ML20217Q206

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Forwards Semi-Annual Radioactive Effluent Release Rept from July-Dec 1997 & Rev 3 to Process Control Program Manual
ML20217Q206
Person / Time
Site: Nine Mile Point 
Issue date: 03/02/1998
From: Conway J
NIAGARA MOHAWK POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17059B911 List:
References
NMP1L-1295, NUDOCS 9803120050
Download: ML20217Q206 (2)


Text

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NIAGARA MOHAWK G E N E R ATIO N NINE MILE POINT NUCLEAR STATION / LAKE ROAD, P.O. BOX 63. LYCOMING, NEW FORK 13093/ TELEPHONE (315) 3444213 BUSINESS GROUP FAX (315)349 2605 JOHN T. CONWAY March 2,1998 NEn%9 NMPIL 1295 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE:

Nine Mile Point Unit 1 Docket No. 50-220 DPR-63

Subject:

July - December 1997 Semi-Annual Radioactive F/ fluent Release Report Gentlemen:

In conformance with the Nine Mile Point Unit 1 (NMP1) Technical Specifications, we are enclosing the Semi-Annual Radioactive Effluent Release Report for the reporting period July -

December 1997. Included in this report is a summary of gaseous, liquid, and solid effluents released from the station duAg the reporting period (Attachments 1 - 6), a summary of revisions to the Offsite Dose. mculation Manual and the Process Control Program during the reporting period (Attachments 7 and 8), and an explanation as to the cause and corrective actions regarding the inoperability of any station liquid and/or gaseous effluent monitoring instrumentation (Attachment 9). Attachments 10 and 11 provide a summary and assessment of radiation doses to members of the public within and outside the site boundary, respectively, from liquid and gaseous effluents as well as direct radiation in accordance with 40CFR190.

The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21, Revision 1. Dose assessments were made in accordance with the NMP1 Offsite Dose Calculation Manual. Distribution is in accordance with Regulatory Guide 10.1, 10CFR50.4(b)(1) and the Technical Specifications.

< 2 to this report is an update of Emergency Condenser Vent data for the period March 1996 through June 1997, and actual data for the second quarter 1997 elevated releases i

used in the January - June 1997 Semi-Annual Radioactive Effluent Release Report.

i yLj 3 is a copy of Revision 3 of the Process Control Program Manual.

)

During the reporting period from July - December 1997, NMP1 did not exceed any 10CFR20, 10CFR50, or Technical Specification limits for gaseous effluents. There were no normal liquid effluent releases during the reporting period from NMP1. There was a liquid release 9903120050 900302 DR ADOCK 0500 2 0 l

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Page 2 from NMP1 associated with the post maintenance testing of the Emergency Condensers (EC's) following the replacement of EC tube bundles.

If you have any questions concerning the attached report, please contact Mr. Anthony M.

Salvagno, (315) 349-1456 or Mr. Timothy M. Kurtz, (315) 349-7666, Fuels and Analysis, Nine Mile Point.

Very truly yours, l-John T. Conway Vice President - Nuclear Engineering JTC/AMS/Imc Attachments xc:

Mr. H. J. Miller, Regional Administrator, Region I Mr. S. S. Bajwa, Director, Project Directorate I-1, NRR Mr. B. S. Norris, Senior Resident Inspector Mr. D. S. Hood, Senior Project Manager, NRR Records Management

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