IR 05000228/1997201
| ML20149E783 | |
| Person / Time | |
|---|---|
| Site: | Aerotest |
| Issue date: | 07/11/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20149E761 | List: |
| References | |
| 50-228-97-201, NUDOCS 9707210065 | |
| Download: ML20149E783 (11) | |
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U. S. NVCLEAR REGULATORY COMMISSION 0FFICE OF NVCLEAR REACTOR REGULATION
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Docket No:-
50-228 License No:.
R-98
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Report No:
50-228/97-201
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Licensee:
Aerotest Operations Facility:
Aerotest Radiography and Research Reactor (ARRR)
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Locat' ion:
San Ramon, California Dates:
June 3-4, 1997
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Inspector:
Marvin M. Mendonca, Senior Project Manager
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Seymour H. Weiss, Acting Deputy Director Division of Reactor Program Management
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9707210065 970711 PDR ADOCK 05000228 G-PDR
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EXECUTIVE SUMMARY
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This routine, announced inspection consisted of the review of selected conditions and records since the last inspection, and related discussions with licensee personnel.
This inspection was conducted in accordance with the guidance of NRC Inspection Manual. Activities were safely implemented as described in the report details and summarized in the following.
Operational logs and records were acceptably maintained.
Events were e
acceptably identified and resolved by the licensee. Operations were in accordance with Technical Specifications.
Surveillances were completed as required.
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Procedures were acceptably used.
Requalification training and activities were focused on safety and were
as required by the Requalification Plan.
New personnel met training requirements. On-shift staffing and conduct
of operations met or exceeded the requirements.
Review and audit functions and resolution of associated findings were
acceptable.
The experimental review, approval and implementation program met e
regulatory requirements.
The fuel was handled as required during fuel inspection.
Conservative
action was taken to not use potentially damaged fuel elements.
Maintenance activities were in accordance with approved procedures.
e No design change was made since the last inspection.
e The radiation protection personnel and reactor staff have an effective
working relationship, and radioactive material controls are acceptable, The emergency plan was acceptably implemented. Acceptable training was e
provided to licensee personnel.
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Security and Safeguards implementation was in accordance with regulatory e
requirements, Two open items (50-228/9601-01 and 50-228/9601-02) were closed.
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Report Details
Summary of Facility Status During the onsite inspection period, the facility was being started up and operated several hours a day at 180 kw to allow for the conduct of various
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radiographic work.
Maximum authorized power level is 250 kw and the licensee operates at the reduced power level to reduce personnel exposures.
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Operations
Conduct of Operations 01.1 Operational Loos and Records
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a.
Inspection Scope (Inspection Procedure 69001)
The inspector reviewed operational logs and record, selected events and research reactor operational parameters.
b.
Observations and Findinas Operational logs and records since the last inspection were prepared and maintained as required.
Logs were clear and provided an acceptable description of operational activities.
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Events were first recorded in the console logbook.
The essential event information and corrective actions was documented to Operational Request Forms. The inspector verified corrective actions for nuclear instrument
meter and detector repairs on August 1, 1996, April 14, 1997, and May 12, 1997, respectively.
This process tracked completion of the corrective actions, The inspector also verified, that selected operational parameters were t
in accordance with Technical Specification Limiting Conditions of Operation, by observation of instrumentation and facility conditions
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during startup and operations.
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Conclusions
Operational logs and records were acceptably maintained.
Events were acceptably identified and resolved by the licensee. Operations were in accordance with Technical Specification Limiting Condition of Operation requirements.
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02 Operations 1 Status of Facilities'and Equipment 02.1 Surveillance and Limitina Conditions of Operation
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a.
Insoection Scone (Inspection Procedure 69001)
The inspector reviewed surveillance procedures, surveillance data, and
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Limiting Conditions of Operation.
b.
Observations and Findinas The inspector reviewed the settings of selected safety systems and the conduct of safety system surveillances during the research reactor pre-critical startup procedure. The procedure was of acceptable detail, and was current and acceptably performed.
The inspector also verified i
surveillance records and or conditions for items such as water level temperature and flow alarms, control rod and nuclear instrument. checks and calibrations, and control room ventilation monthly emergency
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security alam surveillance, c.
Conclusions
Surveillances required by Technical Specifications were completed as
required.
Operations Procedures and Documentation
i 03.1 Procedures
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a.
