ML20138P889

Forwards Annual Insp of Retired Westinghouse Test Reactor (License TR-2) for 1985.Status of Retired Facility Remains Same as Last Rept

ML20138P889
Person / Time
Site:	Waltz Mill
Issue date:	12/16/1985
From:	Nardi A WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Office of Nuclear Reactor Regulation
References
LA-85-98, NUDOCS 8512260324
Download: ML20138P889 (4)

Text

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• 4 b' Y]s Westinghouse Water Reactor $3EEh PennsyNania 15230-0355 Electric Corporation Divisions s

LA 85-98 December 16, 1985 U. S. Nuclear Regulatory Commission Office of Nuclear Regulation Division of Reactor Licensing Washington, D. C. 20555 Attention: Branch Chief, Standardization and Special Projects Brar.ch Gentlemen:

Subject:

Annual Report - License No. TR-2. Docket 50-22 The Westinghouse Electric Corporation transmits herewith the attached

" Annual Inspection of Retired HTR per License TR-2" for 1985. This report has been prepared in compliance with the requirements 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 me at the above address or telephone me on (412) 256-6054.

Very truly yours, A . Nardi,.Nanager NES License Administration AJN/pe/0059w:12 Attachment Copies Transmitted: 3 notarized & 10 conformed COMMONNEALTH OF PENNSYLVANIA) '

COUNTY OF ALLEGHENY) ss.

Sworn and subscribed before me this

= /f M. day of NU+> 4/ - , 1985 "

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I ANNUAL INSPECTION OF RETIRED WTR PER LICENSE TR-2 During the period August 15 through September 6 and on October 15, 1985, tho fccilities of the retired Westinghouse Testing Reactor (WTR),

,rGtnined under NRC License TR-2, were entered for the purpose of ctnducting the annual inspection and for performing any preventive c31ntenance required. Those personnel entering the facilities for the purpsce of conducting the inspection were: M. J. Kabo, Manager, Works Engincering; D. T. Galm, Manager, Health and Safety Services; R. G.

Kitzcr, Jr., Manager, Industrial Hygiene and Safety; and J. T. DiNicola ,

End J. A. Moskanick, Radiological Safety Technicians. 1 Tho findings and action taken are summarized below:

1. During the pant year, entries continued to be made into the vapor ccntainer on a periodic basis to ascertain if significant water was  ;

eccumulating on the floor. Actions were previously taken to reduce this accumulaton including covering the canal with plastic sheeting and polyurethans boards; installing two (2) dehumidifiers; and in-otalling a sump pump in a small hole in a low area of the floor.

, These actions continue to prove extremely effective because the

humidity within the vapor container is being maintained at a very low level and essentially no accumulation of water has been observed en the floor during the various inspections.

2. The overall condition of the vapor container was good and no oignificant moisture was observed on any walls, either above or bolow ground level. Visual inspection of the interior surface chowed little or no increased deterioration of the surface coating.

Scae rusting was observed on the interior bottom portion of the vapor chall skin, but this condition was unchanged from the last several ycars. Therefore, no action is deemed necessary relative to the Gtructural 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 hnving chipped off at the top.

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3. No work was done under the water in the vapor container canal since l the last annual report (submitted October 22, 1984) so the conditions rcuain unchanged. The water level in the canal was measured and found to be slightly higher than observed during the previous annual inspection. The canal low level water alarm was manually activated and l responded properly; i.e., audible alarm and printout in the Security '

centrol Center and audible and visual alarm in the Health Physics l Office.

i A3 noted in Table I of this report, the canal water was sampled and '

fcund to have a gross beta-gamma activity of 1.40x10-4 u ci/ml. This l 4

indicates very little change from last year's value of 1.29xl-4  !

pCi/ml and the 1983 value of 1.92x10-4 yCi/ml.

l 4. Overall housekeeping within the vapor container remains l

I catiofcctory. All lecco floor tilo have boon rcmoved and no othsr debris was observed on the floor.

s

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 valves in the ventilation ducts in the Truck Lock area were inspected and found to be in the CLOSED position.

7. The absolute filter through which the reactor primary system breathes into the Annex Area was inspected and found to be in catisfactory condition. This filter had been replaced during the 1982 inspection.

8. As previously noted, periodic entries were made into the vapor container during the past year by Westinghouse personnel. Records are raintained by the Manager, Health and Safety Services, which indicate the date and time of entries, who made the entry and the purpose of each cntry.

9. The following changes in management relative to the administration of License TR-2 were made since the submission of the 1984 annual report:

a) D. E. Simpson was appointed Manager, Engineering, replacing .

T. C. Varljen. Mr. Simpson reports to Dr. W. H. Arnold, General Manager, Advanced Energy Systems Division, and senior management ,

person at the Waltz Mill Site having responsibility for the l retired WTR facilities.

10. The inspection of the snakepit (primary coolant pipe tunnel)

, currounding the vapor container indicated that approximately 7100 gallons of water, with a beta-gamma activity of 2.2x10-6 pCi/ml, were in the tunnel, so the increase in water volume over the last year was 2300 gallons. This compares to the 2300 gallon increase in 1983/1984 and the 1650 gallon increase in 1982/1983.

Since the volume is still relatively small and the gross activity low, we do not plan to remove and process this water in 1985.

11. The results of the radiological survey are shown in Table I, attached. A general review of the survey data obtained since 1963 indicates that the radiation and contamirundon levels are low and relatively stable. Frequently, some scatter is seen in the data which is attributed to sampling techniques, sensitivity of the counting equip-Eent used and the relatively low levels of activity present. Any slight changes in a specific set of data from year-to-year are not considered to be significant.

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-' Survey Dates: 8-15-85 thru 9- 6-85

-\ TABLE 1 RADIATION AND COFDMINATION AREAS SURVEY REPORP Retired WrR Facility

Reference:

WIR-172 License 'IR-2

. General B y Contaunation Ievels*

s S M ace Water LOCATIONS 2 Air

' B y. mr/hr '

dprV100 an uCi/ml , uCi/ml I. Reactor Building

- 1. 16 ft Elevation -

<1 <200 1.1x10-12

%g gg NA

2. Rabbit PLup Rxan - <1 <200 1.1x10-12 NA General Background

- 3. Sub 11e kxxn - 6.5 305 0.6x10-12 NA General Background

4. Reactor 'Ibp - General <1 <200 0.6x10-12 NA

Background

"I2

5. Reactor 'Ibp - Over <1 <200 0 NA Closed vessel - General

Background

6. Raactor 'Ibp - Around <1 <200 0.5x10-12 NA Trench - General Background

7. Canal Wall 'Ibp <1 <200 NA NA

8. Canal Water 1.5 NA NA 1.4x10-4

9. Pit-PC 'Ibnnel <1 <200 0.4x10-12 NA 16 ft Elevation d

j

• = Average values '

NA = Not Applicable

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