IR 05000225/1998201
| ML20217H656 | |
| Person / Time | |
|---|---|
| Site: | Rensselaer Polytechnic Institute |
| Issue date: | 04/28/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217H650 | List: |
| References | |
| 50-225-98-201, NUDOCS 9804300025 | |
| Download: ML20217H656 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION Docket No: 50-225
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License No: CX-22 Report No: 98201 Licensee: Rensselaer Polytechnic Institute Facility: L. David Walthousen Critical Experimental Facility Location: Schenectady, New York Dates: April 7-10,1998 Inspector: Thomas F. Dragoun, Reactor inspector Approved by: Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management
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9804300025 980428 PDR ADOCK 05000225 l G PDR , l
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EXECUTIVE SUMMMY The licensee's programs were directed toward the protection of public health and safety and were found to be in compliance with NRC requirements. No significant safety concern or violation as identifie l l
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Reoort Details Summarv of Plant Status i
The reactor was operated for student tours, training of reactor operator candidates, and a radiation survey. Housekeeping was acceptable. The 400 cycle motor-generator set, city water supply piping, reactor water dump valve and downstream piping had been replace A Gamma-Metrics digital nuclear instrumentation unit was installed in the control console but not electrically connecte Organization and Staffing Insoection Scone (Insoection Procedure 40750)
The inspector reviewed:
e organizational changes, and e staffing levels Observations and Findinas The college president and dean of the engineering school were replaced during this inspection. No impact on facility operation was anticipated. Since the last inspection, the Operations Supervisor, a position normally filled by a student, graduated and was replaced. However, no replacement has been named for the incumbent who will graduate in May 1998. The Facility Director retired to become an " active" professor emeritus but remained fully involved with the critical facility. Eight students were in training to obtain an NRC senior reactor operator licens Three SROs were available to support reactor operations. Records indicated that a Duty SRO and On-call SRO were designated whenever the reactor was not shutdown as required by T.S.6. The facility license expires in approximately five years. The additional workload to support license renewal has not been assessed by the licensee, Conclusions The organization satisfied T.S. 6.1 requirement Operation Logs and Records Insoection Scone (Insoection Procedure 40750)
The inspector reviewed:
o reactor startup and t5utdown checklists, e console operations log, e surveillance records, and e maintenance record .
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2 Observations and Findinas Records, checklists, and logs were clear and detailed. A separate list was added to !
the back of the consolo log which gave the page number where surveillance data and unanticipated scrams were recorded. This list assisted the inspector in quickly locating dat Surveillances were performed on schedule and results met the applicable acceptance criterion's requirements. No radioactive material was shipped and there were no reportable occurrences. Limiting conditions for operations were satisfie Two of the four area gamma radiation monitors were out of commission. The licensee used portable units in these areas as allowed by T.S. 3.3(d). The two remaining operable units included the criticality monitor. The Facility Director stated that two new area monitors (detector and console readout) were ordered to replace the defective equipment. Management was also considering replacing the remaining two channels in anticipation of future failure The air monitor for the reactor room was calibrated semiannually. Since this device monitors airborne particulate activity as specified in T.S. 4.3, use of a button source with known activity for calibration was appropriate. Inspector fo!!ow-up item 92-01-01 is close Conclusions i
Records were maintained as required by T.S. 6.6 and surveillances conducted as required by T.S. Procedures Insoection Scone Unsuection Procedure 40750) j The inspector reviewed:
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e current procedures, and e procedure implementation, Observations and Findinos Written and approved procedures required by T.S. 6.2 were available. Some activities are documented as student experiments. The Operations Supervisor indicated that there was a need for additional procedures and improvement of existing procedures to ensure consistency of program implementation during the frequent turnover of operations personnel.. This effort would be completed as time permitte l
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Procedures were used verbatim during the training class for SRO candidates. Some students read each step allowed for the benefit of the class during the evolution. The startup checklist, reactor startup, power changes, and reactor shutdown were done in accordance with procedures. The two SROs providing the training also quizzed students during performance of the procedure, Conclusions Availability and use of procedures satisiled T.S. requirement R1 Radiation Protection Scone (Insoection Procedure 40750)
The inspector reviewed:
o radiation protection policies and procedures, e personnel, environmental, and area dose records, e radiological signs and postings, e instructions to personnel, e control of effluent releases, e a routine radiation survey, and e instrument calibration Observations and Findinos During inspection 96-01, the licensee stated that revised Radiation Safety Regulations and Procedures (Revision 4) would be provided for NRC review. This was done. A review determined that the program was clear, comprehensive, and satisfied requirements specified in 10 CFR 20.1101. Inspector follow-up item 96-01-02 is close Personnel, environmental, and area doses were measured using commercially available 4 chip TLD badges. TLD processing was done in-house as allowed by 10 CFR 20 Subpart F because doses were less that 10% of the NRC limits and there were no high radiation areas. All doses were within these limits. However, the inspector noted that some TLDs used within the critical facility as full time area monitors indicated an average dose rate of several millirem por hour across the year. Also, the relative contributions of neutron and gamma radiations shifted significantly from the first half of the year to the second half. These levels did not coincide with the results of monthly routine radiation surveys. Furthermore, given the distance of the TLDs from the core and PuSe source, and limited reactor operation during the year, there was the possibility that high radiation areas existed under certain conditions. Advised of this concern, the licensee conducted a gamma and neutron survey with portable instruments on April 10,1998. Reactor conditions during the survey included: core tank drained and filled, PuSe neutron source exposed and stowed, and the reactor at different power levels. Preliminary analysis of the survey data indicated that the TLD results were in error. The licensee's final resolution of this matter will be reviewed in a future inspection. (Inspector Follow-up item 50 225/1998201-01).
