ML19263A748
| ML19263A748 | |
| Person / Time | |
|---|---|
| Site: | University of Virginia |
| Issue date: | 12/14/1978 |
| From: | Williamson T VIRGINIA, UNIV. OF, CHARLOTTESVILLE, VA |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19263A743 | List: |
| References | |
| NUDOCS 7901020259 | |
| Download: ML19263A748 (3) | |
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I UNIVERSITY OF VIRGINIA SCHOOL OF ENGINEERING AND APPLIED SCIENCE L-- -
O C H AR LOTT ESVILLE. 33808 DEP A ft TM ENT OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS T ELEPHON E:
804 884 793 REACTOit FACILITY December 14, 1978 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, GA 30303 Re:
License R-66 Docket 50-62 Gentlemen:
This letter provides our response to possibic items of noncompliance with NRC requirements and possibic deviations from generally accepted industry practices which were identified in your letter RII: SCE 50-62/78-2 dated November 28, 1978.
Our response to each item is as follows:
Appendix A, Item A - Calibration of the Reactor Room Constant Air Monitor Prior to the NRC inspection. calibration of the Reactor room constant air monitor used vendor data to relate the airborne radioactivity to the monitors response. This was considered adequate by the reactor staff since the pro-cedure supplied by the manufacturer was for the specific model of monitor used.
Based on the NRC inspectors comments the calibration procedure for the air monitor has been revised to include a quantitative response test of the monitor using a reference radioactive source.
The reactor room constant air monitor was calibrated using this procedure on December 8,1978.
In addition a procedure for relating the monitor response to the airborne activity, using the revised alibration procedure has been developed. This procedure is in reasonable agreement with the vendor supplied procedure and shows that the air monitor has an adequate response. This procedure will be submitted for approval by the Reactor Safety Committee at its next meeting, which is presently planned for sometime in January 1979.
Based on this information, we consider that we were effectively in com-pliance with the cited requirements on December 8,1978 We will be formally in compliance once the Reactor Safety Committee approves the calibration pro-cedure which should occur in early 1979.
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Mr. James P. O'Reilly December 14, 1978 Appendix A, Item B - Retention of Records of Surveys for Radioactive hbterial s.
The records of weekly surveys for radioactive materials were not avail-able for ten survey periods between January through July 1978.
An additional search of the Health Physicist's files and other locations was made to find the missing records, however, they were not located.
It is noted that all surveys for which records are availabic and the NRC inspectors surveys showed that no radioactive contamination existed.
The Reactor Health Physicist has been directed to maintain records of surveys as required by 10 CFR 20.201 (b). A review of the records of radiation surveys will be a recommended item for the Reactor Safety Commit-tee when they perform their cemiannual audits to ensure that adequate records are maintained.
We are currently in compliance with 10 CFR 20.201 (b) with the execption of the ten missing records which cannot be found.
Appendix B, Item B - Air Flow Velocity in Laboratory Hoods.
It was noted that the air flow in four laboratory fume hoods was less than 100 feet per minute as specified in National Bureau of Ctandards Hand-book 92.
Shintenance personnel from the Department of Buildings and Grounds have serviced the laboratory fume hoods. hkasurements made on December 5, 1978, using two different types of velometers, showed flow rates greater than 100 fpm in all four laboratory fume hoods with the hoods positioned in their normal use configurations. The Reactor Health Physicist has been directed to measure the flow rates in the laboratory fume hoods on a quarterly basis and to maintain records of the measurements.
Additional Comment Section 11.e of the inspectors report indicates that the reactor room duct argon-41 monitor will be calibrated in the test duct with a known argon-41 concentration every six months.
This is not consistent with our present calibration procedures.
The present procedure includes a quantitative response test using a reference solid radioactive source instead of argon-41. A correlation between the response of the argon-41 monitor to the reference source to its response to a known concentration of argon-41 was determined during the hhrch 1978
hfr. James P. O'Reilly December 14, 1978 calibration in the test duct.
Thus the present procedure provides a valid method for ensuring that the argon-41.
itor performs its intended function.
Sin :erely, I b kDi l10d Sc T. G. Williamson, Director Reactor Facility TGW/1t cc: lbssrs. Steve Ramos Operating Reactor Branch #4 Division of Reactor Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 J. P. Farrar, U.Va.
A. B. Reynolds, U.Va.
II. W. Berk, U.Va.
B. L. Shriver, U.Va.
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