IR 05000228/1991003
| ML19302E697 | |
| Person / Time | |
|---|---|
| Site: | Aerotest |
| Issue date: | 06/14/1991 |
| From: | Qualls P, Reese J NRC Office of Inspection & Enforcement (IE Region V) |
| To: | |
| Shared Package | |
| ML19302E698 | List: |
| References | |
| 50-228-91-03, NUDOCS 9106260209 | |
| Download: ML19302E697 (6) | |
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U. S. NUCLEAR REGULATORY COMMISSION REGION Y Report No. 50-228/91-03 Docket No. 50-228 License No. R-98 Licensee: Aerotest Operations, Inc.
3455 Fostoria Way San Ramon, Califonia 94583 Facility Name: Aerotest Radiography and Research Reactor (ARRR)
Inspection at:
San Ramon, California Inspection Conduc ed: April 30 - May 22, 1991
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Approved by:
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h QuF,lReese,' Chi ~ef~ /y Preparedness and Date Signed Safe #dards,Emerger.s Nonpower Reactor Branch Sumary:
Inspection on April 30 - May 22. 1991 (Recort No. 50-228/91-03)
Arf.as insoected: Routine announced inspection of ARRR operations, including organization, review and audit, experiments, reactor operator requalification training, environmental monitoring program, procedures, radiation protection activities, transportation activities ' emergency preparedness program and drills, a tour of the facilities and dis ussions of relevant Information Notices and Generic Letters.
Inspectiot.,:rocedures 30703, 40750, 86740, and 92701 were addresses.
Results:
In the areas inspected, the licensee's programs were fully capable of meeting their safety objectives. No violations or deviations were identified.
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DETAILS 1.
Persons Contatigd
- H. G. Simens, President, Aerotest Operations (RO)
- R. Tsukimura, Radiation Safety Officer (RS0)
- S. Warren, Quality Assurance Manager (*) Denotes those individuals present at the exit interview.
In addition to the individuals identified above the inspector met and held discussions with other members of the licensee's staff.
2.
Class 11 Research and Test Reactor Ooerations (40750)
The licensee's reactor operations program was reviewed for compliance with the requirements of 10 CFR Parts 19, 20, 50, 55; including the Technical Specifications (TSs) and licensee procedures. The inspection included a review of reactor operating records, tours of the licensee's facility, and the review of selected procedures.
Reactor operatiens were determined to be consistent with the information provided in the licensee's 1989 and 1990 annual reports.
The facility continues to provide support for neutron radiography and sample irradiations.
A.
Reactor Operations A raview of licensee records and discussions with staff members established that only one new experiment had been performed.
This experiment involved the use of the 6 inch exposure port to test electronic components in a fast neutron flux.
Reactor operations have otherwise been limited to neutron radiography and sample irradiations.
Between July 1, 1989, and June 30, 1990, the reactor achieved
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724,953 kilowatt-hours of operation. The reactor was critical about 2900 hours0.0336 days <br />0.806 hours <br />0.00479 weeks <br />0.0011 months <br /> during this period.
Several spurious scrams occurred due to aging electronic components (vacuum tubes) which are being replaced as they fail. The licensec noted that eventually, when replacement vacuum tubes become unavailable, they will have to consider the rather expensive upgrade to solid state circuitry. The earthquake scram system actuated twice during the report period.
The first occurred with the reactor shutdown on October 17, 1989.
On April 6,1990, the system activated for a second time, due to a
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local earthquake which resulted in a reactor trip. All licensee reactor operations were logged and documented in accordance with licensee procedures.
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B.
Oroanization The licensee's organir.ation is as specified in TS Section 12.
The inspector observed t'.iat no changes in the organizational structure have occurred since the inspection documented in report number 89-01.
C.
Doerations and Maintenance Records A review of reactor operating logs (such as start-up and shutdown check lists and maintenance records) for the period of July 1990 through April 1991 was conducted.
The reactor operating logs, check lists, and maintenance logs were adequately filled out and were consistent with facility operating procedures and TS requirements.
