ML20137F053
| ML20137F053 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/15/1986 |
| From: | Standerfer F GENERAL PUBLIC UTILITIES CORP. |
| To: | Travers W Office of Nuclear Reactor Regulation |
| References | |
| 0382A, 382A, 4410-86-L-0004, 4410-86-L-4, NUDOCS 8601170414 | |
| Download: ML20137F053 (3) | |
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GPU Nuclear Corporation NUCIMr Post Office Box 480 Route 441 South Middletown Ponnsylvania 17057 0191 717 944-762)
TELEX 84-2386 Writer's Direct Dial Number:
(717) 948-8461 4410-86-L-0004 Document ID 0382A January 15, 1986 c
TMI-2 Cleanup Project Directorate lj, iijl,c Attn: Dr. W. D. Travers u
Director L
Wn US Nuclear Regulatory Commission
%~g c/o Three Mile Island Nuclear Station OO l
Middletown, PA 17057
-o g
Dear Dr. Travers:
i C'
Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No. DPR-73 Docket No. 50-320 l
Auxiliary and Fuel Handling Building Decontamination Schedule In accordance with your letter dated March 7, 1984, the following status of the Auxiliary and Fuel Handling Building Decontamination schedule for the fourth quarter of 1985 is provided. This update lists only those areas where Technical Specification Surveillances are not being performed due to ALARA considerations.
M_ake-up Filter Cubicle ALARA exemption is being taken for Technical Specification Surveillance 4210-SUR-3775.02 (4331-R3), " Fire Barrier Penetration Fire Seal Inspection".
During this past quarter, the cubirle remained inaccessible due to the location of portions of the Make-up and Purification Cesium Elution Process System. The radiation dose rate for the general area is 800 mr/hr with hot spots up to 1.25 R/hr.
Software has been prepared to remove the make-up elution equipment. It is expected that the elution equipment will be removed early in the first quarter of 1986. This action will be followed by detailed 8601170414 860115 PDR ADOCK 05000320 P
PDR I
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
~' W Dr. Travers January 15, 1986 4410-86-L-0004 characterization of the cubicle. Planning and engineering are currently underway to perform both external surface and system flushing in order to reduce the dose rates.
Make-up Pump Suction 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".
General area radiation dose rates for this cubicle range from 100 mR/hr in the suction alley to 1.5-5 R/hr in the discharge alley.
During the past quarter. chese cubicles were characterized using gamma spectrometry instruments to detect the presence of fuel material.
Analysis of tha data is not yet complete; however, it is expected to be completed during the first quarter of 1986.
In addition to the characterization performed during the past quarter, engineering specific to both external surface and internal system decontamination was completed. The actual implementation of this activity is currently pending the results of the characterization efforts and is not scheduled to begin until the second quarter of 1986.
Seal Injection Cubicle ALARA exemption is currently being taken for Technical Specification Surveillance 4210-SUR-3244.01 (4301-H8), " Con N nment Integrity Verification."
During the past quarter, no additional decontamination activities were performed in this cubicle due to high radiation levels. The gamma radiation dose rate for the general area is 25 R/hr with hot spots up to 110 R/hr.
Extensive efforts have been devoted to the development of implementing software and procurement of equipment to support a comprehensive decontamination program for this cubicle. The field work will commence in the first quarter of 1986 with the installation of a supplemental ventilation system for the cubicle, installation of additional video cameras and lighting, and installation of other support systems. The actual decontamination work is scheduled to begin late in the first quarter with debris removal and gross flushing.
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."
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- c Dr. Travers January 15, 1986 4410-86-L-0004 The general. area radiological dose rate is approximately 400 mR/hr. A
- few hot spots, which average 2-3 R/hr, remain in the piping and related components. A hot spot of 20 R/hr exists at the floor drain.
During the past quarter, the engineering required to flush much of the piping in this cubicle was completed. The flushing is planne to be performed once the Make-up Filter Cubicle is accessible. Additional engineering is currently underway to evaluate the disposition of the block orifice and related bypass piping which present the greatest radiological concern. The only field work currently planned for the
.first' quarter is a detailed characterization using gamma spectrometry instruments.
- We will continue to keep you apprised of progress in the decontamination of the Auxiliary and Fuel. Handling Building.
Sincerely, g
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e4 *sp e F. R. Standerfer Vice President / Director, TMI-2 FRS/CJD/eml Attachment
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