ML20212H168
| ML20212H168 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/15/1987 |
| From: | Standerfer F GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| 4410-87-L-0005, 4410-87-L-5, NUDOCS 8701210293 | |
| Download: ML20212H168 (3) | |
Text
J GPU Nuclear Corporation g
gf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057-0191 717 944-7621 TELEX 84-2386 YlkhN8N1 4410-87-L-0005 Document ID 0050P January 15, 1987 US Nuclear Regulatory Comission Document Control Desk Washington, DC 20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No. DPR-73 Docket No. 50-320 Auxiliary and Fuel Handling Building Quarterly Decontamination Schedule In response to the NRC letter dated March 7, 1984, the following is the status of Auxiliary and Fuel Handling Building Decontamination for the Fourth Quarter of 1986. This update only addresses those areas where Technical Specification Surveillances are not being performed due to ALARA considerations.
Make-up Filter Cubicle ALARA exemption is t,aing taken for Technical Specification Surveillance 4210-SUR-3775.02 (4331-R3), " Fire Barrier Penetration Fire Seal Inspection."
l Recent radiological surveys show general area dose rates of 600 to 3000 l
mrem /hr with contact readings as high as 5.5 Rem /hr.
The fuel characterization program for tnis cubicle was completed during the past quarter. The results indicate no presence of reactor fuel above the Minimum Detectable Level (MDL). Therefore, it is estimated that not more than 42 grams of fuel is present in the two (2) Make-up and Purification Demineralizer Filters and two (2) Make-up Filters that are located in this cubicle.
8701210293 870115 0/
PDR ADOCK 05000320 gC R
PDR GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation i
Document Control Desk January 15,1987 4410-87-L-0005 Flushing operations of the Make-up system initiated during the past quarter will continue into the first quarter of 1987. This work involves the use of system filters located in this cubicle, and may intermittently affect local radiation and contamination levels. After system flushing, decontamination of l
external surfaces will begin.
Seal Injection Cubicle ALARA exemption is currently being taken for Technical Specification Surveillance 4210-SUR-3244.01 (4301-M8), " Containment Integrity Verification."
General area dose rates in the cubicle proper range from 1 R/hr - 56 R/hr, with hot spots of 100 R/hr - 355 R/hr.
The corridor area of the cubicle has been scabbled and temporary shielding placed between the inner end of the corridor and the main area. These actions have reduced general area dose rates in the corridor to 100-1000 mrem /hr.
Future work will include the incremental movement of temporary shielding into the main portions of the cubicle with follow-up scabbling operations to further reduce radiation levels. When feasible, resurfacing of the scabbled surfaces will be performed.
Maka-up Pump Suctinn and Discharge Valve Alley ALARA exemption is being taken for Technical Specification Surveillance 4210-SUR-3775.02 (4331-R3) and 4210-SUR-3775.01 (4331-A1), " Fire Barrier Penetration Fire Seal Inspections."
The general area dose rates for the suction alley range from 2 - 105 mR/hr, with hot spots reduced to no more than 1.5 R/hr. For the discharge alley, the general area dose rate ranges from 300-600 mR/hr, with hot spots of 5-10 R/hr.
System flushing operations were initiated during the past quarter and will continue as needed into 1987. Final surface decontamination activities will be performed in these cubicles when flushing operations have been concluded.
General area radiation levels continue to be controlled by hot spots in the system piping, although a distinct reduction in hot spot radiation levels in the suction valve alley was indicated in recent radiological surveys
( l.5 Rem /hr). This reduction is attributed to system flushing operations.
305' Elevation Make-up Valve Alley ALARA exemption is being taken for Technical Specification Surveillance 4210-SUR-3775.02 (4331-R3), " Fire Penetration Fire Seal Inspection."
The general area dose rates are approximately 50-400 mR/hr with an average of approximately 100 mR/hr. A few hot spots, averaging 1 R/hr, remain in the piping and related components; a hot spot of 4 R/hr exists at the unshielded floor drain.
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~ ~ '
Document Control Desk January 15, 1987 4410-87-L-0005 System flushing operations began last quarter and will continue into 1987.
External surface decontamination will be performed following system flushes.
Dose rates have been reduced in this cubicle to a point that performance of the Technical Specification Surveillance may be feasible. An ALARA review will be performed during the first quarter 1987 to determine if the surveillance can be performed.
Sincerely,
. R. Standerfer Vice President / Director, TMI-2 FRS/CJD/eml cc: Regional Administrator, Office of I&E - Dr. T. E. Murley Director, TMI-2 Cleanup Project Directorate - Dr. W. D. Travers
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