The inspector concluded that reactor operations met the conditions prescribed in the TSs.
Preventative maintenance activities had been factored into the facility operating procedures.
The inspectors concluded that the licensee was implementing an effective maintenance program.
D.
Procedures The inspection disclosed that the licensee maintains reactor operating procedures in effect es described in the TSs.
The inspector reviewed the licensee's operating procedures. The inspectors noted that the procedures are routinely reviewed and whenever changes occur that may require revisions.
E.
Chances Discussions with the Reactor Supervisor and the review of reactor operating records for the period of July 1990 to the time of this inspection disclosed that no changes had been made to the facility or procedures that would require a safety evaluation pursuant to 10 CFR Part 50.59.
F.
Experiments The inspector reviewed new experiments completed since the last inspection. One new experiment involving use of the 6 inch exposure port for fast neutron exposure of electronic components was evaluated and conducted. The experiment was properly evaluated and reviewed by the Reactor Safeguards committee. No discrepancies were identified.
G.
Surveillances Records for the surveillances prescribed in the TSs were examined.
All surveillances reviewed by the inspector were performed at the frequencies specified in the TS. The inspector reviewed completed check off sheets for the period: July 1990 through December 1990.
No deficiencies were identified.
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Review and Audit Reactor Safeguards Comittee minutes for the period of December 1989 until the inspection period were reviewed.
The review and discussions disclosed that members of the comittee
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were conducting routine audits of the facilities activities. The
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audits were broad in scope and were designed to assure that the activities were performed in accordance with the 1Ss. None of the audit findings appeared to represent a significant safety finding.
Audit findings were effectively corrected in a timely manner. The
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inspector concluded that the licensee's review and audit program met and/or exceeded the requirements prescribed in Section 12 of the J
TSs.
I.
Reactor Operator Recualification Proaram
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The licensee's implement. tion of the NRC-approved Reactor Oper. tor's
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Requalification Program, dateo.'.pril 12, 1974, was examined.
Annual written examinations that were administered since the previous inspection were reviewed. No problems were noted.
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Records for each Reactor Operator (RO) and Senior Reactor Operator (SRO) are maintained by the Reactor Supervisor. These records are reviewed by members of the Reactor Safeguards Comittee for compliance with the licensee's approved SRO/R0 requalification program. The inspector concluded that the records that were reviewed in this subject area demonstrated that the SR0/R0 requalification program was consistent with 10 CFR Part 55 and the
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licensee's approved program of April 12, 1974.
The licensea's performance in this area appeared to be fully capable of meeting its safety objectives.
J.
Radiation Protection Proaram
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The licensee's radiation protection program for assuring compliance with 10 CFR Parts 19 and 20 and the ISs was examined.
Records involving personnel co imetry, contamination surveys,
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radiation measurements and measurement of airborne concentrations
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obtained at the reactor facility since the previous inspection were reviewed.
In addition, the inspectors held discussions with the
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licensee's radiation protection staff.
The inspector noted that posting and labeling practices were consistent with 10 CFR Part 19.11 and 20.203 and radiation
measurements were consistent with the requirements of 10 CFR Part 20.201.
Licensee records continue to indicate that radiation levels
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at the reactor facility are well monitored and that contamination levels and airborne concentrations are essentially undetectable.
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Personnel exposures of the reactor staff continue to indicate that reactor operations are perfor.ned in accordance with ALARA practices.
The inspector conducted a survey of the reactor room and outside areas and found no discrepancies with licensee surveys.
A review of records maintained by the licensee disclosed that no radioactive liquids were discharged from the facility during the period of December 1989 until May of 1991.
The annual releases of Argon - 41 for the last annual reporting period were determined by licensee calculations that are based on reactor power operations. Argon - 41 releases for the period were below the 10 CFR 20 release limits.
Portable radiation measurement instruments and pocket ionization chambers used by the reactor facility were observed to be in current calibration.
The licensee's radiation protection program was determined to be capable of protecting the health and safety of the reactor staff and the public.
K.
