ML19343A781
| ML19343A781 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/13/1980 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8011210398 | |
| Download: ML19343A781 (3) | |
Text
Alabama Power Company 600 Nortn 18tn Street Post Omco Box 2641 Birmingham. Alabama 35291 Telephone 205 250-1000 m
F. L CLAYTON, JR.
Senior Vice President Alabama Power the sournem electnc system November 13, 1980 Docket Nos. 50-348 II r
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Mr. S. Varga, Director y
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U. S. Nuclear Regulatory Conmission u
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Phillips Building 7920 florfolk Avenue Washington, D. C.
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Dear Mr. Varga:
Re: Verbal Questions on Farley Nuclear Plant Unit 1
" Semi-Annual Radioactive Effluent Release Report" January 1,1980 throuch June 30, 1980 Members of the NRC Staff verbally requested further infonnation concerning data included in the referenced Farley Nuclear Plant Unit 1 Semi-Annual Radioactive Effluent Release Report. Attached is the requested infonnation.
If there are further questions, please contact us.
Very truly yours, B %0 j Q
as A, F. L. Clayto, Jr. y WMJ:de Attachment cc: Mr. R. A. Thomas
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Mr. G. F. Trowbridge
/f007 Mr. E. A. Reeves y
Mr. W. H. Bradford Mr. C. Patel
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801121039T j(
Questions on Farley " Semi-Annual Radioactive Effluent Release Report," January -1,1980 through June 30, 1980 NRC Question What is the source of the argon-41 shown in Table IB and 1C for the continuous release mode? What corrective action will be taken to minimize future releases of argon-417
Response
Investigation of the source of the argon-41 indicates that activation of stable argon used to operate the Unit 1 post-accident sampling system (schematic attached) was the source. During the first quarter of 1980 the system underwent extensive testing and was placed into routine operation for taking three primary coolant samples per week.
It has been determined that during startup and testing of the post-accident sampling system approximately one bottle of argon (33 liters at 2200 psia pressure) leaked into the reactor coolant sample line.
During this period of time minor leakage was encountered from two level control valves on the excess letdown system which provided a path for escape of argon-41 to the vent stack.
During the first quarter of 1980 both the inieakage of stable argon and the valve leakage were corrected, resulting in a substantial reduction of argon-41 released during the second quarter.
The leakage of argon into the primary coolant system was the result of a procedural deficiency of not requiring backup isolation valves to be closed when the system was not in use.
Alabana Power will develop procedure changes to minimize the release of argon-41 to the environment. To verify that the procedure changes reduce the argon-41 leakage, fo'ur months of full power operation is required due to the small leakage rates. The above actions will be completed for Unit 1 following startup from the refueling outage. The Unit i refueling outage is scheduled to end in early January,1981.
The above actions will be completed for Unit 2 after four months of full power operation.
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