ML20072T139: Difference between revisions

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Northern States Power Company Prairie Island Nuclear Generating Plant
Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch, Minnesota 55089 l
!                                                                      1717 Wakonade Dr. East Welch, Minnesota 55089 l
August 25, 1994 Technical Specification 6.7.A.4 i
!        August 25, 1994                                             Technical Specification 6.7.A.4 i
i US Nuclear Regulatory Commission i
i US Nuclear Regulatory Commission i         Attn: Document Control Desk j         Washington, DC 20555 l
Attn: Document Control Desk j
l l
Washington, DC 20555 l
I l                                PRAIRIE ISLAND NUCLEAR GENERATING PUJIT Docket Nos. 50-282 License Nos. DPR-42 50-306               DPR-60 Effluent and Waste Disposal Semi-Annual Report for January throup.h June 1994 l
I l
In accordance with the Prairie Island Technical Specifications, Appendix A to i         Operating Licenses DPR-42 and DPR-60, we are submitting one copy of the Effluent and Waste Disposal Semi-Annual Report for the first half of 1994.
PRAIRIE ISLAND NUCLEAR GENERATING PUJIT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Effluent and Waste Disposal Semi-Annual Report for January throup.h June 1994 l
In accordance with the Prairie Island Technical Specifications, Appendix A to i
Operating Licenses DPR-42 and DPR-60, we are submitting one copy of the Effluent and Waste Disposal Semi-Annual Report for the first half of 1994.
The report is completed with the exception of the Sr-89, Sr-90, and Fe-55 composite values which are reported using default values in accordance with our Offsite Dose Calculations Manual. An amended report with the actual composite results will be forwarded with the next semi-annual report.
The report is completed with the exception of the Sr-89, Sr-90, and Fe-55 composite values which are reported using default values in accordance with our Offsite Dose Calculations Manual. An amended report with the actual composite results will be forwarded with the next semi-annual report.
Also attached is the revised semi-annual report for the second semi , annual period of 1993. This revision includes the actual composite results for Sr-89, Sr-90, and Fe-55.
Also attached is the revised semi-annual report for the second semi, annual period of 1993. This revision includes the actual composite results for Sr-89, Sr-90, and Fe-55.
The Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP)
The Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP)
Manual are not attached since they remained unchanged during the reporting period.
Manual are not attached since they remained unchanged during the reporting period.
This letter contains no new NRC commitments, nor does it modify any prior commitments.
This letter contains no new NRC commitments, nor does it modify any prior commitments.
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annual.efi 9409150087 DR          940825                                                           /     l I
annual.efi 9409150087 940825
ADOCK 05000282 PDR
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DR ADOCK 05000282 PDR


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USNRC l         August 25, 1994 Page 2 i
USNRC l
August 25, 1994 Page 2 i
l Please contact Gene Eckholt (612-388-1121, Ext, 4663) if you require further information.
l Please contact Gene Eckholt (612-388-1121, Ext, 4663) if you require further information.
ddett.
ddett.
Roger O Anderson Director l         Licensing and Management Issues c:       Regional Administrator - III, NRC NRR Project Manager, NRC Sr Resident Inspector, NRC State of Minnesota Attn: Rris Sanda J Silberg Attachment A           Effluent and Waste Disposal Semiannual Report, Period Jan-Jun 1994 (8 pages) l         Attachment B           Effluent and Waste Disposal Semiannual Report, Period Jul-Dec 1993, Supplemental Report (8 pages)
Roger O Anderson Director l
Attachment C           Off-Site Radiation Dose Assessment for January 1 - July 1, 1994 (7 pages) l l
Licensing and Management Issues c:
Regional Administrator - III, NRC NRR Project Manager, NRC Sr Resident Inspector, NRC State of Minnesota Attn: Rris Sanda J Silberg Attachment A Effluent and Waste Disposal Semiannual Report, Period Jan-Jun 1994 (8 pages) l Attachment B Effluent and Waste Disposal Semiannual Report, Period Jul-Dec 1993, Supplemental Report (8 pages)
Attachment C Off-Site Radiation Dose Assessment for January 1 - July 1, 1994 (7 pages) l l
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Attachment A Effluent and Waste Disposal Semiannual Report Period Jan-Jun 1994 L
Attachment A Effluent and Waste Disposal Semiannual Report Period Jan-Jun 1994 L
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Latest revision as of 04:18, 15 December 2024

Forwards Effluent Semiannual Rept 940103-0703, Rev 0 & Rev 5 to Effluent & Waste Disposal Semiannual Rept Solid Waste & Irradiated Fuel Shipments
ML20072T139
Person / Time
Site: Prairie Island  
Issue date: 08/25/1994
From: Richard Anderson
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20072T141 List:
References
NUDOCS 9409150087
Download: ML20072T139 (3)
v • d • e


Text

i i

Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch, Minnesota 55089 l

August 25, 1994 Technical Specification 6.7.A.4 i

i US Nuclear Regulatory Commission i

Attn: Document Control Desk j

Washington, DC 20555 l

I l

PRAIRIE ISLAND NUCLEAR GENERATING PUJIT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Effluent and Waste Disposal Semi-Annual Report for January throup.h June 1994 l

In accordance with the Prairie Island Technical Specifications, Appendix A to i

Operating Licenses DPR-42 and DPR-60, we are submitting one copy of the Effluent and Waste Disposal Semi-Annual Report for the first half of 1994.

The report is completed with the exception of the Sr-89, Sr-90, and Fe-55 composite values which are reported using default values in accordance with our Offsite Dose Calculations Manual. An amended report with the actual composite results will be forwarded with the next semi-annual report.

Also attached is the revised semi-annual report for the second semi, annual period of 1993. This revision includes the actual composite results for Sr-89, Sr-90, and Fe-55.

The Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP)

Manual are not attached since they remained unchanged during the reporting period.

This letter contains no new NRC commitments, nor does it modify any prior commitments.

L*

annual.efi 9409150087 940825

/

l I

DR ADOCK 05000282 PDR

l f

t 9

USNRC l

August 25, 1994 Page 2 i

l Please contact Gene Eckholt (612-388-1121, Ext, 4663) if you require further information.

ddett.

Roger O Anderson Director l

Licensing and Management Issues c:

Regional Administrator - III, NRC NRR Project Manager, NRC Sr Resident Inspector, NRC State of Minnesota Attn: Rris Sanda J Silberg Attachment A Effluent and Waste Disposal Semiannual Report, Period Jan-Jun 1994 (8 pages) l Attachment B Effluent and Waste Disposal Semiannual Report, Period Jul-Dec 1993, Supplemental Report (8 pages)

Attachment C Off-Site Radiation Dose Assessment for January 1 - July 1, 1994 (7 pages) l l

l l

l annual. eft

I l

l l

Attachment A Effluent and Waste Disposal Semiannual Report Period Jan-Jun 1994 L

i t

r l

t t

I armual. efi w

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