ML20238A403
| ML20238A403 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 12/31/1973 |
| From: | BOSTON EDISON CO. |
| To: | |
| References | |
| NUDOCS 8708310061 | |
| Download: ML20238A403 (35) | |
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C" * ! [ g I RETS MASTER ( A P)/\ suu -73 3 PILGRIM NUCLE AR GENER ATING STATION li I i Environmental Radiation Monitoring Program 1 i l l l 1 1 SEMIANNUAL REPORT NO. 3 i JULY 1,1973 THROUGH DECEMBER 31,1973 ' DATE OF ISSUE: M ARCH 1,1974 l l l l I 1 o
, BOSTON EDISON COMPANY h[hB310061731231 R ADDCK 05000273 PDR
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I s i , l 1 CONTEbTS l l l SECTION PAGE I ABSTRACT 1 l 1 II DESCRIPTION OF MONITORING PROGRAM 2 III MOUITORING DATA AND RESULTS 2 ) i A. Air Surveillance 2 B. External Gaema Exposure Rates 11 l C. Milk 21 f I I D. Crops 21 j l E. Domestic and Recreational Uater 21 j
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F. Precipitation 21 [ G. Seawater 28 H. Marine Lif e 28 ;
- 1. Bottom Sediment 28 f IV CONCLUSIONS 33
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. 1, I ABSTRACT The operational environmental radiation surveillance program continues to be conducted in accordance with the specifications in the Pilgrim f
Stacion operating license. Reactor operation during the reporting period j averaged about 60% of full power. An administrative limit of 50% of full
- power was maintained from October 6 until the maintenance and refueling shut-I down on December 28. Effluent discharges decreased as compared to the previous semiannual period, primarily as a result of reduced plant capacity factor. i I
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'etailed D operating information, including a summary of plant releases, is reported j l 4 in a separate semiannual report entitled, " Operating and Maintenance Report." I No significant increases in environmental radiation or radioactivity i
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1 levels beyond the station property were evident in the monitoring data. I Radiation levels in areas close to the turbine building continued to show an increase over background. The increase was attributed to direct radiation
'1 from the N-16 present in the turbine steam. Two onsite visitor areas were l l
subjected to this increase. As a result, the increased radiation dose to the { 57,000-visitors over the reporting period was estimated to bc 0.25 r e-rem. Increased exposures were also calculated for transient workers, work'J 6 out-side of the security area. Two visitor area attendants e u:h received about 1,7 millirem (mrem), while a third received about 0 9 mrem. Four groundskeepers absorbed approximately one millirem each and two research workers cach received less than 0,4 mrem of increased radiation dose, over the reporting period-, l The background dose over this period was about 50 mrem. l l s
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\ , I II DESCRIPT!0N OF MOMITORING PROGRAM _
The environmental radiation and radioactivity surveillance program is being performed in accordance with the requirements specified in the l'ilgrim , Facility Operating License (DPR-35) . Letails of the program can be found in the ' previous report (1) . A summary of the' sampling media, locations, frequencies of co11cetion, and analyses is given in Tables 1 through 4. Sampling locations 1 I
-arc shown in Figures 1 and 2.
