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Radiological Environ Monitoring Program for 1988
	ML20245J634
Person / Time
Site:	North Anna
Issue date:	12/31/1988
From:	Drego E; TELEDYNE ISOTOPES MIDWEST LABORATORY, VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
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{{#Wiki_filter:_ _ _ - _ _ - I i VIRGINIA POWER COMPANY i NORTH ANNA POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I FOR 1988 I l { i l 4 I I i Prepared by 1 I l VIRGINIA ELECTRIC AND POWER COMPANY and TELEDiNE IS0 TOPES I 8905040208 890428 ADOCK 0500 8 gDR 4

I ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT I NORTH ANNA POWER STATION I JANUARY 1, 1988 to DECEMBER 31, 1988 I I I 'I I Prepared by: zd D[ Assistant Supervisor Health Physics (Count Room and Environmental) Reviewed by: f Supervisor Health Physics (Technical Services) Approved by: / A 5%erintendeggealth Physics I I

l TABLE OF CONTENTS I l S_ECTION TITLE PAGE - g 1. INTRODUCTION................................................ 1 II. SAMPLING AND ANALYSIS PR0 GRAM............................... 5 i III. PROGRAM EXCEPTIONS......................................... 20 'V.

SUMMARY

AND DISCUSSION OF 1988 ANALYTICAL RESULTS.......... 24 i A. AI RBORNE EXPOSUR E P ATHWAY.............................. 24 1. Ai r Iodi ne/Part icul ates............................ 24 l 2. Precipitation...................................... 40 3. 5o11...............................................43 B. WATERBORNE EXPOSURE PATHWAY............................ 44 1. Ground /Well Water.................................. 44 2. River Water........................................ 47 3. S u r f ac e W a t e r...................................... 51 C. AQUAT I C EXPOSUR E P ATHWAY............................... 57 1. Sediment / Silt.............................. ...... 57 2. Sh o r e l i ne 5o i 1..................................... 6 4 D. INGESTION EXPOSURE PATHWAY............................. 67 1. Milk............................................... 67 2. Fish...............................................72 3. Terrestrial Vegetation............................. 78 E. DIRECT RADIATION EXPOSURE PATHWAY...................... 81

1. TLD Dosimeters......................................

81 V. CONCLUSION................................................. 90 VI. 1988 L AN D U S E C E N SU S....................................... 9 5 I VII. SYN 0PSIS OF ANALYTICAL PROCEDURES.......................... 99 VIII. EPA I NTERL ABORATORY COMPARI SON PROGRAM.................... 110 IX. REFERENCES................................................ 129 I l 1

I TABLE OF CONTENTS (Cont.) LIST OF FIGURES I 1. ENVIRONMENTAL SAMPLING LOCATIONS........................... 17 2. LAND USE CENSUS MAP........................................ 98 I I I I I E I I I l l I ii

I I I FORWARD l This report is submitted as required by Technical Specification l 6.9.1.8, Annual Radiological Environmental Operating Report for North Anna Power Stations Units 1 and 2, Virginia Electric and Power Company Docket Nos. 50-338 and 50-339. I I I I E I I I I I I I 111

I I I I I I I 1. INTRODUCTION I I I I I I I I I 1

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION I RADIOLOGICAL ENVIRONMENTAL OPERATING PROGRAM I. INTRODUCTION The operational radiological environmental monitoring program conducted for the year 1988 for the North Anna Power Station is provided in this report. The results of measurements and analyses of dcta obtained from saniples collected from January 1,1988 through December 31, 1988 is summarized. I A. The North Anna Power Station of Virginia Electric and Power Company is located on Lake Anna in Mineral, Virginia, approximately 35 miles i west of Fredericksburg, Virginia. The site consists of two units, each with pressurized water reactor (PWR) nuclear steam supply systems and turbine generator furnished by Westinghouse Electric Corporation. Each unit is designed with a gross electrical output of 970 megawatts electric (MWe). Unit 1 achieved commercial opera-tion on June 6, 1978, and Unit 2 on December 14, 1980. I B, The United States Nuclear Regulatory Commission (USNRC) regulations (10CFR50.34a) require that nuclear power plants be designed, con-structed, and operated to keep levels of radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARA). To ensure these criteria are met, the operating license for North Anna Power Station includes Technical Specifications which govern the release of radioactive effluents. Inplant monitoring is used to determine that these predetermined release limits are not exceeded. As a precaution against unexpected or undefined I 2

environmental processes which might allow undue accumulation of radioactivity in the environment, a program for monitoring the plant environs is also included in North Anna Power Station Technical Specifications. C. Virginia Electric and Power Company is responsible for collecting the various indicator and control (background) environmental samples. Teledyne Isotopes is responsible for sample analysis and the submission of reports of radioanalyses. The results are used to determine if changes in radioactivity levels could be attributable to station operations. Measured values are compared with background levels, which vary with time due to such external events as cosmic ray bombardment, weapons test fallout, and seasonal variations of naturally occurring isotopes. Data collected prior to the plant operation is used to indicate the degree of natural variation to be expected. This preoperational data is compared with data collected during the operational phase to assist in evaluating the radiological impact of the plant operation. l D. Occasional samples of environmental media show the presence of man-made isotopes. As a method of referencing the measured radio-nuclide concentrations in the sample media to a dose consequence to } man, the data may be compared to the reporting level concentrations t listed in the USNRC Regulatory Guide 4.8 and Table 4.12-2 of North Anna's Technical Specifications. These conce.ntrations are based upon the annual dose commitment recommended uy 10CFR50, Appendix 1, to meet the criterion of "As Low As Is Reasonably Achievable". 3

I E. This report documents the results of the Radiological Environmental Monitoring Program for 1988 and satisfies the following objectives of the program: 1. To provide measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead j to the highest potential radiation exposure of the maximum exposed members of the public resulting from the station operation. 2. To supplement the radiological effluent monitoring program by verifying that radioactive releases are within allowable limits. 3. To identify changes of radioactivity in the environment. 4 To verify that the plant operations have no detrimental effect on the health and safety of the public. I I 4 l

I I I I-1 I I-1 i I l II. SAMPLING AND ANALYSIS PROGRAM I I E I I .I I I-I 5 i

II. SAMPLING AND ANALYSIS PROGRAM A. Sampling Program 1. Table 1 summarizes the sampling program for North Anna Power Station during 1988. Figure 1 indicates the locations of the environmental monitoring stations. 2. For routine TLD measurements, two dosimeters made of CaSO4:Dy in a teflon card are deployed at each sampling location. Several TLDs are co-located with NRC and Common-wealth of Virginia direct radiation recording devices. 'I These are indicated as "co-location" samples. 3. In addition to the Radiological Environmental Monitoring Program required by North Anna Technical Specifications, Virginia Electric and Power Company splits samples with the Commonwealth of Virginia. All samples listed in Table 1 are collected by Vepco personnel except for those labeled state s pl i t. All samples are shipped to Teledyne Isotopes in Westwood, New Jersey. 4 All samples listed in Table 1 are taken at indicator loca-tions except those labeled " control". I I I i 6

2 B. Analysis Program 1. Table 2 summarizes the analysis program conducted by Teledyne isotopes. for North Anna Power Station' during 1988. l \\

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TABLE 2 (Page 1 of 3) NORTH ANNA POWER STATION l SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Thermoluminescent 2mRi2mR mR/std. month Dosimetry (TLD) Quarterly Gamma Dose (84 routine station TLD's) 12 station TLD's Annually Gamma Dose 2mR 2mR mR/std. month Airborne Weekly I-131 0.07 pCi/m3 Radiciodine Airborne Weekly Gross Beta 0.01 pCi/m3 Particulate Quarterly (1) Gamma Isotopic pCi/m3 Cs-134 0.05 Cs-137 0.06 Annually Sr-89/90 i Surface Water Monthly Gamma Isotopic pCi/f Mn-54 15 Fe-59 30 Co-58,60 15 Zn-65 30 Zr-Nb-95 15 1-131 10 Cs-134 15 Cs-137 18 Ba-La-140 15 Quarterly (1) Tritium (H-3) 2000 pCi/E { 2nd Quarterly Sr-89/90 J~ Composite (1) Quarterly Composites of each location's samples will be used for the required analysis. LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environ-mental Program. Actual analysis of the samples by Teledyne Isotopes may be 1^wer than those listed. 13

TABLE 2 i i (Page 2 of 3) NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS River Water Quarterly Gamma Isotopic pCi/E Mn-54 15 i Fe-59 30 I Co-58,60 15 Zn-65 30 Zr-Nb-95 15 I-131 10 I Cs-134 15 Cs-137 18 Ba-La-140 15 Quarterly Tritium (H-3) 2000 pCi/E 2nd Quarterly Sr-89/90 5/1 pCi/E Sample Ground Water Quarterly Gamma Isotopic pCi/E (Well Water) Mn-54 15 Fe-59 30 I Co-58,60 15 Zn-65 30 Zr-Nb-95 15 I I-131 1 Cs-134 15 Cs-137 18 Ba-La-140 15 Quarterly Tritium (H-3) 2000 pCi/l Aquatic Semi-Annually Gamma Isotopic pCi/kg (dry) I Sediment Cs-134 150 Cs-137 180 Annually Sr-89/90 200/40 pCi/kg (dry) Shoreline Semi-Annually Gamma Isotopic pCi/kg (dry) Soil Cs-134 150 Cs-137 180 Soil Once per 3 yrs. Gamma Isotopic pCi/kg (dry) Cs-134 150 Cs-137 180 Once per 3 yrs. Sr-89/90 200/40 pCi/kg (dry) LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environ-mental Program. Actual analysis of the samples by Teledyne Isotopes may be lower than those listed. 14

TABLE 2 (Cont.) (Page 3 of 3) NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Milk Monthly I-131 1.0 pCi/l Monthly Gamma Isotopic pCi/l Cs-134 15 Cs-137 18 Ba-La-140 15 Quarterly Sr-89/90 5/1 pCi/l Fish Semi-Annually Gamma Isotopic pCi/kg (wet) (Quarterly - Mn-54 130 i tarim period) Fe-59 260 Co-58,60 130 Zn-65 260 Cs-134 130 Cs-137 150 Food Products Monthly if Gamma Isotopic pCi/kg (wet) (Broadleaf available or Vegetation) at harvest Cs-134 60 Cs-137 80 I-131 60 pCi/kg (wet) l l NOTE: This table is not a complete listing of nuclides which can be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported. LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Progr am. Actual analysis of the samples by Teledyne Isotopes may be lower than those listed. 15

LEGEND FOR THE NORTH ANNA POWER STATION ENVIRONMENTAL MONITORING STATIONS OVERVIEW MAPS (FIGURES 1, 2, 3) MAP ENVIRONMENTAL STATION MAP EFtIRONMENTAL STATION DESIGNATION IDENTIFICATION DESIGNATION IDENTIFICATION l 1 N-1/33 23 WSW-23/55 2 N-2/34,05A 24 WSW-24/56,22 3 NNE-3/35 25 W-25/57 4 NNE-4/36 26 W-26/58 i l 5 NE-5/37,01 27 WNW-27/59,21 6 NE-6/33,14 23 WNW-28/60 7 ENE-7/39 29 NW-29/61 8 ENE-8/40 30 NW-30/62,09 9 E-9/41 31 NNW-31/63 10 E-10/42 32 NNW-32/64 11 ESE-11/43 33 03, C-Sc4 12 ESE-12/44,06 34 04 13 SE-13/45,01A 35 05 14 SE-14/46 36 07 C-1&2 15 SSE-15/47,23 37 08 16 SSE-?6/48 38 11 i 17 S-17/49 39 12 18 S-18/50 40 13 19 SSW-19/51 41 15 20 SSW-20/52,02 42 16 21 SW-21/53 43 24, C-3&4 22 SW-22/54 44 C-7&B I O Map Designation # U Road Numbers 16

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FIGURE 1 (Page 3 of 3) NORTH ANNA POWER STATION ENVIRONMENTAL MONITORING STATIONS OVERIEW MAP I I w LRt.,33} l [Rt. 208) l G2en Marge Shopping Center (Rt. 22/33}

