ML20205J073
| ML20205J073 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/28/1986 |
| From: | Standerfer F GENERAL PUBLIC UTILITIES CORP. |
| To: | Travers W Office of Nuclear Reactor Regulation |
| References | |
| 0392A, 392A, 4410-86-1-22, 4410-86-L-0022, 4410-86-L-22, NUDOCS 8601300092 | |
| Download: ML20205J073 (2) | |
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a GPU Nuciaar Corporation Ng gf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057-0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
(717) 948-8461 4410-86-L-0022 Document ID 0392A January 28, 1986 TMI-2 Cleanup Project Directorate -
Attn: Dr. W. D. Travers Director b
US Nuclear Regulatory Commission r-17 c/o Three Mile Island Nuclear Station Middletown, PA 17057 N
Ms ca g
Dear Dr. Travers:
g Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No. DPR-73 Docket No. 50-320 Makeup and Purification Demineralizers This letter is intended to transmit the results of the Makeup and Purification Demineralizers Elution Process, the current condition of the demineralizers, and our plans for future disposition.
Radioactive cesium was removed from the makeup and purification demineralizer resins by gradient elution using sodium hydroxide solutions. Approximately 790 Ci of D7Cs were eluted from the A-demineralizer (W-K-1A) and 3,455 Ci of 137Cs were eluted from the B-demineralizer (W-K-1B). This left an 137 s in the A-demineralizer and an estimated 440 Ci of estimated 380 Ci of C
137Cs in the B-demineralizer. The majority of the radiocesium in the eluants was absorbed onto the zeolites in one SDS liner (U-00009) and shipped to Rockwell-Hanford operations in Washington for disposal. Approximately 68%
137 s activity were removed from the A-and and 89% of the original C
B-demineralizer resins, respectively, by the batch elutions. The process consisted of 23 batch elutions on the A-demineralizer and 24 batch slutions on the B-demineralizer and was performed between September 30, 1984, and April 12, 1985. A total of 30,755 gallons of diluted eluant was processed by the SDS during these operations.
0601300092 860128 ADOCKOSOOgO DR y
GPU Nuclear Corporatico is a subsidiary of the General Public Utilities Corporation
4 6r. Travers January 28, 1986 4410-86-L-0022 Although the initial target of 90% curie removal based on the Non-Destructive Assay assessments could not be obtained, the post-elution radiation surveys indicated that the curie removal efficiency of the elution process closely matched that of the laboratory tests. The discrepancy between the actual curic removal efficiency and the target 90% curie removal efficiency was caused by overestimates of the initial curie inventory for the demineralizers.
The post-elution radiation surveys showed that the residual activity remaining on the resins is less than that handled at TMI-2 on EPICOR 11 pre-filter resins and is also less than the 10 C1/ft3 loading recommended by the NRC for organic ion-exchange resins (Branch Technical Position 204.1.5, January 5, 1983). In light of this, GPU Nuclear considers that the cesium elution of the makeup and purification demineralizer resins accomplished the original goal; that is, it reduced the radioactivity on the resins so as to reduce the radiation exposure during removal and packaging of the resins for disposal.
As to the current status of the demineralizers, they have been placed in a wet layup condition. This condition was established through a process consisting of three (3) 150 gallons flushes of processed water through each demineralizer to remove the residual sodium hydroxide used for elution. Both demineralizers were then eluted with two (2) 150 gallon batches of Reactor Coolant System (RCS) grade water (i.e., 5000 ppm baron, 1500 ppm Sodium, pH=7.6).
The A-demineralizar was left with approximately 150 gallons of RCS grade water covering the resins, while the 2-demineralizer was left with approximately 175 gallons of RCS grade water covering the resins. Both demineralizers were valved open to the waste gas vent header so as to prevent gas buildup.
Future plans for the demineralizer resins call for sluicing the resins to a modified spent resin system, dewatering these sluiced resins, packaging the resins and shipment of the packaged resins in accordance with the DT/GPUNC-Contract for Abnormal Wastes, No. TC-024029. The timeframe currently anticipated for commencement of resin sluking is the fourth quarter of 1987.
The Technical Plan is currently being written to address the sluicing and disposal evolutions.
Sincerely,\\
w F. R.'Standerfer Vice President / Director, TMI-2 FRS/JCA/eml Director, Licensing and Nuclear Safety - R. E. Rogan cc:
Site Operations Director - S. Levin Manager, Project Plar.ning and Analysis - R. H. Fillnow Radio-Chemical Engineering Supervisor - K. J. Hofstetter
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