The analyses of radioactivity in environmental samples have continued to The environmental sample analysis para-- be performed by Interex Corporation. meters are given in Tabic .5. During this reporting period, results of Interex's participation in the EPA Radionuclides in Milk Crosscheck Program (Specifically analyses for I-131, Cs-137 and Es-140) were made availabic to Boston Edison Co. s The results of these analyses indicated that the accuracies associated with the Interex procedures are comparabic to the accuracies recommended by the EPA. 1 The results of the quality assurance efforts of Interex will continue.to be .] reviewed as availabic. I- d III MONITORING DATA AND RESULTS 1 1 - The results of environmental radiation and radioactivity measurements per-formed during the semiannual reporting period (July 1,1973 to December 31, 1973) are presented in Tables 6 through 16 according to sampling media and analyses performed. All sample analyses indicated to be incomplete will be reported in l. I a later report. Results for each sampling media are discussed below. A. Air Surveillance Air particulate analyzed for gross beta activity showed no signif-l icant increases over background levels. l l 1 I f (1) Pilgrim Nuclear Generating Station, Environment 1' Radiation Monitoring Program,-Seniannual Report No. 2, August 29,.1973. hi m
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s Table 1 Air Particulate and Gaseous Radiciodine Surveillance Stations i Distance and i
. Sampling Location Direction from St' lon - i Offsite Stations i j
East Weymouth (EW) 23 miles liW H Plymouth Center (PC) 4.5 miles W-WfiW llanomet Substation (i4S) 2.5 miles SE' i j Cleft Rock Area (CR) ' O.9 miles-S Onsite Stations 61 i Rocky Hill Road (ER) 0.8 miles SE Rocky Hill Road (WR) 0.3 miles W-WiiW Overlook Area (0A) 0.03 miles W Onsite Stations Not Required by Operating License Property Line (PL) 0.34 miles fiW
._ Pedestrian Bridge (PB) 0.14 miles N East Breakwater (EB) 0.35 miles ESE Warehouse (WS) 0.03 miles SSE' s
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Fr , i t , . Tabic 2-External Can Exposurc Surveillance Stations (TLD)
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Distance and Dosimeter loc'ation Direction f rom Station Offsite Stations
- East Veymouth (EW) 23 miles IN Kingston (ES) 10 miles WNW i
Sagamore (CS) 10 miles SSE-S Plymouth Airport (SA) 8 miles WSW North Plymouth (NP) 5.5 miles WfM Plymouth Center (PC) 4.5 miles W-WNW South Plymouth (SP) 3 miles WSW flanomet (MS) 2.5 miles SSE Manorret (ME) 2.5 miles SE Manomet (l:P) . 2.25 miles ESE-S Cicft Rock Area (CR) 0.9 miles S Offsite Stations !!ot Required by Operating License BayshoreDrive(BD) 0.8 miles WNW , Emerson Road (EM) 0.96 miles SSE Whitchorse Road (WH) 1.28 miles SSE Manomet Beach (Ma) 3.5 miles SSE College Pond (CP) 6.5 miles SW i I Standish Shores (SS) 5 9 miles NW Onsite Stations . Rocky Hill Road (ER) 0.8 miles SE Microwave Tower (MT) 0.38 miles S Rocky Hill Road (WR) 0.3 miles W-WNW Rocky Hill Road (B) 0.26 miles SSE Property Line (H) 0.21 miles SSW Property Line (1) 0.14 miles W ' Public Parking Area (PA) 0.07 miles N-NNE Overlook Area (0A) 0.03 miles W t Onsite Stations I;ot Required by Operating License 0.03 miles SSE
. Warchouse Property (Line (WS)(PL) 0.34 miles NW Station F) 0.25 miles IM Station (D) 0.37 miles NNW t
PedestrianBridge(PB) 0.14 miles N Station (A) 0.24 miles WSW Station (G 0.4 miles W
. Station (E 1.6 miles S Statici. (J 1.6 miles 5-SSE l
Station (K) 1.7 miles S-SSE EastBreakwater(EB) 0.35 miles ESE Station (L) 0.35 miles ESE-SE Station (C) .. 0.35 miles SE-Hall'sBog(H3) 0.35 miles SE-SSE 4 L_._____.____._____.__.___ _ _ _ _ . _ n
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l 1 I Table 3 ~ I Terrestrial and Acuatic Surveillance Stations ! l l Distance and Direction l l , Sample Type - Sample Location From Station i l i 1411k Plymouth 3.5 miles W ! Local Store (a) ... Bridgewater 20 miles W ,
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Cranberries fianomet (Bog F) 2 miles S 1 \ fianomet(BogC) 2 miles SSE I lianomet (Bog E) 2.4 miles SE tbnomet (Bog D) 2.75 miles SSE-S Crops (potatoes, cabbage, Plymouth 3.5 miles W' lettuce and hay) t:anomet 2 miles SSE l Bridgewater 20 miles.W l Precipita tion SouthPlymouth(a) 4.75 miles W j Domestic and recrea- Deep Water Pumping Station 4.75 miles W l tional water (Lout Pond Well and Littic ; i South Pond)--Plymouth Warner's Pond Pumping Station 2.75 miles SSE l (llanomet Well)--fianomet i 24 miles WNW-NW I Great Pond Pumping Station (b)] [GreatPond--SoythWeymouth
- College Pond lal 6.5 miles SW Seawater Discharge channel Onsite Cooling water intake Onsite l Priscilla teach 0.8 to 1.6 miles ESE-SE White Horse Beach 1.6 to 2.7 miles ESE-SE liarine life Marine waters in Sampling ranges from (lobster, fish, station vicinity 2.4 miles W-WNW to 1
mollusks) 2.9 miles ESE-SE Bottom sediment Arca in vicinity of discharge channel outfall
- a. Additional stations operated during reporting period although not required by operating license
- b. Control station.
