IR 05000294/1981001
| ML20010E251 | |
| Person / Time | |
|---|---|
| Site: | 05000294 |
| Issue date: | 08/20/1981 |
| From: | Boyd D, Janke R, Ridgway K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20010E249 | List: |
| References | |
| 50-294-81-01, 50-294-81-1, NUDOCS 8109030239 | |
| Download: ML20010E251 (7) | |
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U.S. NUCLEAR REGULAwRY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-294/81-01 Docket No. 50-294 License No. R-114 Licensee: Michigan State University East Lansing, MI 48824 Facility Name: Tr1GA Reactor Inspection Conducted: July 28-31, 1981 h
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Inspectors:
K. R. Ridgway 8-Za 5 /
iglq <j R. C. Janke 6'- L2 '-k )
g).kk:s c'I Approved By:
D. C. Boyd, Chief S-Jo -il Projects Section 1A Inspection Summary:
Inspection on July 28-31, 1981 (Report No. 50-294/81-01)
Areas Inspected: Routine, tnannounced inspection of records, logs and organization, review and audit functions; requalification training; pro-cedures; surveillance and maintenance experiments; radiation protection
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program; radwaste management program; security plans, material control
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and accountability; emergency plan; and followup action relative to IE Circulars and Open Inspection Items. This inspection involved a total of 58 inspector-hours onsite by two NRC inspectors including 0 inspector-
hours onsite during offshifts.
Results: No items of noncompliance were identified in eleven areas I
inspected.
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8109030239 810821 PDR ADOCK 05000294 G
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DETAILS 1.
Persons Contacted B. W. Wilkinson, Chairman, Reactor Safety Committee
- J.
Carrick, Supervisor, Nuclear Reactor
- W. H. Malchman, Radiation Safety Officer A. P. McEntee, Captain, MSU Department of Public Safety T. Green, Operator Trainee
- Denotes those present at the exit meeting.
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2.
General This inspection, which began at 9:00 a.m. on July 28, 1981, with an
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overall examination of the reactor and other laboratory facilities to determine that required security, radiation protection and operational safety measures were being carried out.
On July 28 and 29, the in-spectors observed the pre-startup checks and startup of the reactor.
On July 30, the inspectors observed preparation of irradiation samples and the handling procedures. No problems were noted.
3.
Organization, Logs and Records The facility organization was reviewed and verified to be consistent with the Technical Specifications and/or Hazards Summary Report.
The minimum staf fing requirements were verified to be present during reactor operation, and fuel handling or refueling operations.
The reactor logs and records were reviewed to verify that:
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a.
Required entries were made.
b.
Significant problems or incidents were documented.
c.
The facility was being maintained properly.
d.
Records were available for inspection.
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No items of noncompliance or deviations were identified.
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4.
Reviews and Audits The licensee's review and audit program reco ds were examined by the inspector to verify that:
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a.
Reviews of facility changes, operating and maintenance procedures, t
design changes, and unreviewed experiments had been conducted by a safety review committee as required by Technical Specifications or Hazards Summary Report.
b.
That the review committee and/or subcommittees were composed of qualiJied members and that quorum requirements and frequency of meetings had been met.
c.
Required safety audits had been conducted in accordance with Technical Specification requirements and that any identified problems were resolved.
The licensee, by letter-f May 21, 1981, notified Region III, that, due to scheduling problems, the maximum time interval between Reactor Safety Committee (RSC) meetings of four months as specified in the Technical Specifications (TS), had been exceeded by twenty days between meetings of December 10, 1980 and May1979.),1981.The maximum interval had previously been exceeded in
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The present TS does not require audits, however, the licensee applied for a license renewal on July 13, 1978, and the proposed TS will require quarterly audits of operations. The licensee developed an audit checklist ar.d had instituted audits in late 1980.
The inspectors noted tnat the RSC had reviewed and approved:
a.
The Maintenance Procedures, 10/1/80 b.
The RSC Charter, Rev. 2, 12/10/80 c.
The Reactor Rules and Regulations i
d.
The Emergency Plan, 12/10/80 e.
The Physic Security Plan, Rev. 4, 3/12/81 5.
