IR 05000184/1997201
| ML20149E771 | |
| Person / Time | |
|---|---|
| Site: | National Bureau of Standards Reactor |
| Issue date: | 07/11/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20149E769 | List: |
| References | |
| 50-184-97-201, NUDOCS 9707210060 | |
| Download: ML20149E771 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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J Docket No:
50-184 i
License No:
TR-5 l
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l Report No:
97201
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Licensee:
U. S. Department of Commerce
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Facility:
National Bureau of Standards Reactor e
Location:.
National Institute of Standards and Technology
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Gaithersburg, Maryland 20899 i
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Dates:
June 16-18,1997 i
inspector:
Thomas F. Dragoun, Project Scientist d
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i Approved by; Marvin M. Mendonca, Acting Director
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Non-Power Reactors and Decommissioning a
Project Directorate j
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EXECUTIVE SUMMARY
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j National Institute of Standards and Technology
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l NRC Inspection Report No. 50-184/97201 The facility is fully staffed with additional reactor operator trainees on board in anticipation of retirements. Requalification training of operators was acceptably focused. Updated safety
system electrical drawings were in final draft. Reviews of proposed neutron beam experiments were thorough. Significant facility improvements were noted.
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9707210060 970711
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PDR ADOCK 05000184 G
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t Report Details
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$_ummary of Plant Status The reactor was operated continuously at 20 Megawatts.
l 01 Conduct of Operations
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l 01.1 Orcanization and Ooerations and Maintenance Activities a.
Inspection Scope (Inspection Procedure 39745)
The inspector reviewed:
' e organization and staffing, e maintenance tabulated in the annual report, e control room logs, records, and instruction books, and, e facilityimprovements.
b.
. Observations and Findinas Two additional reactor trainees were hired since the last inspection raising the number of"overhires" to four. The Chief Nuclear Engineer stated that active involvement and transfer of program responsibility to the younger staff was done in anticipation of retirements. This was confirmed during selected staff interviews. In addition, an electrical engineer has been added to the Technical Support group.
The tabulation of major maintenance in operations report no. 49 demonstrated vigorous attention to the condition of plant equipment.
Licensee administrative rule A.R. 4.0 required various logs, records, and instruction books be maintained in the control room. These were determined to be acceptably maintained with the specified information and readily available for use by the operator on duty and shift supervisor.
The inspector observed a demonstration of a replacement spent fuel transfer system control panel. Designed and constructed in house, the unit uses digital technology and a programmable logic controller while using the original system sensors and wiring. Advantages included increased system status information for the operator, flexibility, and ease of maintenance. An engineering change notice (ECN) to install the system awaited validation and verification of the hardware and software configuration.
The inspector observed a design meeting for an automatic rabbit manipulator. This device will flip and re-insert the rabbit, or direct it to a storage or experiment location.
Radiation exposure savings to experimenters were anticipated through reduced handling. An inspection of assembled but un-installed units indicated that the equipment was acceptably engineered and constructed.
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A tour of the warm lab area indicated major housekeeping and contamination control improvements.
A full scale mockup of part of the refueling head and two manipulator arms with a dummy fuel element has been constructed on the operating floor and extending
through two floors below. The licensee stated that operators can practice fuel element transfers with the same look and feel as actual conditions. The lower portion of the mockup was enclosed in a safety cage since it extended into the beam experiment area.
c.
Conclusions Management plans to maintain stable staffing levels were acceptable. Record-keeping satisfied requirements. Facility improvements were notable,
Operator Training and Qualification
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a.
Inspection Scope (Inspection Procedure 41745)
The inspector reviewed:
e active license status,
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i e records of reactivity manipulations, e medical examinations, and
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e selection oflecture topics,
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Observations and Findinas
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License status, medical evaluation, operating test, reactivity manipulations, and written exams were acceptable for licensed operators reviewed. Annual written exams covered required subject areas and were technically challenging.
Lectures topics were determined by the CNE and the training coordinator based on analysis of exam results, observed performance, significant events in-house and at other research reactors, including DOE facilities. Refresher training on fundamental topics such as nuclear theory and procedure changes were included. Re rds of subject matter and attendance were maintained and easily retrievable.
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Conclusions
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The requalification program satisfied the requirements in 10 CFR Part 55. Lecture topics were timely and focused on significant safety issues.