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Alievet % Error Sarple Typ Analysis _ petectionLinit e 4 x 10-3 pCi/m 3 10,E00 ft 3 110 Air particulate Gross beta Cross gamma 2 x 10'3 com/m 3 (b) 10,000 f t3 110 1 pCi/M 10,800 f t 3 110 Iodine-131 1,000 ml 110 lionseline water Gross tota 1001/1 5 cpm / I ICI 4.000 ml 110
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"" ' I " ' I' 0.01 cum /gi ') 1,000 g 110 )
Cross gamma l (d) 1,000 g Cama spect..um 0.005 pCi/9 100 g fl0 l Strontium-50 . Cesium-134,-137 0.1 pCi/9 100 g 120 f 0.1 0C1/g 100 g 120 ! Manganese-54 l 0.1 pCi/9 100 g f20 Cobalt-ED , l Cobalt-00 0.1 nC1/g 100 g 120
- 0.1 pCi/g 100 g *20 Zine-05 60 pCi/l 30 g 120 Seawater Cross beta Fractional gross beta 5 pCi/1 500 ml I02 ?
'S cpm /1(c) 4,000 m1 110 c Gross gama Cama spectrum (d) 4,000 ml Tritiva. 2.5 pCi/t1 4 m1 110 0.5 pCi/1 15,000 m1 113 Strentium-90 0.05 pct /1 15,000 m1 115 Cesium-137 5 eCi/l 1,000 ml 120 Hanganese-54 Cobalt-5B 5 pCi/l 1,000 ml I20 5 pCi/1 1,000 m1 120 Cobalt-00 5 pCi/1 1,000 ml 120 l Zinc-65 lodinc-131 5 pC1/1 1,000 ml 115 Strontium-go 0.5 pC1/1 1,000 m1- 115 Hilk 1 pC1/1 1,000 m1 t15 Cesium-137 5 pCi/1 '1,000 m1 115 Carium-140 5 pCi/1 1,000 m1 115
- Iodipo-131 2 pCi/g 19 115 Bottom sediment Gross beta 0.02 cpm /g 1,000 g 110 l
Gross gama Strontiuc-go 0.005 pC1/g 100 g 120 i Cama gyposure 1-month Background exposure 210 l radiation ratetcJ 1 UR/hr
, a, provided by Intcrex Corp., 6(, Koerd Avenue, Waltham, Mass. (formerly ICf;/Tracerleb).
- b. In the counter used.1 cpm corresponds to 2.2 pCi of cesium-137.
- c. In the counter used. 1 cpm correstends to o pti of cesium-137.
- d. Sensitivity depends on the specific r.uclide and the presence of interfering nuclides.
A typicci sensitivity is 30 pCi/sampic counted.
- c. Measured with thermoluminescent dosimeter.
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These data are given in Table 6, The air particulate filters were I composited and analysed monthly for gross gamma activity (Tabic 7). Both the particulate filter and the iodine filter for each sample were j analyzed for radiciodine. No activity was found above the minimum detectabic (Table 8) . Figures 4 and 5 show air particulate radio - activity over 42 months at the control station and onsite respectively.
. B. External Gamma Exposure Rates The environmental gamma exposure rate measurements from July to December 1973 are presented in Tabic 9. The reported rates include the inherent dosimeter scif-irradiation Vhich is typically 6 to G microroentgens per hour (uR/h) . Exposure rate readings at each loc-ation have been normalized for relative self-irradiation effects to provide continuity of measurements. This normalization is lacking Whenever replacement dosimeters are used due to the loss of the ori-ginal. Such data are noted in Tabic 9.
