IR 05000112/1983001
| ML20023D901 | |
| Person / Time | |
|---|---|
| Site: | 05000112 |
| Issue date: | 05/17/1983 |
| From: | Crossman W, Redano R, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20023D895 | List: |
| References | |
| 50-112-83-01, 50-112-83-1, NUDOCS 8306060133 | |
| Download: ML20023D901 (10) | |
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APPENDIX B U. S. NUCLEAR REGULATORY' COMMISSION
REGION IV
NRC Inspection Report:
50-112/83-01 Docket:
50-l'.?
License:
R-53 Licensee: The University of Oklahoma College of Engineering Norman, Oklahoma 73019 Facility Name: AGN-211 Research Reactor (15 watts)
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Inspection At: Norman, Oklahoma Inspection Conducted: April 20-22, 1983 Inspector:
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I//7/D Tf F. Westerman, Chief Date Reactor Project Section A Yw Tb7bi'R W. A. Crossman, Chief Da'te Reactor Project Section B Inspection Summary Inspection Conriucted April 20-22, 1983 (Report 50-112/83-01)
Areas Inspected:
Routine, unannounced inspection of organization, operations and maintenance logs, Reactor Safety Committee (RSC) activities, procedures, surveillance tests, experiments, and previously identified items. The inspec-tion involved 16 inspector-hours onsite by one NRC inspector.
Results: -Within the seven areas inrpected, one violation was identified (failure to follow procedure (8301-31), paragraph 6). One unresolved item 8301-03, was identified in paragraph 4.
Three open items, 8301-02, 8301-04, and 8301-05 were identified in paragraphs 4, 6, and 7, respectively.
8306060133 830517 PDR ADOCK 05000112 O
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Details 1.
Persons Contacted Principal Licensee Employees
- J. James, Reactor Supervisor
- C. Terrell, Professor of Nuclear Engineering
- P.
Skierkowski, Radiation Safety Officer
- C. Jensen, Reactor Director
- Denotes presence at the exit interview conducted on April 22, 1983.
2.
Status of Previously Identified Items a.
Open Items (0 pen) Open Item (211/8101-01): This item deals with the development of methods to implement timely corrective action to RSC audit finding.
This item remains open pending the implementation of new audit procedures by the RSC.
(0 pen) Open Item (211/8101-03): This item remains open pending the implementati.on of a new water activity monitor procedure.
b.
Violations (0 pen) Violation (211/8101-03): Tnis violation remains open pending the implementation of a new sample irradiation form.
(Closed) Violation (211/8201-01): This violation deals with failure to perform audits in the area of equipment performance. The NRC inspector reviewed the newly defined audit functions as specified in the February 14, 1983, letter from the University of Oklahoma to the NRC. These audit categories appear adequate; this violation is closed.
(Closed) Violation (211/8201-02): This violation dealt with failure to adequately document surveillance tests and failure to perform security alarm system test at required frequency. The NRC inspector
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reviewed the Master Maintenance Log Book (MMLB) and the instrument books for the air monitor and the reactor console recorder, noting that calibration and surveillance activities were logged as required and the security alarm test had been performed in its required frequency. This violation is close !
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(0 pen) Violation (211/8201-03): This violation remains open pending Reactor Safety Committee (RSC) review of the functional test developed to verify operability of the safety rod drive motor sprocket and proper documentation of the performance of this test.
(Closed) Violation (211/8201-04): The NRC inspector reviewed the documentation of the requalification exams administered in 1982 and found them to be adequate. This violation is closed.
3.
Organization The NRC inspector reviewed the structure and personnel qualifications of the licensee organization and found it to be in compliance with Section 7.0 of the Technical Specifications (TS).
No Violations or deviations were identified in this area of inspection.
4.
Logs and Records The NRC inspector reviewed all entries in the MMLB and Reactor Startup Log for the period of October 1, 1982, through April 19, 1983, to determine whether these logs were maintained in accordance with regulatory require-ments. The NRC inspector found the log entries to be complete and thorough.
Both logs reviewed were in consistent agreement with respect to common event descriptions. The NRC inspector did note several late entries in the MMLB, some of which were made several weeks after the described activity. Two late entries of particular concern to the NRC inspector were the October 14, 1982, failure of the safety rod lead screw drive which was not recorded'in the MMLB until November 11, 1982, and the March 2, 1983, control rod servo mechanism failure which was not recorded until March 29, 1983. The licensee was informed that the frequency of late entries in the MMLB was undesirable and more effort should be applied in this area.
Both the safety rod and control rod failures described aboved were logged into the Reactor Startup Log on their date of occur-rence.
The NRC inspector determined from discussion with operations personnel and examination of the March 29, 1983, log entry described above that the rod position indication (RPI) for the control rods failed due to mechanical interference from a newly installed digital clock mounting receptacle in the reactor console. As an interim remedy to this problem the licensee has removed the digital clock and mounting receptacle from the reactor console ~and replaced the damaged servo unit with one of like design from the University of West Virginia AGN-211 reactor. The licensee plans to modify the plastic mounting receptacle so that no mechanical interference with the servo unit occurs when the clock is reinstalled. The operations staff had not informed the RSC of this event or of their intended solution.
The NRC inspector informed the operations staff that it is the purpose and responsibility of the RSC to review occurrences of this nature and to decide whether they constitute an unreviewed safety question. The failure of the control rod servo mechanism and the resulting loss of RPI that took
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place on March 2, 1983, is an open item (8301-02) pending documentation and reporting of this occurrence and the proposed remedy to the RSC for their review.
