraska Dates: March 15-17,1999 I
I Inspector: T. M. Burdick, Reactor inspector )
l Appro/ed by: Ledyard B. Marsh, Chief Events Assessment, Generic Communications and Non Power Reactors Branch Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation
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990414-0154 990407 PDR ADOCK 05000131 G PDR ,
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EXECUTIVE SUMMARY Omaha Veteran's Affairs Medical Center Research Reactor Report No. 50-131/99201(DRIP)
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This routine, announced inspection included aspects of organization, operations and maintenance; operations and maintenance procedures; requalification training, surveillance, experiments, radiation controls, environmental protection, design chanDe, audit and review, emergency preparedness, and fuel handling activities (69001); transportation i activities (86740); review of licensee reports (90713); Physical Security (81431); and Material Control (85102).
Oroanization (69001)
e The Veteran's Affairs Medical Center Research Reactor organization has been limited to one licensed senior reactor operator for some time. (Section 1.0)
I Operations and Maintenance (69001)
I e Reactor operation and maintenance were acceptable and in accordance with the reactor's license conditions and Technical Specification (TS) requirements. Logs and records were acceptable. Year 2000 computer issues have been evaluated and are not a concern. (Section 2.0)
Procedures
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- The licensee has developed some new procedures yet needs to review and update them to ensure consistency with current requirements, practices, and expectation (Section 3.0)
Reaualification Proaram o Requalification program requirements were met through exemptions allowed by the requalification program and self review. (4.0)
Surveillance, Experiments. Fuel Handlina (69001), and Periodic and Special Reports (90713)
e No concerns were identified. (Sections 5.0,6.0,11.0,12.0)
Radiation ControLL69001)
e The radiation protection program was effective in protecting the staff and public.
f 1 Exposuret were consistently maintained at extremely Inw levels.
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e Radiation safety audits were acceptable. (Section 7.0)
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Environmental Protection (69001)
- Airborne releases were within the regulatory limits. Radioactive waste accumulations were properly stored. (Section 8.0)
Audits and Reviews (69001)
- Reactor Safeguards Committee (RSC) meetings and audits were conducted within the specified time period. (Section 9.0)
Emeraency Preparedness (69001_1
- Emergency Plan evacuation exercises and training were conducted satisfactoril (Section 10.0)
Transportation (86740)
- The licensee had not conducted any transportation activities since the last inspectio (Section 13.0)
l Safeauards and Materials Accountina (81431 and 85102)
- Physical security and material controls were acceptabl (Sections 14.0 and 15.0)
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DETAILS Plant Summary The Omaha Veteran's Affairs Medical Center Research Reactor has been operating for training and limited neutron activation analysis since the last inspection. Facility license renewalis pending NRC revie .0 Organization Inspection Scope (69001)
The inspector reviewed TS and the Safety Analysis Report (SAR) related to organization and staffing and compared the requirements with current condition Observations and Findings The inspector determined that the organizational structure and assignment of j responsibilities were as specified in TS The membership of the Reactor Safeguards Committee (RSC) was in accoraance with TS and the SAR. RSC membership and meetings were as required Meeting minutes were reviewed with no problems note The inspector verified that minimum staffing requirements were met during reactor operations. The reactor supervisor has been the only licensed senior reactor operator the past two years. One other person has been a designated trainee for operator licensing which permitted completion of TS required surveillance and should provide for some limited flexibility in the staffing, Conclusions Compliance with TS requirements and observed reactor facility material conditio were goo .0 Operations and Maintenance Activities Inspection Scope (69001)
i The inspector reviewed the reactor operations logs and discussed reactor !
operations and maintenance with the staff to determine compliance with the !