Figures 6 and 7 show the measured exposure rates at two offsite and two onsite loct. ions, respectively. As discussed in the previous report, the operational increase in exposure at the overlook area (which is controlled by Boston Edison Co.) is due to direct radiation from ( the turbine. Since this area, as well as the shorefront area, was opened to visitors during July through November of the reporting period, an estimate is made-of dose to the public. As discussed in Appendix B of Semiannual Report No. 2, the exposure due to station operation was extimated to be approximately 12 uR/h at the overlook area and about 1.3 uR/h at che pedestrien bridge (shore-front) with the plant operating at 85% of capacity. Using this analysis and the monthly power generatien over the period of interest, exposure
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19 72 i 1973 1971 J lF lMl AlMlJ lJ j A lS j0 lt1l0 l ilI}Il 0 M[ M l A lli k J l A l S l 0 l tll 0 South Plymouth figurc 6. Offsite Gamma Exposure Rates (East Weymouth and South Plymouth).
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' I 1971 1972 O 1973 S l0 [II}i J l F l M[hlIII[ dl'Al Sl 0 l N l D 'J l F lM l A lM lJ lJ l A lS l0 lN lD Pedestrian Dridge Figurc 7. Onsite Garana Exposure Rates (Overlook Area and Pedestrian Dridge).
l l , L _ _ _ _ - __ _ _' -
i rates were determined for the visitor areas and are shown below. Plant Capacity Exposure . Rate Above Background (uR/h). Month Factor *- 7. Overlook Shorefront. July 50 5 0.5 , August 91 16 16 September - 66 8 0.8 56 6 0,6 October November 50 5 0.5 These values incorporate previous data and are statistically more reliable than the single dosimeter readings for. these months. Increased population dose to visitors at Pilgrim Station is cal-culated to be 0.25 man-rem for the 6-month period. The. calculation f assumptions are residence times of fifteen minutes at the overlook and sixty minutes at the shorefront, and an air exposure of one roentgen is l assumed equivalent to a whole body done of one rem. A summary of nonthly l doscs is shown below. Dose at Dose at Average to Overlook, Shorefront, Total Individual Month No. Visitors July 26,000 0.03 man-rem 0.01 man-rem 0.04 man-rem 1.5 x 10 crem August 25,000 0.1 0.04 0.14 5.6 x 10 -3 September 20,000 0.04 0.02 0.06 3 x 10 -3 October 3,000 0.005 0.002 0.007 2 x 10 - 1,000 0.001 0.000 0.001 1 x 10,33 November Totals 57,000 0.176 0.072 0.248 4.4 x 10 The increased doses to three men working at the visitor areas were calculated. One guard, wori<ing 50 hours per week at the shorefront, received about 0.9 trrem. Two attendants, each working 40 hours per week divided between the overlook and shorefront areas until September 30, received about 1.7 mrem. Four groundskeepers each spent 48 hours per week working at Pilgrim
- Approximate values.
^
'. *
- I Station. Assuming an increased exposure r ste of 1 uR/h, each received 0,2 mrem per month from July to' November. .The increased dose to two L research workers from the Manomet Bird Otiservatory, conducting a study around the facility, was estimated to.be 0.2 mrem and 0.4 mrem, respect-l ively over the reporting period.
1 I - C. Milk Milk continued to be' analyzed at the rate of three samples per ;
- 1 month. Sr-90 and Cs-137 were found ct backgrounds icvels, and 1-131 and Ba, La-140 were not detected (Tabic 10). Background and operational I
levels of strontium and costum in Plymouth milk are shown in Figure 8. l 1 l D. Crogs ]
)
Tabic 11 lists the results of the radionssay of crops grown in the 1 vicinity of' Pilgrim Station as well as at control sites. Also included is one campic listed es incomplete in the previous report. All radio-activity icvels were comparable to preoperational values. I E. Domestic and Recreational Water Monthly composites of weekly water samples were analyzed for radio-activity and the isotopes 11-3, Sr-90 and I-131. The results are shown in Table 12. No Icycis above background were detected, as shown in I Figuro 9 for gross beta. I F. Precipitation l One sampling station for precipitation was operated in Plymouth
. during the reporting period. The radioactivity found in the monthly precipitation samples is given in Tabic 13. Gross beta activity is the result of the rainout of particulate daughters of naturally occurring radon-222, and others.
