ML20214V658

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Forwards Effluent & Waste Disposal Semiannual Rept,First Half 1986. Quarterly Radiation Dose Assessments Included. Continuous Samples of Process Vent,Containment Vent & Auxiliary Bldg Vent Exhaust Incomplete Due to Planned Maint
ML20214V658
Person / Time
Site: Beaver Valley
Issue date: 08/22/1985
From: Carey J
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20214V660 List:
References
NUDOCS 8612090775
Download: ML20214V658 (3)


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A Telephone (412) 393-6000 Nuclear Group P.O. Box 4 Shippingport, PA 15077-0004 United States Nuclear Regulatory Commission Director of Inspection an. Enforcement Region I 631 Park Avenue King of Prussia, PA 19406

Reference:

Beaver Valley Power Station Unit No. 1 Docket No. 50-334, License No. DPR-66 Semi-Annual Radioactive Effluent Release Report for the First Six Months of 1985 Gentlemen Under the Beaver Valley Power Station Unit No. 1 License DPR-66, and in accordance with the requirements of Specifications 6.9.1.12 and 6.9.1.13 of the Technical Specifications, the Semi-Annual Radioactive Effluent Release Report is hereby submitted. This report has been prepared in accordance with USNRC Regulatory Guide 1.21, Revision 1, and the format presented in Appendix B of that guide.

The applicable quarterly radiation dose assessments are submitted in this report as Table 5.

They were performed for all Liquid and Gaseous Effluents that were released from Beaver Valley Power Station Unit No. 1.

All doses listed in this Table were calculated in accordance with the Offsite Dose Calculation Manual at the identified receptor locations.

Documentation of the Effluent Monitoring Instrumentation Channels not returned to operable status within 30 days (during the report period) is provided as Table 6.

This table includes the information required by Action Statement b. of Technical Specification 3.3.3.9 and 3.3.3.10.

Technical Specification Tabic 4.11-2 (Radioactive Gaseous Waste Sampling and Analysis Program) requires continuous sample collection of the Process Vent, the Containment Vent, and the Auxiliary Building Vent Exhaust. The electrical supply to the monitors (SA-9/10 monitors VS-111, VS-112, CW-110 and SPING monitors VS-109, VS-110, and CW-109) used for continuous sample collection on these three pathways was interrupted for five hours (1700-2200) on May 23, 1985. This planned electrical maintenance evolution resulted in no continuous sample collection during the five hour period.

Please note that although no continuous samples r

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Benysr Voll2y Prwer Stetien, Unit Ns. 1 Docket No. 50-334, License No. DPR-66 Page 2 were collected during the five hour period, there were gas and particulate monitors operating on each of these pathways (VS-101 A & B, VS-107 A & B, and GW-108 A & B).

The recorders for each of these monitors showed no menoimal conditions greater than background for the five hour period.

In accordance with reporting requirement 6.9.1.12 for Technical Specification 3.3.3.9, Table 3.3-12, Action Statement 24, the time between

. grab sample analyses exceeded 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> while the following two Gross Activity Liquid Effluent Monitors were declared inoperable. The two monitors are the Auxiliary Feed Pump Bay Drain Monitor (RM-DA-100) and the Component Cooling-Recirculation Spray Heat Exchangers River Water Monitor (RM-RW-100). All the appropriate grab samples were taken within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and subsequently analyzed for isotopic concentrations. None of these analyses indicated any isotopic concentrations greater than the lower limits of detectability (LLD), therefore, there were no safety implications to the health and safety of the public or plant personnel.

Please note that both of these monitors were recently returned to operable status.

This should eliminate any future violations of the above Action Statement.

Very truly yours,

. Ca O.S i e President, Nuclear Attachment i

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Benysr Vclley P&wer Staticn, Unit No. 1 Docket No. 50-334, License No. DPR-66 Page 3 cc:l Director of Inspection and Enforcement (2 copies)

United States Nuclear Regulatory Commission Washington, DC 20555 Document Control Desk United States Nuclear Regulatory Commission Washington, DC 20555 Dottie Sherman American Nuclear Insurers Library The Exchange Suite 245 270 Farmington Avenue Farmington, CT 06032 Thomas Cerusky Department of Environmental Resources Bureau of Radiation Protection P.O. Box 2063 Harrisburg, PA 17120

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