CR76003 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 September 10, 1976 J. P. O'Reilly, Director, Region I N. C. Moseley, Director, Region II J. G. Keppler, Director, Region III E. M. Howard, Director, Region IV R. H. Engelken, Director, Region V IE CIRCULAR 76-03 - RADIATION EXPOSURES IN REACTOR CAVITIES The subject document is transmitted for issuance by close of business September 13, 1976. The Circular should be issued to all holders of Reactor OL's for action and to applicants for, or holders of Reactor CP's for information. Also enclosed are draft copies of transmittal letters. Dudley Thompson, Acting Director Division of Field Operations Office of Inspection and Enforcement Enclosure: Circular 76-03 Transmitted via Wylbur 9/10/76 11:40 a.m. . (Transmittal letter for Circular 76-03 to each holder of a NRC Operating License.) Addressee: The enclosed Circular 76-03 is forwarded to you for action. The same document is being transmitted to each applicant for, or holder of a Construction Permit for information. Therefore, if you have a nuclear power plant in the construction stage, you will also receive a copy of Circular 76-03 which will not require a separate response. Signature (Regional Director) Enclosure: IE Circular 76-03 . (Transmittal letter for Circular 76-03 to each applicant for, or holder of a Construction Permit.) Addressee: The enclosed Circular, 76-03, is forwarded to you for information. No response is required. If you are also the holder of a NRC Operating License, you will also receive a copy of Circular 76-03 which will require a response. Signature (Regional Director) Enclosure: IE Circular 76-03 . NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C. 20555 IE Circular No. 76 - 03 DATE: September 13, 1976 RADIATION EXPOSURES IN REACTOR CAVITIES DESCRIPTION OF CIRCUMSTANCES: On March 18, 1976, an employee at the Zion station received a "whole body" radiation dose of 8 rems or more upon entering the cavity beneath the reactor vessel during a refueling outage. On April 5, 1976, a similar reactor cavity entry at Indian Point resulted in a 10-rem whole body dose to a licensee employee. A similar entry on October 5, 1972 caused a 5-rem dose to a Point Beach employee. These three overexposures appear to have been caused by failure to appropriately control entry into high radiation areas, failure to conduct adequate surveys and failure to compensate for exposure rate variations that can occur in various areas in power reactors, e.g., the cavity beneath the reactor vessel. With the incore thimbles and detectors inserted into the core, radiation levels in the cavity appear to be low. With the thimbles or detectors withdrawn into the cavity, however, exposure rates of hundreds or possibly thousands of roentgens per hour can exist. Overexposures can occur in seconds. All three overexposure events involved entry into potentially high radiation areas without surveys and/or special controls over equipment which could cause transients in the exposure rate. . IE Circular No. 76 - 03 Date: September 13, 1976 ACTION TO BE TAKEN BY LICENSEES: While the three exposures above occurred at pressurized water reactors, similar situations could develop at other types of reactors, e.g., pneumatic irradiation equipment areas (research reactors) and traveling incore probe equipment areas (boiling water reactors). Accordingly, holders of power, test and research reactor operating licenses are to complete the following: 1. Perform a thorough review of plant areas and operations to identify high radiation areas, both continuous and transient, as defined in 10 CFR 20.202(b). 2. Verify that entryways into high radiation areas are conspicuously posted and locked or otherwise controlled in such a manner as to explicitly identify the nature of the hazard, appropriately control entry, and require adequate pre-entry surveys, 3. Ensure that radiation protection procedures and radiation protection training and retraining programs specifically address the matter of control of and access to such areas and initiate appropriate retraining of all plant personnel, 4. Ensure that the procedures governing personnel entry into all actual or potential high radiation areas permit such entry only after appropriate management review and approval so that conditions within the area are known and not subject to change while the area is occupied, 5. Periodically audit whatever controls result from item 1-4, above, to ensure their continued effectiveness, and 6. Confirm by written reply within 60 days that the actions for items 1-4 above, have been or are being taken. A record, detailing findings, actions taken, and actions to be taken, should be retained for review by NRC during the next radiological safety inspection. This request for information was approved by GAO under a blanket clearance number B-180225 (R0072); this clearance expires July 31, 1977.
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