L_________.____ _ _ _ _ _ _ _ _ _ . _. _ . . _ . _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . . _ . __ __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
.,, )
8
' Table 10 l
Radienuclide Concentrations 15 tiill: (pCi/1) Bridgewater- ) Collection Plymouth . (Bridgewater .. Local l Period (County Farm) Store. ;j Analysis (19731_ Farm) 8.9 10.9 10 11 Cs-137 July - 12 1 August 8.4 20.8 5.0 0.5 10 1 5.1 30.5 4.8 10.5 10 11 Stptember 15 12 October 8.0 0.8 4.8 20.5 6.8 to.7 17 t2 llovember 13 +1 I Ia) 6.5 l:0.6- 8.9 10.9 December 7.1-20.7 ) July 8.9 0.9 7.9 to.8 Sr-90 9.1 20.9 7.9 0.8 6.8 0.7 August 5.9 0.5 L September (b) 4.8 0.5 (b) (b) (b) October I 4 i, flovember I I 1 l I 1 1 December
<5 <5 . <5 1-131 July <5
<5 <5 August <5
<5 <5 September <5
<5 <5 October <5
<5, <5 flovenber <5
<5 <5- l December
\
<5 <5 Da/La-140 July <5
-<5
<5 <5 August <5 September <5 <5
<5 <5 October <5
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<5
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- a. I indicates incomplete analysis, value to be reported in next semiannual !
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- b. Aliquot lost; reanalysis in progress.
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_ rr r FF C PDSBR pd ei _ n e ee e RK ( LBPRB xets o t tt t (( ((((( et ey
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_ t t w t t ww wttt t tt xtt eipa - a ue u uee euee u eeaee rl m _ c og o ogg gomm o mmf mm a _ o md m mdd d moo m ooico - sc _ . L yi l r y yi i l rr
- i. y n n rl aa y nnl nn aaaaa sanm PB l
P PBB l nwiu BPMM P MMHMM o i est tl ecg _ a pt e _ r m a e ; s t ac _ p ) e nsi y b , i e _ T ( s r e e csnm1 e g e r niim _ c o e oh l a u t b CTIG p b t n a n - m b t y r t a . a a e a o o r . . . S C L H C P C abcd sy
t 9 Tabic 12 Pcdia ctivity in Dc".?rtic cnd P.ccrcation Ka_ter, Little Lout Pond Collection South fond College Pond 1,'el l Ma nre t '..'el l_ Grcat Pond tocation Da te _(1973 [ 4.6 11.0 <1. 0 <1.0 July 17 22 <l.0 <l.0 <l.0
~
Cross Cr.tc August 7 :1 2.7 11.0 3.4 1.0 1.1 :1.0 (pCi/1) 3.3 1.0 2.8 1.0 1.5 11.0 Sep tc: b:r 6.5 11.0 1.4 11.0 <1.0 <l.0 Octch.c 4.7 1.0 1.9 :1. 0 <l.0 <l.0 3.0 1.0 1.5 1.0 1.6 1.0 <1.0 Novcmicr 2.0 1.0 3.2 11.0 <l.0 Decctber 5.7 1.0
<5 9 5 9 15
<5 Gross Gant: July <5
<5 <5 16 15 16 25 August <5 <5
<a (cpa/1) <5 <5 <5 Septenber <5 <S <5
<5 Octchcr <5
<5 <5 8 15 10 5 November <5 <5
<5 <5
<5 <5 r Occcmbar '
<0.5 <0.5 <0.5 July 0.6 10.5 <0.5 <0.5 Strontius-90 < 3. 5 0.6 10.5 <0.5 (pCi/1) fxcutt e0.5 < 0. 5 <0.5 Septcmber 0.9 10.5 1.0 10.5 0.9 10.5 <0.5 0.8 20.5 <0.5 Octct:r 0.9 :0.5 0.8 10.5 1.1 10.5 1.4 10.5 1.2 20.5 1 1,av;rie r I 1.1 10.5 0.7 $0.5 i Deccceer 2.3 21 I Ib )5 I 9
<2.5 <2.5 <2.5 l
<2.5 <2.5 <2.5 Tritiur July
<2.5 <2.5 <2.5 <2.5 (pci/n)) AuEust <2.5 <2.5 <2.5 Septc.cber <2.5 <2.5 <2.5
<2.5 <2.5 <2.5 Octcher <2.5 <2.5 <2.5 l
<2.5 <2,5 <2.5
!!avaler <2.5 <2.5 <2.5 <2.5 l Deccmber <2.5 .