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[to Mineral, VA) I I g (Main Street] N Orange VA o ? c,t. 2n l l I I I a LRt. 153 I 19

1 l I III. EXCEPTIONS TO PROGRAM I I I I I 20

III. PROGRAM EXCEPTIONS l During the 1988 environmental reporting period, several samples were not available. There were also some analyses of samples that did not meet the required sensitivity (LLD). The following is a discussion of the exceptions and actions taken to limit re-occurrence. Several air iodine / particulate samples were lost. In some cases the sampler malfunctioned and no sample was available. In several other cases the required LLD's were not met due to low air volume. One precipitation sample was not collected due to an oversight in the field. Two food / vegetation samples did not meet the required LLD for Cs-134 due to small sample size. One-fish sample from station 08 was not collected until 06/21/88 due to collection problems and personnel scheduling problems. Four direct radiations TLD's were vandalized or dislodged and lost due to weather conditions; two during the second quarter and two during the third quarter. In addition, there were two TLD's for the second quarter that were missing at the time of collection. They were discovered at the collection of the third quarter TLD's. Surf ace water samples are collected by the Commonwealth of Virginia on a monthly basis from two stations. The analyses for barium /lanthanium-140, and I-131 f ailed to meet the required Lower Limit of Detection (LLD) in several cases due to delay in receipt of samples from the State of Virginia. The exceptions to the 1988 Radiological Environmental Monitoring Program are not indicative of programmatic weaknesses. Corrective actions were taken as appropriate and changes to the administration to the program are not deemed necessary. I 21

1 i REMP EXCEPTIONS FOR SCHEDULED SAMPLING AND ANALYSIS DURING 1988 - NORTH ANNA j i l Date of Reason (s) for Loss / Location Description Sampling Exception 01 Air Iodine 05/24/88-05/31/88 LLD not met due to low I chemical yield. Sample counted over 10,000 min. 01 Air Particulate / 07/12/88-07/19/88 Power outage due to ^ Air Iodine damaged electrical outlet. No sample available. j J 03 Air Iodine 08/02/88-08/09/88 The 24 hour timer had I loose on/off connections yielding low sample volume causing LLD not to be met. l 03 Air Particulate 08/02/88-08/09/88 Above with elevated results I due to low air sample I volume not LLD problems. 04 Air Particulate / 08/31/88-09/06/88 Power outage due to loose Air Iodine power cord connection; i no sample available. { 03 Air Particulate / 10/11/88-10/18/88 Pump vanes damaged causing Air Iodine motor to trip fuse; no sample available. I 24 Air Particulate / 12/13/88-12/20/88 The 24 hour timer f ailed; Air Iodine no sample available. 24 Air Particulate / 12/20/88-12/27/88 Pump vanes damaged Air Iodine causing motor to trip fuse; no sampe available. 23 Air Particulate / 03/22/88-03/29/88 Power outage due to loose i power cord connection; no sample available. 01 Precipitation 01/01/88-02/03/88 Technican oversight, sample not collected i I until 03/01/89. / 1 l I 1 1 22 l }

RdMP EXCEPTIONS FOR SCHEDULED SAMPLING AND ANALYSIS DURING 1988 - NORTH ANNA I Date of Reason (s) for loss / Locatiun Description Sampling Exception I W27/ Surface Water 01/15/88 thru LLD could not be met W33 12/15/88 for Ba/La-140 due to long lar,se of time from collection to receipt at TI. W27/W33 Surface Water 05/15/88 LLD for I-131 could not 08/01/88-08/31/88 be met due to long lapse 11/15/88 of time from collection to receipt at TI. 08 Fi sn 05/14/88 Collection / scheduling problems delayed collet tion until 06/21/88. I. 16 Food / Vegetation 06/07/88 Insufficient garden samples available due to lack of precipitation thus insuffi-cient sample size to meet specifications (0.98 kg.). l 16 Food / Vegetation 10/25/88 Insufficient vegetation available for this time of year, thus LLD not met. I Se-14 Direct Radiation Second Quarter TLD Vandalized or dislodged Third Quarter and lost due to weather conditions. SW-22 Direct Radiation Second Quarter TLD missing at collection at end of second quarter. TLD found when collecting i third quarter TLD's. WNW-28 Direct Radiation Second Quarter TLD missing at collection at end of second quarter. I TLD found when collecting third quarter TLD's. SW-22 Direct Radiation Third Quarter TLD Vandalized or dislodged and lost due to weather conditions. i g l 23 j

I. IV.

SUMMARY

AND DISCUSSION OF 1988 ANALYTICAL RESULTS ,I Data from the radiological analyses of environmental media collected during the report period are tabulated and discussed below. The procedures and specifications followed in the laceratory for these analyses are as required in the Teledyne Isotopes Quality Assurance Manual and are explained in the Teledyne Isotopes Analytical Procedures. A synopsis of analytical procedures used for the environmental samples is provided in Section VII. In addition to internal quality control measures performed by Teledyne, the laboratory also participates in the Environmental Protection Agency's l Interlaboratory Comparison Program. Participation in this program ensures that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples are performed. The results of the EPA Interlaboratory Comparison are provided in Section VIII. Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measure-ment methods. Teledyne Isotopes analytical methods meet the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC Branch Technical Position of Radiological Monitoring (November 1979, Revision 1). l The following is a discussion and summary of the results of the environmental measurements taken during the 1988 reporting period. ) I A. Airborne Exposure Pathway 1. Air Iodine / Air Particulate Gross beta activity was observed in all fif ty control samples with an average concentration of 0.030 pCi/m3 and a range of 0.013 to 0.048 pCi/m3 The average measurement for the indicator locations was 0.035 I 24 1

I I 3 pCi/m3 with a range of 0.005 to 0.075 pCi/m. The results of the gross beta activities are presented in Table 5. The monthly averages of the gross beta concentrations for the eleven indicator locations and the control location are plotted from 1977 through 1988. With the exception of the five week period in 1986 influenced by the Chernobyl accident, the gross beta activities were comparable to levels in the 1982-1987 period. Prior to that period the gross beta activities were higher due to atmospheric nuclear weapons testing by other countries. Air particulate filters were composited by locations on a quarterly basis and were analyzed by gamma ray spectroscopy. The results are listed in Table 6. Cosmogenically produced beryllium-7 was measured in all 48 composite samples. The average measurement for the control location was 3 3 with a range of 0.028 to 0.071 pCi/m. The indicator loca-0.048 pC1/m tions had an average concentration of 0.065 pC1/m3 and a range of 0.029 to 0.110 pCi/m3 Naturally occurring potassium-40 was detected in one 3 and in eleven indicator control sample with an activity of 0.020 pCi/m samples with an average measurement of 0.020 pCi/m3 and a range of 0.011 to 0.044 pCi/m3 Cesium-137 was measured at 0.0022 pCi/m3 in the first quarter composite at station 03. All other gamma emitters were below the detection limits. j The second quarter composites of air particulate filters from all l twelve stations were analyzed for strontium 89 and 90. There were no detections of these fission products at any of the eleven indicator stations nor at the control station. lI i 25 L-__-___________-

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0 1 4 66555 16b5 7755 2 2 i i iii iiii i i 11 1 A T 66856 8476 1 51 0 1 S 33112 4333 3422 3 0 3 66656 5655 7766 1 2 i1 iii 1ii1 1 i ii i A T 43634 121 2 0597 2 S 33323 3333 34 22 3 1 2 76666 6665 7877 1 2 i i i ii1 i i i i t A T 95940 4533 824 3 0 S 34334 3433 3544 4 4 1 77777 6666 7766 1 2 i 1 i ii11 1i ii i A T 617 98 3417 2149 i S 35434 3444 3533 4 3 S 7 77667 6666 87 67 1 E 0 T iiiii i i ii i ii i i A A L T 43493 8685 9380 4 8 U S 45335 3344 4435 4 8 IC 9 1 T R 2 A P 6 67 666 6666 87 66 1 A a 0 N R m i i 1ii i i ii i iii t A I g A N A i T 481 84 5997 4515 2 ) S S 34 434 3334 5443 4 4 H N 5 f R I 2 T S o O A i N E N T IOA L 3 E 3 5 67666 6655 8766 8 B B m T 0 A e / A - i 1 i i i 1ii1 i i1 t i T A T g R S i ST 20854 0311 4 640 4 a E S C P W O p S 34333 3333 4333 3 ( O R P G 3 s A F 0 e 3 g I O 1 N 5 66565 5984 6666 1 a I S 0 r G N i i ti i iii 1 iii i e R O A v T 86556 5338 3485 9 a I I S 23222 2431 3322 2 V T A n R i T N d 5 e L C 4 76567 8445 544 1 d O i1 i it i iii aiii i lu ) N 0 C A ( 1 c T 20304 8391 24 2 n S 43234 3313 322 3 i ) t b o ( n 0 8 3 55487 4767 8777 2 0 e 1i i i 1 1 i i i i ti 1 i ns A T 04 57 0 0491 5856 9 lt S 33255 254 6 7544 4 o 3 v r i 2 8 a 0 67 7 67 6655 7766 1 w T lo A i i i i i i ii1 i1 1 1 1 S 387 56 6613 8220 0 35534 3333 3434 4 o .t dee t u 7 cd 77 7 576 757 5 1 e l 69)a1 t iii i 1 1 1 t lorl U l t ii A 1 T 56 ( 8 7 64 3 504 6 6 cs S 35 45 4355 4453 4 e t r o nd e 52962 9631 6307 8E 01 1 20 0123 01 22 leta 3T //' // //// R //// pv 9A 7i 7 7 8 8888 E 990 9 me 1 D 0O000 0000 B 0000 o d. al T M n SE 95296 S 2963 E 1 63 0 a s l Y 201 1 2 O 001 2 T 3 01 2 r )) t L ///// G //// P //// e2 O U 67 7 /7 l 8888 E P999 v ab l C J 00000 A 0000 5 O000 A 1 (( l t

3 6 4 76666 6666 66 1 1 2 )) iii1i ii1i 1icc i i A (( T 58507 3539 77 2 0 S 4 3 '.3 2 2232 23 3 3 4 5 3 76666 6666 6665 1 1 2 11iii 11i1 iiii i t A T 05535 5261 5767 2 0 S 43332 1333 2333 3 3 5 7 2 86667 7676 6676 1 1 2 i1i11 i111 iii1 i i A T 21 571 6050 7500 2 7 S 53334 3454 3455 4 3 9 9 1 77677 6676 6666 1 1 2 1iii1 1i1i t1it t i A T 65895 1489 0586 0 6 S 44335 2342 3344 4 3 S 1 1 E 7 76667 7776 6666 1 2 T 0 A ii1ii i i1i iiii i i L A U T 57743 6646 2796 1 7 8 C S 43334 3443 3444 4 1 8 I 9 T 1 RA P 6 9 6 76666 6666 6866 1 1 A R a 0 N I m 1iiii i iii iiii i i N A A ig A 7 T 147 36 9390 4861 5 ) N S S 43333 1323 2444 3 3 4 H I 2 S T 5 f R A N o O T 1 O E N E IA 7776 7666 8 12 L 4 B 3 T5 76767 B m A0 A e S / T - i i1ii 1i1i iiii i i T g R S i SA a E O C T 661 38 31 89 5641 9 4 P W R p S 33433 3433 3444 3 3 ( O G P 3 F s I O 0 e A G O i ii 11 iii1 i 1ii i t e 1 4 4 g I S 5 76666 7666 67 66 1 1 a N N 0 r R I A v I T T 4041 2 1787 4358 7 2 a V A S 33333 3333 3544 3 3 R T in N E d C 6 8 e N 4 55556 7677 7776 1 1 d O 0 u C iiit i 1 ii1 i i i i i i l A c T 417 08 4522 7 897 0 3 n S 33333 3344 3544 4 3 i e. l t b oa 0 8 i nl 3 77 56 7766 666S 2 2