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in addition to the special radiation survey discussed above, the inspector accompanied the Assistant RSO during a routine survey of dose rates and contaminatio Acceptable survey techniques were used, procedure was followed, and results were well organized and clearly recorded on survey maps. The surveyor was aware of expected levels and able to identify anomalies. Warning signs and postings were appropriate for the radiation levels measured during the survey Annual refresher training was provided to radiation workers. Written exams and lecture outlines indicated that material presented satisfied requirements in 10 CFR 19.1 *
Liquid waste was analyzed for beta and gamma emitters using generally accepted techniques. Laboratory analytical equipment was properly quality controlled and efficiency factors measured each time a sample was analyzed. Discharge records indicated that affluent concentrations were below NRC limits. Gaseous discharges were not monitored due to the low reactor power levels. However, the licensee indicated that the EPA COMPLY computer code will be used to demonstrate compliance with the NRC constraint criteria effective January 9,1997. No solid radioactive waste was produced at the reacto Portable S/y survey instruments and laboratory al proportional counters are calibrated semiannually by students as experiments. The procedures were updated in Spring 1998 and followed recommended practices. The neutron survey meter was calibrated by a vendor.' Conclusions The radiation protection program has been maintained in accordance with regulatory requirements and licensee commitment S1 Material Control and Accounting l
a. Insoection Scone (Insoection Procedure 85102)
The inspector reviewed:
e designated storage areas, i e shipment, receipt, and burn up records, !
e annualinventory results, and i e reports, b. Observations and Findings Records indicated that all nuclear material shipped or received was accurately accounted for. The licensee had one receipt of SNM and made no shipments between September 30,1993 and September 30,199 _ .
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Storage and accountability of SNM were accomplished through item control. All SNM was stored in designated areas which included the reactor core and security cabine Physical inventories were conducted at least annually as required by 10 CFR 70.51(d).
The licensee's last inventory was performed on September 26,1997. The operations staff conducts a monthly piece count of fuel pins and fuel pellets at the facility and reports the results to the Facility Director. The following material was accounted for:
- one Plutonium Beryllium Source, number M-734
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597 fuel pins containing 35,995 pellets with 434,480 total grams of enriched uranium with 20,855 grams U-235 All Material Balance Reports (DOE /NRC Form-742) submitted by the licensee for the period September 30,1993, through September 30,1997, satisfied the requirements specified in 10 CFR 70.53. Total uranium and uranium-235 depletion records were satisfactor c. Conclusions No deficiencies were identified in the licensee's Material Control and Accounting progra X1 Exit Meeting Summary (Inspectica Procedure 30703)
! The inspector presented the inspection results to members of licensee management on April 9,1998. The licensee acknowledged the findings presente I
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PARTIAL LIST OF PERSONS CONTACTED Licenses
- 'W. Christenson, Assistant Radiation Safety Officer
! *B. Craig, Operations Supervisor
'D. Harris, Director, Reactor Critical Facility
'D. Steiner, Chairman, Department of Environmental and Energy Engineering G. Xu, Radiation Safety Officer and Director, Office of Radiation and Nuclear Safety
' Attended the Exit Interview on April 9,1998 l
l INSPECTION PROCEDURES USED IP 40750: CLASS 11 NON-POWER REACTORS -
IP 85102 MATERIAL CONTROL AND ACCOUNTING - REACTORS l
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- ITEMS OPENED, CLOSED, AND DISCUSSED l
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50-225/1998201-01 IFl Resolve discrepancy between area TLD results and routine surveys Closed 50-225/92-01-01 IFl Review calibration procedure for continuous air monitor 50-225/96-01-02 IFl Provide copy of RSRP manual to NRC
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LIST OF ACRONYMS USED CFR Code of Federal Regulations l IFl Inspector Follow-up item NRC Nuclear Regulatory Commission !
PuBe Plutonium-Beryllium neutron source ,
i RP Radiation Protection l
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RSO Radiation Safety Officer l SRO Senior Reactor Operator ,
TLD Thermoluminescent dosimeter l Technical Specifications
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