ML20238A812: Difference between revisions
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{{#Wiki_filter:y Northern States Power Company 414 Nicol.et Mall Minneapolis, Minnesota 55401 Telephone (612) 330 5500 August 28, 1987 | {{#Wiki_filter:y Northern States Power Company 414 Nicol.et Mall Minneapolis, Minnesota 55401 Telephone (612) 330 5500 August 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 January 1, 1987 through June 30, 1987 In accordance with the Prairie Island Technical Specifications, Appendix A to Operating License DPR-42 and DPR-60, we are submitting one copy of the Effluent and Waste Disposal Semi-Annual Report, covering the first half of 1987. | ||
Effluent and Waste Disposal Semi-Annual Report for January 1, 1987 through June 30, 1987 In accordance with the Prairie Island Technical Specifications, Appendix A to Operating License DPR-42 and DPR-60, we are submitting one copy of the | j i | ||
Effluent and Waste Disposal Semi-Annual Report, covering the first half of | Analyses for isotopes Sr-89, Sr-90 and Fe-55 were not completed for Quarter l | ||
Analyses for isotopes Sr-89, Sr-90 and Fe-55 were not completed for Quarter | 2 in time to be included in this report. These analyses results are not expected to significantly change the reported doses and will be included j | ||
Also enclosed, is an amendment to the Effluent and Waste Disposal Semi-Annual | with the next Semi-Annual Effluent Report. | ||
F. L.. Fey, Jr., General Superintendent Radiological Protection and Chemistry Attachments cc: Project Manager, USNRC | Enclosed with this submittal is Revision 9 of the Offsite Dose Calculation Manual (0DCM). Changes are designated with sidelines. | ||
MPCA - Attn: J. W. Ferman NRS File gdw gaa0228870828 R | Also enclosed, is an amendment to the Effluent and Waste Disposal Semi-Annual Report for the second half of 1986, which did not include the results of analyses for Fe-55, Sr-89 and Sr-90. | ||
R-2 LETTER L | F. L.. Fey, Jr., General Superintendent Radiological Protection and Chemistry Attachments cc: Project Manager, USNRC 1 | ||
Resident Inspector - Prairie Island G.Charnoff(w/ attachments) | |||
MPCA - Attn: J. W. Ferman NRS File gdw gaa0228870828 R | |||
DOCK 05000282 h | |||
PDR | |||
\\\\ | |||
R-2 LETTER L | |||
J}} | |||
Latest revision as of 06:00, 2 December 2024
| ML20238A812 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/28/1987 |
| From: | Fey F NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20238A816 | List: |
| References | |
| NUDOCS 8708310228 | |
| Download: ML20238A812 (1) | |
Text
y Northern States Power Company 414 Nicol.et Mall Minneapolis, Minnesota 55401 Telephone (612) 330 5500 August 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 January 1, 1987 through June 30, 1987 In accordance with the Prairie Island Technical Specifications, Appendix A to Operating License DPR-42 and DPR-60, we are submitting one copy of the Effluent and Waste Disposal Semi-Annual Report, covering the first half of 1987.
j i
Analyses for isotopes Sr-89, Sr-90 and Fe-55 were not completed for Quarter l
2 in time to be included in this report. These analyses results are not expected to significantly change the reported doses and will be included j
with the next Semi-Annual Effluent Report.
Enclosed with this submittal is Revision 9 of the Offsite Dose Calculation Manual (0DCM). Changes are designated with sidelines.
Also enclosed, is an amendment to the Effluent and Waste Disposal Semi-Annual Report for the second half of 1986, which did not include the results of analyses for Fe-55, Sr-89 and Sr-90.
F. L.. Fey, Jr., General Superintendent Radiological Protection and Chemistry Attachments cc: Project Manager, USNRC 1
Resident Inspector - Prairie Island G.Charnoff(w/ attachments)
MPCA - Attn: J. W. Ferman NRS File gdw gaa0228870828 R
DOCK 05000282 h
\\\\
R-2 LETTER L
J