ML19269F444

Responds to NRC 791024 Ltr Re Violations Noted in IE Insp Rept 50-062/79-02.Corrective Actions:Door to Possible High Radiation Area Locked.Pocket Dosimeters Response & Leak Tested

ML19269F444
Person / Time
Site:	University of Virginia
Issue date:	11/16/1979
From:	Shriver B VIRGINIA, UNIV. OF, CHARLOTTESVILLE, VA
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19269F441	List: ML19269F444
References
NUDOCS 7912210038
Download: ML19269F444 (2)

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s N / UNIVERSITY OF VIRGINIA '

s g SCHOOL OF ENGINEERING AND APPLIED SCIENCE G j C H A R LOTT ESVILLE. 22901 V /' . m DEP ARTM ENT OF NUCLEAR EN GI N E E91 N G AND ENGINEERING PHY$1CS '), TELEPHONE: 80(-924-7136 REACTOR FACILITY '*

h November 16, 1979 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission-Region II 101 Marietta Street, NW. Suite 3100 Atlanta, GA 30303 Re: NRC 1ctter RII:SCE 50-62/79 02

Dear Mr. O'Reilly:

This letter responds to the item of noncompliance and deviation identified in the reference letter as required by 10 CFR 2.201.

The item of noncompliance concerned a po' .ible high radiation area for which personnel access was not controlled when the reactor was not operating. This occurred because the alarm system which was installed to meet the requirements of 10 CFR 20.203 (c) was deactivated when the reactor was secured.

On September 20, 1979 the door to the subject area was locked to limit access to this area. The keys for this door are kept in the safe used for other keys associated with the reactor and security system. The keys are not removed without the cognizance of the Reactor Supervisor or his dcsignee.

This method of access control meets the requirements of 10 CFR 20.203 (c) (2), so full compliance was achieved on September 20, 1979.

In addition, a training session covering the special controls re-quired for radiation areas and high radiation areas was conducted by the Radiation Safety Officer to ensure that the Health Physicist understands the requirements of 10 CFR 20. Additional administrative reviews of the survey reports will also be conducted to ensure that all radiation areas and high radiation areas within the Facility are identified.

The deviation discussed in the reference letter concerned the calibration of pocket dosimeters. It was noted that the pocket dosimeters had not been response or leak tested within the previous six months as specified by Regulatory Guide 8.4.

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2167 104 79 2210 031ccrv

Letter to James P. O'Reilly, Director November 16, 1979 Page 2 The response anu Icak tests were completed on September 26, 1979.

We have also established additional administrative controls to ensure that the dosimeter calibrations are performed in accordance with Regulatory Guide 8.4. The controls include ti.e establishnunt of a status list which will list the due date and completio.: date for the calibration or survey items performed by the Health Physicist. The status of items on this list will be reviewed by the Radiation Safety Officer and tl*

Facility Director.

Sincerely, a

B.(L'. Shriver, Director Reactor Facility BLS:ph cc: Mr. J. T. Sutherland, Chief Fuel Facility and hhterials Safety Branch NRC - Region II Mr. Steve Ramos Division of Reactor Licensing NRC - Washington, D. C.

Reactor Safety Committee Dr.11. W. Berk 4 jng Dr. T. G. Williamson U iUJ Mr. J. P. Farrar F