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) ev 1i aii i iii i1 i i i 1 ma A ( u T 34 91 2487 61 02 6 5 l e S 55 23 3422 2443 3 3 ol vp m 2 7 ira s a 0 7 7667 7666 6766 9 1 o wn A iiiii 1 tit 1 i i i i o T l ; S 02959 6844 1 81 9 8 5 d 4 4333 3333 3443 3 3 oe .t n d o eei t ut 6 4 cd c 1 75467 7776 7766 1 2 e n 0 l t u i i1 i i iii 1 i i1 i l l f A oul T 37099 4435 9470 3 7 cs a S 53333 3453 4544 4 3 em t r o t nd nee 41 851 8529 6307 8E 011 20 0122 0122 let m ap 8T /// // //// //// y e d. pvi 9A 00001 R 1111 R 2222 lr e d. laas meu al q 1D R 111 11 E 1111 E 1111 E B 1 852 M 9630 t a s B ag c SEE B 741 85 M L O 2011 2 E 0012 E 2012 r r ur L T ///// V //// C O C 90000 O 1111 E 1//// a e2 ne2 ))) C O 011 11 N 1111 D 1111 QA i AAi (ab c 222 uv n v ((

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4 5 4 9 Ed 1 73 6 0 G. 36 41 66 0 2 As )) )) )) )) R aa1i - - - - - aa1i - - - - - aai1 - - - i - aa1 - - - - - - M E2 (( (( (( (( V 47 05 94 8 0 At 1 38 51 55 9 61 72 61 2 5 M R9 S E8 E T/ 5 2 T R3 4 9 2 5 A A0 0. 1 L U/ 19 8 8 9 89 1 9 9 89 ( )) 0 )) 0 U Q1 )) 0 )) C 0 aaii1l011 aai201 001 aat32111 2 aai201001 I H - (( (( (( <<<( (( T T7 43 1 5 2 R R2 A U/ 26 0. M I 0 7 P O9 51 6 4 5 F0 R A Y L R R E E7 0 T T2 3 1 0 4 R R/ A A9 8 8987 8 8 )) 0 )) 0 88 1 1 99 0 )) 0 U U0 )) Q Q-aai200001 aai201001 aai21111 l aai211002 8 9 (( (( (( (( 0 0 8 N D2 3 6 1 9 I R/ 1 I6 3 7 1 6 H0 8 6 4 5 T R M A E a N T m N T g ) A I i 3 M s H E 6 f T 2 o R A R E O M 1 E9 1 0 L 1 N M T2 54 7 3 B A 3 R/ 00 2 A e G m A6 311 319 88 297 99 49 T g / U0 0 a R D i Q-30ii11111 30ii11001 301i11002 40i31l111 P E N C 9 ( W A p D2 50 06 01 M O N/ 1 8 P 0 3 O3 91 16 03 0 9 C0 62 1 81 1 A / 0 E I 9 1 S N 8 M I G M R U I I V T N R 9 0.1

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4 O E9 R T2 0 0. 0. 9 1 T R/ 1 1 89 98 18 0 1 S A3 )) 0 )) )) )) 0 U0 aai211112 aaii01001 aaii221 i2 aai312112 F Q-(( (( (( (( O 9 5 43 96 8 7 T2 1 5 S/ 8 26 67 1 Oy N R2 4 62 31 2 6 Ll O l1 Ll I f <a T u A en R rn T ea N w E d M C se N rm O er C to tf 7 *78 3478 347 8 3478 ir E 90 00332 90 00332 Q0 00332 90 0O332 me D 897061112 391 061112 R9706111 2 897 06l112 ep M I 4 - - - - - 4 - - - - - L rre 0ussh rre oussh rre - oussh rre - 0ussh a0 C SSBK0RCCT SSBKCRCCT SSBKCRCET SSbK0RCCT m9 U m/ N a9 g8 M rm eu hi ttono l r N lt M l 0 0 0 0 0 1 2 3 4 AS l A A A A A ) T T T T T

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R3 M A A0 0 L U/ 917978 98 99 1 979 997177 U Q1 )) )) )) 0 )) C 0 aa1i00001 aaii11001 aai210001 aaii00001 I H - (( (( (( <( <<<< (( T T7 07 30 1 94 R R2 A U/ 16 36 0 26 M P O9 52 51 5 62 F0 R I A Y M L R R E E7 4 00 5 9 T T2 0 R R/ 1 11 A A9 1 11 1 9 8979 U U0 )) 0 )) )) 0 )) 0 Q Q-aai312112 aaii12112 aai311111 aai200001 M 8 9 (( (( (( (( 8 N D2 7 83 8 4 9 I R/ 1 I6 8 66 1 3 H0 2 42 7 7 S T R M A E a N T m N T g ) A l. i 3 s H E 6 f T 2 o R A R MA E O M i E9 L 2 N M T2 99 8 9 B A 3 R/ 1 1 e G m A6 37977 68 39 21 68 3176777 T g / U0 0 0 a R D i Q-30ii00001 20i512112 20i211 001 30ii00001 P E N C 9 <<<<<( ( W A p D2 55 4 1 35 M O N/ 0 1 P 0 3 O3 59 6 1 1 2 9 C0 41 6 2 A / 0 E I 9 1 S N 8 M I G M R U I I V T N R 1 2 0.1 8 O E9 3 2. 6 R T2 T R/ 9 889 1 18 1 89 M S A3 )) 0 )) 0 )) )) 0 U0 aai210001 aai211111 aaii11111 aai211001 F Q-(( (( (( (( 0 9 5 04 O 9 T2 S S/ 9 8 67 3 Dy N R2 6 8 61 6 Ll O I1 Ll I F < a T u A en R rn T ea N w E d M C se N rm O er C t o tf 3478 3478 3478 3478 i r E 90 00332 90 00332 90 00332 90 00332 me 112 897061112 897061 112 8970611 12 ep D 897061 M I 4 - - - - - 4 - - - - - 4 - - - - - L rre - oussh rre-oussh rre oussh rre - 0ussh a0 C SSBKCRCCT SSBKCRCCT SSBKCRCCT SSBKCRCCT m9 U m/ N a9 g8 rm eu hi tton l or N A lt M O 5 5 6 7 AS I 0 0 0 0 T A A A A A ) T T T T T

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V 62 9 27 36 Ai 11 3 83 89 62 7 42 41 R9 S E8 0 8 3 1 E T/ 9 T R3 A A0 1 2 0 3 88 1 1 8 78 1 98 L U/ 1 8 U Q1 )) 0 )) 0 )) )) 0 C 0 aai201 001 aai4121 1 2 aai111 001 aai211 001 I H - (( (( (( (( 3 50 1 T T7 4 R R2 A U/ 2 9 36 8 P O9 5 6 31 2 F0 R I A Y L R R 9 8 R R/ 6 3 3 .5 E E7 7 T T2 1 A A9 1 1 1 1 U U0 )) 0 )) 0 )) 0 )) 0 Q Q - aai522222 aai3121 12 aai522112 aai4 12112 8 9 (( (( (( (( 8 N 02 1 4 3 1 9 I R/ 1 I 6 E 6 2 2 H0 S 7 3 4 5 T R A E a. N T e N T g ) A I i 3 M s H E 6 f T 2 o R A R E D M i E9 1 67 5 L 3 N M T2 82 B A 3 R/ 8 31 20 A e G m A6 3 9 7 0 8 6. P. 0 38 9 411 311 T g / U0 a R O i Q - 20ii00001 20 i211012 20ii11112 20ii111 12 P E N C 9 << < ( < <<< ( W A p O2 42 1 14 26 O N/ P 0 3 O3 91 1 41 19 9 C0 82 6 83 71 A / 0 E I 9 1 S N 8 I G M R U I I V T N R 5 O E9 8 7 3 R T2 0 2 T R/ 1 1 9 998 8 7967 S A3 )) 0 )) 0 )) 0 )) 0.... U0 aai2211 12 aai31 21 1 2 aai200011 aai1 00001 F Q-(( (( (( (( O 9 3 9 9 6 T2 S S/ 8 8 2 1 N R2 4 8 4 5 O I1 I F T A R T N E C N O C 3478 3478 3478 3478 E 90 00332 90 00332 90 00332 90 00332 D 897 061 112 8970611 1 2 897061112 8970611 12 I 4 - - - - - 4 - - - - - L rre - 0u5 sh rr e-ous sh rre - oussh rr e-oussh C SSBKCR0CT SSBKCRCCT SS8KCRCCI SSBKCRCCT U N N 0 1 2 3 4 1 2 2 2 2 T A A A A A T 1 T T T S 5 5 S S l

I 2. Precipitation I 1 A sample of rain water was collected monthly at station 01, on site, 0.2 miles, 42 degrees NE and analyzed for gross beta activity. The results are presented in Tables 7 and 8. The average gross beta activity for eleven months was 4.8 pCi/l with a range from 2.4 to 9.6 pCi/4. (There was no sample available for the month of January. A semi-annual composite was prepared and analyzed for gamma emitting isotopes and tritium. Cosmogenically produced beryllium-7 was measured in one sample at a level of 49.6 pCi/f. Tritium was measured in one sample with a level of 250 pCi/2. All other i gamma ere tter s were below their detection limits. These results were comparable to those measured in 1986 and 1987. I I I l 1 I I I I I I 40

Il ll l S T E N FN E OIDM TEE RUTR O O O EORU BROS MNPA UOEE NNRM M NO I T N A O C EI ONGT LANC E E E EAA N N N LMRR O O O O F N N N R T NO C M N ) O 1) ) 8 EI 16 2 ) 8 NGT / / 2 9 ANC 19 1 / 1 N EAA 1 - (. 1 A MRR (4 6 ( 9 1 M

8. 2 0

E F M 9 5 3 3 N 4( 4 2 3 T O / R S I 8 E E T Y 3 B H C R 3 M G E A E I R n M 0 C H I o M M 5 E D U D H n S O T D o N o I N E E E i M t W LA N N N t. A T M i9 R E N AE i i i s7 G K 1 O NC m m m o9 O C I N P1 R O Y T A M 2 2 2 P D R A T l r A C S 0 0 0 ae G U O I cb N N L D inem A 1 1 1 I R J 0 0 0 h v O co T eN M I S T N N 7 O O h1 M I c E T nn L L A ao B A C ri A T O Bs T N N L i O N ) Cv E I R EO 1) ) R e M N T O NGI 15 2 ) NR O A T ANT / / 2 S R T A EAC 19 1 / U, I S I MRA 1 - ( 1 m C V R (4 6 ( na 0 ir N R D F

8. 2 9

5 g E E A N W I I 4( 4 2 do M I A I A ug L O N er A P I L rP C G L i R R G qn O E V ei L L rr O I C T o U Y dt D N T I N) ni M A N I O1 an R A U L I( 0 o N O T 0 dM ) 0 e N C RFC) A EOED 4 2 nl A W TL i a H S O EL ft T I L D( en . M R U da O O m N L 1 2 2 2 sn 1 ao ) r DR y ni NES l ABE la iov n MSD tE SUYE a u c NLM t n el I S AR e n t a YLNO yB A n ec a LAAF l AT R h s ai it di g AT OP no me it f o NOFE t s mm 7 ol or aS e r o = MG G( B T iti M ima d ) T R N l E e Y M rl A E eb W R wa H U ot M T S n l p A A P E io e sc DM t ic RE a A OLF it D PO ) L n NM M ISI ipf L a t AT / ci D N eC ) E U rp 1 M ( P( ( 3w

M I N O T A L T L s M I N c I A e 0 8 5 9 6 5 4 8 5 4 0 8 P F h 3 3 5 8 8 4 2 4 2 5 6 0 C I n 2 2 1 1 2 1 3 1 1 2 1 1 E AI R R P N 9 I N 8 8 O / 8 I 0 9 S T 1 0 1 R A / c06 E T 1 e41 T M 0 p<< I T ) P S A I e A 8 9 0 8 8 8 C 8 a 1 8 3 8 0 2 I 8 = N M t T N E a i Ef 0 0 1 0 1 0 0 1 0 0 1 4 E / m7 A m s 8/ ) R 1 m3 A g i a 1 1 i 1 i i i i 1 i i i P 0 ae-H M i n SC ( / G8H 8 T M S O S p 4 9 4 6 2 4 4 8 4 8 4 2 F 7 R A ( O O 0 E O G 2 R 2 5 5 3 9 3 3 4 3 4 7 4 L N G S B D i E A N 1 T T A f 0 I R / S M E M i N O W U C O P O I p I M 0 P T T O 8 I A C 8 70 A R T / 29 I T S L 1 N A 0 1i I U / G A N 7 0