TS 4.1 states, "The fine control rod, coarse control rod, and two safety rods shall be operable and the carriage position of the control rods shall be displayed at the console whenever any rod is above its lower limit."
In the area of reporting requirements, TS 3b states, "The licensee shall report to the director, DRL, in writing within 30 days of its observed occurrence.any substantial variance disclosed by operation of the reactor from performance specifications contained in the safety analysis report or the Technical Specifications." The licensee's failure to report the loss of RPI which occurred during two reactor startups on March 2, 1983, is an unresolved item (8301-03), pending interpretation of the above TS require-ments.
No violations or deviations were identified in this area of inspection.
5.
RSC Activities The NRC inspector reviewed the minutes of the November 5, 1982, RSC meeting and found the scope of subjects addressed by the meeting to be adequate. The meeting attendance met the TS quorum requirements.
The licensee informed the NRC inspector that written audit procedures are currently being developed for use by the RSC.
The NRC inspector concurred with the licensee that the use of audit procedures should improve the thoroughness and consistency of RSC audits. The NRC inspector expressed concern to the licensee over the fact that 1 month has elapsed since the March 22, 1983, RSC meeting and no meeting minutes have been issued. The licensee was reminded that the issuance of minutes is a requirement of the RSC charter and that more timely compliance with this requirement is desirable.
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No violations or deviations were identified in this area of inspection.
l 6.
Procedures The NRC inspector reviewed procedures used for surveillance testing, I
operations, and experimentation to determine whether their technical l
content, implementation and RSC review were in compliance with regolatory l
requirements.
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The procedure " Check of Water Flow Rate for the Water Purification System for the AGN-211 Nuclear Reactor," dated June 20, 1975, requires in Step 11 to, " Keep a plot of water flow rate versus time in the Master Maintenance Book." The NRC inspector discovered that this flow rate data has not been plotted since October 1979. When asked why this data had not been plotted in over 3 years, the reactor supervisor replied that he did not realize that the Step 11 plotting requirements existed.
It became evident to the NRC inspector that the licensee was performing the water flow rate test without using the procedure; the reactor supervisor concurred with this i
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conclusica. The NRC inspector explained to the reactor supervisor and the reactor director that the intent of the requirement to have procedures was that they be used whenever the activity which they prescribe is performed and that failure to use existing procedures defeats the purpose for having them.
TS 7.2.a states, " Detailed written procedures shall be provided and followed." The failure to follow the procedure entitled " Check of Water Flow Rate for the Water Purification System for the AGN-211 Nuclear Reactor," constitutes violation 8301-01.
The NRC inspector reviewed the lab experiment which was used as the procedure to obtain the rod worth data entered in the MMLB on January 27, 1983.
The licensee used a different type of recorder to compile the raw data than that type of recorder which was specified in the rod worth experiment, but no entry was made in the test data documenting the change in instrumentation. The NRC inspector also noted that in most cases the data from surveillance tests is recorded in the MMLB, resulting in an undesirable separation of test procedure and test data.
The licensee informed the NRC inspector that all procedures were being rewritten to provide ample space for test data obtained to be recorded and to eliminate the practice of using lab experiments to perform required surveillances.
The licensee's entire procedure program is an open item (8301-04) pending development and implementation of new procedures which contain the follow-ing items:
a.
Space for test director's initials after each step.
b.
Space for test director's signature at the end of procedure.
c.
Space for identification and description of all measuring and test equipment used.
d.
Page for recording test data including explicit acceptance criteria and tolerances.
e.
Ample space to describe and explain any changes or deviations from procedure which occurred while conducting test and a signature /date line to document review and approval of such changes.
The licensee's procedure program further remains an open item (8301-04)
pending implementation of the following administrative controls:
a.
All procedures are to be filled out in ink.
b.
Errors are to be deleted by drawing a single horizontal line through the unwanted items and initialing each single line correction.
c.
All data reduction methods and arithmetic operations are to be shown on the data pag c
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7.
Surveillance The NRC inspector reviewed the MMLB and instrument logs to ascertain whether the surveillance tests were performed in their required frequency.
The licensee appeared to be performing all surveillance tests in their required frequency, using approved procedures, and satisfactorily anclyz-ing test data.
The " Procedure for the Checkout of the Conductivity of the Reactor Pool Water of the AGN-211 Nuclear Reactor," dated July 11, 1975, states in Step 6, "if the readings differ significantly.
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informed the licensee that the term "significantly" is unacceptable in a quantitative application in a test prccedure.
This is an open item (8301-05) pending replacement of the term "significantly" in the pool water conductivity procedure with explicit quantitative criteria.
No violations or deviations were identified in this area of inspection.
8.
Experiments The NRC inspector learned that a new sample irradiation form had been developed but not yet implemented (paragraph 2). With the exception of this item, the NRC inspector found all experiments which were reviewed were properly documented and the reactor was operated within TS limits during the experiments.
No violations or' deviations were identified in this area of inspection.
9.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, violations, or
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j deviations. Unresolved items disclosed during this inspection are dis-l cussed in paragraph 4.
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10. Exit Interview l
l An exit interview was conducted on April 22, 1983, with those persons I
denoted in paragraph 1 of this report. At the interview, the NRC inspector l
discussed the findings indiccted in the previous paragraphs. The licensee l
acknowledged these findings.
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