ML20059H607
| ML20059H607 | |
| Person / Time | |
|---|---|
| Site: | Idaho State University |
| Issue date: | 11/04/1993 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20059H608 | List: |
| References | |
| 50-284-93-01, 50-284-93-1, EA-93-232, NUDOCS 9311100142 | |
| Download: ML20059H607 (4) | |
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i APPENDIX A NOTICE OF VIOLATION Idaho State University Docket: 50-284 Idaho State University Reactor Facility License:
R-110 EA 93-232 During an NRC inspection conducted August 2-6, 1993, violations of NRC requirements were identified.
In accordance with the " General Statement af Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, '
the violations are listed below:
A.
10 CFR 55.59(c) requires that a facility licensee have a reactor R
operator requalification program, reviewed and approved by the Commission.
Technical Specification 6.3, requires that all licensed reactor operators participate in requalification training as set forth in 10 CFR Part 55.
1.
Section 4.a of the licensee's NRC-approved reactor operator requalification program requires that an annual written examination covering the entire area of reactor operations for the AGN-201 reactor be administered to all operators and senior reactor operators by the Reactor Safety Committee.
Contrary to the above, the licensee's Reactor Safety Committee did not administer an annual written examination to a senior operator and two operators in 1992. This is a repeat violation.
2.
Section 4.b of the licensee's NRC-approved reactor operator requalification program requires that a member or members of the Reactor Safety Committee observe the operation of the reactor by each licensed operator or senior operator at least once during each calendar year.
Contrary to the above, members of the licensee's Reactor Safety Committee did not observe the operation of the reactor by two senior operators and two operators during 1992.
This is a Severity Level IV violation (Supplement I) (284/9301-01).
B.
10 CFR 55.21 requires that an applicant for a license have a medical examination by a physician every 2 years to determine if the applicant or licensee meets the requirements of 10 CFR 55.33(a)(1).
Contrary to the above, one senior operator did not have a medical examination by a physician between April 24, 1990, and January 21, 1993.
This is a Severity level IV violation (Supplement I) (284/9301-02).
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. C.
10 CFR 30.51 requires that licensees keep records showing the receipt, transfer, and disposal of byproduct material.
Contrary to the above, receipt records for all byproduct material transferred from the reactor licensee were not kept.
Examples were byproduct material transferred on March 3, 1992, May 21, 1992, and June 4, 1992.
This is a Severity Level V violation (Supplement I) (284/9301-04).
D.
10 CFR 30.41 requires that licensees only transfer byproduct material to specified individuals, such as those with a specific license from the NRC.
Contrary to the above, on March 3, May 21, and June 4,1992, byproduct material was transferred from the reactor licensee to individuals in the physics department and the school of pharmacy who were not authorized to receive such byproduct material.
This is a Severity Level IV violation (Supplement I) (284/9301-05).
E.
10 CFR 20.201(b) requires that each licensee shall make or cause to be made such surveys as are reasonable under the circumstances to evaluate the extent of radiation hazards that may be present.
10 CFR 20.401(b) requires that each licensee maintain records showing the results of surveys performed in accordance with 10 CFR 20.201(b).
Contrary to the above, records were not maintained for surveys that evaluated the extent of radiation hazards present of activated samples removed from the reactor on March 3, May 21, and June 4, 1992.
This is a Severity Level V violation (Supplement IV) (284/9301-06).
F.
10 CFR Part 50.54(q) requires that a licensee authorized to possess and/or operate a research reactor shall follow and maintain in effect emergency plans.
Section 6 of the NRC-approved Emergency Plan, Revision 4, dated May 2, 1989, states that the training of university personnel who are responsible to act under the emergency plan is the responsibility of the Radiation Safety Officer.
It further states that the Radiation Safety Officer will provide a training program at least once a year to train other university personnel who may be called upon to assist in the event of a nuclear incident. The reactor administrator is identified in the Emergency Plan as a person with responsibilities to act in an emergency.
Contrary to the above, training was not provided by the radiation safety officer to the reactor administrator.
This is a Severity Level IV violation (Supplement VIII) (284/9301-08).
. G.
Technical Specification 6.4 requires that audits of facility activities be performed under the cognizance of the Reactor Safety Committee.
1.
Technical Specification 6.4.3.a requires that the licer.see audit the conformance of facility operations to the Technical Specifications and applicable license conditions, at least once every 12 months.
Contrary to the above, an audit of this area was not performed between May 1990 and January 1993.
This is a repeat violation.
2.
Technical Specification 6.4.3.b requires that the licensee audit the performance, training, and qualifications of the entire facility staff, at least once per 24 months.
Contrary to the above, an audit of this area was not performed between May 1990 and December 1992.
3.
Technical Specification 6.4.3.c requires that the licensee audit the results of all actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nucle w safety at least once per calendar year.
Contrary to the above, an audit on this area was not performed during 1991 and 1992.
4.
Technical Specification 6.4.3.e requires that the licensee audit the Facility Security Plan and implementing procedures at least once per 24 months.
Contrary to the above, an audit of this area was not performed between May 1990 and February 1993.
This is a Severity Level IV violation (Supplement I) (284/9301-09).
Pursuant to the provisions of 10 CFR 2.201, Idaho State University is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region IV, 611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a " Reply to a Notice of Violation" and should include for each violation:
(1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
If an adequate reply is not received within the time specified in this Notice, an order or a Demand for Information may be issued to show cause why the license should not be modified, suspended, or revoked, or why such other I
I action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.
Dated at Arlington, Texas this 4th day of November 1993
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