Inspection Scope (Inspection Procedure 69001)
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The inspector reviewed administrative controls, operating procedures and updates, and the performance of procedures.
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b.
Observations and Findinas
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The inspec*or observed that the conduct of startup and low ~ power l
operations,.as well as the setup for an experiment, was in accordance with current, approved procedures. No changes to procedures had been
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made since the last inspection.
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Conclusions Procedures were effectively used by the operator.
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Operator Training and Qualification i
05.1 Reaualification Trainina a.
Jpsoection Scope (Insoection Procedure 69001)
The inspector reviewed active license status, training records, examinations, and corrective actions.
b.
Observations and Findinas
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Associated records were maintained as required. ' Records and discussions with operators showed that training was conducted on selected conditions and events as required by the requalification plan.
Records also showed that active duty. status and requalification plan requirements were i
maintained, j
The licensee developed the exams for the current cycle.
The inspector reviewed these exams and determined that they demonstrated acceptable content and questions.
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Conclusions Requalification training and activities were focused on maintaining the research reactor safety and were in accordance with the requirements.
Operations Organization and Administration-06.1 Graanization and Staffino a.
Inspection Scope (Inspection Procedure 69001)
i The inspector reviewed the organization and staffing, and research
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reactor operations, logs and procedures.
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b.
Observations and Findinas Records for new employees were reviewed.
These records and discussions with selected employees showed that new employees were trained in radiation protection, emergency preparedness, and security.
-The number of licensed operators remained relatively unchanged. A senior reactor operator was in the control ro *. The inspector verified through-review of selected logs and procedures that a senior reactor operator directed. activities as required by the regulations. The staff size and supervisory oversight were acceptable to support the research reactor utilization schedule. These observations verified that the requirements of Technical Specifications were being satisfied by the licensee.
Also records showed that regular training was being performed for all employees. There were no organizational changes.
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Conclusions
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Employees were acceptably trained to fulfill the requirements of the position. On-shift staffing and conduct of operations met or exceeded the requirements and ensured acceptable safe staffing levels.
Quality Assurance in Operations 07.1 Committees. Audits, and Reviews a.
Insoection Scope (Inspection Procedure 69001)
The inspector reviewed committee membership, management and meeting minutes, and the results of audits and reviews.
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Observations and Findinas The minutes showed that activities were as required for frequency, quorums, and minutes. These_ minutes showed that the committee was communicating issues to management.
The' inspectors review of records and discussions found an effective, independent committee that evaluates and verifies safe implementation of research reactor activities in accordance with the requirements of Technical Specifications. The inspector found the audits raised issues
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consistent with the charter of the committee.
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c.
Conclusions
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Committee review and audit functions were as required by the Technical Specifications.
Miscellaneous Operations Issues 08.1 Exoeriments a.
Inspection Scope (Insoection Procedure 69001)
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The inspector reviewed experiment review and authorization records.
b.
Observations and Findinas
The neutron radiography authorization form (#114-7013) was reviewed and approved by.the licensee.
The review provided an acceptable safety analysis of the experiment.
The review also addressed potential hazards, reactivity and radiation levels, and experiment operational
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Implementation of some _ experimental. protection features (radiation field posting and control requirements) were observed by the inspector.
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Conclusions The experimental review, approval and implementation program met regulatory requirements.
08.2 Fuel Handlina Loas and Record a.
Scope (Inspection Procedure 69001)
The it.spector reviewed fuel handling procedures and records.
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Observations and Findinas Fuel elements in the pool were moved and examined in-the December 1996, time frame.
Records indicate that this activity and controls were established as required by administrative procedure.
Control of potentially damaged fuel elements was also verified in that the licensee has not used such elements.
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Conclusions
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The fuel was acceptably handled in accordance with procedural requirements, and conservative action was taken to not use potentially damaged fuel.
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II. Maintenance l
M1 Conduct of Maintenance M1.1 Maintenance Loas and Records j
a.
Inspection Scope (Inspection Procedure 69001)
The inspector reviewed maintenance review and approval records, maintenance procedures, and maintenance authorizations.
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b.
Observations and Findinas The replacement parts for the repaired channels 2, 3, and 4 previously discussed under operational logs and records was an equivalent and did not involve any unreviewed safety questions. The maintenance was acceptably documented, tracked and tested. Within the scope of this review, no safety concerns were identified.
