ML19208D425
| ML19208D425 | |
| Person / Time | |
|---|---|
| Site: | Waltz Mill |
| Issue date: | 09/25/1979 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML19208D420 | List: |
| References | |
| NUDOCS 7909280409 | |
| Download: ML19208D425 (3) | |
Text
.
ANNUAL INSPECTION OF RETIRED WTR PER NRC LICENSE TR-2 During the period September 12 through September 17, 1979, 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 wert::
W. R. Ellis, Manager, Administration; M. J. Kabo, Manager, Works Engineering; D. T. Galm, Manager, Engineering Services; R. G. Kitzer, Jr., Manager, Industrial Hygiene and Safety; T. S. Kvamme, Plant Engineer; R. J. Stretch, Safety Engineer and B. L. Hartung, Senior Health Physics Technician.
The findings and action taken are summarized below.
1.
During the last four (4) years, entries have been made into the vapor container on a 1-2 month basis 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 the floor. These actions have proven effective because the humidity within the vapor container is remaining quite low.
2.
The overall condition of the vapor conta ?ner was good and no moisture was observed on any walls, whether above or be. low grade.
Visual inspection of the interior surface showed little or no incr'.4 sed daterioration of the surface coating.
Some resting was observed on the interfor bottom portion of the vapcr shell skin, but this condition was not significantly changed from last year. The exte ior surface had been painted in mid-1976 and its condition is still good.
Therefore, no action is deemed necessary relative to the structural staciliu of the vapor container.
3.
No work was done under tha water in the canal since the last annual report so the conditions retain unchanged. The air space between the top of the canal wall and the water level was measured and found to be 16.0-16.5 inches.
This is essentially the same level as was measured last year.
As we committed in the addendum to last years annual report, a water level indicator has been installed in the WTR canal and is set to alarm when the water level drops two (2) inches.
Since installation in January,1979, the alarm has not been activated.
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.
As noted in Table I of this report, the canal water was sampled and found to have a gross s-y activity of 2.52x10-4 pCi/ml. This is very close to last years value of 2.85x10-4 pCi/ml.
4.
Overall housekeeping within the vapor container remains satisfactory.
Ne additional floor tile have come loose and no other loose debris was observed on the floor.
7900280yd7 1033
' 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 and 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 of 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 inspected.
Although the filter appeared to be in good overall condition, it was decided to install a new filter because the old one had been in service for 5 years.
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.
There have been no changes in management relative to the administration of License TR-2 since the 1978 annual report.
10.
The inspection of the snake pit surrounding the vapor container indicated that the depth of infiltrated water had increased from 3 inches in August, 1978 to 5.5 inches now.
This represents a total volume of 3700 gallons and an increase of 1700 gallons in the last year.
Since the gross e-y activity of this water is low (2.76x10-6 pCi/ml) and we are never able to remove the last 2000 gallons, a decision was made not to remove any water from the Snake Pit at this time.
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 piece of data from year to year is not considered to be significant.
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Dates:
9-12-79 and 9-13-79 P-TABLE 1 RADIATION AND CONTAMINATION AREAS SURVEY REPORT WTR/TR-2
Reference:
WTR-172 Appendix A Table 1 (Revised;g)
Locations Radiation LeveJs(
8-Y Contamination Levels (3)
Surface Air Water 8-y/y mr/hr dpm/100 cm2 uCi/ml uCi/mi I.
Reactor Building 1.
16 ft. Elevation
<1 27 0 1.6x10~
NA( }
-11 2.
Rabbit Pump Room
<1
< 200
.29x10 NA Gen. Bkg.
-ll 3.
Sub-Pile Room 15
< 200
.75x10 NA
Background
C
-11 4.
Reactor Top
<1
< 200
.29x10 NA Gen. Bkg.
-1 5.
Reactor Top
<1
< 200
.20x10 NA Over-Closed Vessel 6.
Reactor Top
<1
< 200
. 07 x10' NA around Trench 7.
Canal Wall Top
<1 300 NA 2.52x10 8.
Canal Water 5.0 NA NA NA
-11 9.
Pit-PC Tunnel
<1
< 200
.05x10 NA 16' Elevation NOTES:
1.
Table 1 Revised to Delete areas eliminated by license changes (Docket 50-22).
2.
General Background Values for areas tabulated.
(Maximum levels may be higher on contact.)
3.
Average Values for areas tabulated.
e 4.
NA Not Applicable
=
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