6. 5 R

T N 0 c I E S 8 8 8 8 8 8 8 8 8 8 8 9 A e92 V B E 8 8 8 8 8 8 8 8 8 8 8 8 8 p4 T / / / / / / / / / / / / I 8 S S A 3 1 9 3 1 1 6 1 7 1 9 0 M /

S D 0 0 2 0 3 0 2 3 2 0 2 1 E 3 a O / / / / / / / / / / / / S 0 m7 R N 2 3 3 5 5 7 7 8 9 1 1 1 / m3 G O 0 0 0 0 0 0 0 0 0 1 1 0 2 ae - I F T 8 8 8 8 8 8 8 8 8 8 8 8 0 GBH O C 8 8 8 8 8 8 8 8 8 8 8 8 e d. . M E / / / / / / / / / / / / g S L 1 3 1 9 3 1 1 6 1 7 2 9 as N L 0 0 0 2 0 3 0 2 3 2 0 2 r O O / / / / / / / / / / / / e2 I C 1 2 3 3 5 5 7 7 8 9 1 1 v T 0 0 0 0 0 0 0 0 0 0 1 1 A1 A R T N E C N O C _ M . M M ll I l

3. Soil Soil samples are collected every three years from twelve stations. l Since the samples were collected in 1986 Tables 9 and 10 will not be included in the 1988 report. I I I I I l 43

l 1 B. Waterborne Exposure Pathway 1

1. Ground /Well Water

{ l i Water was sampled que-terly from the on site well at the biology i laboratory. These samples were analyzed by gamma ray spectroscopy and for tritium. The results are p' esented in Tables 11 and 12. No gamma emitting isotopes were detected. Tritium was detected in the second and i third quarterly samples at an average level of 170 pCi/E with a range from 110 to 230 pCi/f. These are normal environmental levels. The second quarter sample was analyzed fer strontium-89 and 90. There were no detections of these isotopes above the detection level. I I I I 44

RUTR O 9 _ M EORU BROS MNPA JOEE 'N N R M NO I T N A O C EI ONGT LANC E E EAA N N LMRR O O 0 F N N T. T NO C NO ) EI )0 8 NGT 43 8 ANC /2 9 NEAA 2 -0 1 AMRR (01 E F A M / 0l 9 3 1 N N 7( 3 3 T O / S I 8 R E T Y 3 E i C 'C R 3 B I R n E M 0 E H I o W M 5 C D b E H E n T D S S O D IWEA im is7 N N io M o t A T t M 9 R E NAE G K ONC 5 o9 O C 1 I N 7 P1 M I A O h v R O T A P D Y A T 0 l r R C S ae G A O I A icb U L D / A m i N M I ne RO J co T eN M I S T N N O h1 1 O I c 1 M T nn E L A ao L A C ri B T O B s A N N L T E O N Civ R EO R e M I ONGI ) NR N T )0 O A T ANT 43 S R T AEAC ) /2 U, 2 - m I S ICMRA 4 (01 i g V R / 0 na N R D F 0 r E E N ( 1( d o 7l W A I L O T er A P N L irP C I A ug L R G I A I ei G R qn O E L L V rr O C T o dt I O 1 N) ni 1 D N Y I' O1 an A T R A N L I( o N U T dM N O RF C) 0 e A C EOED 0 0 inl V TL 6 0 a H A U EL 2 f t T S L D( en O I de R U m N O sn L ao 4 4 4 r DR ni ABE iov NE S n MSD tE SUYE c iNLM el 3 AR t a i LNO m ec AT R a i di LA AF u g NOFE m 0 t f o AT OP m 4 i ol a r o G K T ti id T l ma ) iR N E e Y M r rl A E a eb W R wa H U ta A A lot _ M T S W pe P E l sc DM l i c R E e A OLF W D ' PO /) L a M df L t P t AT n/ iSI ui D N oC ) E U r p 1 M ( G( ( . E g l

2 5 9 6 8 h T 0 4 0 0 1 6 1 1 6 a B R E ) T b M 4 A 1 ( W 3 1 3 5 3 L L 1 0 0 0 0 E ( W M / D N U O R G N I 0 0 0 0 0 0 8 5 4 4 2 5 7 9 R 9 E K 1 T M T I M A E N N A a e A M m l M g 2 H A i 7 0 0 0 0 p 1 T G S 3 5 4 4 m R e a E O D 2 B s L N N B A i r A e T M f t R U / r E I i a W T C u O I p q P R T 0 9 d A 9 ) ) ) n I a 0 a a o N M r ( ( ( c I V S e G l s R f N n I O o V R T y S l n F o O 9 Dd S 8 ) ) ) L e N a 3 a a t m O r ( ( ( < r I S o T ef A rry R eer T w pt N 0 0 s M E 0 1 7 ssi 0 1 rem C 9 1 0 ese N 0 O 3 1 i 2 i t yh C 1 tl c H 0 0 0 i ao 1 3 7 mni 1 2 1 ead a a0R m9 m/y a9b g8 1 . M rm3 eu1 hi - A t t e N l onn O O oi I 8 8 8 8 l rd d. l t o TS N 8 8 8 8 e CE O / / / / gs ASI ET I 0 1 7 7 a LA T 3 0 2 2 r. LD A / / / / e2 )) O T 3 7 9 2 v

ab C

S 0 0 0 1 A1 ((

I 2. River Water A sample of water from the North Anna River was collected monthly from March 88 through December 1988 at station 11, 5.8 miles downstream from the discharge lagoon, 128 degrees SSE. The results are presented in Tables 13 l l and 14. The samples were analyzed by gamma spectroscopy, and for tritium. j i The second quarter samples were analyzed in addition for strontium-89 and strontium-90. All gamma emitters were below the detection level. No detections of strontium-89 er strontium-90 occurred. Tritium was analyzed by proportional gas counting and was measured with an average level of 3925 pCi/l with a range from 3300 to 5350 pCi/f. This is comparable with the average tritium activity level for 1987. It was measured in 1987 with an average concen-i tration of 3630 pCi/f with a range of 2600 to 5170 pCi/f. I I I ~ l l { 'I 47

I I 'I I I t.s .I e l l 1 \\ \\ M \\ l liC M \\ \\ C \\ I E \\ I \\ s L m W j ~ / lM / Mb / / / / IM / / ) / lI k h N l N I@ N \\ \\ \\ \\ D 8 8 $~ 8 0 o o Units in pCl/ liter I 48 t

TEE RUTR O O m t EORU BROS ENPA OEE NNRM m I N NO T A O C EI ONGT LANC E E EAA N N m LMRR O O O F N N R T N OC m )) N 00 O 1 5 EI /3 8 NGT 05 8 ANC (50 1 9 AWRR N AA 0 1 E F A 23 m 9 M / 93 3 1 N N 3( 3 3 T O / S 8 R E TI Y 3 E H C R 3 B G E A M I R n M 0 E H I o m M 5 C D U E H n S O D T D io N I N E M o WLA S t A T t M G K NAE i 9 R O TIONC i c7 R E m o9 O C 1 N P1 A 8 m I A N 1 h v P D Y A T l r G A O I 5 ae R C S N U L D A icbm N / 1 ne RO J co T eN I S T N N 3 O I h1 O 1 M c T nn E L A ao L A C ri B T O B s A N N L )) i O N 00 C v T E I ONGI /3 NR M I S CMRA ) 1 U, M R EO 1 5 R e N T O A T ANT 05 S R T AEAC 3 (0 m N R I 4 / 50 ina V D f 0 23 r E E N ( 3( d o 93 g W A A P I L O I er m I A I ei N L rP C I L iug R G A G R qn O E L L V r r O C T o U dt . m I N Y I N) ni D M A T I O1 a n R A N I TI( dM o N U N O RFC) 0 0 e A C E OED 0 0 inl W TL 2 0 a H A O EL 2 f t T S O I L D( en _ m R d e U m N O sn L 0 0 0 ao DR 1 1 1 r ni NES MSD iov ABE n tE . m I SUYE c NLM el S AR t a Y LNO m ec LAAF NOFE m 0 iu di AT R a g t f o AT OP m 4 i ol a r o G K T ti _ m ) ma i d T i N l R E e Y M rl A E wb W R a H U lot . m T S p A A e P E r sc DM e i c RI t A OLF a D PO W) L n MM f L a UAT r/ _ m ISI ei ) D N vC E U i p 1 M ( R( ( _ m l

2 7 7 5 6 7 5 8 5 6 ( _ M n I 6 0 2 0 0 0 0 0 0 0 0 0 0 2 8 8 5 7 8 1 6 9 7 7 ( a R M 0 4 0 1 8 6 7 8 7 1 5 9 7 6 a B 7 R 3 E 1 3 4 3 3 5 7 3 4 3 3 M T A s h C R E V I R 4 3 3 4 2 3 4 5 4 3 N 1 3 I 1 0 0 0 0 0 0 0 0 0 0 ( ( ( ( 5 1 8 R 8 E 9 T M I 1 T M E A N A 0 0 0 0 4 0 0 0 0 0 0 0 0 0 0 M NA a 6 1 4 5 1 2 4 6 5 5 A m K M 4 H G 1 T ig R D S E O N L N A 2 BA M i T U R I f E T / W i 7 O I C 0 0 0 0 0 0 0 0 0 0 R P T p e 3 3 3 3 4 6 3 4 3 3 B ( A M I U N I I G T R NO I R V T S 6 0 0 0 0 0 0 0 0 0 0 1 e F 0 0 8 0 0 0 0 0 0 6 3 l O 2 1 1 2 2 1 1 6 3 1 1 p 3 m M I 5 4 6 7 3 4 1 1 7 3 9 e S 1 t t 1 i i 1 1 i i a N H ) 0 0 0 0 0 0 5 s O 0 0 0 0 0 0 0 0 5 2 r 0 4 6 0 T A 3 3 3 3 3 3 4 4 4 5 3 t R r T a N u E .q C O N Ld O Ln C <o 0 c ee 9 6 4 ) ) ) rs ) 4 0 0 a a a ) ) ) e a a a r a M S ( 0 { ( ( ( ( ( wno s rd ee m t t iomf ere 9 ) 2 2 ) ) ) ) ) ) ap 8 a 2 a a a a a a m r my S ( ( ( ( ( ( ( al gno res 1 hi 1 t s N oy O l IS 8 8 8 8 8 8 8 8 8 8 l a T E N 8 8 8 8 8 8 8 8 8 8 e d. l n CT O / / / / / / / / / / g AA 8 2 2 9 5 1 5 3 9 5 as EA I 0 2 1 0 1 1 1 1 0 M LD T L A / / / / / / / / / 1/ e2 ) O T 3 4 5 6 7 8 9 0 1 2 v

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1 I 3. Surface Water i i Samples of surface water were collected monthly from two stations. Station 08 is at the discharge lagoon,1.1 miles,148 degrees SSE on Lake Anna. Station 09 is 2.2 miles upstream on Lake Anna, 320 degrees NW. The samples were analyzed for iodine-131 by radiochemical separation. No iodine was detected in the 24 samples analyzed. The results are presented in Tables 15 and 16. The samples were also analyzed by gamma ray spectrometry. Naturally occurring potassium-40 was observed in one sample from station 09 at a level of 57.5 pCi/f. All other gamma emitters were below the detection levels at either station. The second quarter composite from each station was analyzed for the fission products strontium-89 and strontium-90. The activity of these isotopes were below the limit of detection. i A quarterly composite from each station was prepared and analyzed for tritium. The tritium activity at station 00 was at an average level of 3915 l pCi/l with a range of 2840 to 5020 pCi/f. The trend of the tritium activity at station 08 has been plotted. The tritium level had been increasing since the middle of 1978 when the average level was below 300 pCi/l.

