ML20249A700
| ML20249A700 | |
| Person / Time | |
|---|---|
| Site: | General Atomics |
| Issue date: | 06/11/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20249A698 | List: |
| References | |
| 50-089-98-202, 50-89-98-202, NUDOCS 9806180119 | |
| Download: ML20249A700 (2) | |
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General Atomics Docket No.: 50-89 TRIGA Reactors Faci %v License No.: R-38 During an NRC inspection conducted on May 4-7,1998, violations of NRC requirements were identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violations are listed below:
A.
Technical Specifhation 9.3.c requires the licensee to have written instructions for emergency and i"1ormal conditions including provisions for evacuation, reentry, recovery, and medical support.
Section 10.3 of the Radiological Contingency Plan (RCP) requires that criticality evacuation drills be conducted semiannually at each facility that uses special nuclear material (SNM) in quantities sufficient to require a criticality warning alarm system.
The TRIGA Reactors Facility has a criticality warning alarm system.
Contrary to the above, on Saturday, July 12,1997, a " drill" was documented as completed to fulfill the requirements specified in RCP Section 10.3 but it did not qualify as a drill because no one was told that it was a drill and no one evacuated.
This is a Severity LevelIV violation (Supplement Vill).
B.
The licensee's Physical Security Plan, entitled " Fixed Site and Transportation Plan for the Protection of Special Nuclear Material of Moderate and Low Strategic Significance," dated April 1997, requires in Part 11, Section 3.2 that key locks and combinations for controlled access areas (CAAs) will be changed anytime a new area is activated or... at least annually. Section 1.3 of Part 11 stipulates that the Mark I reactor CAA encloses all accesses to the reactor's pool, control console, and shop area.
Contrary to the above, the key locks for the Mark i reactor controlled access area were changed in 1995 and 1996 but not changed for 1997.
This is a Severity Level IV violation (Supplement Ill).
C.
10 CFR 55.3 requires that a person must be authorized by a license issued by the Commission to perform the function of an operator or a senior operator as defined in this part.
10 CFR 50.54(i) requires that, except as provided in 10 CFR 55.13, the licensee may not permit the manipulation of the controls of any facility by anyone who is net a licensed operator or senior operator ss provided in 10 CFR Part 55.
ENCLOSURE 1 hh l
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2 10 CFR 50.54(k) requires that an operator or senior operator licensed pursuant to Part 55 of this chapter shall be present at the controls at all times during the operation of the facility.
Contrary to the above, the licensee's TRIGA Mark I research reactor was operated on various occasions in 1996 and 1997 by two individuals whose licenses had i
expired and were not renewed until March 21,1997. Individual A, whose reactor operator license had expired on November 8,1995, operated the reactor on various occasions in 1996 and on January 23,1997. Individual B, whose reactor operator license had expired on November 7,1996, operates the reactor on various occasions in 1997 including February 21 and March 4.
This is a Severity Level IV violation (Supplement 1).
Pursuant to the provisions of 10 CFR 2.201, General Atomics 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 responsible inspector, U.S. Nuclear Regulatory Commission, Region 11, 61 Forsyth St. S. W., Suite 23T85, Atlanta, GA 30303, 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. Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response, if an adequate reply is not received within the time specified in this Notice, an order or Demand for Information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.
Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without a redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure or information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financialinformation). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
Dated at Rockville, Maryland this lith day of June 1998.
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