ML20212H249

Errata,Consisting of Missing Pages 5 & 6,to 1985 Annual Operating Rept

ML20212H249
Person / Time
Site:	Byron
Issue date:	12/31/1985
From:	Ponzio M COMMONWEALTH EDISON CO.
To:	Oestmann M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 8703060051
Download: ML20212H249 (3)

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Concentrations of Particulates in Air F ' Concentration contours of radioactive airborne particulates are t 'shown.in Figure 3.1-4. The maximum off-site average level is estimated to be 6.29E-06 pCi/m3, Summ ry of Doses 1 Table 3.1-1 summarizes the doses resulting from releases of airborne 1  ; radioactivity via the different exposure pathways.

p 1 3.2 Liquid Effluent Pathways The three principal pathways through the aquatic environment for potential doses to man from liquid waste are ingestion of potable water, eating . aquatic foods, and exposure while . walking on the shoreline. Not all of these pathways are applicable at a given time or station but , a reasonable approximation of the dose can be made by adjusting the dose formula for season of the ye r or type and degree 'of use of the aquatic environment. NRC* developed equations were used to calculate the doses to the whole body, lower GI tract, thyroid, bone and skin; specific parameters for.use in the equations are.given in the Commonwealth Edison Off-site Dose Calcu-t lation Manual. The maximum whole body dose for the year was 2.48E-01 mrem and no organ dose exceeded 3.54E-01 mram.

4.0 ~ SITE METEOROLOGY A summary of the site meteorological measurements taken during each J quarter of the year is given in Appendix II. The data are presented as 4

cumulative joint frequency distributions of 250' level wind direction and wind speed class by atmospheric stability class determined from - the temperature difference between the 250' and 30' levels.

Data recovery for these measurements was about 99.1%.

5.0. ENVIRONMENTAL MONITORING f

' Tables 5.0-1 and 5.0-2 provide an outline of the radiological environ-mental monitoring program as required in the Technical Specifications.

Except for tables of special interest, tables listing all data are no

,. longer included in the annual report. All data tables are available for

.. . inspection at the Station or in the Corporate offices, k

p Specific findings for various environmental media are discussed below.

• Nuclear Regulatory Commission, Regulatory Guide 1.109 (Rev. 1).

8703060051 861231 PDR ADOCK 05000454 5

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5.1 Gamma Radiation l I

External radiation dose from on-site sources and noble gases re- /

leased to the atmosphere was measured at nine indicator and three reference (background) locations using solid lithium fluoride .

thermoluminescent dosimeters (TLD). A comparison of the TLD results -

for reference stations with on-site and off-site indicator stations is included in Table 5.1-1. Additional TLDs, a total of 64 were installed on September 28, 1981 such that each sector was covered at both five miles and the site boundary.

5.2 Airborne I-131 and Particulate Radicactivity Concentrations of airborne I-131 and particulate radioactivity at 4 monitoring locations are summarized in Tables 5.0-2 through 5.0-5. '

Locations of the samplers are shown in Figure 5.0-1. Airborne I-131 '

remained below the LLD of 0.1 pCi/m3 throughout the year.

Gross beta concentrations ranged from 0.007 to 0.085 pCi/m3 at i indicator locations and 0.011 to 0.070 pCi/m3 at control locations with an average concentration of 0.026 both at indicator and control locations. No radioactivity attributable to station operation was detected in any sample.

5.3 Terrestrial Radioactivity Precipitation samples were collected monthly from four milk sampling  ;

locations ed inalyzed for gross beta, tritium, strontium-89 and '

-90, and gamma-emitting isotopes. Except for gross beta and one Sr-90 (2st pCi/1), all other radioactivity was below the limits of detection indicating that there was no measurable amount of radio- s activity attributable to the station releases. g Annual mean gross beta concentration measured 25.6 pCi/1, which is the level expected in precipitation samples.

Vegetables were collected in August and analyzed for gross beta, strontium-89 and -90 , and gamma-emitting isotopes. In addition, green leafy vegetables were analyzed for iodine-131. Gross beta

, concentration ranged from 1.2 to 5.5 pCi/g wet weight and averaged

! 3.2 pCi/g wet weight. The range and mean values were those expected in the vegetation samples. All other isotopes were below the limits i of detection indicating that there was no measurable amount of radioactivity attributable to the station releases.

I Cattlefeed and grass samples were collected quarterly from milk i sampling locations and analyzed for gross beta, strontium-89 and -90 and gamma-emitting isotopes. Except for gross beta, the level of l radioactivity was below the detection limits. Gross beta concen-trations were at the level usually encountered in these samples. 1 6  ;

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rx )(6 N Commonwealth Edison 2* \f' '~ '772Address West Adams Street, Chicago, Illinois Rep'y to: Post Offica Box 767 V Chicago, Illinois 60690 0767 November 6, 1986 PRIORITY ROUTING First Seetnd b RA RC Ms. M. J. Oestmann fN khk U. S. Nuclear Regulatory Commission MS ML 799 Roosevelt Road '4 i*BS E-b-

Glen Ellyn, IL 60137 Sk.-

FILE. f h

Subject:

Byron Nuclear Station Docket 50-454 Annual Operating Report

Dear Ms. Oestmann:

Enclosed are the missing pages from Byron Nuclear Station Annual Operating Report as you requested. Sorry for any inconvenience this may have caused you. If I can be of any further assistance, please do not hesitate to call.

%Ak M. E. Di Ponzio u

cc: EPG-06-RE-RADc I e \

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