ML19305E484
| ML19305E484 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/05/1980 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-80-03, IEB-80-3, NUDOCS 8005120520 | |
| Download: ML19305E484 (2) | |
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80051205.70 g O
POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NO. 3 NUCLEAR POWER PLANT P. O. BOX 215 BUCHANAN,N.Y.1o511 TELEPHONE 914 73942oo O
March 5, 1980 IP-RH-8184 Docket No. 50-286 License No. DPR-64 Director, Nuclear Regulatory Commission Office of Inspection & Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406
Subject:
I. E.Bulletin 80-03, Loss of Charcoal from Standard Type II, 2 Inch, Tray Absorber Cells
Dear Mr. Grier:
The following is in response to I. E. Bulletin No. 80-3.
Carbon cells used at our facility are manufactured by Mine Safety Appliances Company of Evans City, Pennsylvania. There are two types of carbon filters used, the Sure-Sorber and the flat bed carbon cells.
The Sure-Sorber cells are a pleated-bed activated charcoal cell constructed of perforated 26 gauge stainless steel, the casing is constructed of 14 gauge stainless steel with stiffeners.
Some spot welding is used in construction of the bed section and casing, nominal spacing of spot welds is 1 inch.
The casing is also bolted, using 1/4 inch stainless steel bolts, nuts and washers, maximum spacing is 2 3/4 inches.
The flat bed cell is constructed of 12 and 16 gauge stainless steel to form the framing and 20 gauge perforated stainless steel to enclose the carbon absorbent.
These components are spot welded together, nominal spot weld spacing is 1 inch.
These construction details were obtained by visual inspection of replacement units and indicates that they have no potential for leakage of the charcoal absorbent.
The Sure-Sorber cells are used in the Control Room and Post Accident Containment Ventilation Systems.
The flat bed cells are used in the Fuel Storage Building Ventilation and the Containment Cooling and Filtration systems.
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Letter to Director, Page Two March 5, 1980 Nuclear Regulatory IP-RH-8184 Commission 1
i Periodic surveillance tests are performed on these filtration systems in accordance with ANSI N510-1975 and consist of a visual inspection and an in-place leak test using a refrigerant tracer to determine absorber effi-ciency. Surveillance tests were last completed on mil cells on December 20, 1979, all tests were completed. satisfactorily, assuring cell integrity.
Visual inspections were also performed on normal ventilation exhaust filtration systems, these inspections revealed no degradation of the char-coal cells dua to leakage thus ensuring cell integrity.
Exhaust filtration systems insr2cted were Containment Building and Primary Auxiliary Building ventilatior exhaust systems and the Containment Pressure Relief System.
These filtration systems are manufactured by CVI Corporation of Colum us, b
l Ohio design A996-5900 and A996-5908 respectively.
l Very truly yours, 1
).
J j.P.Bayne 6
~
Resident Manager l
RH/jd cc: Director, Division of Fuel Facility and Materials Safety Inspection Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.
20555 1
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