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Quality Assurance in Operations O7.1 Desian Chance Functions and Experiments l
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Inspection Scope (Inspection Procedures 40745 and 69745)
The inspecter reviewed l
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e review and approval of beam experiments b.
Observations and Findinas l
in response to increased NRC emphasis on the conduct of 50.59 reviews, the CNE
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had proposed a pilot program for reviews of ECNs. The basic element of the program was appointment of a Safety Analysis Report coordinator who willidentify SAP-iderations for changes requiring SEC approval. The program will be fin,
'ter formal guidance is received from NRC. Inspector follow-up item t.
23-02 is closed.
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'pector reviewed final draft drawings of the nuclear instrumentation safety cha.s..els. These were needed to update the safety analysis report and were of acceptable quality. Inspector follow-up item 50-184/96-03-01 is closed.
Experiments using the thermal and cold neutron ports are exempt from the requirements of TS 4.0. However, SEC approvalis required for new beam experiments. Records indicated that beam experiments were processed in a comprehensive manner similar to ECNs under direction of the Beam Experiment Coordinator. The reviews included a 50.59 licensing basis review and safety lessons leamed at other facilities.
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Conclusions Reviews of facility changes and new experiments were thorough and well documented.
P1 Conduct of EP Activities a.
Scope (Inspection Procedure 82745)
The inspector reviewed:
e facilities, equipment, and supplies, and o exercises.
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Observations and Findinas The emergency wind speed and direction strip chart recorder was on lina but the rolled paper was removed and replaced by a computer data logger. The licensee stated that this change provides more data and eliminates the need to maintain a non-repairable strip chart recorder. A 50.59 review of this change was acceptable.
The emergency SCBA respirators were replaced with new " emergency escape breathing units". The new units consisted of a light weight oxygen generator attached to a fabric bubble hood and are NIOSH approved. The devices do not require fit testing, maintenance, or heavy tanks on a backpack. Emergency supply inventory lists were acceptably revised.
The biennial exercise was due this year and was in the planning stages. Since medical treatment is the only off site support needed, an event involving injuries was planned.
During this inspection, a new public address system was placed in operation to improve routine and emergency communications.'
Building evacuation drills were effectively conducted with observers stationed to verify audibility of the evacuation alarms, check of work spaces, and use of assembly areas. A problem with foreign experimenters using the main building exit rather than the nearest available exit was resolved through training and counseling.
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Conclusions The emergency preparedness program was acceptably implemented.
X1 Exit interview (Inspection Procedure 30703)
The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on June 18,1997. The licensee acknowledged the findings presented.
PARTIAL LIST OF PERSONS CONTACTED Licensee D. Brady, Electrical Engineer T. Myers, Senior Reactor Operator T. Raby, Chief Nuclear Engineer J. Rowe, Chief, Reactor Radiation Division i
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3l lNSPECTION PROCEDURES USED
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IP 30703: ENTRANCE AND EXIT INTERVIEWS
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j IP 39745 CLASS l NON-POWER REACTORS ORGANIZATION AND OPERATIONS
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IP 40745 CLASS I NON-POWER REACTOR REVIEW AND AUDIT AND DESIGN
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CHANGE FUNCTIONS
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IP 41745 CLASS I NON-POWER REACTOR OPERATOR LICENSES, j
REQUALIFICATION, AND MEDICAL ACTIVITIES i
IP 69745 CLASS I NON-POWER REACTOR EXPERIMENTS IP 82745 CLASS I NON-POWER REACTOR EMERGENCY PREPAREDNESS
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3-ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
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50-184/96-03-01 IFl Update engineering drawings within slx months
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50-184/96-03-02 IFl Modify change approval records to delineate 10 CFR
l 50.59 considerations t
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LIST OF ACRONYMS USED
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l CFR Code of Federal Regulations CNE Chief Nuclear Engineer.
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ECN Engineering change notice j
IFl Inspector Followup item i
IP inspection procedure
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NIOSH National Institute of Occupational Safety & Health j
'NRC Nuclear Regulatory Commission l
SAR Safety Analysis Report j<
SEC.
Safety Evaluation Committee SCBA Self contained breathing apparatus i
TS Technical Specifications i
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