Emeroency Preparedness Procram The licensee's capability for responding to emergencies as specified in their NRC approved Emergency Plan (EP) and for demonstrating compliance with 10 CFR Part 50.54 was examined.
Based on the review of records and the discussions, the inspector noted that the licensee appeared to have an adequate EP program and drills appeared to have been properly performed. The inspector also noted that emergency response equipment was being properly maintained. No additional concerns were identified in this area.
L.
Facility Tour The inspector toured the licensee's facility.
Posting and labeling were found to be consistent with 10 CFR Part 19.11 and 20.203 requirements.
All fixed and portable radiation monitoring instruments were in current calibration and the reactor facility cleanliness was adequate.
M.
Annual Report The licensee's annual reports covering the period of July 1,1988 through June 30, 1989 and July 1,1989 through June 30, 1990 were reviewed.
The reports were submitted in accordance with TS No.
6.7(e) and summarized plant operations, changes, tests, experiments, surveillances, and maintenance activities. The report also includes a summary of radiation levels, radioactive effluent releases, and the results obtained from the licensee's environmental monitoring au vr t1 a. %,%,,
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program. The information was found to be consistent with the inspectors' observations discussed in this report. No errors or anomalies were identified.
3.
Iransoortation of Radioactive Materials (86740)
The licensee's program for assuring compliance with Department of Transportation regulations (49 CFR Parts 171 through 178) and requirements of 10 CFR Parts 20.205, 20.311, 61 and 71 associated with the packaging and shipment of radioactive materials was reviewed.
Discussions with the licensee's staff and the review of records disclosed that transfer and/or shi> ment of radioactive materials from the reactor facility are made throug1 the licensee's State of California radioactive material license. No concerns were identified in this area.
The licensee seemed to be maintaining their previous level of performance in this area and their program appeared capable of accomplishing its safety objectives.
No violations or deviations were identified.
4.
{xit Interview The inspector met with the individuals denoted in paragraph I at the conclusion of the inspection on May 2, 1991.
The scope and findings of the inspection were summarized.
The licensee was informed that no violations or deviations were identified. The inspector concluded that the facility was being operated in a safe and conservative manner.
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. as IM WDEMAlloa DOCKET NO. 50-228 Aerotest Operations, Inc.
3455 Fostoria Way San Ramon, California 94583 Attention:
Mr. Hugo G. Simens, President Gentlemen:
SUBJECT: NRC INSPECTIONS OF AER0 TEST OPERATIONS, INC.
This letter refers to the subject routine, announced inspections of your activities authorized under NRC License Number R-98.
These inspections werr; conducted by L. Norderhaug and P Qualls of this office on April 30 throusn May 21, 1991. This letter also refers to the discussion of the prelim 4;iary inspection findings with you and your staff on May 2, 1991.
Furthc;, this letter refers to subsequent in-office review of documentation provided during the inspection visit regarding items of inspection interest and to a conversation between you and P. Qualls on May 22, 1991.
Areas examined during this inspection visit are described in the enclosed inspection reports (Enclosure A -- physical protection, and material control and accounting and Enclosure B -- reactor operations). Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations by the inspector.
Within the scope of these inspections, no violations or deviations were identified.
In accordance with Section 2.790(d) of the NRC's ' Rules of Practice,' Part 2, Title 10, Code of Federal Regulations, documentation of the findings of your programs and procedures for safeguarding special nuclear material are exempt from public disclosure; therefore, Enclosure A will D21 be placed in the NRC Public Document Room.
However, in accordance with 10 CFr. 2.790(a), a copy of this letter and Enclosure B will be placed in tb., NRC Public Document Room.
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WILMAL IMh54illiii m wt *llii *Winst UE WF0 Wall 0N Should you have any questions concerning this letter, we would be pleased to discuss them with you.
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eese, Chief dafeguards, Emergency Preparedness and Nonpower Reactor Branch Enclosures:
A.
Inspection Report No.
50-228/91-01 & 50-228/91-02 B.
Inspection Report No.
50-228/91-03 Mit RiAt l ena'.'... a
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