However, during 1988 the results were within the same range as those measured in 1986 and 1987.

The tritium activity in the four quarterly composites from station 09 was at a level of 3010 pCi/f with a range of 1110 to 4130 pCi/f. This is particu-larily significant since this level is found upstream of the plant. The level of tritium for 1988 for station 09 is also within the same range as those measured in 1986 and 1987. Samples of surf ace water were collected by the Commonwealth of Virginia I I 51

i i l l from two stations. Station W-33 is located at the discharge lagoon and station W-27 is located on the North Anna River at the RT 208 Bridge, which l I ( is upstream cf the site. Ten grab samples and two composite samples were collected and analyzed by gamma ray spectroscopy and for tritium. The results are shown in Table 15 and 17. All gamma emitters were below their detection levels. Six samples from each station were analyzed for tritium. The average level at station W-33 was 4333 pCi/l with a range from 3000 to 6000 pCi/1. 1 This is similar to the average result of 3915 pCi/l detected at station 08. the discharge lagoon. The average level of tritium at station W-27 was 1505 pCi/E with a range of 720 to 2400 pCi/f. I I I 1 I 52

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C. AQUATIC EXPOSURE PATHWAY 1. Sediment / Silt Sediment samples were collected in March and in September from each of three locations and were analyzed by gamma spectrometry. The results are presented in Tables 18 and 19. A number of man-made and naturally occurring radioisotopes were detected in these samples. Cesium-137 was detected in all samples with an average activity of 269 pCi/kg (dry weight) and a range from 142 to 589 pCi/kg (dry weight). Cesium-134 was measured in one sample from station 11 with an activity i of 232 pCi/kg (dry weight). The highest readings for cesium-134 and I cesium-137 were obtained at station 11 located 5.8 miles downstream in the North Anna River, 128 degrees SSE. Naturally occurring potassium-40 was observed in all samples with an average activity of 10402 pCi/kg (dry weight) and a range from 3160 to 22500 pC1/kg (dry weight). Radium-226 was measured in five of the six samples with an average concentration of 1402 pCi/kg (dry weight) and a range of 1180 to 1590 pCi/kg (dry weight). Also naturally occurring, thorium-228 was observed in all six samples with an average concentration of 751 pCi/kg (dry weight) and a range of 389 to 1340 pCi/kg (dry weight). A composite was prepared of the semi-annual samples and analyzed for strontium-89 and strontium-90. There were no detections of these fission products in aquatic sediment / silt. In the accompanying [ figures the isotopes cobalt-58, cobalt-60, cesium-134, and cesium-137 are plotted for the sediment samples collected during 1988 at stations 08, 09, and 11. All results are consistent with previous years. 57

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2. ' Shoreline Soil A sample of shoreline sediment was collected in March and September from station 09, 2.2 miles upstream of the fiorth Anna Power Station The samples were analyzed by gamma ray spectrometry.

The results are presented in Tables 20 and 21. The naturally occurring nuclide potassium-40 was measured in both samples at ' an average of 4100 pCi/kg (dry weight) and a range of 1970'to 6230 pCi/kg (dry weight). Thori um-228 was measured at an average of 143 pCi/kg (dry weight) and a range of 112 to 173 pCi/kg (dry weight). Radium-226 was detected in one sample at a level of 579 pCi/kg (dry weight). Cesium-137, also a fission product was monitored in one sample with a level of 53.2 pCi/kg (dry weight). The two quarterly samples were composited and analyzed for stron-tium-89 and 90. Strontium-89 was detected in the March sample at a level of 760 pCi/kg (dry weight). There were no detections of strontium-90 in shoreline soil. I i I i 1 ) 64

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0. INGESTION EXPOSURE PATHWAY 1. Milk

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' E The results of the iodine-131 analysis of milk samples are pre-sented in Tables 22 and 23. A sample was collected monthly from two stations. A total of 24 samples were analyzed. There were no measure-ments of iodine-131 above the detection limits. The milk samples were also analyzed by gamma ray spectroscopy and the results are also presented in Tables 22 and 23. A total of 24 samples were anolyzed. Naturally occurring potassium-40 was measured in all of the samples with an average of 1304 pCi/E and a range of 965 to .I 1440 pCi/t. Cesium-137, which is a fission product, has been detected sporadically in recent years. The activity has been attributed to global fallout from past atmospheric weapons testing. Cesium-137 was detected in one January sample with a level of 5.10 pCi/f. After January there were no additional detections of cesium-137. All other gamma emitters were below their detection levels. A quarterly composite was prepared from each of the two collection stations and analyzed for strontium-89 and strontium-90. Strontium-89 was not detected in any of the samples monitored. Strontium-90 was detected in the eight samples monitored with an average level of 1.5 pCi/l and a range of 0.48 to 1.9 pCi/f. This is similiar to activities determined in previous years and lower than the reoperation levels of 2.2 to 5.4 pCi/t. I I 67

EORU 8ROS MNPA I OEE NNRM N O I T N A O C EI ONGT LANC E E E E E AA N M M M N LNRR O O O O O O F N N N N N R T NO C )) 'N 20 ) O 1 4 2 )) 8 E' I 21 / / /4 1 49 8 NGT 9 ANC 1 - 1 41 0 AMRR 38 ( ( N AA ( 1 0 86 E F 72 7.1 1 A 9 1 M A 31 3 3 N N 1( 5 N l( O 3 T I J / R S 8 E E T Y 3 B H C R 3 M G E A E I R n M 0 C H I o M 5 E D U D H n S O T D N o I N W W W io M t WEA N N N it 9 A T M i i s7 E NAE Ar i K 1 ONC m r m o9 0 C I N P1 R O Y T A 3 3 3 l r P D R A T A C S 8 8 8 ae G U O I cb m N N L D ine A A 2 2 A 2 I J N 1 1 N 1 h v RO co T eN 2 I S T N N 2 O O h1 M I c E T nn L L A ao B A C ri A T = O Bs T N N L ) iv O N 4) ) ) C E I ONGI /4 2 8 R e 9 M R EO 20 4 ) NR P T O A T ANT ) 44 / /1 S V I R / - (21 1 ) 8 - U, A AC 4 R T CERA 8 n I S 2 ( 8 (04 ina 45 0 / - N R D F 0 06 0 r 1 50 E E A N ( 39 ( g L O I I 1( 5 1( do W A P I L er N I A I A irP C G L R R ug G qn O E V ei O rr L L I C T o U Y dt D N T I N) ni M A N R A U I O1 an L I( 0 5 0 8 dN N O T N C RFC) e A EOED 0 3 0 inl A W TL a H S O EL ft T I L D( en R U d e O O m N L 4 4 4 4 8 8 sn 2 2 2 2 aor OR ni ABE iov NES n MSD SUYE ) ) tE S AR r ly c y NLM l el I r t a Y LNO e e ec LAAF 7 t t di AT R 1 a 3 9 r 0r g NOFL 3 m 0 1 8a 9a f o AT OP 1 m 4 - u - u ol a s rQ rQ o I G K C S( S( ti id ) ma T iR N l E e Y M rl A E eb W R wa H t p f T S lot A A e P E sc DM i c RE A OLF D PO ) L n MM f L a i AT / t SI D N lki C ) E U ip 1 M ( M( ( ~ [

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0 r L N M i 6 1 3 e B e A 3 4 14 3 t A g G f 1 1 1 1 r T a / a P R F i u ( E O C q W p O S Dd P N L e O t m A I < r I T o N A ef I R rr G T E 7 7 7 7 ee R N D 90 31 90 31 90 31 90 31 wp I E I 8901 3 89013 8901 3 89013 V C L 4 1 4 1 - - 4 1 4 1 ss N C rr - s - rr - s - rr - s - rr - s - re O U SSXC1 SSKCI SSKCI SSKC1 es C N t y E i a tl mn ea a9 m8 m/ a9 g8 rm eu hi t tono l r l t H T AS T 5 N E Y b O Y N L G ) M A U U U

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0 30 0 0 3 3 4 0 2 1 1 3 01 1 3 1 3 )) 4 )) )) A aa140 2 i i5 0 aai70 aai40 T (( (( (( S 0 1 0 5 0 8 8 6 7 3 1 3 9 1 1 1 1 K L I M 8 8 N 9 I 1 R A E N T a ) N T m 0 0 0 0

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A I g 2 3 4 4 01 3 1 3 1 3 M i 1 1 5 )) )) 3 f H E S )) 2 o T A aai40 2ii4 0 aai40 aai50 R A 2 T (( (( (( E 3 O M S 0 7 0 0 0 L N M 1 8 3 0 4 B e A 2 1 4 4 4 A g G l 1 1 1 1 T a / ( E O l P R F C W p O S P N O A I T T N A I R G T E 7 7 7 7 R N D 90 31 90 31 90 31 90 31 I E I 89013 8901 3 89013 89013 V C L - - 4 1 - - 4 1 4 1 4 1 N C rr - s - rr - s - rr - s - rr - s - O U S$KC1 SSKCI SSKCI SSKC1 C N M M R E R R B R F E H M E B B T E B M M N T O E E O P T V C M E C O E S O N D M 8 a "'

1 J 2. Fish ) Marine biota can be sensitive indicators of rerlionuclide accumulation in the environment because of their ability to concentrate certain chemical elements which have radioactive isotopes. The results are presented in Tables 24 and 25. Three samples of fish were collected from station 08, the f discharge lagoon. These samples were analyzed by gamma ray spectroscopy and the naturally occurring isotope potassium-40 was found in all three samples at an average of 2183 pCi/kg (wet weight) with a range of 1960 to 2420 pCi/kg (wet weight). Cesium-134, a fission product, was found at an average of 51.5 pCi/kg (wet weight) in all three samples with a range of 31.5 to 68.7 pCi/kg (wet weight). The fission product cesium-137 was found at an average of 262 pCi/kg (wet weight) in ali three samples with a range of 119 to 386 pCi/kg (wet weight). Three samples were also collected from station 09, the control location 2.2 miles upstream on Lake Anna. The same nuclides were detected by gamma ray spectroscopy. Naturally occurring potassium-40 was monitored in all i 1 three samples at an average of 2867 pCi/kg (wet weight) with a range of 2110 to 4190 pCi/kg (wet weight). Cesium-134 was detected in all three samples j at an average of 52.6 pCi/kg (wet weight) with a range of 16.5 to 81.5 pCi/kg (wet weight). Cesium-137 was found in all three samples at an average of 262 pCi/kg (wet weight) with a range of 102 to 351 pCi/kg (wet weight). In the accompanying figJres the fission products cesium-134 and I cesium-137 are plotted for the fish samples collected at stations 08 and 09 from 1981 to the present. The increase seen in 1985 was due to substantial primary to secondary steam generator problems experienced at No-th Anna. l 7"

i The subsequent decreasing cesium activities are due to repairs made to the steam generator, thus reducing the effluent activities released to the environment, I I I I I 4 I .t I I I 1 I I i 73 ....................................i ...J

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7 2 1 3 3 3 1 2 M 3 1 1 t 1 i 1 i i s 2 9 6 2 1 2 2 C 8 1 8 3 5 0 6 2 1 3 3 3 1 2 M 0 4 1 1 . 0 7 1 M 2 6 8 4 1 9 9 6 1 6 4 3 1 i t i i i i 1 4 5 7 5 5 1 M 8 6 2 s C 4 1 8 9 1 5 3 6 5 8 1 5 H S 8 I 5 0 0 M 8 F 9 1 6 6 1 7 8 o 9 N C 1 I S a A R m M I N E g N T i A T S H M 2 2 5 T E 0 0 0 0 0 0 6 2 R i 4 0 2 3 2 1 6 O A 2 2 2 2 4 2 1 M 0 E N M ) ) L M t 4 a i i t 2 1 i i B A e ( A G w K 0 0 0 0 0 0 5 T R ( 2 6 7 0 9 1 2 E F 4 9 1 3 1 1 5 W O g 2 1 2 2 4 2 2 M I I p O k P S / N t A O C N T I A G R E M I N Y R T P V E T C D N E L O L L C P M M A e S re w s r M i e e t td N O mt I ec T 8 8 8 8 9 9 9 e A 0 0 0 0 0 0 0 al T ml S mo ac g t r o en ) h a t e N O ( ol p I 8 8 8 8 8 8 8 8 l m T 8 8 8 8 8 8 8 8 e d. l a CE / / / / / / / / g AS ET 4 1 6 2 4 1 2 0 as LA 1 2 2 2 1 2 2 2 r LD / / / / / / / / e2 ) O 4 6 7 9 4 6 7 9 v