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Conclusions Research reactor maintenance activities were docunanted and performed in accordance with approved procedures.
III.
Enaineerina El Conduct of Engineering El.1 Desian Chanaes a.
Insoection Scone (Insoection Procedure 69001)
The inspector reviewed facility records and configuration, b.
Obsorvations and Findinos No design changes were conducted since the last inspection.
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Conclusions I
The facility is relatively stable and design changes have not been (
necessary.
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IV. Plant Support
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R1 Radioloaical Protection and Chemistry Control Rl.1 Health Physics a.
Scone (Insoection Procedure 69001)
I The inspector reviewed coordination between the health physics and research reactor facility staff, and equipment condition.
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b.
Observations and Findinas I
The inspector discussed training and ALARA issues with the Radiation
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Safety Officer and the reactor staff.
Since the last inspection,
radiation surveys of the facility have been initiated to try to further l
define and potentially reduce doses. The licensee is continuing to work on this ALARA related topic.
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Conclusions
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The radiation protection personnel and reactor staff have an effective working relationship, and the licensee is working to improve practices
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consistent with ALARA principles.
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R8 Miscellaneous Radiation Protection and contro? Issues R8.1 Transportation (Inspection Procedures 86740)
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Scope The inspector reviewed facility records for transportation of radioactive waste.
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Observations of Findings Records show no transfer of radioactive material, and inventory of materials were reviewed to verify this situation, c.-
Conclusion There has been no transportation of radioactive waste.
'R8.2 (Closed) Violation 50-228/9601-02:
Failure to control high radiation area.
The inspector verified the physical changes were performed to control the high radiation area. Corrective actions were acceptable.
P1 Conduct of Emergency Preparedness Activities
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Pl.1 Emergency Planning a.
Scoce (Inspection Procedure 69001) ~
The inspector reviewed the emergency plan, changes to implementing procedures, facilities, equipment and supplies, exercises and drills, and training.
b.
Observations and Findinas The Emergency Plan and. implementing procedures were kept up-to-date and copies were readily available in response locations.
Facilities, equipment and supplies were maintained in working order. The inspector verified that emergency call lists were _ accurate and available in the required places.
Exercises, drills, and training were in accordance with Emergency Plan requirements and provided an acceptable challenge to the participants.
Licensee key emergency response personnel demonstrated that they could respond to emergency situations as required.
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Conclusions The: emergency plat, was acceptably implemented and acceptable training was provided to licensee personnel.
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.g-S1 Conduct of Security and Safeguards Activities Sl.1 Security and Safeguards a.
Scope Insoection Procedures 81401. 81402. 81431. 81810. and 85102 The inspector reviewed the physical security and safeguards programs, b.
Observations and Findinas The physical security plan was maintained as required.
Record reviews and discussions with personnel showed no reportable events per 10 CFR 73.71 or Appendix G to Part 73. The physical protection of the facility was in accordance with the security plan (e.g., alarms and key control).
Security system surveillance and monitoring were as required.
Information was kept as required. Material accountability forms were verified to be completed and filed acceptably.
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Conclusion The implementation of the security and safeguards program was i
acceptable.
S.8 Miscellaneous Security and Safeauards Issues S.8.1 (Closed) Violation 50-228/9601-02:
Failure to maintain security gate closed.
The inspector verified changes to the administrative controls and physical changes to ensure control of the gate.
Corrective actions were acceptable.
V.
Manaaement Meetinas X1 Exit Meeting Summary The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on June 4, 1997.
The licensee acknowledged the findings presente __ __ ______-_____-__
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PARTIAL LIST OF PERSONS CONTACTED
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Licensee R. R. Tsukimura, President, Aorotest Operations, Inc. (Aerotest)
A. W. Meren, Manager Neutron Radiograpy, Aerotest S. L. Warren, Radiological Safety Officer, Aerotest I. C. Molina, Neutron Radiographer, Aerotest B. L. Anderson, Assistant Manager Neutron Radiography, Aerotest C. A. Schmidt, Office Manager, Aerotest INSPECTION PROCEDURE (IP) USED IP 69001:
CLASS II NON-POWER REACTORS ITEMS OPENED, CLOSED,' AND DISCUSSED Opened None Closed l
50-228/9601-01 VIO High Rad Area Control 50-228/9601-0E VIO Security Gate Left & Open
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