operating license conditions and the requirements in T Observations and Findinas The i,Jensee had operated the reactor intermittently at various thermal power levels in accordance with operating license cor'ditions. The inspector verified that they were in compliance with T I i
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Selected reactor operator logs were reviewed and found to be sufficient to retrieve
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routine operating, maintenance, and surveillance data. No operations or maintenance activities were performed during the period of the inspectio The licensee replaced the failed pool cooling pump with an original equipment model. The replacement pump, which has been out of production for years, was l procured as a custom order by the pump manufacture The licensee had concluded that the Y2K issue does not affect their reactor
. systems, Conclusions The reactor was operated and maintained in accordance with the reactor's license conditions, safety limits and limiting conditions for operation. The licensee's logs and records appropriately documented reactor operations and maintenance activities. Replacement components were equivalent to original design. The Y2K issue does not affect reactor system .0 Procedures Inspection Scoce (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 Observations and Findinas Violation 50-131/9601-02 (Closedh f ailure to prepare written surveillance procedures required by TS 6.7. The licensee prepared and implemented the three procedures identified by the Notice of Violation. They included scram time, pool level alarm, and ventilation systcm operability verifications. The procedures appeared to cover the intended activities acceptabl The inspector noted some old information in selected p4 .;edures that the licensee acknowledged should be update . Conclusions The licensee had approved procedures to satisfactorily conduct reactor operations, maintenance, experiments, surveillance testing, and instrument calibrations to ensure compliance with TS requirements.
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l l 4.0 Requalification Training Insoection Scope (69001)
l The inspector reviewed the reactor operator requalification training program to
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determine compliance with the requirements in 10 CFR 19.12 and 10 CFR 55.5 Observations and Findinas As the only licensed senior reactor operator on staff, the Reactor Supervisor has been participating in a documented self review program covering the required subjects of the program. The Reactor Supervisor was exempted by the program from the annual written test and operating evaluations, Conclusions An acceptable training program was being conducted. Acceptable training records were being maintaine .0 Surveillance Insoection Scone (69001)
The inspector reviewed selected surveillance test documentation and observed demonstrated activities to determine compliance with the requirements in T Observations and Findinas Routine surveys and surveillances observed were acceptable. Tests of the pool level alarm and pool area radiation monitor were demonstrated at the inspector's request. TS required calibration and surveillance records were reviewed. No problems were identifie Conclusions Selected reactor surveillance tests had been completed and documented at the required frequencies, and the surveillance test results met TS requirement .0 Experiments
, Insoection Scoce (69001)
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The inspector reviewed the licensee's program to control and conduct experiments performed in the reactor to determine compliance with the requirements in TS.
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4 Observations and Findinas No new types of experiments were conducted since the last inspection. Records of experiments were complete, Conclusions All reactor experiments were conducted in accordance with properly reviewed and approved procedures and satisfactorily documented in the reactor operations lo .0 Radiation Control Inspection Scope (690C -
T he inspector reviewed the radiation protection program and records to determine compliance with the requirements in 10 CFR Part 20 and T Observations and Findinas Radiation exposures were very low and survey results indicated that the reactor lab was a very low dose facility. Instrumentation was calibrated and verified operabl The inspector conducted surveys that confirmed the licensee's records. The Radiation Safety Officer conducted annual audits at the reactor as require Results were documente Conclusion The licensee's facility does not pose a significant radiation problem to workers, visitors, or the publi .0. Environmental Protection Inspection Scope (69001)
The inspector reviewed the licensee's program for the discharge or removal of radioactive liquid, gases, and solids from the reactor laborator Observations and Findinas The facility design does not permit direct connection of the reactor pool with either drains or makeup supplies making unmonitored liquid releases difficult. No liquid releases have been made since the last inspectio Airborne effluent monitoring records showed that the releases were within the regulatory limit _ _ _ _ _ _ _ _ _ _ _ _
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The inspector determined that they properly stored and posted the solid radioactive waste as required for decay in storage or prior to shipment, Conclusions Airborne and liquid releases and solid waste disposal were within the regulatory limit .0 Audit and Reviews Inspection Scoce (69001)
The inspector reviewed the meetings, aucits and reviews conducted by the RSC to determine compliance with the requirements in T Observations and Findinas Facility operations for conformance to the TS, requalification, and emergency plan l audits were conducted as required. Qualified outside auditors may increase the l objectivity of these audits.
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RSC members conducted reviews of procedures and other matters as required.
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l Audits and reviews were conducted appropriately at the required intervals.
