ML20031G341
| ML20031G341 | |
| Person / Time | |
|---|---|
| Site: | Waltz Mill |
| Issue date: | 10/16/1981 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20031G337 | List: |
| References | |
| NUDOCS 8110220235 | |
| Download: ML20031G341 (2) | |
Text
I ANNUAL INSPECTION OF
_ RETIRED WTR PER NRC LICENSE TR-2 During the period August 26 through September 25, 1981, the facilities of the retired Westinghouse Testing Reactor (WTR), retained under NRC License TR-2, were entered for the purpose of conducting the annual inspection and for performing any preventive maintenance required. Those personnel entering the facilities for the purpose of conducting the inspection were:
M. J. Kabo, Manager, Works Engineering; D. T. Galm, Manager, Engineering Services; R. G. Kitzer, Jr., Manager, Industrial Hygiene and Safety; C. B. Speicher, Plant Engineer; and B. L. Hartung, Senior Health Physics Tech-nician.
The findings and action taken are summarized below:
1.
During the last six (6) years, entries have been made into the vapor container on a periodic bae's to ascertain if significant moisture was accumulating on the floor. Actions were taken to reduce this accumulation including covering the canal with plastic sheeting and polyurethane boards; installing two (2) dehumidifiers; and installing a sump pump in a small hole in a low area of the floor. These actions have proven extremely effective because the humidity within the vapor con-tainer is being maintained at a low level and very little accumulation of water has been observed during the periodic inspections.
2.
The overall condition of the vapor container was good and no moisture was observed on any walls, whether above.or below grade.
Visual inspection of the interior surface showed little or no increased deterioration of the surface coating. Some rusting was observed on the interior bottom portion of this vapor shell skin, but this condition was not significantly changed from the last several years. The exterior surface had been painted in mid-1976 and its condition is still good.
Therefore, no action is deemed necessary relative to the structural stability of the vapor container.
3.
No work was done under the water in the canal since the last annual report (submitted September 19,1980) so the conditions remain unghanged. The air space between the top of the canal wall and the water level was measured and found to be 17.0 inches. This represents a very small change from what was measured the last several years.
In January, 1979 a water level indicator was installed in the WTR canal and was adjusted to alarm when the water level drops two (2) inches.
Since installation, the alarm has never been activated due to low water. During this annual inspection, the alarm was manually activated and responded properly, i.e., audible alarm and printout in the Security Control Center and audible and visual alarm in the Health Physics Office.
8110220235 81161'6 DR ADOCK OSoooogg PDR
s As noted in Table 1 of this report, the canal water was sampled and found to have a gross beta-gamma activity of 1.97 x 10-4 pCi/ml. This is very close to last years' value of 2.27 x 10-4 pCi/ml and the 1979 value of 2.52 x 10-4 pCi/ml.
4.
Overall housekeeping within the vapor container remains satisfactory.
No additional floor tile have come loose and no other debris was observed on the floor.
5.
The submarine type entrance doors on the east and west side of the vapor container were found to be locked at the time of entry, as were the doors leading into the Rabbit Pump room, the Sub-Pile room and the cover over the Primary Coolant Pipe Tunnel. The areas had to be unlocked to permit access for this inspection, but were relocked when the inspection was completed.
6.
The valve on the drain line on the bottom of the reactor vessel was inspected and found to be in the open position, thereby assuring venting c,f the vessel. The butterfly valves in the ventilation ducts in the Truck Lock were inspected and found to be closed.
7.
The absolute filter through which the primary system piping breathes into the Annex was removed and replaced.
8.
As noted in Item 1, periodic entries were made into the vapor container during the past year.
Records are maintained by the Manager, Engineering Services, which indicate the date and time of entries, who made the entries and the purpose of each entry.
9.
The following changes in management relative to the administration of License TR-2 were made since the submission of the 1980 annual report:
a.
Dr. J. B. Yasinsky was appointed General Manager of the Advanced Power Systems Division replacing G. W. Hardigg.
b.
Dr. W. H. Arnold was appointed General Manager of the Advanced Reactors Divi-sion replacing R. H. Fillnow.
c.
A. J. Nardi was appointed Manager of NES License Administratior. replacing R. P. DiPia7za.
- 10. The inspection of the snake pit (primary coolant pipe tunnel) surrounding the
-6 vapor container indicated that 5500 gallons of water with an activity of 1.5 x 10 pCi/ml, was in this tunnel.
At the time of the 1980 inspection, 8000 gallons of water was in the tunnel and 6000 gallons of this water was" removed and processed through our ion exchange system in October,1980. Therefore, this increase in water volume between October,1980 and September,1981 is 3500 gallons. We do not plan to remove the 5500 gallons before August, 1982.
- 11. The results of the radiological survey are shown in Table I, attached. A general review of the data obtained during the surveys conducted since 1963 indicate that the radiation and contamination levels are relatively stable.
Frequently some scatter is seen in the data which is attributed to sampling techniques, sensitivity of counting equipment used and the relatively low levels of activity present. Any slight increase in a specific set of data from year to year is not considered to be significant.
Dates: 8 26.g]
thru 8-28-81 TABLE 1 RADIATION AND CONTAMIFATION AREAS SURVEY REPORT WTR/TR-2
Reference:
WTR-172 Appendix A Table I (Revised)1 2
3 Locations Radiation Levels B y Contamination Levels 3urface Air Water BdY mr/hr dom /100 cm2 uCi/ml pCi/ml 1.
Reactor Building
-12
- 1. - 16 ft. Elevation
< 1 280 0.5 x 10 NA( }
2.
Rabbit Pump Room
< 1
< 200 0.5 x 10~
NA (Gen. Background)
-12 3.
Sub-Pile Room 10.0 500 0.3 x 10 NA (Gen. Background) 4.
Reactor top
< 1
< 200 0.3 x 10" NA (Gen. Background) 5.
Reactor Top
< 1
< 200 0.2 x 10-NA Over-Closed Vessel
-12 6.
Reactor Top
< 1
< 200 0.1 x 10 NA around Trench 7.
Canal Wall Top
< 1 350 NA NA 8.
Canal Water 5.0 NA NA 1.97x10"
-12 9.
Pit-PC Tunnel
< 1
< 200 0.5 x 10 NA 16' Elevation NOTES:
1.
Table 1 Revised to Delete areas eliminated by license changes (Docket 50-22).
2.
Gencral Background Values for areas tabulated.
(Maximum Icvels may be higher on contact.)
3.
Average Values for areas tabulated.
Not Applicab]c 4.
NA
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