ML20209F652
| ML20209F652 | |
| Person / Time | |
|---|---|
| Site: | University of Iowa |
| Issue date: | 06/30/1999 |
| From: | Wendt S IOWA STATE UNIV., AMES, IA |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9907160094 | |
| Download: ML20209F652 (4) | |
Text
.
IOWA STATE UNIVERSITY '""'**"'"*'"""""
Department of Mechanical Engineering dF SCIE NC E AN D TECH NOLOG Y
,g,5 g .ht Black Engineering liutiding Ames. Iowa 500 a 1-23 6i 515 294-1423 FAX 515 294-326:
http1/www.eng iastate.edu/me Docket No. 50-116 Ref: 10 CFR 50.71 (a)
July 9,1999 U.S. Nuclear Regulatory Conunission ATIN: Document Control Desk Washington, DC 20555 To Whom it May Concern:
Please find enclosed the Annual Operations Report for the Iowa State University UTR-10 reactor. The period covered by this report is from July 1,1998 to June 30,1999.
Sincerely, 6
[
Scott E. Wendt, Reactor Manager Mechanical Engineering Department [
Enclosure r c: American Nuclear Insurers . )
' (
D.B. Bullen, Facility Director, Chm., Radiation Safety Committee W.R. DeVries, Chm., Mechanical Engineering Department D.A. Inyang, Dir., Environmental licalth & Safety A.F. Rohach, Reactor Use Committee U.S. NRC, Region III l
l 9907160094 990630 4
Annual Operations Report
~ Iowa State University's UTR-10 Reactor Docket No. 50-116
-July 1,1998 to June 30,1999 This is a routine operations report to the Nuclear Regulatory Commission in accordance with the requirements of Section 6.6 of the Technical Specifications, Appendix A to Operating License R-59.
The final reactor criticality was May 8,1998. Reactor operations were officially ceased on May 15,1998.
- 1. Major preventive and corrective maintenance operations having safety significance:
All surveillance and maintenance activities required by Technical Specifications were completed within the specified time intervals.
Three new area radiation monitors were installed in the controlled access area surrounding the UTR-10 reactor. An amendment to the Technical Specifications that reduced the required number of area monitors from five to two proceeded the installation. (The third monitor is an installed spare.) The new monitors and control module are functionally equivalent to the old system they replaced. The old system was still operational, but was
- becoming difficult to calibrate and maintain. The Reactor Use Committee reviewed and approved the amendment to the Technical Specifications, the new system and the procedure for their installation. It was determined that there were no unreviewed safety questions with the replacement area monitors.
The AC/DC Power Irr/erter, which is 'part of the backup power supply for the area radiation monitors, was replaced with an equivalent unit. It had been observed that the l automatic cooling fan in the old power inverter no longer cycled on and off even though the power inverter was warm to the touch.-
Annual Operations Report for R-59.... Page 1 of 3 j
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'2.;Maijor changes in the reactor facility and procedures that are significantly different from those performed previously and are not described in the Safety Analysis Report, including conclusions that no un-reviewed safety questions were involved:
' On July 27*,1998 the reactor's LEU core was off-loaded and placed in the dry storage pits located next to the reactor. The LEU fuel will remain in storage until it is shipped to
- the DOE's Savannah River Site. The current shipment date is October 1999.
On July 27*,1998 the remainder of the reactor's shield tank water was released to the sanitary sewer system. See section 3 of this report for details.
For two' days in July and then for two weeks in September, Duke Engineering & Services performed a site characterization of the UTR-10 reactor facility. The purpose of the characterization was to quantify all hazards that will be encountered during the decommissioning of the UTR-10. The results of the characterization were included in the UTR-10 Decommissioning Plan that was submitted to the NRC for review on January 6, ,
1999.
I An amendment to the UTR-10 Technical Specifications was submitted to the NRC for review on January 22,1999. License amendment number 13 effectively requests for a possession only license reflecting the current status of the UTR-10 as defueled and permanently shut down. The amendment was approved by the NRC on March 2,1999.
An update to the UTR-10 facility's Emergency Plan was submitted to the NRC on November 25,1998 for review. The main purpose of the update was to re-define how emergency levels based on effluent release would be determined. The revision was approved on anuary J 26,1999.
- A new procedure for the in-transit protection of special nuclear material of strategic low significance was reviewed and approved. The procedure was required in order to ship the
- LEU fuel to the DOE's Savannah River Site. Similar procedures were reviewed and approved for shipments of smaller quantities of SNM to the Y-12 plant in Oak Ridge, Tennessee and to KAPL in Schenectady, New York.
Several new procedures were developed to cover the use of the DOT's 6M shipping l i
container. One procedure was for loading the container and the others were pre-load and
_ post-load inspections of the drums. The procedures were derived from information provided by the owner of the drums (the DOE).
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Annual Operations Report for R-59.... Page 2 of 3 I J
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'3. Suinmary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the University as determined at or before the point of such release or discharge. (Estimates of individual radio-nuclides present in the effluent are included, to the extent practical.):
)
Argon-41: No Ar-41 was released. )
d On July 2 , approximately 220 gallons of water from the reactor's dump tank was released to the sanitary sewer system. The water originated in the experimental " shield tank" and was released through the dump tank to help purge that part of the system of primary coolant. The water was processed using a series of filters to remove insoluble particles.
Per NRC information notice 94-07, the final filter was a 0.45 micron membrane filter.
Before release, it was determined that the water contained a maximum of 0.146 pCi of Cs-
-137.
On July 27*, approximately 2200 gallons of water in the reactor's experimental " shield tank" was released to the sanitary sewer system. The water was processed using a series l I
of filters to remove insoluble particles. Per NRC information notice 94-07, the final filter was a 0.45 micron membrane filter. Before release, it was determined that the water I
contained a maximum of1.58 pCi of Cs-137.
- 4. Summarized results of any environmental surveys performed outside the facility:
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No environmental surveys outside the facility were required since the trigger level, based on surveys inside the facility, was not exceeded.
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- 5. Summary of exposure received by facility personnel and visitors:
No facility personnel or visitors had exposures greater than 25% of that allowed or mended.
- 6. Summary ofitems or events of significance which are NOT required to be reported to the NBC by Technical Specifications:
The remainder ofISU's HEU fuel (24 plates) as well as 16 spare LEU fuel plates were returned to the DOE during this reporting period. These spare fuel plates had been in storage at the facility and had never been irradiated. The fuel was shipped to the Y-12 plant in Oak Ridge, Tennessee, using two DOT 6M drums. The shipment occurred on June.7,1999.
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