IR 05000128/1982002
| ML20027E604 | |
| Person / Time | |
|---|---|
| Site: | 05000128 |
| Issue date: | 10/18/1982 |
| From: | Constable G, Crossman W, Cummins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20027E592 | List: |
| References | |
| 50-128-82-02, 50-128-82-2, NUDOCS 8211150530 | |
| Download: ML20027E604 (10) | |
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s APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report: 50-128/82-02 License:
R-83 Docket: 50-128 Catagory:
F Licensee:
Texas A & M University (TAMU)
College Station, Texas Facility Name:
Inspection At:
College Station, Texas Inspection Conducted: June 21-25, 1982 Inspectors-
/ O// 8/62 6. L. constable, denior Hesident inspector Uate Wmn
/O/f8/82-d. t. Cummins, Heactor inspector Uate
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W. A. Crossman, Chlet Uate ReactorProjectSectionB
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Approved:
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w. A. Crossman, chlet Date ReactorProjectSectionB Inspection Summary Inspection Conducted June 21-25, 1982 (Report 50-128/82-02)
Areas Inspected:
Routine unannounced inspection of the licensee's facility operation, organization,keactorSafetyBoard(RSB) audits, logs, experiments, training, fuel handling, maintenance calibration of test equipment, ing, and radiation monitoring radioactive waste, emergency plann procedures, The inspection involved 60 inspection-hours by three NRC site tour.
inspectors.
Results:
Within the 13 areas inspected, no violations or deviations were identified.
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' DETAILS l.
Persons Contacted
- C. A. Erdman, Professor and Head, Nuclear Engineering
- D. E. Feltz, Acting Director, Nuclear Science Center
'*D. Rogers, NSC Manager of Reactor Operations
- R. ' D. Neff,~ Radiological Safety Officer
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- H. J. Deigl, Senior Health Physicist, Nuclear Science Center
- Present at exit interview.
In addition to the above personnel, the NRC inspectors held discussions with various operations and technical support members of the licensee's staff.
2.
Scope of Inspection The purpose of this inspection was to review the operating history of the reactor for the period March 1980 through June 1982, and to review implementation of radiation control programs.
3.
Organization Several changes have occurred in the facility organization since the last NRC inspection.
The facility now reports administratively to the director of the Texas Engineering Experiment Station which is a part of the Texas A & M University system and is identified for legislative appropriation purposes as a separate state agency. On June 1,1982, John Randall stepped down as director of the Nuclear Science Center. Donald Feltz has assumed duties as acting. director.
Dale Rogers has recently become the manager of reactor operations.
In addition,. several reactor supervisors, operators, and other staff members have resigned. The NRC inspectors reviewed the organizational changes and determined that although the turnover rate was high, the facility appears to be adequately staffed.
No violations or deviations were noted.
4.
Review and Audit Texas A & M conducts combined RSB meetings for both the AGN-20lM and the Nuclear Service Center pool-type research reactors. The NRC inspectors reviewed RSB minutes and audits listed below.
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April 30, 1980
June 3, 1980
October 24, 1980
January 23, 1981
January 28, 1982
March 5, 1982 The NRC inspectors observed weakness in the RSB function that borders on a violation. This weakness is discussed below.
It was noted that corrective action had begun prior to'this inspection.
The NRC inspectors noted that a full year elapsed between RSB meetings 90 and 91.
While this in itself is not a violation, it appears to have resulted in RSB decisions and responsibilities being carried out at a lower level'.
In reviewing Nuclear Science Center operations memoranda, it appears that the facility staff is making safety evaluations and approving procedures that should rightfully be the responsibility of the RSB.
In addition, it appears that the RSB does not review the operations memoranda to ensure that safety decisions are appropriate and are made at the proper level.
It should be noted that the NRC inspector concluded that the operations staff meetings and resulting operations memoranda appear to be an effective way to review some issues and that no specific decision is being questioned.
Rather, it appears that the RSB needs to conduct a thorough audit to assure itself that it is not relinquish'ing-its responsibilities as defined by the Technical Specifications.
The NRC inspectors were informed that a procedure change now requires the RSB to meet Semiannually, with length of time between meetings not
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to exceed 8 months.
This matter is considered unresolved (8202-01) and will be reviewed
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during a subsequent inspection.
Audits
Requalification Program Aprilol4, 1980
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Health Physics July 9,1980..
