IR 05000193/1988002

Insp Rept 50-193/88-02 on 880622-23.No Violations Noted. Major Areas Inspected:Radiation Protection Program Including Status of Previously Identified Items,Training & Qualification & Implementation of Radiation Program

ML20151L036
Person / Time
Site:	Rhode Island Atomic Energy Commission
Issue date:	07/21/1988
From:	Thomas W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20151L010	List: IR 05000193/1988002 ML20151L004
References
50-193-88-02, 50-193-88-2, NUDOCS 8808030338
Download: ML20151L036 (5)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No. 88-02 Docket N License N R-95 Licensee: Rhode Island Atomic Energy Commission South Ferry Road Narragansett, Rhode Island 02882 Facility Name: Rhode Island and Providence Plantation AEC Inspection At: Narragansett, Rhode Island Inspection Conducted: June _22721 1988

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Inspectors: # M , , ,w-n e#b 9' 9/h[

Walt 6r~ V."Thomas, Radiation Specialist,- / dats FRSSB, DRSS Approved by: M M. M. Shanbaky, Chief,4acilities

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date Radiation Protection Section, FRSSB, DRSS Inspection Summary: Inspection conducted on June 22-23, 1988 (Inspection Report No. 50-193/88-02)

Areas Inspected: Routine, unannounced inspection of the radiation protection program including: status of previously identified items; training and qualifications, implementation of the radiation protection program, external exposure controls, effluent monitoring, and emergency plannin Results: No violations were identified in this review.

l 8808030338 880721 PDR ADOCK 05000193 O PDC

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Details Personnel Contacted

• A. Dimeglio, Directar of Operations

• Jacob, Radiation Safety Officer D. Johnson, Staff Health Physicist

• Attended the exit meeting on June 23, 1988. Purpose The purpose of this routine, unannounced inspection was to review selected elements of the Rhede Island Atomic Energy Commission (RIAEC) Research Reactor Radiation Protection program. The following elements of the Radia-tion Protection Program were reviewed:

- status of previously identified items;

- training and qualification of personnel;

- implementation of the Radiation Protection Program;

- external exposure controls;

- effluent monitoring; and

- emergency planning Status of Previously Identified Items 3.1 (Closed) 88-01-01 (UNR) TS G.3c states "A radiation monitor shall be provided to monitor all persons leaving the reactor room for Beta-Gamma contamination."

A Beta-Gamma monitor with two probes (one on each side of the hallway)

is provided. Additionally, a portable Beta-Gamma survey meter is provided in the hallway if required for hand and foot surveys. Daily smears are taken at 13 points on the reactor facility floor at the end of each daily reactor run, also weekly smears at 65 points are taken. Any contamination found is immediately remove Activities which have produced contamination in the past or have a high potential for producing contamination are closely monitored. Personnel involved in these activities are instructed to use the hand and foot survey meter when exiting the reactor room. This item is close . Training and Qualification of Personnel The licensee's program for training and qualifying personnel for access and use of the research reactor facility was reviewed with respect to criteria contained in:

- 10 CFR 19.12, "Instructions to Workers."

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The licensee's performance relative to the above criteria was determined by:

- review of the Rhode Island Nuclear Science Center (NSC) Radiation _ Safety '

Guide";

- review of training records of all radiation workers; and

- discussions with licensee personne Within the scope of this review, no violations were identifie The licensee maintained complete records for all users of the research reactor facility. Additionally, the Radiation Safety Guide provides comprehensive instruction, procedures, and precautions to workers for compliance with regulatory requirement The present Radiation Safety Guide, dated June 1984, is in the process of revision by the Radiation Safety Office This revision will be completed and implemented for facility use by the end of the calendar year, and will be reviewed during a subsequent inspection, (88-02-01). Implementation of the Radiation Protection Program The licensee's program for controlling radioactive materials and contamination providing surveillance and monitoring, and establishing and maintaining administrative radiological work controls was reviewed relative to criteria in:

- 10 CFR 19.11, 19.12, 20.201, 20.203 and 20.401; I

- Technical Specification G.3, "Other Radiation Monitoring Equipment",

and G.4, "High Radiation Area".

The licensee's performance relative to the above criteria was determined by:

- observations of housekeeping, postings, signs, and labels during a facility tour on June 22, 1988;

- review of records of survey instrument calibration, survey records, and access controls; Within the scope of this review, no violations were identifie The licensee indicated that vigorous controls are exercised for access to the Nuclear Science Center throug5 the use of keys controlled by the senior reactor operators or health physics staf All records of surveys, logs, and calibrations were complete, thorough and timel . External Exposure Control The licensee's external exposure control program was reviewed against criteria provided in:

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- 10 CFR 20.101, 10.202, 20.203 and 20.40 The licensee's performance relative to the above criteria was determined by:

- review of dosimetry records for all radiation workers for 1986, 1987 and 1988 to dat discussions with licensee personne Within the. scope of this review, no violations were identifie The licensee uses Landauer film badge service for dosimetry of record. Daily dose tracking is performed with self-reading dosimeters. In general, the licensee was conducting external exposure monitoring in accordance with regulatory requirement . Effluent Monitoring The licensee's program for monitoring liquid and gaseous effluents from the Nuclear Science Center was reviewed against criteria contained in:

- 10 CFR 20.106, "Radioactivity in effluents to unrestricted areas"; and

- Technical Specifications G.1, G.2, and The licensee's performance relative to the above criteria was determined by:

- review of calibrations of area radiation monitors; '

- review of gaseous and liquid releases for 1986, 1987 and 1988 to date;

- discussions with licensee personne ,

Within the scope of the above review, no violations were identifie . Emergency Planning The licensee has prepared and implemented an Emergency Plan which provides l the basis for actions to cope with an emergency at the Nuclear Science Center (NSC). The NSC contains a 2 MW swimming pool research reactor which is utilized for neutron activation analysis and neutron spectroscopy experiments. The reactor is housed in a nine inch thick concrete buildin Adjacent and connected to the reactor building are the offices and labora-tories. A basement area extending beyond the reactor building contains reactor equipment, laboratories, the heating plant, offices and general work area The emergency organization is shown in figure 3-1 of the Emergency Plan dated April, 1987. It consists of three major components: NSC staff, local governmental agencies, and other offsite organizations. The offsite agencies will provide services such as fire fighting, security, medical transport, medical treatment and weather forecasting. Letters of agree-ment have been negotiated with each offsite agency. Copies of current letters of agreement and offsite agency response procedures are contained in the Emergency Pla :

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As a result of review of the NSC emergency planning activities, it was verified that the scope of-the licensee's planning is complete and adequate for the facility and in accordance with regulatory requirement Discussions were held with the NSC Health physicist and reviews were conducted of previous annual emergency exercises and drills. The drills

'and exercises included medical, radiaticn emergency, and communication drills. As a result of review of the drills and the evaluations of the drills conducted by NSC it was concluded that these events could be handled with existing procedures, equipment, and personnel in a manner appropriate to protect the public health and safet . Exit Interview 'x The inspector met with the licensee's representatives (denoted in Paragraph 1) at the conclusion of the inspection on June 23, 1988. The inspector summarized the purpose and scope of the inspection and findings as described in this report.

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