ML20196E600
| ML20196E600 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 02/26/1988 |
| From: | Fey F NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20196E604 | List: |
| References | |
| NUDOCS 8803010190 | |
| Download: ML20196E600 (2) | |
Text
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TRANSMITTAL MANIFEST NORTHERN STATES POWER COMPANY NUCLEAR GENERATION DEPARTMENT PRAIRIE ISLAND h0 CLEAR GENERATING PLAN 2 Effluent and Waste Disposal Semiannual Report fpr July 1.
1987 throuch December 31, 1987 Manifest Date:
February 26, 1988 USNRC 4
ANI Library 1
Regional Admin-III FPSI 3
NRR Project Manager C E Agan DCD.
A A Garrow
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Resident Inspector Corporate Library L R Eliason 1
NUS 1
G T Goering/G H Nails 1
S D Weerakkody S D Northard 1
Shaw Pittman Potts &
P H Kamman 1
Trowbridge 1
Prairie Island Plant Manager 10 G Charnoff Monticello Plant Manager 1
Westinghouse Electric 2
ERAD Dept.
1 W J Johnson Attn: Records Clerk R T Meyer Media Services Dept.
1 Safety Audit Committee 9
NRS File 1
D M Musolf NSS File 1
K J Albracht MDH 1
C W Giesler Attn: Commissioner of Health F W Hartley MPCA 1
H S Isbin Attn: J W Ferman J A Thie F P Tierney 8803010190 871231 b
PDR ADOCK 05000202 Secretary R
PDR File (Manifest only)
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s Northem States Power Company 414 N. collet Mat Mnneapons unnesota $5401 Tee' phone (612)330 5500 February 26, 1988 Prairie Island Technical Specification TS6.7A 5 & 6 U S Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Prairie Island Nuclear Generating Plant Docket No. 50-282 License No. DPR-42 50-306 DPR-60 Effluent and Waste Cisposal Semiannual Report for July 1.
1987 throuch December 31, 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 tha Effluent and Waste Disposal Semiannual Report, covering the second half of 1987.
Analyses for isotopes Sr-89 and Sr-90 were not completed for the 4th quarter in time to be included with this report.
These analysis results are not expected to significantly change the computed offsite doses, and will be included with the next semiannual report.
Enclostd with this report is an amendment to the Effluent and Waste Disposal Semiannual Report for the first half of 1987, which did not include the results of analyses for Sr-89 and Sr-90.
During this period, Revision 1 of the Process Control Program was placed into effect.
A copy of the changes is attached for NRC Staff review in accordance with the Prairie Island Technical Specifications.
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F.
L.
Fey, Jr., General Superintendent Radiological Protection and Chemistry Attachment
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