ML20207C511

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Annual Insp of Retired Westinghouse Testing Reactor Per License TR-2 for 1986
ML20207C511
Person / Time
Site: Waltz Mill
Issue date: 12/31/1986
From:
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20207C486 List:
References
NUDOCS 8612300163
Download: ML20207C511 (3)


Text

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.. ANNUAL INSPECTION OF RETIRED WTR PER LICENSE TR-2 During the period September 22 through September 26 and on October 16, 1986, 5 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.

Kabc, Manager, Works Engineering; D. T. Galm, Manager, Health and Safety Services; A. W. Turk, Jr., Site Fire Prevention Administrator; and B. L. Hartung, J. T.

DiNicola and J. M. Huber, Radiological Safety Technicians.

The findings and actions taken are summarized below:

1. During the past year, entries continued to be made into the vapor container on a periodic basis to ascertain if significant water was accumulating on the floor. Actions were previously 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 continue to prove extremely effective and the humidity within the vapor container is being maintained at a very low level and essentially no accumulation of water has been observed on the floor during the various inspections.
2. The overall condition of the vapor container was good and no significant moisture was observed on any walls, either above or below ground level.

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 the vapor shell skin, but this condition was unchanged from the last several years. Therefore, no action is deemea necessary relative to the structural stability of the vapor container.

The exterior surface of the vapor container was repainted in October 1982, and its overall condition remains satisfactory, with some paint deterioration being evident at the top.

3. The water level in the canal was measured and found to be slightly higher than observed during the previous annual inspection. This slight increase in water volume is attributed to the fact that the dehumidifiers drain into the canal. The canal low level water 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 beta-gamma activity of 1.97x10-4 uCifml. This indicates very little chang value of 1.29x10 guCi/ml.

from last year's value of 1.4x10 pCi/ml and the 1984 No work was done under the water in the vapor container canal since the last annual report (submitted December 16, 1985) so the conditions remain unchanged. Piping was installed to permit the ion exchange processing of the canal water. The water is withdrawn by a submersible pump at the south end of the vapor container, pumped through particulate filters and ion exchange resin and discharged back to the canal at the north end. The pump controls, filter housings and ion exchange columns are all located in the Annex area (not retired area) and only the submersible pump and withdrawal and discharge piping is located in the vapor container. An independent water level float device is interlocked with the pump so that the pump will shut off if the water level drops for any reason. Since installation in early September, approximately 90,000 gallons of water have been processed through the ion exchange system and decontamination factors of 104 are being achieved.

8612300163 861222 PDR ADOCK 05000022 R PDR

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' , 4. Overall housekeeping within the vapor container remains satisfactory.

' All loose floor tile have been removed and no other debris was observed on the floor.

5. The personnel entry doors on the east and west sides 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. These 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 valve in the ventilation ducts in the Truck Lock area was inspected and found to be in the CLOSED position.

7. The absolute filter through which the reactor primary coolant system breathes into the Annex area had been in service since 1982, so the filter was replaced during this inspection.
8. As previously noted, periodic entries were made into the vapor container during the past year by Westinghouse personnel. Records are maintained by the Manager, Health and Safety Services, which indicate the date and time of entries, who made the entry and the purpose of each entry.
9. There were no changes in Westinghouse management relative to the administration of License TR-2 since the submission of the 1985 annual report.
10. The inspection of the snakepit (primary coolant pipe tunnel) surrounding the vapor container indicated that appro gross beta-gamma activity of 1.1x10 gimately pCi/ml, were in 9000 gallons the tunnel. Thisofrepresents water, with a a volume increase, due to groundwater infiltration, of 1900 gallons over the last year, which compares with a 2300 gallon increase in both the 1984/1985 and 1983/1984 periods.

Since the volume is still relatively small, and the gross activity low, we do l not plan to remove and process this water in 1986.

11. The results of the radiological survey data are shown in Table I, attached.

l A general review of the survey data obtained since 1963 indicates that the radiation and contamination levels are low and relatively stable. Frequently, some scatter is seen in the data which is attributed to sampling techniques, sensitivity of the counting equipment used and the relatively low levels I

of activity present. Any slight changes in a specific set of data from year-to-year are not considered to be significant, t

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. Survey Dates 9/22 - 9/26/86

'DBLE 1 RADIATION A!O CCNDMINATION AREAS SURVEY REPORP Retired WrR Facility

Reference:

WIR-172 License 'IR-2 General B-y Contaminaticr1 Ievels*

LOCATIONS Radiation Ievels Surface & hw By mr/hr ' dpn/100 an uCi/ml , uCi/ml I. Ranctor 9d16 W

1. 16 ft Elevation - <l <200 0.8x10-I2 NA General Background
2. Rabbit Ptmp Itxxn - <1 <200 1.0x10-12 General Background
3. 'Sub Pile Bean - -

4 280 4.7x10-12 NA General Background

4. Reactor Top - General <1 <200 0.3x10-12 NA Background (MDA)
5. Reactor Top - Over -12 Closed Vessel - General <1 <200 0.3x10 NA Background (MDA)

-12

6. Reactor 'Ibp - Around <1 <200 0.3x10 NA Trench - General Background (MDA)
7. Canal Wall 'Ibp <1 <200 NA NA
8. Canal Water <1 NA NA 1.97x10-4

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9. Pit-PC Tunnel <1 <200 0.3x10 NA 16 ft Elevation (MDA)
  • = Average Values NA = Not Applicable MDA = Minimum Detectable Activiny t

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