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10.0 . Emergency Preparedness Insoection Scoce (65001)
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.The inspector reviewed the emergency plan and the last three annual drills for the l reactor laboratory, interviewed licensee employees, and inventoried the equipment
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storage cart to determine compliance with the requirements in 10 CFR 50.54(q) ;
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and (r) and the pla Observations and Findinas The inspector ' discussed the emergency calllist with the reactor staff and contacted the hospital switchboard operator to verify the accuracy of information and the procedure guidance. Annual emergency drills and procedure reviews were '
documente I The inspector noted that drill scenarios may be more effective if they were prepared and conducted by an outside qualified party, t-
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. Conclusions The licensee maintained the emergency program in a state of operational readines ,0 Fuel Handling Insoection Scoce (69001)
The inspector reviewed the fuel handling procedures and records at the reactor laboratory, and interviewed employees to determine compliance with T Observations and Findinas The licensee only handles fuel for inspection purposes. The quarterly inspections we% routine with no problems noted by the licensee. The licensee has applied for a reduced inspection frequency in the pending license renewa Conclusions The licensee's procedure and documentation for quarterly fuelinspections were acceptabl .0 Review of Periodic and Special Reports Inspection Scope (90713)
' The inspector reviewed the licensee's submittal of reports and notifications to the l NRC to determine compliance with the requirements in T Observations and Findinas l The inspector found the last three annual reports routine and acceptable.
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! Violation 50-131/9601-01 (Closed):. failure to address all required topics in the annual report to NRC. - The licensee had not included all new experiments. The last three reports included all required topic Conclusions The licensee had submitted required reports to the NRC in accordance with TS requirement _
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l 13.0 Transportation of Radioactive Materials
! Insoection Scope (86740) J The inspector discussed radioactive materials shipping with the staf t l Observations and Findinas The inspector determined that no transportation activity had occurred in the past and that the licensee had no plans to do so in the future, I Conclusion The licensee had not transferred radioactive materials during the period reviewe .0 Safeguards Inspection Scone (81431)
To assure that the licensee has a physical protection system that will minimize the !
potential for unauthorized removal of special nuclear material: (SNM), facilitate the location and recovery of missing SNM; and assure that the licensee's physical protection program adequately implements the applicable provisions of 10 CFR Part 7 Observations and Findinas The licensee hd revised the access control system such that the level of protection was increased since the last inspection. The physical security protection features employed by the licensee were beyond the scope of the program requirement Conclusions The licensee satisfactorily implemented the program required for fixed site physical !
protectic.) of SNM of low strategic significanc .0 Material Controls and Accounting Insoection Score (85102)
Determine whether the licensee has limited possessicn and use of SNM to the locations and purposes authorized under the license. Determine whether the licensee has implemented an adequate and effective program to account for and control the SNM in their possessio m
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, Observations and Findinas
% The licensee had minimized its possession of SNM material and maintained all the authorized rnaterial in the reactor pool, Records of material possession were accurate, Conclusions The licensee maintained control of authorized materia .0 Exit interview (30703)
The inspector presented the inspection results to members of the licensee management at an exit meeting on March 17,1999. The licensee acknowledged the findings preserted. The inspector asked the licensee whether any material examined during the inspection should be considered proprietary. They identified no proprietary informatio _ _ _ _ .
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Partial List of Persons Contacted Oms 5 Veteran's Affairs Medical Center
- John Claasen Reactor Director
- Dr. L. Klassen Associate Chief of Staff, Research
- Michael Caldwell Associate Director, Diagnostics M. Christensen Radiation Safety Officer The inspector also e ntacted other supervisory, technical and administrative staff personne * Denotes those attending the exit meeting on March 17,199 Inspection Procedures Used IP 69001 Class 11 Nonpower Reactors IP 86740 inspection of Transportation Activities IP 90713 Review of Periodic and Special Reports IP 81431 Safeguards and Materials Accounting IP 85102 Safeguards and Materials Accounting items Opened and Closed Open None Closed 50-131/9601-01 NCV Failure to include all required topics in the annual report to the NR /9601-02 VIO Failure to prepare all written surveillance procedures required by TS . _ - _ _ _ _ _ _ _ _ -
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List of Documents Reviewed Safety Analysis Report Safety Evaluation Report Reactor Operating License Technical Specifications Administrative Procedures Operating Procedures Maintenance Procedures Surveillance Procedures Maintenance and Surveillance Records Emergency procedures Training Program Emergency Plan Dosimetry Records Training Records Various Reports List of Acronyms Used ALARA As Low as Reasonably Achievable CFR Code of Federal Regulations DOT Department of Transportation HP Health Physics NRC Nuclear Regulatory Commission PDR Public Document Room RSO Radiation Safety Officer RSC Reactor Safeguards Committee SAR Safety Analysis Report SNM Special Nuclear Material TS Technical Specifications
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