IR 05000146/1993001
| ML20057G318 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 10/04/1993 |
| From: | Bores R, Dragoun T, Roth J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20057G313 | List: |
| References | |
| 50-146-93-01, 50-146-93-1, NUDOCS 9310210286 | |
| Download: ML20057G318 (2) | |
Text
c
=
.
.:
- .
.
U. S. NUCLEAR REGULATORY COMAflSSION
.
REGION I
-
-
Report No.
50-146/93-01 m
Docket No.
50-146 License No.
DPR -4 Licensee:
Saxton Nuclear Experimental Corporation /GPUN Corporation i Upper Pond Road Parsiopany. New Jersey 07054 Facility Name:
Saxton Nuclear Experimental Facility Inspection At:
Saxton. Pennsylvania Inspection Conducted:
September 14.1993 Inspectors:
h
[d V 9?
Jer6me Roth', J/oject Manad6r, Ficilities date
~
Radiation Protection Section (FRPS), Facilities Radiological Safety and Safeguards Branch (FRSSB)
W lO ~
9.]
Tifomas Drap6un, Project Scientist, Effluents
'date Radiation Protection Section (ERPS), Facilities
.
Radiological Safety and Safeguards Branch (FRSSB)
~
/o/o y /f3
Approved By:
'
Robert Bores [fC"liief!NRPS, FRSSB, date Division of Radiation Safety and Safeguanis
.
Areas Inspected:
' Acquaint Region-based personnel with the fcilities, n view the current
,
status of the reactor equipment, and discuss plans for decommissioning.
Results: Characterization of the Reactor Containment Building and contaminated areas on site will begin in early 1994. A decommissioning plan will be submitted for NRC approval in late
- 1994.or early 1995.
'
(
e$
.
'
9310210286 931012 l
PDR ADDCK 05000146 G
FOR kL.
l
=
--
.*
a.
.
,
l
.
.
. DETAILS 1.0 Persons Contacted R. Holmes, Saxton Site Manager B. Good, Vice President and General Manager, SNEC L. Porter, Decommissioning Team Section Leader i
R.'Rolph, Radiation Safety Officer, SNEC 2.0 Background
. The 20 megawatt (thermal) Saxton Experimental Reactor was operated from April 1962
!
until May.1972. At that time the mactor was deactivated and the fuel shipped off site.
,
Decontamination of site buildings and structures, with the exception of the reactor
- containment building, began in 1986. Demolition of the Control and Auxiliary Building, Radioactive Waste Disposal Facility, Pipe Tunnel, and Refueling Water Storage Tank
-
were completed in 1_992. The Containment Building with the major reactor systems remains intact. The licensee stated that a'chameterization of the type, quantity, a id
-
location of radioactive material remaining on site will begin in early 1994. The data will be used to develop a decommissioning plan that will be submitted for NRC appmval in
^
1994 or early 1995.. A preliminary cost estimate pmjected that approximately_ $14 million will be expended to complete the ' decommissioning. The current possession-only.
'
license expires in February 2.000. Access controls, periodic in'spections, recordkeeping, and reporting requirements are specified in the Technical Specifications, as amended.
3.0 Easility Status r
The inspectors toured the reactor containment building and contaminated soil retention areas accompanied by licensee management and HP personnel. The reactor pressum 2i vessel and spent fuel pool areas were not accessible. In the remaining equipment areas
-
. the reactor systems appeared to be intact and unchanged. The building is vented via a i
small HEPA filter to equalize changes _in atmospheric pressure.
Dose rates 'and
contamination levels were low except for a few isolated hot spots. Radiological _ controls wem ' good. Physical security measures to pmtect against intmders were also good.
'
' Observations by the inspectors were provided to licensee management during the' tour.
Within the scope of this review, no safety concerns were noted.
- i
k.
>
>
f
'
.
i
'
,
0