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1 l l I I 3. Food Products / Vegetation ) Thirty-five food samples were collected from five locations and i analyzed by gamma spectrometry. The samples consisted of green leafy l vegetables such as cabbage and lettuce. The results are presented in Tables 26 and 27. Naturally occurring potassium-40 was monitored in all of the ) I samples with an average activity level of 6878 pCi/kg (wet weight) and a range of 2690 to 16300 pCi/kg (wet weight). Cosmogenic beryllium-7 was j detected in twenty-nine of the thirty-five samples with an average concen-i tration of 2115 pCi/kg (wet weight) and a range of 177 to 6390 pCi/kg (wet l l weight). The terrestrial nuclide thoritsn-228 occurred in six of the samples at an average activity of 131 pCi/kg (wet weight) and a range of 47.3 l to 220 pCi/kg (wet weight). Radium-226 was detected in one sample with an activity of 936 pCi/kg (wet weight). The fission product cesium-134 was observed in one sample with an activity of 122 pCi/kg (wet). Cesium-137 was detected in sixteen of the thirty-five samples with an average activity of 132 pCi/Kg (wet weight) and a range of 13.4 to 370 pCi/Kg (wet weight). In recent years cesium-137 has I been detected sporadically and has been attributed to global f allout from past atmospheric weapons testing. These results are consistent with those measured in previous years. i \\ l 78 L

E N FN E OIDM TEE RUTR O O O O O O EORU BROS MNPA t OEE NNRM M NO I T A N C EO ONGI E E E E E E LANT N N N N N N EAC O O O O O O LMRA N N N N N N O R R F T NO C ) ) 0 8 0 0 ) 8 N )9 )3 5 9 O 73 76 ) )4 ) ) 1 EI /6 /1 7 72 7 7 NGT 7 - 7 - / / - / / 9 ANC (0 0 1 31 1 1 3 1 NEAA 40 (50 ( ( ( ( 3 3 AMRR 7 6 1 4 2 50 6 6 / E F 91 55 2 87 3 3 8 R M 2( 8( 1 1( 9 9 Y 3 E NO R 3 B T I o A M S n M 0 E E T M 5 C H C S O D IG E n U E R io N H I E t. D M o A T t H S W W E W i9 G K I D E S N N S N s7 R E T O C 1 WtA i W i W o9 N S S R O M m im i P1 P D Y NAE i m im m m l r R ONC 3 6 ae G A I N 7 9 0 2 0 icb 3 N U T A 9 m 1 ne I N A T 1 0 1 1 O J O I 0 h v R A C S co 6 I L O 5 3 1 6 3 1 eN T 1 2 2 1 2 2 T N 2 O h1 M c E S nn L N ao L O ri B A I B s A T T N N T i ) C v E O A M I C ) )0 R e NR N T O 5) 50 )) ) S O A L 30 33 ) 50 ) )0 R T N /9 /6 5 37 5 52 U, I S R EO 93 51 3 /3 3 32 n V ONGI 26 3 - / 6 - / / - na L O I CMRA 17 7 6 2 23 6 (63 i r N R T ANT 0 1 1 4 1 E E ALAC (57 (89 ( ( ( g 1 7 d o W A A P N I R 11 82 2 31 3 34 er C I D F 2( 6( 1 1( 9 1( rP M I A I L N i R G ug G R I qn O E ei rr L L V L I C A o O dt U D N Y ni M an A T T o R A N I N) e N U dM N O M L I 0 0 inl A C I O1( 8 8 f t a H A T T S RFC) en O I EOED d e R M n U W T L y N O O EL sr L L D( aor 5 5 5 5 5 5 5 ni DR 3 3 3 3 3 3 3 iov NES n ABE tE MSD c SUYE el I NLM t a S AR ec YLNO di LAAF 4 7 6 8 g AT R a 3 3 2 2 f o NOFE m 7 0 1 1 2 2 ol ATOP m 4 o G B K C C R T iti a e s s a h d ) ima T l R N e E Y M rl A E eb W R n wa T S io lot H U pe A A t) P E at isc DM t e c RE ew A OLF g( O PO e L n MM V g L a IUAT /k SI d/ D N oi ) 1 E U oC ( M ( F p M ll

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1 1 E. DIRECT RADIATION EXPOSURE PATHWAY 1. TLD Dosimeters Thermoluminescent dosimeters (TLDs) determined environmental radiation dose rates and the results are contained in Tables 28, 29 and ]

30. A TLD badge of four readout areas each was deployed quarterly at 12 locations around the periphery of the plant.

The mean values of four readings (calibrated individually for response to a known dose and for intransit dose) are reported in this table. Individual measurements of l external radiation levels in the environs of the North Anna site had an average dose of 5.6 mR/ standard month with a range of 3.1 to 8.7 mR/stan-dard month. The control station, No 24 had an average reading of 4.4 mR/ standard month with a range of 3.1 to 5.0 mR/ standard month. The highest dose was at station 01, NAPS Sewage Treatment Plant, 0.2 miles, 42 degrees NE, with a reading of 7.7 mR/ standard month and a range of 5.9 .to 8.7 mR/ standard month. Sector TLDs are deployed quarterly at thirty-two locations in the environs of the North Anna site. Two badges are placed at each location. The results are presented in Tables 28 and 30. The average l kvel 04 the 32 locations (two badges at each location) was 6.3 mR/ standard month with a range of 2.5 to 16.3 mR/ standard month. The six control TLDs showed an average reading of 4.8 mR/ standard month with a range of 2.8 to 6.7 mR/ standard month. Seven of the badges were vanda-lized; one during the first quarter, one during the second quarter, three during the third quarter and tivo during the fourth quarter. The highest dose levels were at station SW-54 with an average level of 10.0 mR/stan-81

I l dard month and a range of 6.2 to 16.3 mR/ standard month. On one figure the results of the environmental TLDs are plotted from 1977 through 1985 in mR/ day. For 1986, 1987 and 1988 the results were platted in mR/ standard l i month on a second figure. For the period 1985 through 1988, the external ) l radiation levels have remained constant at approximately 0.2 mR/ day (or 6 ) mR/ standard month). The sector TLDs have been in use since 1984 and the results for 1984 through 1985 are plotted on the same two figures discussed above. The results of the sector TLDs are comparable to the results of the environmental TLDs. I I I I l 4 l l 82

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l l t { i V. CONCLUSIONS t 1 90

I I l V. CONCLUSIONS l ) The results of the 1988 Radiological Environmental Monitoring Program for the North Anna Nuclear Power Station have been presented. The results were as expected for normal environmental samples. Naturally occurring activity was observed in sample media in the expected activity ranges. Occasional samples of nearly all media showed the presence of man-made isotopes. These have been discussed individually in the text. Observed activities were at very low concentrations and had no significant dose consequence. As a method of referencing the measured radionuclides concentrations in sample media to the dose consequence, the data may be compared to the Reporting Level Concentrations listed in the NRC Regulatory Guide 4.8. These concentrations are based upon 25% of the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion "As Low as is leasonably Achievable." Specific examples of sample media with positive analysis results are discussed below. AIRBORNE EXPOSURE PATHWAY Air particulate gross beta concentrations of all the indicator 4 locations for 1988 followed the gross beta concentrations at the control location. The gross beta concentrations were comparable to levels observed since 1982 except for a five week period in 1986 which was influenced by the Chernobyl accident. Gamma isotopic analysis of the particulate samples identified the gamma emitting isotopes as natural products (beryllium-7 and potassium-40). Except for one measurement of the fission product cesium-137 no other man-made activity was found in the particulate media during 1988. No iodine-131 was detected in charcoal filters in 1988. I 91

A precipitation sample was collected monthly and analyzed for gross I beta activity. All the gross beta activities were comparable to those measured in previous years. Semi-annual composites were analyzed for gamma emitting isotopes and tritium. There was one measurement of beryllium-7 during 1988, however all other gamma emitters were below their detection limits. Tritium was observed in one sample at a level of 250 pCi/f. I WATERBORNE EXPOSURE PATHWAY No man-made or natural isotopes were monitored in the surface water of Lake Anna except tritium. The average tritium activity at the waste heat treatment facility was 3915 pCi/l which is 19.6% of the reporting level for a water sample. In 1987 the tritium level was 3763 pCi/f. The preopera-tional level was 150 pCi/l and has been rising since 1977. The tritium level upstream of the site was 3010 pCi/1 as compared with 2665 pCi/f in 1987. This is particularly significant since it is upstream of the site. The samples of surf ace water collected by the Commonwealth of Virginia j at tne waste heat treatment f acility had similar tritium results with an average activity of 4333 pCi/f. The upstream location had a lower average I activity of 1505 pCi/f. Naturally occurring potassium-40 was detected in J I one sample at the upstream location. No other gamma emitting isotopes were detected. River water callected from the North Anna Rive-S.8 miles downstream of the site had an average tritium level of 3925 pCi/f. The average tritium i 1 in 1987 had been 3680 pCi/f. No gamma emitters were detected. Ground water from the environmental well on site contained no gamma emitters. The average level of tritium in ground /well water was 170 pCi/f which is a low environmental level. ' I 92

I I AQUATIC PATHWAY Sediment / silt samples provide a sensitive indicator of discharges from ] nuclear power stations. The sediment from North Anna environmental samples indicated that two man-made isotopes were present. Cesium-137 was monitored at all six stations. Cesium-137 was also monitored in preoperational samples of aquatic sediment; however, additional man-made isotopes appear to have accumulated. Cesium-134 was monitored in one sample. Sediment contamin-q ation does not provide a direct dose pathway to man. The samples of shoreline soil monitored downstream of the site contained 1 no cesium-134. Cesium-137 occurred at levels considerably lower than in sediment samples. 1 INGESTION PATHWAY Iodine-131 was not measured in any of the 24 milk samples using the radiochemical separation method. Cesium-137 was detected in one milk sample in January 1988. Cesium-137 has been detected occasionally in previous years and then was attributed to past atmospheric nuclear weapons testing. Strontium-90 was measured in all of the milk samples. The values were comparable to the levels in 1987 and somewhat lower than preoperational years. Strontium-90 from those years is attributed to past atmospheric nuclear weapons testing. No strontium-89 was detected in any of the milk samples. Naturally occurring potassium-40 was measured in all the milk samples at normal environmental levels. Activity in fish and vegetation samples along with milk does present a direct dose pathway to man. Fish samples in 1988 showed the presence of the man-made isotopes cesium-134 and cesium-137. These isotopes were at an I I 93

