IR 05000184/1990001
| ML20006E876 | |
| Person / Time | |
|---|---|
| Site: | National Bureau of Standards Reactor |
| Issue date: | 02/12/1990 |
| From: | Craig Gordon, Lazarus W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20006E870 | List: |
| References | |
| 50-184-90-01, 50-184-90-1, NUDOCS 9002260471 | |
| Download: ML20006E876 (5) | |
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U.S. NUCLEAR REGULATORY-COMMISSION
REGION I
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Report No.
50-184/90-01 Docket No.
50-184 License No'.-
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Licensee:
U. S. Department of Commerce
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National Institute of Standards and Technology
'Gaithersburg, Maryland-20899 Facility Name:
NBS Reactor (NBSR)
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' Inspection Conducted:
January 9-10, 1990
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Inspector:
iMA To
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c. I. Gordon, Emergency Preparedness date SpecialtTt Section,FkSSB,gencyPreparedness Emer DRSS Approved by:
- /6M4 W. dv1.aza Chief, Emergency date
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Preparedn Section, FRSSB, DRSS Inspection Summary: Inspection on January 9-10,-1990 (Report No. 50-184/90-01)
Areas Inspected:
Routine, announced emergency preparedness' inspection-
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conducted by one NRC Region I based inspector of previous 1 : identified items,.
L changes to the emergency preparedness program, emergency cilities and
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equipment, notifications and communications, and training, drills and exercises.
Results:- No violations were identified. The Emergency Plan and Procedures were found to be-implemented in a manner to adequately protect public health and safety.
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DETAILS
- 1. 0, Persons Contacted L.-Lindstrom,f,ReactorRadiationDivision(RRD)
Senior Operator
T. Rabykelford Chie
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J. King, Captain,'a )tain,- Security T. Shac C
rire Department J. Torrence, Deputy Chief, RRD
- Denotes attendance at the exit meeting.
2.0-- Licensee Action on Previously Identified Items During the inspection-the inspector reviewed the licensee's response to items-identified during a previous inspection (Inspection, Report No, m
.50-184/87-03).
CLOSED (50-184/87-03-01 No benefit to graded notification procedure.
which allowed up to fr,ur): hours following serious emergencies for NRC notification.
- Although the procadure still provides for graded NRC notification which
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-is dependent upon elassification, a review of response procedures and-commitment from the Chief, Reactor Radiation Division indicated that NRC notification would be made as soon as practicable.
-during emergencies uncle)ar. ype of self-reading dosimeters to be used CLOSED (50-184/87-03-02 : T In addition to 0-200 mR dosimeters which are assigned t'o individuals workinginthereactorbuildingftypesofemergencies.-(0-5 Rand 0-20R):
~ high range dosimeters-are now designated for differen CLOSED (50-184/87-03-03): Alert and Site Area Emergency-classifications
. using stack monitor RD 4-1 precluded without operation of exhaust dilution fan.
The licensee added alarm trigger points to RD 4-1 for each level of'
emergency classification allowing classification of events either with or
without dilution fan operation.
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' CLOSED (50-184/87-03-04): No direct signal into security station to I
indicate location of NBSR building fires.
Signal alarms and fire notifications made to the security desk are now divided into four general areas which provide firefighters advance notice of where fires are locate w
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3 CLOSED (50-184/87-03-05):
Integrated exercise never conducted which h
included all support groups identified'in. Emergency Plan.
i In December 1987 and September 1989 the licensee conducted emergency L.
exercises which tested most major elements of the Emergency Plan and
. included participation by offsite support groups.
Review of exercise results indicated that the Plan was successfully implemented and that all objectives were met.
CLOSED (50-184/87-03-06):
Exercise critique results not always-reflected in changes to emergency procedures.
The inspector reviewed an internal memo of December 1983 which documented
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exercise critique items to be factored into various program areas.
Inspection of commitments made in the critique revealed that some items L
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were implemented and that others were adequately addressed.
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3.
Operitional Status of the Emergency Preparedress Program 3.1 Changes to the-Emergency Preparedness Program There have been no major changes to the Emergency Plan or
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Implementing Procedures since the last inspection. Changes such as
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p upgrading of fire evacuation alarms and insta11atioil of the supplementary stack monitor JR received engineering and~ safety committee review and a)prova1'M4-2) to implementa prior The L
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change was made in the location of the primary assembly area and j
appropriate personnel were notified:of the change.
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Based upon the above, this area is acceptable.
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3.2 Facilities and Equipment L
lD The inspector toured the Control Room, LEmergency Support Center (ESC?
security building and fire station and noted only minor
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fact Ity changes since tbe last inspection.
Facility enhancements the addition of fire alarms in the ESC and were identified by dditional telephonesiin the ESC. The inspector
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security desk and a noted that a major change to the reactor buildin is currently in
'i progress. The new Cold Neutron Research Facilit located adjacent
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to the reactor is expected to begin operation wi hin two years. The
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Chief, RRD indicated that emergency plans for the facility were d
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considered by licensee staff and would be in place prior to operation. During the next inspection this area should be followed L
up to ensure that plans for the new facility are adequate.
i Designated emergency equipment, field kits, and instrumentation were
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calibrated and operable. Inventories of supplies and equipment were current.
Except as noted above, this area is acceptable.
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,3.3L Notifications and Communications After an emergency-is classified, the' reactor Supervisor notifies operating staff, health physics, NIST management, and other site support groups who may be needed to assist in the response.
Notifications are made via commercial tele > hones and portable'
radios. An extra telephone was added to-tie ESC to help improve initial notification, particularly to NRC. Off-hour emergency'
notifications'are directed to the NIST security desk.-- The inspector, touredthesecuritybuilding.andfiredepartmentbuildingIcation-inspected changes made at the security desk to fire alarm and notif
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panels, and held discussions with security and fire response staff.
- Notification and communications capability are adequate and no concerns were-identified.
Based upon the above review, this area is acceptable.
3.4 Training and Drills The Senior Operator who is familiar with the Emergovicy Instructions-Manual (implementing procedures) provides training for the Emergency Response Organization (ERO) via classroom and practical instruction.
All reactor operators are members of the ERO and receive emergency =
response training. Review of training fil.es indicated that information on previously identified NRC concerns and findings identified during drill critiques.are covered in classroom ler.tures.
Operators have attended recent emergency preparedness courses and
- have also participated in drills and exercises.
The licensee' conducted exercises and building ev6cuation drills as required by the NBSR emergency plan, The drills were well documented and reviewed by the Chief, RRD.: Problem areas were also identified and factored into-training sessions. The 1987'and 1989
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exercises were adequate in scope and tested major portions of the plan including-coordination with support groups.. A concern was identified with accountability of personnel inside-the reactor building.and the licensee stated that changes to procedures were being made. Since the last inspection a drill involving a contaminated /in ured victim was also he,ld, but did not include participation b Bethesda Naval Hospital which is designated by the plan as the fac lity to provide medical assistance.
RRD staff stated that future drills which included the hospital would be considered.
Except as noted above, this area is acceptable.
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4.0 Exit Meeting-
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The inspector met with the licensee representatives listed in Section 1 of this report at the conclusion of the inspection and summarized the observations made during the inspection.
The licensee was informed that previously identified findings were adequately addressed and no violations were found.
Licensee management acknowledged the findings and agreed to evaluate'them as appropriate,
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