IR 05000020/1999201
| ML20210H697 | |
| Person / Time | |
|---|---|
| Site: | MIT Nuclear Research Reactor |
| Issue date: | 07/30/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20210H676 | List: |
| References | |
| 50-020-99-201, NUDOCS 9908040074 | |
| Download: ML20210H697 (10) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket Nos:
50-20 License Nos-R 37 Report No:
50-20/99-201 Licensee:
Massachusetts Institute of Technology Facility:
MIT Research Reactor Location:
138 Albany Street Cambridge, Massachusetts Dates:
June 28 July 1,1999 Irispector:
Thomas F. Dragoun Approved 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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L 9900040074 990730 PDR ADOCK 05000020
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EXECUTIVE SUMMARY This routine, announced inspection included onsite review of selected aspects of the design change functions program, radiation protection program, operator requalification program, surveillance program, safeguards program, physical security program, and year 2000 computer readiness since the last NRC inspection of this program.
The licensee's programs were acceptably directed toward the protection of public health.
and safety, and in compliance with NRC requirements.
' REVIEW AND AUDIT The design change program satisfied NRC requirements.
RADIATION PROTECTION The radiation protection program met regulatory requirements.
OPERATOR REQUAllFICATION Operator requalification was conducted as required by the Requalification Program.
SURVEILI.ANCE l
. The surveillance program was conducted as required by the Technical Specifications.
SAFEGUARDS I
Special Nuclear Materials were acceptably controlled and inventoried.
SECURITY l
The NRC approved security program was acceptably implemented.
Y2K No threat to health or safety was identified as a result of Year 2000 computer issues.
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Report Details t
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Summarv of Plant Status l
The reactor had been shut down and the secondary water system drained. The cooling tower structures and water basin had been dismantled and removed. A contractor was excavating the buried cooling tower piping. The operating staff attended a full' day training session on crane safety taught by a contractor. Forms were fabricated for casting
' dd shaped high density concrete shadow shields for areas around the fission converter.
o The fission converter mechanical shutter was being installed. Measurements were taken for relocating a control rod drive and other interferences at the reactor top hat adjacent to the fission converter tank. Training of reactor operator candidates was underway.
Quarterly change out of personnel dosimetry was initiated, industrial safety practices were properly implemented.
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DESIGN CHANGE FUNCTIONS j
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Scooe (IP 407451 The inspector reviewed selected aspects of:
e facility design changes and records e
facility configuration b.
Observations and Findinos Records and observations showed that changes at the facility were acceptably reviewed in accordance with 10 CFR 50.59, the TS, and applicable licensee administrative controls. Completed reviews were comprehensive and submitted to the Reactor Safeguards Committee as specified in the TS. However, records of -
safety reviews and the 50.59 review for the cooling tower replacement had not been completed. The Director of Reactor Operations stated that the records required by procedure PM 1.4 wtwid be completed by July 14,1999. This matter will be j
reviewed in a future inspection (Inspector Follow-up item 50-20/99-201-01)
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Conclusions i-The design change program satisfied NRC requirements.
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RADIATION PROTECTION '
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Scone (IP 83743)
The inspector reviewed selected aspects of:
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e radiological oversight of work e radiation surveys e release of trash and debris e exclusion area control
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Observations and Findinas Radiological oversight of the severaljobs in progress appeared adequate. A contracted HP technician and helper provided continuous oversight of the cooling tower pipe removal project. Appropriate survey meters were readily available.
Release criteria, survey techniques, and records for the unconditional release of trash, debris, and soil from the cooling tower demolition were acceptable. The inspector noted that the radioactive waste storage areas were near full as a result of
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current and previous work. The Assistant Reactor Radiation Safety Officer and the
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Director of Reactor Operations stated that radwaste disposal was postponed until completion of projects such as installation of the fission converter.
Warning signs, postings, and control of access to exclusion areas was acceptable.
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Conclusions
The radiation protection program met regulatory requirements.
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OPERATOR REQUALIFICATION a.
Scoce (IP 41745)
The inspector reviewed selected aspects of:
e operator training records e
operator physical examination records e
operator examination records e
operator active duty status f
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Observations and Findinas The Requalification Program was maintained up to date. Records showed that operator training was consistent with the Requalification Program requirements.
Physical examinations of the operators were conducted as required. Records showed that written and operating examinations of the operators were acceptably implemented. Logs showed that operators maintained active duty status as required.
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Conclusions Operator requalification was conducted as required by the Requalification Program.
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SURVEILLANCE a.
Scope (IP 61745)
The inspector reviewed selected aspects of:
e surveillance procedures, e
suNeillance data sheets and records b.