I-I. activity level somewhat higher than preoperational levels but statistically l similar to levels in 1986 and 1987. Only cesium-137 was measured in pre-operational environmental fish samples. Due to primary and secondary steam generator problems experienced at North Anna during 1984/1985, a build up in activity levels both in effluents and fish did occur. Repairs to the steam generators has reduced these activity levels in effluents and thus decreased activity levels are now being observed in the fish. The average level of g activity in 1988 of cesium-134 was 5.2% of the reporting level and cesium-137 was 13.1% of the reporting level. I Vegetation samples contained the man-made isotope cesium-137. One measurement of cesium-134 was observed. The cesium-137 activity levels in j 1987 and in preoperational samples were statistically similar to the 1988 level. DIRECT EXPOSURE PATHWAY The direct exposure pathway as measured in the environment of the North Anna site by thermoluminescent dosimetry has remained essentially the same since the preoperational period in 1977 at 6 milliroentgen per month or 0.2 milliroentgen per day. The average dose levels monitored have shown a normal fluctuation about these levels which are less than the estimated whole body dose due to natural terrestrial and cosmic radiation and the internal dosage from natural radionuclides. Based upon the evidence of the environmental monitoring program the station is operating within regulatory limits. Thus, no unusual radiological characteristics were observed in the environs of the North Anna Nuclear Power Station in 1988. I I 94

l r 4 I I I I I ) I VI. LAND USE CENSUS I I I I I I I 95

i VI. LAND USE CENSUS Technical Specification 3.12.2 requires that a Land Use Census be conducted within a distance of 8 km (5 miles) from North Anna on an annual basis. This census identifies the location of the nearest milk cow, the nearest resident and the nearest garden of E greater than 50 m2 (500 ft.2) producing broad leaf vegetation in each of the 16 meteorological sectors. The results of the Land Use Census are used to calculate the principal exposure pathway from gaseous effluents. This pathway analysis is compared to previous analysis to determine the requirements for modification of the Radiological Environmental Monitoring Program and/or the calculational model used for determining dose contributions to the unrestricted area. I The results of the 1988 Land Use Census show no changes to the Radiological Environmental Monitoring Program or to the Offsite Dose Calculation Manual Pathway Models. The results of the Land Use Census are presented in tabular form I on page 97. A map indicating the locations of the nearest resident, nearest milk animal, and the nearest garden greater than 50m2 producing broad leaf vegetation is presented on page 98. E I 4 E I E 96 l l

I VIRGINIA POWER NORTH ANNA POWER STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL LAND USE CENSUS DATA FOR 1988 ( SEPTEMBER 07 - 09, 1988 ) NEAREST NEAREST SITE MILK MEAT MILK VEG. CARDEN SECTOR RESIDENT BOUNDARY COW

ANIMAL COAT *

> 500 Sq.Ft. (km) (km) (km) (km) (km) (km) l N 1.43 1.40 4.02 2.62 NNE 1.61 1.36 2.82 3.06 1.32 6.44 3.62 NE 1.53 i ENE 2.94 1.31 4.18 3.02 E 2.09 1.33 5.23 3.46 ESE 2.01 1.37 4.02 4.02 SE 2.62 1.41 2.62 2.62 SSE 1.81 1,47 2.62 1.81 S 1.85 1.52 2.62 2.62 SSW 2.25 1.62 2.49 2.25 SW 2.62 1.70 2.66 2.62 WSW 2.21 1.75 2.90 2.90 W 2.66 1.71 3.22 3.22 WNW 2.90 1.64 6.84 4.43 NW 2.62 1.56 4.22 2.62 NNW 1.21 1.45 3.42 3.46 I

Note:

No milk cows or milk goats within a five mile radius of North Anna Power Station. I I E 97

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l l l l l l l I l l l VII. SYNOPSIS OF ANALYTICAL PROCEDURES I [ l i l l 1 l l i 99 1

I Vll. SYN 0PSIS OF ANALYTICAL PROCEDURES I Section VII is a synopsis of the analytical procedures performed on samples collected for the North Anna Power Station Radiological Environmental i Monitoring Program. All analyses have been mutually agreed upon by VEPC0 and Teledyne Isotopes and include those requested by the USNRC Regulatory Guide 4.8,BTP, Rev. 1, November 1979. ANALYSIS TITLE PAGE Gross Beta and Gross Alpha of Air Particulate Samples................. 101 Gros s Beta An alysi s of Water Samples.................................. 102 An al ys i s o f Sampl e s fo r T r i t i um....................................... 103 Water............................................................103 An alysi s of Sampl es for Iodi ne-131.................................... 104 Milk or Water.................................................... 104 Gamma Spectrometry of Samples.......................................... 05 Milk and Water................................................... 105 Dried Solids other than Soils and Sediment....................... 105 Fish............................................................. 105 Soils and Sediments.............................................. 105 Ch arco al Ca rtridges ( Ai r Iodi ne)................................. 105 Air Particulate................................................. 105 E n v i ro nme n t al Do s ime t ry............................................... 107 An alys i s of Sampl es for St ront i um-89 and -90.......................... 108 Total Water...................................................... 108 Milk............................................................. 108 Soil and Sediment................................................ 108 Organic S011ds................................................... 109 Air Particulate................................................. 109 I 100 a

i l GROSS BETA AND GROSS ALPHA ANALYSIS OF AIR PARTICULATE SAMPLES j Af ter a delay of five or more days, allowing for the radon-222 and radon-220 (thoron) daughter products to decay, the filters are counted in a gas-flow proportional counter. The sample is counted at one operating voltage for gross beta and then changed to a second operating voltage for gross alpha. Calculation of the results, the two sigma error and the lower limit of detection (LLD). 3 RESULT (pCi/m ) =((S/T) - (B/t))/(2.22 V E) =((S/T ) + (B/t ))1/2 (2.22 V E) 2 2 / TWO SIGMA ERROR (pCi/m3) l =4.66 (B /2)/(2.22 V E t) LLD(pCi/m3) where: S = Gross counts of sample B = Counts of background (different for alpha and beta) E = Counting efficiency (different for alpha and beta) T = Number of minutes sample was counted t = Number of minutes background was counted V = Sample aliquot size (cubic meters) l } 101

I I 4 GROSS BETA ANALYSIS OF WATER SAMPLES I One liter of sample is evaporated to near dryness and the residue is trans-ferred to a tared, 2" diameter planchet and final evaporation to dryness takes place under heat lamps. The planchet is weighed and then counted in a gas-flow proportional counter. I Calculation of the results, the two sigma error and the lower limit of detection (LLD). RESULT (pCi/l) =((S/T) - (B/t))/(2.22 V E) ) =((S/T ) + (B/t ))1/2 (2.22 V E) ) 2 2 / TWO SIGMA ERROR (pCi/2) l =4.66 (B /2)/(2.22 V E t) LLD(pCi/f) where: S = Gross counts of sample 8 = Counts of background I E = Counting efficiency T = Number of minutes sample was counted t = Number of minutes background was counted V = Sample aliquot size (liter) i l I l 102 l

I I ANALYSIS OF SAMPLES FOR TRITIUM i Water l l Approximately 2 ml of water are converted to hydrogen by passing the water, I I heated to its vapor state, over a granular zinc conversion column heated to 400* C. The hydrogen is loaded into a one liter proportional detector and j the volume is determined by recording the pressure. The proportional detector is passively shielded by lead and steel and an electronic, anticoincidence system provides additional shielding from cosmic rays. Calculation of the results, the two sigma error and the lower limit detec-tion (LLD) in pCi/f: I l V) RESULT = 3.234 T V (CG - B)/(CN 3 N N I 1 TWO SIGMA ERROR = 2((CG+ )'.t) / 3.234 T Y /((C V ){ G-B)) S N N N LLD = 4.66 (3.234)T V (C ) / /(6t C S) N N G N I where: T = tritium units of the standard N 3.234 = conversion factor changing tritiun units to pCi/f V = volume of the standard used to calibrate the N efficiency of the detector in psia I V = volume of the sample loaded into the detector in psia 3 C = the cpm activity of the standard of volume VN N C = the gross activity in cpm of the sample of volume V3 G and the detector volume I l B = the background of the detector in cpm i at = counting time for the sample l I I I 103

I I i ANALYSIS OF SAMPLES FOR 10 DINE-131 Milk or Water Two liters of sample are first equilibrated with stable iodide carrier. A batch treatment with anion exchange resin is used to remove iodine from the l I sample. The iodine is then stripped from the resin with sodium hypochlorite l solution, is reduced with hydroxylamines hydrochloride and is extracted into l carbon tetrachloride as free iodine. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting. The chemical yield is corrected by measuring the stable iodide content of the milk or the water with a specific ion electrode. Calculations of results, two sigma error and the lower limit of detection (LLD) j i in pCi/f: RESULT =-(N/At-B)/(2.22 E V Y DF) TWO SIGMA ERROR = 2((N/At+B)/At)1/2(2.22 E V Y DF) = 4.66(B/At)1/2 (2.22 E V Y DF) / LLD I total counts from sample (counts) where: N = I At = counting time for sample (min) B = background rate of counter (cpm) 2.22 = dpm/pCi V ' volume or weight of sample analyzed I Y = chemical yield of the mount or sample counted DF = decay factor from the mid-collection date to the I counting date E = efficiency of the counter for I-131, corrected for I self absorption effects by the formula E = E (exp-0.0061M)/(exp-0.0061M ) s s E = efficiency of the counter determined from an l s l-131 standard mount M = mass of PdI on the standard mount, mg s 2 M = mass of PdI2 on the sample mount, mg I 104

GAMMA SPECTROMETRY OF SAMPLES Milk and Water A 1.0 liter Marinelli beaker is filled with a representative aliquot of the s ample. The sample is then counted for at least 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis. 9 Dried Solids Other Than Soils and Sediments A large quantity of the sample is dried it a low temperature, less than 100*C. As much as possible (up to the total sam)le) is loaded into a tared 1-liter Marinelli and weighed. The sample is then counted for at least 1000 minutes with a shielded Ge(Li) detector coupled :o a mini-computer-based data acquisi-tion system which performs pulse height analysis. Fish As much as possible (up to the total sample) of the edible portion of the sample is loaded into a tared Marinelli and weighed. The sample is then counted for at lea.st 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis. Soils and Sediments Soils and sediments are dried to a low temperature, less than 100*C. The soil or sediment is loaded fully into a tared, standard 300 cc container and weighed. The sample is then counted for at least six hours with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system I which performs pulse height analysis. Charcoal Cartridges ( Air Iodine) Charcoal cartridges are counted up to five at a time, with one positioned on the face of a Ge(Li) detector and up to four on the side of the Ge(Li) detector. Each Ge(Li) detector is calibrated for both positions. The I detection limit for I-131 of each charcoal cartridge can be determined (assum-ing no positive I-131) uniquely from the volume of air which passed through it. In the event I-131 is observed in the initial counting of a set, each I charcoal cartridge is then counted separately, positioned on the face of the detector. Air Particulate The four or five (depending on the calendar month) air particulate filters for l a monthly composite for each field station are aligned one in front of another ) and then counted for at least six hours with a shielded Ge(Li) detector ) coupled to a mini-computer-based data acquisition system which performs pulse l height analysis. { I 105

I. A mini-computer software program defines peaks by certain changes in the slope of the spectrum. The program also compares the energy of each peak with a library of peaks for isotope identification and then performs the radio-activity calculation using the appropriate fractional gamma ray abundance, j half life, detector efficiency, and net counts in the peak region. The calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/ volume or pCi/ mass: RESULT = (S-B)/(2.22 t E V F DF) i = 2(S+B)1/2 (2.22 t E V F DF) / TWO SIGMA ERROR = 4.66(B)l/2 (2.22 t E V F DF) / LLD where: S = Area, in counts, of sample peak and background (region of spectrum of interest) B = Background area, in counts, under sample peak, deter-mined by a linear interpolation of the representative backgrounds on either side of the peak t = length of time in minutes the sample was counted 2.22 = dpm/pCi E = detector efficiency for energy of interest and geometry of sample V = sample aliquot size (liters, cubic meters, kilograms, or grams) F = fractional gamma abundance (specific for each emitted l gamma) l DF = decay factor from the collection to the counting date ' I I l 106 i