<5 <5
<5 <5 lodine-131 July <5
<5 <5 <5
<5 <5 (pci/1) Aucust
<5 <5 <5 <5 Septcmber <5 <5
<5 <5 <5 October <5 <5
<5 <5 Novea,ber <5 <5 <5
<5 .'5< <5 Deccaber <5
- a. I cpm corresponds to 9 pCi of cesium-137.
- b. 1 indicates incomplete analysis, value will be reported in next semiannual report.
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'Tuble 13 ,
Radioact_ivity in Preg pitation--Plymouth, llassachusetts(a) Collection Gross Beta Gross Gamma Sr-90 ll-~3 Period (1973)_ jpCi/m2) (cpm /m2) (pCi/m2)_ (nCi/n2 ) April (b) <225 <120 130 40 <330
<120 50 120 <260 llay(b) 800 1200 340 170 <120 (a ) <250 l . June (b)
July 220 60 <120 30 i20' <270 j 335 106 <120 <6 <150 j August / 1 September 280 80 <120 20 20 <360 1(c) <120 <6 <220 l October \ l l <120 I <150 l November 1 , l 1,190 r160
<120 I I December l 1
9
- a. Analysis not required by operating license,
- b. Data reported as incomplete in previous report.
- c. I indicates incomplete analysis, value to be reported in next semiannual report.
- d. Sampic lost in process.
-i 4
h
r
., > I G. Seawaty ,
Seawater unmpics are taken weekly from the intake and discharge channels and are auslyzed as monthly composites. A second weekly sample is composited for quarterly analysis. During the summer, sea- < watcr was also anmpled f r:m rececational beaches. 'Results of radio- l
- activity analyses are given in Tabic 14'. Data reported as incomplete in the last report are also included. All sampics showed either'Icss <
\
than detcetabic or background icvels of activity. l The previously reported slight increase of radiocesium in the dis.
- charge canal appears to have been due to natural variations in.back-ground Icycle. Additional analysis done over the reporting period showed a range of Icvels from 0.29 pCi/1 (August, Prisilla Ucach) to
. I 0.76 pCi/1 (November, intake channel). It is'also of internst to note j
\
that the November discharge channel sample showed 0.35 pCi/1. s 11 . Marine Life 0 1 The radionoclyses of tnarine life sampics f rom Cape Cod Bay con-4 tinued as described in the previous report. Tabic 15 shows the results .( of these analyses which indicate no ' increase over pre-operational values . I Tabic 15 also includes the data reported as incomplete in the previous report. I. Bottom Sed _iment In addition to the required cediment sampics taken from the dis- l
- charge channel outfall, sampics were also taken from recreational beaches.
in the vicinity of the station. Results of gross beta and gross gamma counting of these sampics are given .in Table 16. Radiochemical and gamma spectrum analyses were also performed and showed no nuclide activity L icvels attributable to plant operation (Tabic 16), i h
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.I Table 16 Radioactivity in Bottom Sediment i
Gross-Deta Gross Gamma
- Collection Date (1973)_ (OCi/a) (c[p/q)_
' Location _
I Dischargeoutfall(a) 14 1 0.69. 0.07 300 ft. from shore August 15 , i Dischargeoutfa~ll(b) 0.34 10.03 600 ft. from shore August 15 I(c) { September 20 14 1 0.31 0.03 .) Priscilla beach September 20 10 1 0.27 0.02 White horse beach ) September 20 14 il 0.33 0.03_ Plymouth beach Gamma spectrum analysis indicates: K-40,
- a. Strontium-90 less than 0.02 pCi/g.
13 2 pCi/g; Cs-137, (7.6 1.3) x 10-2 pCi/g; fla-226,' 2.51.4 pCi/g; and Th-228, 0.61 .1 pCi/a. 1
- b. Strontium-90 less than 0.008 pCi/g, and' cesium-137 less than 0.02 pCi/g.
- c. 1 indicates incomplete analysis, value will be reported in next semiannual report.
l h 4 s
- - _ . - - - ---______a
(7 # .$ f l' t se # 'd L IV CONCLUSIONS The results of the environmental r'adiation monitoring' program for this edx months period indicate that offsite icvels of radiation and radioactivity have remained at preoperational levcis. The only increase was detected onsite in external-gamma exposur,e rates in the vicinity of the turbine building. The
; resultant radiation dose to on-site visitors and transient workers, not in the o
controlled security areas, was not significant. r 1 1
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