ML20211R044

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Forwards Effluent & Waste Disposal Semiannual Rept,Jul-Dec 1986 & Rev 8 to Prairie Island Nuclear Generating Plan Offsite Dose Calculation Manual. Analyses for Sr-89,Sr-90 & Fe-55 Not Completed in Time to Be Included in Rept
ML20211R044
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 02/28/1987
From: Fey F
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20211R050 List:
References
NUDOCS 8703030247
Download: ML20211R044 (1)


Text

eff Northem States Power Company 414 Nicollet Mall Minneapohs, Minnesota 55401 Telephone (612) 330 5500 February 28, 1987 Prairie Island Technical Specification TS6.7A 5 & 6 U S Nuclear Regulatory Commission Attention: Document Control Desk Washington, D C 20555 Prairie Island Nuclear Generating Plant Docket No. 50-282 License No. DPR-42 50-306 DPR-60 Effluent and Waste Disposal Semi-Annual Report for July 1,1986 through December 31, 1986 In accordance with the Prairie Island Technical Specifications, Appendix A to Operating License DPR-42 and DPR-60, we are submitting one copy cf the Effluent and Waste Disposal Semi-Annual Report, covering the last half of 1986.

Analyses for Isotopes Sr-89, Sr-90 and Fe55 were not completed for Quarter 4 in time to be included in this report. These analyses results are not expected to significantly change the reported doses and will be included with the next Semi-Annual Effluent Report.

Also attached to this submittal is Revision 8 of the Offsite Dose Calculation Manual (0DCM). This revision was completely retyped with all changes noted by sidelining.

F. L. Fey, Jr., General Superintendent Radiological Protection and Chemistry Attachment cc:

Project Manager, USNRC Resident Inspector - Prairie Island G. Charnoff (w/o attachment)

MPCA -

Attn: J W Ferman Bert Clark File:

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