IR 05000022/1993001

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Insp Rept 50-022/93-01 on 930913.No Safety Concerns or Violations Noted.Major Areas Inspected:Review Current Status of Reactor Equipment & to Discuss Plans for Decommissioning
ML20057F343
Person / Time
Site: Waltz Mill
Issue date: 09/29/1993
From: Bores R, Dragoun T, Roth J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20057F341 List:
References
50-022-93-01, 50-22-93-1, NUDOCS 9310150166
Download: ML20057F343 (2)


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U. S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No.-

'50-22/93-01:

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Docket No.:

50-22

License No.

TR-2 i

Licensee:.

'iVestinehouse Electric Corocration.

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Nuclear Services Division -

P.O. Box 355 '.

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- Pittsbureh. Pennsylvania 15230,

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Facility Name:

.Westinehouse Testine Reactor.

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Inspection At':

Waltz Mill. Pennsylvania -

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' Inspection Conducted:

September 13.1993

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I Inspectors:

JA M T9 eff Jepe Roth; Project Manager, Facilities

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Ramation Protection Section (FRPS), Facilities ~

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l Radiological Safety and Safeguards Branch (FRSSB)..

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' thomas Dragoun,14qip61 Scientist, Effluents date j

Radiation Protection' Section (ERPS), Facilities.

Radiological Safety.and Safeguards Branch (FRSSB)

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i Approved By:

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R$ert Bores, f)fef, ERPS, FRSSB,-

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Division of Radiation Safety and Safeguards i

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Areas Inspected:

Acquaint Region-based personnel with the facilities, review the current status of the reactor equipment, and discuss plans for decommissioning.

i Results: Characterization of the reactor was underway but no schedule was set for submission of a reactor decommissioning plan to the NRC.

9310150166 931004 i

PDR ADOCK 05000022

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DETAILS 1.0 Persons Contacted

- R. Decker, Scientific Ecology Group (contractor HP foreman)

R. Kitzer, Manager and Radiation Safety Officer A. Sabo, Director, Environment and Regulatory Services 2.0 Background I

License TR-2 for the operation of the Westinghouse Testing Reactor was issued in June l

1959.

In 1960 the cladding on one fuel element failed, resulting in fission product contamination of the reactor cooling system. Decontamination and recovery required about six months prior to resuming operation. Reactor operations were discontinued in i

1962 and the facility was deactivated. The license was amended to possession only in March 1963. In 1969, the NRC approved the dismantling of the head tank and the associated structure, fencing, and system piping. In 1970, the Truck Lock Building and Process Building were removed from the facility description. In 1973, the possession

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only license was renewed until November 30,1993. The licensee has recently filed a timely renewal with the NRC requesting renewal of the possession only license. The

. security and equipment surveillance requirements that have been in effect are described in the " Final Shutdown Report for. Westinghouse Testing Reactor, WTR-172" dated January 1963.

3.0 Facility Status The inspectors toured the reactor containment building, areas adjacent to containment, the unused liquid radwaste processing areas, and the backfilled retention pond areas accompanied by licensee management and HP personnel. The reactor vessel, support structures, and biological shield were intact. The contractor health physics foreman descri'oed the sampling techniques being used to characterize the radioactive material

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remaining in various reactor components and the liquid radwaste processing areas.

Generally accepted techniques were being used. Analysis of the samples will be done in the well equipped laboratories on site.

Licensee management stated that the characterization will be completed by year end. A decommissioning plan for the radwaste areas listed on the NRC's Site Decommissioning Management Plan (SDMP)

will be submitted for NRC approval in early 1994. Regulation of the radwaste areas has been consolidated under the special nuclear materials license SNM-770. However, there is no plan to decommission the reactor facilities in the near term and the characterization data will be retained for future use. For the interim, the reactor containment building was kept locked and control of access by HP personnel appeared to be good.

Observations by the inspectors were provided to licensee management during the tour, in lieu of a formal exit meeting. Within the scope of this review, no safety concerns were noted.