Requalification Training The inspector reviewe i procedures, logs and training records; and interviewed personnel to verify that the requalification training
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program was being carried out in conformance with the facility's appreved plan and NRC regulations.
Two requalification examinations had been conducted in December 1980.
The inspector noted that training material (lectures, tests, etc.) is not maintained for the two individuals preparing for Operators
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License Exams. The licensee has agreed to prepare such packages.
i 1/ IE Inspection Report No. 50-294/80-01
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No items of noncompliance were identified.
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6.
Procedures
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The inspector reviewed the licensee's procedures to determine if
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procedures were issued, reviewed, changed or updated, and approved
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in accordance with Technical Specifications and IISR requirements.
I This review also verified:
That procedure content was adequate to safely operate, refuel a.
j and maintain the facility.
l b.
That responsibilities were clearly defined.
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c.
That required checklists and forms were used.
l The inspector determined that the required procedures were available and the contents of the procedures were adequate.
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The inspectors noted that many of the operating and some maintenance procedures had been retyped, dated, and approved.
No items of noncompliance were identified.
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7.
Surveillance The inspector reviewed procedures, surveillance test schedules and test records and discussed the surveillance program with responsible
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i personnel to verify:
That when necessary, procedures were available and adequate to a.
perform the tests.
i b.
That tests were completed within the required time schedule.
c.
Test records were available.
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The inspectors noted that the rod interlock check of simultaneous withdrawal of the regulating rod and shimrod is performed as a weekly I
check, and the licensee has agreed to increase the frequency to a
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daily, as part of the pre-startup check list.
In addition, the
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inspectors noted that the linear and log in recorder is not dated
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j for each day of operation. The licensee has agreed to do so.
i No items of noncompliance were identified.
8.
Experiments
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The inspector verified by observing and reviewing irradiation records and other reactor logs that:
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i a.
Irradiatiens were conducted using appre/ed procedures and under
j approved reactor conditions.
b.
New irradiations were properly reviewed and approved.
c.
The irradiations did not involve an unreviewed safety question, i.e.,
10 CFR 50.59.
d.
Reactivity limits were not or could not have been exceeding during the experiment.
The inspector noted that there has not been an experiment performed or proposed for several years.
9.
IE Circular Followup
For the IE Circulars listed below, the inspector verified that the Circular was received by the licensee management, that a review for
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applicability was performed, and that if the circular was applicable to the facility, appropriate corrective actions were taken or were scheduled to be taken.
IEC 81-02 Performance of NRC-Licensed Individuals While On Duty
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10.
Review of Periodic and Special Reports i
The inspector reviewed the following reports for timeliness of stibmittal
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and adequacy of information submitted:
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Annual Operating Report for 1980, dated April 15, 1981.
11.
Followup on Items of Noncompliance a.
(Closed) 50-294/80-03-01 - Annual requalification examinations exceed the annual frequency. The licensee has completed the requalification examinations for 1980.
l b.
(Closed) 50-294/80-03-02 - Failure to complete required surveillance tests on the required time interval. The licensee l
has completed required tests in the proper time intervals l
in the past year and has established an audit checklist that includes all TS tests.
l 12.
Radiation Control The inspectors reviewed records, interviewed personnel, and made l
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observations and independent surveys to verify that radiation controls were being carried out in accordance with the licensee ani NUC regula-tions. The areas covered were:
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a.
Posting and labeling of restricted areas and radioactive materials.
b.
Control of irradiated samples.
c.
Calibration of radiation detection instruments.
d.
Required periodic dose and contamination surveys.
e.
Exposure records of personnel and posted areas of the facility.
f.
Personnel training.
The inspectors noted that although the operator trainees appeared to be getting adequate training in radiation protection, there was no readily available documentation of this training.
In addition, the trainees had not been assigned film badges and had been using spare or visitors badges. The licensee stated that training record folders would be established for the trainees and other personnel routinely using the facility and the trainees would be issued film badges. The Office of Radiation Chemical and Biological Safety (ORCBS) had revised and re-issued the MSU Radiation Safety Manual in 1981.
No items of noncompliance were identified.
13.