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Records October 23,1980 Requalification Program January 9,'1981 QA/QC SNM Shipping Packages April 30,1981 Recorders July 23, 1981
' Effluent Release November 3, 1981 Requalification Program November 3, 1981 Maintenance Records February 12, 1982 Operations May 14, 1982
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The audits were recorded on a single page (Form 114) that generally described the audit results, including comments.
It was difficult to
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determine what was actually audited or how the audit was conducted;,
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however, no significant problems were identified.
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No violations or deviations were identified.
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5.
Reactor Operations
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The NRC inspector observed a reactor startup, including the prestartup checkoff.
The startup was performed in accordance with Standard Operating Procedure (50P) II-C.
The NRC inspector noted that the prestartup checklist does not test:
the scram initiated when the door to the neutron radiography area is opened. Testing of a similar scram for the irradiation cell door was a part of the checklist.
The addition of a scram test for the radiography area door was discussed with the reactor operator and the senior reactor operator on duty during the observed reactor startup.
No violations or deviations were noted.
6.
Logs and Records
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The NRC inspectors reviewed the licensee's logs and records to determine that they were being maintained in accordance with Technical Specifications.
The following were audited:
Reactor Operations Log for June 1981 through June 1982 Instrumentation Log for October 1980 through June 1982 Master Maintenance Schedule Reactor Instrumentation Log Red Tag Log to Number 149 SCRAM Log, January 23, 1980, through June 21, 1982 Staff Meeting Minutes 265 dated March 17,1980, through 303 dated l
May 19, 1982 Operations Memorandum Log 129 dated May 10, 1980, through 153 dated June 10, 1982 Supervisors Log for January 1980 through June 21, 1982 Modification Authorization 24 P
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The NRC inspector noted that several reactor scrams had been caused by operator error and by moving experirgents.
The licensee was cautioned
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that such errors can reflect' a casual attitude toward safety and therefore should be minimized.
' No' violations ~or deviations.were identified.
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Experiments ~
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The NRC inspector reviewed the request for irradiation (514 log) for January 1982'through June 1982. Approximately 546 experiments were-J conducted during the first half of 1982. The NRC inspector reviewed the following safety evaluations for new experiments:
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Installation and Operation of a Multiple, Rotisserie Irradiation Device
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Installation and Operation of an N 6 Gamma Source Generator -
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,;During the course of the inspection, the NRC inspector observed the
. handling of several experiments and discussed various experiments
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with operations and health physics personnel.
No violations or deviations were noted.
8.
Operator Requalification Training The NRC. inspector reviewed the reactor operator and senior reactor operator requalification training program, Revision III, June 1979, and requalification records to determine compliance with this program.
No violations or deviations were identified.
9.
Fuel Handling Activities The Texas A & M pool reactor has the ability to conduct pulsing operations; however, there has been no pulsing since 1976 when fuel damage was discovered. The completed study of the damaged FLIP (TRIGA) fuel has been reviewed by NRC and it is expected that pulsing operations will resume in the near future.
The NRC inspector reviewed the fuel loading / movement records to June 1982.
The present core (VIIA) was arranged in February 1982 to enhance the flux available to the multiple rotisserie irradiation device'. On reviewing the fuel map, the NRC inspector discovered several inconsist-encies regarding individual fuel element location. Apparently an error had been made in updating the core map.
It was found that the fuel log i
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significance was identified.
No violations or deviations were noted.
10. Maintenance and Surveillance-TheNRC$inspectorreviewedmaintenanceandsurveillancetestresults
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to determine compliance with Technical Specifications. The test results listed below were reviewed:
Linear Power Measuring Channel, S0P III-C Safety s'ower Measuring Channel, S0P III-E Fuel Element Temperature Measuring Channel, S0P III-B Scram Circuit Surveillance, S0P III-I Control Rod Calibration, S0P II-K The NRC inspector had questions concerning maintenance of the linear power measuring channel (S0P III-C). The record for maintenance performed on January 6, 1982, and June 18, 1982, showed that the instrument did not read within the specified range on the lower range of the calibration checkpoints. The operability of an instrument that does not meet all the calibration checkpoint values is questionable and should be reviewed to determine if reactor operation was in accordance with Technical Specification 3.3.2 which requires that the linear power level channel be operable for reactor operation.
