ML19338E229
| ML19338E229 | |
| Person / Time | |
|---|---|
| Site: | Waltz Mill |
| Issue date: | 09/19/1980 |
| From: | Dipiazza R WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| WRD-LA-211, NUDOCS 8009250257 | |
| Download: ML19338E229 (4) | |
Text
_
T WRD-LA-211 Westinghouse Water Reactor Ba355 Electric Corporation Divisions Pitthrg*iPennsyNn315230 September 19, 1980 U.
S. Nuclear Regulatory Commission Office of Nuclear Regulation Division of Reactor Licensing Washington, D.C.
20555 Attention:
Mr. Robert W.
Reid, Chief Operating Reactors Branch #4 Gentlemen:
Subject:
Annual Report - License No. TR-2, Docket 50-22 The Westinghouse Electric Corporation transmits herewith the attached report, " Annual Inspection of Retired WTR per License TR-2" for 1980.
This report has been prepared in compliance with the requirement of Facility License No. TR-2, Docket 50-22.
The status of the retired facility remains the same as it was at the time of the last report.
If you have any questions regarding this matter, please write to me at the above address or telephone me on 412/373-4652.
Very truly yours,
/
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onald P.
DiPiazza, Manager NES License Administration Attachment Copies Transmitted:
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ANNUAL INSPECTION OF RETIRED WTR PER NRC LICENSE TR-2 During the period August 14 through August 29, 1980, 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 pre /entive maintenance required.
Those personnel entering the facilities for the purpose of conducting the inspection were:
W. R. Ellis, Manager, Administration; M. J. Kabo, Manager, Works Engineering; D. T. Galm, Manager, Engineering Services; W. D. Meikle, Safety Engineer; and B. L. Hartung, Senior Health Physics Technician.
The findings and action taken are summarized below:
1.
During the last five (5) years, entries have been made into the vapor con-tainer 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 a small hole in a low area of the floor.
These actions have proven extremely effective because the humidity within the vapor container is being maintained quite low and very little accumulation of water has been observed during the periodic inspections.
2.
The overall coridition of the vapor container was good and no moisture was observed on any walls, whether above or below grade.
Visual insp2ction 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 25, 1979) so the conditions remain unchanged.
The air space between the top of the canal wall and the wastelevel was measured and found to be 16.0 inches. This is essentially the same level as 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 drons two l2) inches.
Since installation, the alarm has never been activ a due to low water. During this annual inspection, the alarm was manual-t'vated and responded properly, i.e., audible alarm and printout in cne Security Control Center and audible and visual alarm in the Health Physics Office.
l h
As noted in Table 1 of this report, the canal water was sampled and found to have a gross beta-gamma activity of 2.27x10-4 u Ci/M1.
This is very close to last years value of 2.52x10-4 y Ci/M1 and the 1978 value of 2.85x10-4 u Ci/M1.
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 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.
The absolute filter through which the primary system piping breathes into the Annex was removed and inspected. A new filter had been installed in September,1979 and this overall condition was good.
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 (primary coolant pipe tunnel) surrounding the vapor container indicated that the depth of infiltrated water had increased from 5.5 inches in September, 1979 to 13 inches now. This represents a total volume of 8000 gallons and an increase of 4300 gallons in th Although the beta-gamma activity of this water is low (9x10 q last year.
' u Ci/M1), as much water as possible will be removed and processed through our ion exchange system before the end of this year.
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 levles of activity present. Any slight increase in a specific set of data i' rom year to year is not considered to be significant.
i
Dates:
8-14-80 thru 8-20-80 TABLE I i RADIATION AND CONTAMINATION AREAS SURVEY REPORT WTR/TR-2
Reference:
WTR-172 Appendix A Table.1 (Revised)t 2
3 Locations Radiation Levels Bq Contamination Levels Surface Air Water E-v mr/hr dom /100 cm2 y ci f,t gegf,3 I.
Reactor Building I4) 1.
16 it. Elevation
<1 260
- 1. 3x10-12 NA 2.
Rabbit Pump Room
<1
<200 0.6x10-12 NA (Gen. Background) 3.
Sub-Pile Room 8.
840 0.2x10-12 NA (Gen. Background) 4.
Reactor Top
<1
<200 0.8x10-12 NA (Gen. Background) 5.
Reactor Top
<1
<200 0.7x10-12 NA Over-Closed Vessel 6.
Reactor Top
<l
<200
- 0. 2x10-12 NA around Trench 7.
Canal Wall Top
<1 300 NA NA 8
Canal Water 5.
NA NA 2.27x10-4 9.
Pit-PC Tunnel
<1 210 0.7x10-12 NA 16' Elevation NOTES:
1.
Table 1 1(evised to Delete areas eliminated by license changes (Docket 50-22).
2.
General Backgrcund Values for arms tatulated.
('taximum 1cvels may be higher on contact.;
3.
Average Values for areas tabulated.
i 4.
NA Not Applicable
=
.