ML20151Q492

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Forwards Corrected Radioactive Effluent Rept for Jul-Dec 1987.Final Data for Listed Elements Included
ML20151Q492
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 04/12/1988
From: Eenigenburg E
COMMONWEALTH EDISON CO.
To: Davis A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20151G696 List:
References
0727A, 727A, 88-218, NUDOCS 8804270052
Download: ML20151Q492 (1)


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. Commonwealth Edison Dresden Nuclear Power Station PRIO;IfY E NTI V C #1 Morris. tilinois 60450 M

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EDE LTR: #88-218 Mr. A. Bert Davis Regional Administrator Directorate of Inspection and Enforcement Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137

Subject:

Dresder, Station Operating Report, NRC Dockets 50-10, 50-237, l 50-249 I l

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Dear Mr. Davis:

Enclosed is the corrected radioactive effluent report for July through December 1987 for Dresden Nuclear Power Station as outlined in the November 1986 Federal Register. The final data for Sr89 Sr90 Fe55 Tritium and gross alpha have been included in the report.

l One copy of eac.h report is provided for your use and eight copies are being distributed per the rules and regulations outlined in the November 1986 Federal Register.

Sincerely Yours, j

E. D. Eenigenb rg .)

Station Manag Dresden Nuclear Power Station EDE:JW:rg i Enclosure cc: J. Wallace I J.C. Golden File /NRC File / Numerical l

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DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 MEASUREMENTS AND AppROXIHATIONS A. Fission and activation gases: The D-1 chimney and D2/3 chimney are sampled daily via a grab sample. The D-2 and D-3 Reactor Vents are sampled weekly via a grab sample. The samples are analyzed for specific isotopes present in the release using a Ce(Li) spectrometry system. Tritium is co.'.lected via a continuous sample on the D-2/3 chimney and via a grab sample on the D2/3 Reactor Vent and analyzed using a Ligeld Scintillation Counter. Kr-85 is estimated in the D2/3 chimney using a recoil or non-recoil calculation using fission /sec.

plot and the sum of Xe-138. Kr-87. Kr-88 Kr-85m, Xe-133 and Xe-135 activities.

B. Iodine and particulate: Iodine and particulate samples from the D-1 and D2/3 Chimney and the D-2 and D-3 Reactor Vents are collected for a seven day period. These samples are analyzed for specific nuclides present in the release using a Ce(Li) spectrometry system. When particulate samples are not used for reporting the release rate due to management decision that the sample may not be representative, an average of the preceding sample and the following sample is used to calculate the release. A monthly composite is sent to a vendor to be analyzed for Sr-89, Sr-90, and cross Alpha activity.

C. Liquid Effluents: prior to a release duplicate grab samples are collected from each batch and analyzed for gross activity using a gas flow proportional counter. Rad-waste batch discharges are also analyzed for specific isotopes present in the release using a Ge(L1) spectrometry system. A composite of all batches for the month is sent to a vendor to be analyzed for Sr-89, Sr-90, Fe-55, and Gross Alpha. One of the LpCI samples for each month is analyzed for specific isotopes present in the releases using a ce(Li) spectrometry system. This sample is sent to a vendor to be analyzed for Sr-89, Sr-90, Fe-55, and Cross Alpha activity, l

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