IR 05000193/1986003
| ML20209B237 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 08/21/1986 |
| From: | Cioffi J, Shanbaky M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20209B214 | List: |
| References | |
| 50-193-86-03, 50-193-86-3, NUDOCS 8609080195 | |
| Download: ML20209B237 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No. 86-03 Docket No. 50-193 License No. 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: July 24, 198,6, Inspectors
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O 8-l9-86 s6an A. Ciorfig ti4n Specialist, FRPS date Approved by: _
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M. M. Shanbaky, C'11ef, F (111 ties date f
Radiation Protection Section
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Inspection Summar :
Inspection conducted on July 24, 1986 (Inspection Report No. 50-193/86-0 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, and effluent monitoring.
Results:
No violations were identified in this review.
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ADOCK 05000193 PDR
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DETAILS 1.
Personnel Contacted
'M. Doyle, Director of Operatiens
- N. Jacobs, Radiation Protection Officer
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D. Johnson, Staff Health Physicist 2.
Purpose The purpose of this routine, unannounced inspection was to review selected elements of the Rhode Island Atomic Energy Commission Research Reactor Radiation Protection program.
The following elements of the Radiation Protection Program were reviewed:
- status of previously identified items;
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- training and qualification of personnel;
- implementation of the Radiation Protection Program;
- external exposure controls; and
- effluent monitoring.
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Status of Previously Identified Items
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3.1 (Closed) 85-02-01 (Inspector Follow-up). Amend Technical Specifications to redefine " restricted area" to comply with definitions in 10 CFR 20.
The licensee decided to place additional signs on the boundary sur-rounding the Nuclear Science Center to prevent unauthorized entry.
The licensee also locks the only access door into the Nuclear Science Center to prevent unauthorized entry of personnel. This item is closed.
3.2 (Closed) 85-02-02 (Inspector Follow-up).
Calibrate high range of area radiation monitors on a specified frequency.
For ALARA considerations, the licensee plans to only response check the high range of the area radiation monitors with a 4 curie Cesium-137 source. This item is closed.
3.3 (Closed) 85-02-03(Violation).
Failure to maintain documentation for verification of clean up system high efficiency particulate filter testing.
The licensee responded to this violation in a letter dated September 6, 1985.
The letter stated that the original documentation had been lost. However, the licensee did perforu efficiency testing in 1971 and again in 1985. This documentation will be permanently retained.
This item is close r
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3.4 (Closed) 85-02-04 (Unresolved).
In place filter testing of the reactor building clean up system.
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The inspector verified that an in place leak test of the emergency back-up air handling system was performed on August 13, 1985. The test indicated that the DOP penetration did not exceed 0.01%. This item is closed.
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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".
The licensee's performance relative to the above criteria was determined by:
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- review of the "Rhode Island Nuclear Science Center Radiation Safety Guide";
- review of training records of five radiation workers; and
- discussions with licensee personnel.
Within the scope of,this review, no violations were_ identified. _The
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licensee maintained complete record > for all.usersaaf the research
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reactor facility. Additfinally, the Radiation Safety Guide provided
comprehensive instruction, procedurcs, and precautions to workers for compliance with regulatory requirements.
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Impleme1tation of the Radiation Protection Program The licensee's program for controlling radioactive materials and contamination, providing surve'111ance 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;
- Technical Specification G.3, "Other Radiation fionitoring Equipment",
and G.4, "High Radiation Area".
The' licensee's performance relative to the above criteria was determined by:
- observations of housekeeping, and postings, sigr.s, and labels during a facility tour on July 24, 1986;
- review of records of survey instrument calibration, survey records, and access controls;-
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- review of the following procedures:
" Survey Meter Calibration Procedures - Dose Rate Mode"
" Survey Meter Calibration Procedures - Integrating Mode"
- review of the maintenance log and reactor floor air monitor data; and
- discussions with-licensee personnel.
Within the scope of this review, no violations were identified. The licensee stated that vigorous controls were exercised for access to the entire Nuclear Science Center through the use of keys controlled by the senior reactor operators or health physics staff. All records of surveys, logs, and calibrations were complete, thor: ugh and timely.
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External Exposure Control The licensee's external exposure control program was reviewed against criteria provided in:
- 10 CFR 20.101, 20.102, 20.104, 20.202, and 20.401.
The licensee's performance relative to tha above criteria was determined by:
- review of dosimetry records for five radiation workers; and
- discussions with licensee personnel.
Within' the scope of this review, no violations were identified. The licensee used Landauer film badges for dosimetry of record.
Daily dose tracking was performed with self-reading dosimeters.
In general, the licensee was conducting external exposure monitoring in accordance with regulatory requirements.
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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
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- Technical Specifications G.1, G.2, and J.g.
The licensee's performance relative to the above criteria was determined by:
- review of the fo.llowing procedures:
" Preventive Maintenance Program for Air Handling Systems;"
" Emergency Exhaust Systems Efficiency Test for Iodine Removal"
- review of calibrations of the stack monitors, and area radiation monitors; review of the air flow systems log books;
- review of gaseous releases and liquid releases for 1984 to 1985; and
- discussions with licensee personnel.
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Within the scope of the review, no violations were identified. The licensee was implementing an effluent monitoring program in accordance with their technical specifications and regulatory requirement.
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Exit Interview The inspector met with the licensee's representative (denoted in Paragraph 1) at the conclusion of the inspection on July 24, 1986. The inspector summarized the purpose and scope of the inspection and findings as described in this report.
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