ML19330A844
| ML19330A844 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/24/1980 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8007290637 | |
| Download: ML19330A844 (5) | |
Text
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Alabama Power Company 600 North 12h Street Post Office Box 2641 Birmingham, Alabama 35291 Telephone 205 323-5341 L
3e;;o We7 ";ff,n, Alabama Power
'C July 24, 1980 Docket No. 50-364 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Att0ntion: Mit A. Schwencer JOSEPH M. FARLEY NUCLEAR PLAN 1 - UNIT 2 TMI-2 ACTION PLAN i
Gentlemen:
In accordance with Mr. Tedesco's letter dated July 16, 1980, and telephone conversations of July 22-23, 1980, with the NRC staff, Alabama Power Company submits the attached information concerning the TMI-2 Action Plan for Farley Nuclear Plant - Unit 2.
If you have any questions, please advise.
Yours very truly, O f 0i.AIG f
L. Clayton, Jr.
FLCj r/RWS:rt Attachment cc: Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. L. L. Kintner Mr. W. H. Bradford 8i 800729063 7
Question on II.F.1.a.
Describe the interim procedures and methods for quantifying high level accidental radioactivity reieeses for noble gas, particulate and radioactive effluents.
(1) Plant Vent Stack To measure high level accidental noble gas radioactive effluent release from the Unit 2 plant vent stack, Alabama Power Company will mount an ion-chamber perpendicular to the effluent line leading to RE-21 & 22 (plant vent stack monitor) which is an isokinetic sample line from the plant vent stack. This detector will be shielded to reduce background interference and will be sealed in a weather tight container to protect it from the o
elements. A shielded 6-conductor signal cable will be field routed from the detector to a remote readout meter which wil1~
be located in the southeast corner of the control room ventilation equipment room on t6 auxiliary building roof. Once initiated, following offscale readings on permanent vent stack monitors, the readout will be continuous and the values will be verbally trans-mitted at least every 15 minutes to the control room via any one of the three existing communications systems:
(1) plant phone system; (2) sound powered phone system; (3) plant public address system. The monitor, a Jordan Rad Gun, is battery powered with greater than 30 day battery life. The monitor has a range of 0.01 mR/hr to 10,000 R/hr over an energy range of 80 KEV to 1.2 MEV. Calibration will be done at installation and annually using l37 a Cs source. Predetermined calculational methods will be used to convert the radiation level readings to radi'o' active effluent
O release rate (i.e. pCi/sec.). procedures have been developed for operation of the system and provide calculational methods to detennine release rates.
Conversion tables are included in the procedures. Occupational exposures are minimized by remotizing the readout so that the technician is not in the radiation field.
l (2) liain Condenser Air Ejector It is highly improbable that this monitor (RE-15) will go offscale for any anticipated accider.c. flevertheless, a procedure has been developed whereby, in the event that the monitor goes offscale, the main condenser air ejector will be monitored with a portable gamma survey instrument and, by means of a mR/hr vs. pCi/ml conversion f
table, prompt determination of release rates may be obtained'.' The procedure provides a designated location on the discharge line of each main condenser air ejector where a technician will measure the dose rate. By taking a discharge flow rate measurement on an installed manometer, the current and/or total release to the en-vironment may be quickly ascertained. These release rates will be calculated every 15 minutes or as often as required by the emergency director. The technician will be removed from all primary coolant sources and the time in the secondary source fields will be minimized by procedure to minimize occupational exposure.
(3) Atmospheric Steam Relief Valves procedures have been written to provide locations for taking contact dose rate measurements with a portable survey instrument on each of
the three (Unit 2)' steam lines down stream of the atmospheric steam relief valves. The dose rates are to be converted using tables provided in the procedure to obtain pCi/ml. A flow rate will be obtained using a correlation between steam pressure and relief valve flow rate. With pCi/ml and the flow rate known, a release rate to the environment can be quickly determined. These release rates will be calculated every 15 minutes or as often as required by the emergency director. The technician will be removed from all primary coolant-sources and the time in the secondary source fields will be_ minimized by procedure to minimize occupational exposure.
l (4) Particulates and Iodines I
Vent stack monitor RE-21 & 22 has been modified to permit thE collection of particulate filters and silver zeolite cartridges which will be analyzed using a Ge(Li) gamma ray spectroscopy system.
This modification provides adequate shielding for the collection of a-representative particulate and iodine sample of very small volume q
l
'thereby assuring that the technician collecting the sample will
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1 receive minimum exposure and that the analytical detector will not i
i be saturated. The silver zeolite cartridge may also be purged with 1
nitrogen if necessary to sweep out any noble gases which could mask the radio-iodines.
Procedures to operate this system have been
' developed and provide calculational methods to determine release
. rates.
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Q.
Question on IIID.3.3 What location will be utilized as the low background counting facility to analyze radiciodine samples?
Response: Farley fluclear Plant will have two counting rooms (One per unit).
In the event of an accidant, it is anticipated that the background radioactivity level in the non-affected unit's counting room will be low enough to perform the above measurements.
However, if the background radioactivity level is too high in the non-affected unit the necessary measuring equipment will be relocated within one hour to the water treatment plant or to the
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emergency operations facility upon its completion."
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