ENVIRONMENTAL DOSIMETRY Teledyne Isotopes uses a CaSO :Dy thermoluminescent dosimeter (TLD) which 4 the company manufactures. This material has a high light output, negligible thermally induced signal loss (f ading), and negligible self dosing. The energy response curve (as well as all other features) satisfies NRC Reg. Guide 4.13. Transit doses are accounted for by use of separate TLDs. Following the field exposure period the TLDs are placed in a Teledyne Isotopes Model 8300. One fourth of the rectangular TLD is heated et a time and the measured light emission (luminescence) is recorded. The ~LD is then annealed and exposed to a known Cs-137 dose; each area is then read again. This provides a calibration of each area of each TLD after every field use. The transit controls are read in the same manner. Calculations of results and the two sigma error in net milliroentgen (mR): RESULT = 0 = (D +D +D +0 )/4 y 2 3 4 TWO SIGMA EfiR0R = 2((D -0) +(D ~0) +(0 -D)b(0 -D)2)/3) 1 2 3 4 where D = the net mR of area 1 of the TLD, and similarly for D, D, and D4 y 2 3 D =I K/Ry-A y g 1 = the instrument reading of the field dose in area 1 7 K = the known exposure by the Cs-137 source R = the instrument reading due to the Cs-137 dose on area 1 y A = average dose in mR, calculated in similar manner as above, of the transit control TLDs l 107

ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 WATER Stable strontium carrier is added to 1 liter of sample and the volume is reduced by evaporation. Strontium is precipitated as Sr(NO )2 using 3 nitric acid. A barium scavenge and an iron (ferric hydroxide) scavenge are performed followed by addition of stable yttrium carrier and a 5 to 7 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. MILK l Stat'le strontium carrier is added to 1 liter of sample and trichloroacetic acid (TCA) is added to produce a curd. The curd is separated by filtration and is discarded. An oxalate precipitation is performed on the filtrate and I the precipitate is ashed in a muffle furnace. The ash is dissolved and strontium is precipitated as SrN03 using fuming (90%) nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for 7 to 10 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 is determined by precipitating SrC03 from the sample after yttrium separation. is precipitate is mounted on a nylon planchet and iscoveredwithan80mg/cm{aluminumabsorberforlowlevelbetacounting. S0IL AND SEDIMENT The sample is first dried under heat lamps and a 10 gram aliquot is taken. Stable strontium carrier is added and the sample is leached in nitric acid. i The mixture is filtered and the liquid portion is reduced in volume by evapo-l I ration. Strontium is precipitated as Sr(NO )2 using fuming (90%) nitric 3 acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are l i then performed. Stable yttrium carrier is added and the sample is allowed to stand for 7 to 10 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate i is mounted on a nylon planchet and is counted in a low level beta counter to l infer Sr-90 activity. Strontium-89 activity is determined by precipitating l I from the sample after yttrium separation. This precipitate is mounted i SrC03 on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for l low level beta counting. J 108

l l i I-l l Organic Solids A 200g wet portion of the sample is dried and then ashed in a muffle furnace. I Stable strontium carrier is added and the ash is leached in nitric acid. The sample is filtered and the volume is reduced by evaporation. Strontium is precipitated as Sr(NO )2 using fuming (90%) nitric acid. An iron (ferric 3 I hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a 7 to 10 day period for yttrium ingrowth. Yttrium is then precipitate as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity 13 deter-mined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Air Particulate Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The mixture is then filtered and the I filtrate is reduced in volume by evaporation. Strontium is precipitated as Sr(NO )2 using fuming (90%) nitric acid. An iron (ferric hydroxide) 3 scavenge is performed, followed by addition of stable yttrium carrier and a 7 I to 10 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is determined by precipi-from the sample af ter yttrium separation. This precipitate is tating SrC03 mounted on a nylon planchet and is covered with 80 mg/cm2 aluminum absorber for level beta counting. Calculations of the results, two sigma errors and lower limits of detection I (LLD) are expressed in activity of pCi/ volume or pCi/ mass: DF ESR-89) RESULT Sr-89 = (N/At-B -B )/(2.22 V Y3 SR-89 C A TWO SIGMA ERROR Sr-89 = 2((N/At+B +B )/At)1/2 (2.22 V Y / DF ESR-89) C A 3 SR-89 = 4.66((B +B )/At)1/2 (2.22 V Y / DF ESR-89) LLD Sr-89 C A 3 SR-89 Y 0F IF E) RESULT Sr-90 = (N/At - B)/(2.22 V Yi 2 TWO SIGMA ERROR Sr-90 = 2((N/At+B)/At)1/ /(2.22 V Yy 2Y DF E IF)) = 4.66(B/At)1/2 (2.22 V Y Y IF DF E) / y 2 LLD Sr-90 I 109

w I I I I I VIII. EPA INTERLABORATORY COMPARISON PROGRAM I I I I 110

i VIII. EPA INTERLABORATORY COMPARISON PROGRAM Teledyne Isotopes participates in the US EPA Interlaboratory Comparison Program to the fullest extent possible. That is, we participate in the program for all radioactive isotopes prepared and at the maximum frequency of availability. In this section trending graphs (since 1981) and the 1988 data summary tables are presented.for isotopes in the various sample media applicable to the North Anna Stations Radiological Environmental Monitoring Program. The footnotes of the table discuss investigations of problems encountered in a few cases. i l I 111

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N o ih .o t o h no t l o wu ee a p R st)i i t nn an ed rt e 6m l l e or uA pd pp O 4 ) y sv ht a nu ne ess i sP mi e T n l f ne ga n ad i nad c tdet s eE ar r s A O e o aoar ur i7 r n r Ao n hi es r so a R C g i n i p o 8 ga saga r est m k a e l eh O P a t ast h e s9 nd e nd p ra i ah )h eh h B E P a t ar th e1i n p7 i n a gl t ft hc t 8 A V ( n el nu l t p va o8 va 7 w p) n s / t 2 L i nuio A orat t9 at 6e pril Ae l t. t r2 R m osm t ehs o1 hs - n aek o P p C am nr o - E r er, a ob s 2 t a r E o phe i e f a T e yrer .t smrS i rrS 3 e oit t t tl v R N t b t e na i eeB eeB 0h nl n eo 0 b sn n I e rev od ctN rbtN - t /d o h s 5do eo or i rei emi O sgec ti ( er A eh e t6 eDl e h el e R g i mt t p idc s o d d edo af P I r g2r a8 h /h t c/h P n aa t e ea ro e m an l t s ot rd E ei o i/ t eit oel t i e 6.l wh rM v3 ohC DC ys r ug h y psi l o S a o o e1 t ph e ph b u e3ci td m h hd th U m l ef d/ s t h e t h(l s e aAt ci nt a n 0.i th2i 8s t a sl sP c ee g h 1 i w t .w 2t ec3 ee Ef f a rm i st a) e0 l 8 s 0 2l dd tT e o o a s a ms h wd gn t e l d9d an6d - u niyA a h e c pn 1 nio h ee i e as adl P t t he ei p o ( gasi rt wsf - l f e R e ore s. t s cr ai k t o uo l d or r di e d n u nt t n /d1 a fh s g ee g r e pe A e i f a ei oc a o i e .n t a) ea wsea oe t eoh P v oc sn na mg ug f h cl rt E e 0 e e r m i Cd1i ni ( g s pr - m ow aad s ad T ub p i 6ib re dt a( r s sh rn a) rn d d a n eh l pr ex i i 6 c e ag t sea ( s c mea e nt ei h c ol) o l e e 8 set en l rv a v z. osrh t a C e8 em. a l r il e ri uead sh ad ys c et i 8 h s - o a p f dbd t sm e t s e l e f wi f s f v9 tht vi t o a t r eA nr l rnr al so w oi oo1 t i ep n y sr3 na r( aa ueaa np a s N yi m r a e r ti o et p sm p am wndl i s n r bwi r m o l v r rS 6d ee eA ee a ol l l i ok e l n i t usao a 0r vr r( vr es niea lh i nb dd ow r a sif f p 1 aap ap r oti f et t ao eel i e e r es p.. d g 4d g el i ay i a rt st o t n p o r yea ay5 mn s 3 r s wl t r s vw rF c ua r a art ge x b l rm l 1 uasa 1 asa a atl t oo t .O a eaog ot. it ew d ew s gnal Nh n con ih e l gnmi nn1 nsi mni er i ecu ere p o t T aa s a e ci ua ci l o t ci s k s cDv aa c s d r s scd h wnl i t nl pf snme. ne n i h v e e e esi) ii n t eel ss el m eoert at o t pea v. g t vi 7 f a unie e i e ae vch n ra c .c l m n n a c ahh7 ei r cn cwcn ss n cee F c ae agg i o r e t c. rn8 aii eii u i h sd i h mf ni i s e p e i2 eg0 e f r enf r e geei .d gmf wis eg n nihh v r n i a e oe h e e v x hf h - hi h nf a h f a h i AhT t e Di H g( tb3 T r oem T aeM T t A E T I w( T s1 T on t o ) ) ) ) ) ) ) ) ) ) ) ) o a b c d e f g h i j k 1 F ( ( ( ( ( ( ( ( ( ( ( ( 3a E-

dvd dr re u 'm ni u i e gh o at t dv udncb cS oa i nai se l cahhs tr e r l cwe l r v eu adx m uoi h o ceeno sC t t i ic e a n ff n e r r ho oiotb . o ti rin ui a wc c ph mu rnb it eu em Ogl e netii rl sr erirt a o er s wen . mC ro ee po s ec rrd xr ee6. f penet k m7 s rd wa s i a9e ei e no ps1l t e h s) ai s p nl ttd d enm iy ,nosa rhia uh er et s n" yot d t r i - i meur t ayek i c ml e wbt c h4 l m ch ae wt i uL nt Aswh i biMie 8 Pt c eW itE h 8 El A - l sn( yw 9 uP s p so d 1 f sEs m. orgue oe o as. pt nt n M rf r sen sisi A s oc mo r h m R cw eii eessr G iosA ht g hhaie O tl iP t e tt ht R s sE l r o tT e P id y na nh c d rel g i re A ce N enan ec ir .o O ti ni l v n .hidt wd e S caat aea I at a cst p rr R rb rl i p enh oe A A aouu mge titl d P N h oc enc s ipr M N ) c, l hi c t wxo O A 5 1 ya ct a nn e C n4 bc a oet n H f o2 aea i m n gi Y T o i - dn pm ti en R R t mee yeg armis O O 5 pA vh bri reeei T N r iw s a pi b s A e oh r dy px r y R g st e) eb3 eeesl O a bide s s pi a B O P aw n udA nx n A C ( ei aeP Aaepa L P fd vl ciE C e R E l er f T ynt e F V et ud yi e bA sr T sa ce l rh l o N r h bet at nf I hb ns av i u.oe gi oa b n t odib R il i d osi i nt P hat ( ra nduas E cp pws i eork y re i l f ae yov ,g eu pe. S l U ll sr nns h ryewk at bu oii t l s l unac idh nl l l se - t aT neaA aa udfl ce i enCr nnl a er bit ee ueeu r m g vh pss re1 u si e e t oe u od/ i arh s td e cdi th ot f nh e rC n ro ei t h dt p o,soo u t i c7 rt atf s dh g ee7 t n t cnf ll sussdn saio yen oot eee iey e i ml vrn l d eh e d uioo d, pa dgb amstt p eype ii rueasm t r at dh e i rn o oo s o v f t rec nt sn i ea oneer a ei hh omt at nr v eT sral a ) ool) l d st sasf ib oe b l os e t t a vn a. u l esl r n al ni t eo l h apo o i i l sd w eat m C vt o l n ) an ( es nd yrt bi gd s i deoi tt l if no e wil l cu s i hkt s edt o ues sevtl o e hi cs al e ohi eir t T ma( F er Pt gmmp ) ) on t o ) o m n o F ( ( ( "h j

I f I I IX, REFERENCES i 1 ) i l I 1 I 129

--t ^1X. REFERENCE'S l '. United States. Nuclear' Regulatory Commission, Regulatory Guide 4.8 " Environmental Technical Specifications for Nuclear Power Plants", December, 1975.- 2. Virginia-Electric and Power Company, North Anna Power Station Technical Specifications,. Units 1 and 2. 3. NUREG 0472, " Radiological Effluent Technical Specifications for PWRs, Rev. 3, March '1982. 4. United States Nuclear Regulatory Comm'ssion Regulatory Guide 1.109, Rev.1, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I", October,1977. 5. USNRC Branch Technical Position, " Acceptable Radiological Environ-mental Monitoring Program", Rev. 1, November 1979. l

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