Instrument accuracy at lower reactor power levels may not be as significant a concern as it is near full reactor power. This is an unresolved item (8202-02) pending a review by your staff to determine if revised calibration requirements are appropriate.
The NRC inspector had no further questions in this area.
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11. Calibration of Test Equipment The NRC inspector noted that there was no program for ensuring that test equipment (such as a scope or a current source) used to calibrate installed intrumentation was controlled or calibrated. To ensure that installed instrumentation is operable,the test equipment used
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to verify that it is operable must be calibrated.
This is an open item (8202-03).
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12. : Procedures The NRC inspector reviewed the following procedures for technical adequacy _and compliance with Technical Specification 6.5:
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Linear Power Measuring Channel Maintenance and Surveillance, S0P III-C Power Calibration, S0P II-J
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Fuel Element Temperature Measuring Channel Maintenance and Surveillance, S0P III-B Scram Circuit Surveillance, S0P III-I Annual Control Rod Calibration and Determination of Shutdown Margin, S0P III-M Control Rod Calibration, S0P II-K The NRC inspector noted that procedure S0P III-C, " Linear Power Measuring Channel Maintenance and Surveillance," provides instructions for the senior reactor operator to adjust the compensating voltage if analysis of the shutdown characteristic of the linear channel shows that the compensating voltage is improperly set, but the instructions do not specify whether the voltage is to be increased or decreased, or in what increments the voltage should be adjusted. The procedure should clarify how the voltage is to be adjusted.
(0 pen Item 8202-04).
The NRC inspector had no other questions in this area.
13. Radiation Monitoring and Control The NRC inspectors reviewed radiation surveys and calibration of radiation monitoring and measurement instrumentation for compliance with 10 CFR 19 and 10 CFR 20.
In addition, the NRC inspectors measured direct radiation levels during a facility tour and checked various accessible areas for contamination. No unusual levels of radiation or contamination were found.
No violations or deviations were identified.
14. Radioactive Waste The NRC inspector observed the ongoing modifications to the radioactive
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waste holdup tanks.
The facility has three storage tanks with a total storage capacity of 22,000 gallons. When a tank is filled, it.is valved off and sampled.
Depending on the amount of activity in the water, it can be stored for decay, diluted or drained to the storm
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The tank was removed from service for repairs.
No release of radioactive material in excess of resulting limits was identified.
No violations or deviations were noted.
15. Emergency Planning The NRC inspectors reviewed the emergency plan for the Nuclear Scidnce Center', Texas A & M University, June 1979.
The NRC inspectors discussed the subnittal of an upgraded emergency plan for the subject facilities. Guidance criteria as contained in NUREG-0849, " Standard Review Plan for the Review and Evaluation of Emergency Plans for Research and Test Reactors" and Regulatory Guide 2.6,
" Emergency Planning for Research and Test Reactors", Revision 1,
. March 1982, were referenced. The submittal date for the upgraded plans, as contained in the final amendment to 10 CFR 50.54(r), was noted.
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No violations or deviations were identified.
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Site Tour The NRC inspectors made a tour of the reactor facility observing the following operating practices, facility and modifications, and general equipment -conditions.
Availability of Procedures Posting per 10 CFR 19 and 10 CFR 20 Access Control Personnel Monitoririg Availability of Radiation Survey Meters It was noted that the raw water line supplying reactor make up water did not h. ave a check valve or siphon break to prevent water from entering the supply piping in a situation where the supply water lost pressure. A licensee representative said that this matter would be reviewed to determine if a system modification is needed. This is an open item (8202-04).
The NRC inspectors had no further questions in this are r
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17. Open and Unresolved Items Open. items and unresolved items are matters identified during the course of the inspection that may be reviewed during future inspections to determine if future NRC action is appropriate.
During the course of this inspection, four new items were identified and one previous violation was closed.
Number Title Paragraph Status 7802-02 Neutron Monitoring 14c Open 8001-01 Reactor Operation Procedures (Violation)
6c Closed 8202-01 Reactor Safety Board Responsibilities
Open 8202-02 Operability of Linear Power Channel
Open 8202-03 Calibration of Test Equipment
Open 8202-04 Linear Channel Compensation Voltage Adjus tment
Open No violations or deviations were' identified.
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Exit Interview At the conclusion of the inspection, the findings were discussed with the licensee representatives denoted in paragraph 1.
The inspector summarized the purpose and the scope of the inspection and the findings.
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