IR 05000157/1979001
| ML19256E249 | |
| Person / Time | |
|---|---|
| Site: | 05000157 |
| Issue date: | 09/21/1979 |
| From: | Bores R, Donaldson D, Terc N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256E246 | List: |
| References | |
| 50-157-79-01, 50-157-79-1, NUDOCS 7911020019 | |
| Download: ML19256E249 (4) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
Report No.
50-157/79-01 Docket No.
50-157 License No.
R-80 Priority Category G
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,
Licensee:
Cornell University Ithaca, New York 14853
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Facility Name:
Ward Laboratory of Nuclear Engineering Inspection At:
Ithaca, New York Inspection Conducted:
March 28-29, 1979 Inspectors:
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9//2)74 Dapl_,naldson,/RadiationSpecialist
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9hrin NemenM.Terc,RadiationSpeciali[t date date Approved by:
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. J.' BoreV, Acting Chief, Environmental date and Special Projects Section Insoection Summary:
Inspection on March 28-29, 1979 (Report No. 50-157/79-01)
Areas Inspected:
Routine, unannounced inspection of the environmental protec-tion, emergency planning and radiation control programs including:
under environmental protection, airborne effluents, liquid effluents, effluent release data, solid waste, and environmental monitoring; and under radiation control; organization, posting and labeling, personnel monitoring, instrument calibra-tion, and radiation and contamination surveys.
The inspection involved 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> on site by two NRC inspectors.
Results:
Of the areas inspected, no apparent items of noncompliance were identified.
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s REPORT DETAILS 1.
Persons Contacted Principal Licensee Employees
- Mr. H. C. Aderhold, Reactor Supervisor Dr. D. D. Clark, Director, Ward Laboratory Mr. D. Versage, University Health Physicist
- Denotes present at exit interview.
2.
Feneral This inspection consisted of a review of the licensee's Environmental Protection, Emergency Planning, and Radiation Control Programs.
Within these areas the inspection consisted of selective examinations of proce-dures and representative records, interviews with personnel and observa-tions by the inspector.
The inspector, in the company of a licensee representative, conducted a tour of the facility.
Items such as housekeeping, fire protection, and maintenance were observed.
Within the scope of this tour, no problem areas were identified.
3.
Radiation Control a.
Posting, Labeling and Access Control The inspector noted that the posting of notices to workers was con-sistent with the requirements of 10 CFR 19.11.
All entrances to the reactor building were controlled.
' The inspector also noted that restricted areas within the facility exhibited adequate posting, as per 10 CFR 20.
.
b.
Training The inspector held discussions with licensee personnel and reviewed available documentation of training programs and records of personnel training to verify that all personnel working around radiation had been instructed in the health protection problems associated with radiation and the radiation safety procedures to be observed while working at the licensee's facility.
The inspector noted that all personnel who use or are employed at the facility were provided with indoctrination training and an instruction manual addressing the aforementioned areas.
The inspector determined that the training met the requirements of 10 CFR 19.12.
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No items of noncompliance were identified.
c.
Radiation and Contamination Surveys The inspector held discussions with licensee's representatives, and reviewed available records and noted that radiation and contamination surveys were performed every six months.
d.
Personnel Exposures The inspector reviewed personnel exposure records for the period November 1977 thru March 1979.
The maximum quarterly exposure for any individual was 20 mrem to the whole body.
There are nine per-sons permanently badged.
The licensee uses film badges supplied by a vendor, and returns the film for processing every two weeks.
The licensee stated that all film badge exposures were reviewed by the reactor supervisor.
The inspector's review indicated that no expo-sure limits were exceeded.
No items of noncompliance were identified.
e.
Calibration of Health Physics Instrumentation The inspector held discussions with licensee personnel to verify that a program for routine calibration of personnel dosimeters and radiation survey instruments was established.
The inspector noted that GM survey instruments, personnel dosimeters and ion chambers were calibrated at least annually.
The stack exhaust monitor was calibrated annually with a radium source and argon-41.
Review of records indicated that instruments had been calibrated.
The inspector had no further questions in this area.
4.
Environmental Protection The inspector reviewed the licensee's effluent monitoring and environ-mental protection in the following areas:
a.
Airborne Effluents The inspector noted that the reactor building exhaust plenum was being monitored with a thin window GM and RM-14 interconnect.
A strip chart recorder provides a permanent record of discharge levels.
The licensee's operating report covering the period 7/1/77 to 6/30/78 indicated a total gaseous (Ar-41) release of 194 millicuries. Calcula-tions using actual flow rates indicated that the averaged activity con-centrations were within the limits of 10 CFR 20.
The inspector had no further questions in this area.
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b.
Liquid Effluents The inspector noted that the licensee collects liquid radioactive waste in a 2000 gallon waste hold up tank.
The liquid waste is recirculated and sampled prior to discharge to the sanitary sewer system.
The sample was analyzed for radioactivity contents.
The operating report covering the period 7/1/77 to 6/30/78 indicated that a total of 2.4 millicuries of gross beta radioactivity in liquid effluents was discharged during this period. Before each liquid discharge to the sanitary sewer system, a sample was taken and analyzed using gamma spectroscopy.
The inspector reviewed the releases of liquid waste during the period 7/1/77 to 6/30/78 and noted that the yearly average concentration of radioactivity was approximately 29% of the 10 CFR 20 limits, taking into account the dilution factc.' due to a daily average sewer flow of 2 X 106 gallons.
The inspector had no further questions in this area.
c.
Other Methods of Release The inspector checked the facility for unmonitored/ unauthorized dis-charged paths and noted no uses in which discharge paths were not properly monitored or where releases of radioactive materials were unauthorized.
The inspector had no further questions in this area.
d.
Solid Waste Solid waste is being handled by Teledyne Corporation.
Waste is taken to a holding area for pickup and disposal by the vendor. The amount of low level radioactivity solid waste was 7.5 cubic feet for the period 7/1/77 to 6/30/78.
The inspector had no further questions in this area.
5.
Emergency Planning The inspectors noted no regulatory requirements for Emergency Planning and had no further questions.
6.
Exit Interview The inspector met with the licensee representative denoted in paragraph 1 above at the conclusion of the inspection on 3/29/79.
The inspector summarized the scope and findings of the inspection.
The licensee was made aware that no items of noncompliance had been identified in this inspection.
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