Radioactive Effluents The inspectors reviewed records of gaseous releases over the last year.
No liquid or solid wastes outside of wipes, gloves, etc., are generated by the facility.
Solid waste disposal is handled by the ORCBS ;nder the University's broad license.
Gaseous releasees are primarily argon-41, which is released when the pool / temperature is elevated following a long run.
In 1980, this resulted in a yearly average concentration of 1.01E-10 microcuries per cubic centimeter, approximately 0.25% of the 10CFR20 limit.
Surveillance operational checks and calibrations had been carried out at the required frequency.
No items of noncompliance were identified.
14.
Security Program On January 2, 1980, and March 13, 1981, the licensee applied for and NRR approved License Amendment No. 4, dated June 24, 1981. The amend-ment concerned minor changes to the physical security plan which were to be implemented by July 24, 1981. The inspectors reviewed the approved plan and determined that the requirements of the plan were Seing carried out in the areas of:
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Physical Protection of SNM Security Organization Access Control Alarms Systems Keys, Locks, and Hardware
Communications Surveillance Security Procedures Security Program Review Protection Against Sabotage No items of noncompliance were identified.
15.
Emergency Plan The licensee had updated the Emergency Plan and the RSC had approved it on December 10, 1980. Only minor changes had been made in the l
procedures. The inspector reviewed records to determine that an evacuation drill had been successfully conducted in 1980. The Reactor Safety Committee had conducted a re-entry procedure walk through during their May 1, 1981, meeting.
The inspectors reviewed the contents of the emergency locker in Room
- 9 in the basement of the Engineering Building and found the contents as described in the Emergency Plan.
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No items of noncompliance were identified.
16.
Material Control and Accounting
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i The licensee has not received or shipped any fuel or SNM since 1975.
The inspector reviewed records to determine that the fuel inventory and fuel burnup had been reported correctly. One fuel element (176
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in Storage Rack B) was raised for identification since it had been t
carried in the records as being in Storage Rack O.
Other fuel elements were accounted for by visual count only.
On December 12, 1980, the licensee had obtained an amendment to SNM License 390 reducing the plutonium possession limit from 328 to 279 g rams. This made their combined possession limit for License SNM-390 and Reactor License R-114 less than one effective kilogram pnd the procedure requirements of 10 CFR 70.51(d) no longer apply No items of noncompliance were identified.
17.
Licensee Event Reports Followup
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Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to determine 2/ IE Inspection Report 50-294/78-02-7-
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l that reportability requirements were fulfilled, immediate corrective l
action was accomplished, and corrective action to prevent recurrence had
been accomplished in accordance with Technical Specifications.
a.
On June 22, 1979, the licensee reported that on June 13, 1979,
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t while performing a fuel temperature meter calibration, the TI
Temperature Meter was found to be malfunctioning so that at i
full power, indication dropped to zero.
The T2 meter was found
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to be functioning properly.
Cause of the failure was determined to be intermittent opening of the thermocouples in fuel element
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7833, position B-5.
The spare thermocouple from the fuel element in position C11 were connected to the TI meter and operability verified.
b.
On May 21, 1981, the licensee notified Region III that due to the University fiscal crisis and the uncertainty of continued l
operation of the facility, and also to member scheduling problems, the required maximum interval of four months between Reactor Safety Committee meeting had been exceeded by 20 days, April 10 to May 1, 1981.
t 18.
Exit Interview
The inspector met with licensee representatives (denoted in Paragraph 1)
i at the conclusion of the inspection on July 30, 1980, and summarized
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the scope and findings of the inspection.
The licensee acknowledged the inspectors' remarks as follows:
i a.
The need to maintain training records of all personnel in the area of required radiation protection on 10 CFR Part 19 areas as I
well as reactor training records of the reactor operator trainees.
b.
Regular workers at the reactor should be assigned film badges to give better badge usage control and a record of " accumulated exposures".
l c.
The control rod simultaneous manual withdrawal interlock operations test should be included in the Daily Check List to assure operability whenever the reactor is operated.
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I d.
As recommended by the RSC, procedures for the Area Radiation i
Monitor calibration and testing need to be updated for the new
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i Eberline RMS II System.
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