Observations and Findinas Surveillances were completed on schedule and in accordance with licensee procedures. Testing protocols in the procedures provided reasonable assurance of safety system operability. All recorded results were within the TS and procedurally prescribed parameters. The records and logs reviewed were complete and were being maintained as required. One of the semiannual visualinspections of the containment ventilation system entrance and exit isolation valves was signed off as complete, however, the completed checklist was not on file. The Director of Operations stated that all reactor operators and support personnel would be reminded to file the data sheets on completion of surveillance testing including the results of visual inspections, c.
Conclusions The surveillance program was conducted as required by the Technical Specifications.
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SAFEGUARDS a.
Scoce (IP 85102)
The inspector reviewed selected aspects of:
accountability records and reports e
e nuclear material inventory and locations b.
Observations and Findinos The annual physicalinventory of material required by 10 CFR 70.51(d) was completed on September 30,1998, and provided detailed locations for SNM. During a previous inspection, the inspector noted that the labels on some items were not clear. The licensee stated that identification of most items consisted of engravings that are etched on the materialitself which could not be renewed. To aid identification of smallitems, printed location labels were attached to each shelf and location where the items were stored. This was satisfactory. Inspector Follow-up item 50-20/97 201-01 is closed.
The material control and accountability forms (DOE /NRC Forms 741 and 742C) for the period from April 1,1997, to March 31,1999, were prepared and transmitted as required by 10 CFR 70.53.
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Conclusions Special Nuclear Materials were acceptably controlled and inventoried.
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SECURITY FOR SNM OF MODERATE STRATEGIC SIGNIFICANCE a.
Scoce (IP 81421)
The inspector reviewed selected aspects of:
e implementation of the physit -
ction plan i
e records of barrier and alarm
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e physical barriers and access.
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Qbspr stions and Findinas Physical protection systems (barriers and alarms) and equipment were as required by f
the Physical Protection Plan. Frequent checks were performed and recorded. Access controls were as required. Acceptabt,e security response was demonstrated to an intentional alarm in the new fuel vaul,
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5-l The security area was a'Oeptably expanded to provide clearance for heavy equipment
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during the replacement of the cooling towers. Access control during work by contractors was adequate.
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Conclusions The NRC-approved security program was acceptably implemented.
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YEAR 2000 COMPUTER CONCERNS a.
insoection Scooe The inspector reviewed licensee action relative to the elements of a questionnaire developed by the NRC staff to assess potential Y2K computer problems. The questionnaire was published in the February 1998 TRTR Newsletter, b.
Observations and Findinos A campus-wide program to identify and correct Y2K problems is in place. The facility has reported to upper management that the reactor systems, data recorders, major experimental equipment, and the radiochemistry laboratory equipment is either unaffected or is Y2K compliant. Firmware and sof tware for the security entry system will be updated and subjected to vendor certification before year-end.
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Conclusions No threat to health or safety was identified as a result of Year 2000 computer issues.
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EXIT MEETING SUMMARY The inspector presented the inspection results to members of licensee management
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at the conclusion of the inspection on July 1,1999. The licensee acknowledged the findings presented, i
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PARTIAL LIST OF PERSONS CONTACTED Licensee J. Bernard, Director of Reactor Operations T. Date, Assistant Reactor Radiation Protection Officer E. Lau, Assistant Operations Superintendent T. Newton, Assistant Operations Superintendent S. Tucker, Quality Assurance Supervisor F. Wormsley, Training Supervisor INSPECTION PROCEDURES USED iP 30703: ENTRANCE AND EXIT INTERVIEWS IP 40745: CLASS I NON POWER REACTOR REVIEW AND AUDIT AND DESIGN CHANGE FUNCTIONS IP 41745 CLASS I NON-POWER REACTOR OPERATOR LICENSES, REQUALIFICATION, AND MEDICAL ACTIVITIES IP 61745 CLASS I NON-POWER REACTOR SURVEILLANCE IP 81421 FIXED SITE PHYSICAL PROTECTION OF SPECIAL NUCLEAR MATERIAL OF MODERATE STRATEGIC SIGNIFICANCE IP 83743: CLASS I NON-POWER REACTORS RADIATION PROTECTION IP 85102: MATERIAL CONTROL AND ACCOUNTING REACTORS ITEMS OPENED, CLOSED, AND DISCUSSED Ooened 50-20/99-201-01 IFl Complete records of safety and 50.59 reviews for replacement cooling tower.
Closed 50 20/97-201-01 IFl Update labeling of small SNM items
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LIST OF ACRONYMS USED ARRPO Assistant Reactor Radiation Protection Officer CFR Code of Federal Regulations IFl inspector Follow up item IP inspection Procedure NRC Nuclear Regulatory Commission SNM Special Nuclear Material TRTR National Organization of Test, Research, and Training Reactors TS Technical Specifications i
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DISTRIBUTION: w/ enclosure E-MAIL
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HARD COPY Docket File 50-20 PUBLIC REXB r/f DMatthews SNewberry LMarsh i
EHylton GTracy, OEDO (016-E15)
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