ML20210E817

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Forwards Results of Analyses Performed by Westinghouse Advanced Energy Sys Div Analytical Labs Re Radionuclide Content of Selected Processed Water Streams at Facility.Data Reported in Jul 1986 Proposal Remains Valid
ML20210E817
Person / Time
Site: Crane Constellation icon.png
Issue date: 02/03/1987
From: Standerfer F
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
0068P, 4410-87-L-0018, 4410-87-L-18, 68P, NUDOCS 8702100376
Download: ML20210E817 (3)


Text

T GPU Nuclear 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 4410-87-L-0018 Document ID 0068P February 3, 1987 Document Control Desk US Nuclear Regulatory Commission Washington, DC 20555

Dear Sirs:

Three Mile Island Nuclear Station, Unit 2 (TMI-2)

Operating License No. DPR-73 Docket No. 50-320 Disposal of Processed Water Attached for your information are results of analyses performed for GPU Nuclear by the Westinghouse Advanced Energy Systems Division Analytical Laboratories. These analyses were performed as part of the waste stream classification requirements of 10 CFR Part 61. They provide additional information regarding the radionuclide content of selected processed water streams at TMI-2.

This data was not available prior to publication of Draf t Supplement 2 to the Programmatic Environmental Irr. pact Statement - Three Mile Island Unit 2 (PEIS).

The data provided in the attachment is representative of the radionuclide inventory of TMI-2 water which has undergone processing.

In accordance with our July 1986 proposal for the disposal of TMI-2 water by the evaporation process, this water would not be reprocessed prior to evaporation.

Therefore, these data are l

representative of the influent stream to the evaporation system and are provided for your consideration in that context.

Similar data is not reported by Westinghouse for tritium (H-3) since an analysis for tritium was not performed, The data reported in our July 1986 proposal for the " Disposal of TMI-2 Water" t

remains valid.

Sincerely, 7t%

ot o

b F. R. Standerfer Director, TMI-2 II GPU Nuclear Corocration in a nuhsidiary of the General Public Utilities Corporation G702100376 870203 PDR ADOCK 05000320 cD PDR

Document Control Desk February 3, 1987 4410-87-L-0018 FRS/JE/eml Attachment cc: Regional Administrator - Region 1, Dr. T. E. Murley Director - TMI-2 Cleanup Project Directorate, Dr. W. D. Travers J

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ATTACHMENT 4410-87-L-0018 WESTINGHOUSE ADVANCED ENERGY SYSTEMS DIVISION ANALYSES CCT-1 CCT-2 PHST-1 PHST-2 85-10962 85-11240 85-15995 85-16198 09/18/85 09/25/f5

.12/20/85 12/23/85 86-2007 86-2008 86-2009 86-2010 uC1/ml 25 uC1/ml 2S uC1/ml 2S uC1/ml 25 Co-60 1.2E-7 8.4E-8

< 4.5E-8

< 1.0E-7 1.8E-7 5.2E-8 Ag-110m

< 3.6E-7

< 1.2E-7

< 2.3E-7

< l.1E-7 Sb-125

< 3.3E-7

< 1.1E-7

< 2.7E-7 3.4E-7 1.lE-7 Ru-106

< l.1E-6

< 5.3E-7

< 9.8E-7

< 5.2E-7

- Cs-134 3.2E-7 1.2E-7 1.2E-7 4.5E-8 2.4E-7 8.1E-8 2.lE-7 4.4E-8 Cs-137 6.5E-6 2.5E-7 2.8E-6 7.6E-8 6.4E-6 2.2E-7 4.8E-6 9.9E-8 Ce-144

< 7.8E-7

< 3.0E-7

< 5.7E-7

< 2.8E-7 Sr-90 9.0E-6 1.8E-7 1.8E-7 3.6E-8 7.9E-6 1.8E-7 2.1E-5 2.9E-7 I-129

< 4.8E-7

< 5.3E-7

< 6.2E-7

< 5.9E-7 N1-63

< 5.4E-7

< 5.2E-7 8.4E-7 6.5E-7

< 5.6E-7 Tc-99

< 2.6E-7

< 2.7E-7 9.9E-7 3.2E-7

< 2.5E-7 C-14 1.4E-4 9.8E-6 1.lE-4 1.lE-5 5.1E-5 6.2E-6 3.0E-4 1.lE-5 U-234

< l.lE-8

< 1.4E-8

< 1.6E-8

< l.5E-8 U-235

< 6.2E-9

< 6.9E-9

< l.2E-8

< 8.7E-9 U-238

< 8.4E-9

< 8.lE-9

< 1.2E-8

< l.4E-8 Pu-238

< l.1E-7

< l.2E-8

<-1.2E-8

< l.lE-8 Pu-239/240 < 3.7E-8

< 1.3E-8

< 1.4E-8

< l.2E-8 Am-241

< 4.6E-8

< 1.2E-8

< l.2E-8

< 1.lE-8 Cm-242

< l.lE-7

< 8.6E-8

< 6.3E-3

< 6.1E-8 Cm-243/244 < 2.0E-8

< l.0E-8

< 1.1E-8

< 8.6E-9 l

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