0CAN029514, ANO Unit 1 & Unit 2 Semiannual Radioactive Effluent Release Rept,940701-1231

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ANO Unit 1 & Unit 2 Semiannual Radioactive Effluent Release Rept,940701-1231
ML20080L963
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 12/31/1994
From: Mims D
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
0CAN029514, CAN29514, NUDOCS 9503030070
Download: ML20080L963 (47)
v • d • e


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4= RocselLille /Ji 72801 Toi501 B58-5000 l

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February 28,1995 l

OCAN029514  !

U. S. Nuclear Regulatory Commission .

Document Control Desk l Mail Station PI-137-  !

Washington, DC 20555  ;

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Subject:

Arkansas Nuclear One - Units I and 2 l Docket Nos. 50-313 and 50-368 i License Nos. DPR-51 and NPF-6 i Semiannual Radiological EfHuent Release Repon l for the Third and Founh Quarters Of 1994 j l

Gentlemen.

{

Arkansas Nuclear One, Units 1 and 2 (ANO-1 & 2) Technical Specifications 6.12.2.6 and 3 6.9.3, respectively, require the submittal of a Maaan=1 Radioactive EfBuent Release Report. ,

The purpose of this letter is to complete this reporting requirement for the third and founh l quarters of 1994 at ANO. This submittal also includes the additional information required by l Technical Specifications 6.12.2.6 and 6.9.3 which is to be provided in the first report filed i t

cach year. Liquid and gaseous release data show that the dose from both ANO-1 and ANO-2 is generally a factor of 100 below the technical specification limits. This data reveals that the  ;

radioactive effluents have an overall minimal dose contribution to the surrounding  :

environment. -

l Should you have any questions regarding this submittal, please contact me. >

l Very truly yours, b Mb Dwight C. Mims ,

Director, Licensing i DCM@d attachments 9503030070 941231 PDR ADDCK 05000313 R PDR

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  • U. S. NRC February 28,1995-OCAN029514 Page 2 cc: Mr. I4onard J. Callan Regional Adrninistrator l U. S. Nuclear Regulatory Commission i Region IV 611 Ryan Plaza Drive, Suite 400 1 Arlington, TX 76011-8064 NRC Senior Resident Inspector j Arkansas Nuclear One 1448 S. R. 333 i Russellville, AR72801  ;

Mr. George Kalman NRR Project Manager Region IV/ANO-1 & 2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Ms. Greta Dicus Arkansas Department ofHealth Division ofRadiation Control  ;

and Emergency Management  !

4815 West Markham Street I Little Rock, AR 72205 ,

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  • Attachment I to

, OCAN029514 Page1of37 ARKANSAS NUCLEAR ONE UNIT 1 AND UNIT 2 OPERATING LICENSE NO. DPR-51 AND NPF-6 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY 1 THROUGH DECEMBER 31,1994  ;

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.- Attachment I to )

? ,- OCAN029514 i Page 2 of 37 l m TABLE OF CONTENTS  ;

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1. Introduction  ;

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2. Regulatory Limits  !

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-3. Summary ofLiquid EfBuent Data i

4. Summary ofGaseous EfBuent Data ,
5. Summary ofRadiation Doses
6. Summary of Dose to Members of the Public  ;
7. Historical Effluent Data >
8. Solid Waste Summary
9. Unplanned Releases
10. Radiation Instrumentation i
11. Changes to the Process Control Program
12. Changes to the Offsite Dose Calculation Manual i
13. LLD Levels i
14. Radiological Environmental Monitoring Program ,

i A. Changes in Sample Locations  ;

I B. Identification ofNew Sample Locations i

15. Summary of the Hourly Meteorological Data
16. Description of Major Changes to Radioactive Waste Systems ,

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. OCAN029514 Page 3 of37 e

1.- INTRODUCTION  !

Arkansas Nuclear One (ANO) is a two unit plant consisting of a Babcock & Mrdcox (Unit 1) and a Combustion Fap=sg (Unit 2) design. Both liquid and gaseous efBuents are released in accordance with the technical speci6 cations for each unit. This report is a summary of the ,

l- effluent data in accordance with Unit 1 Technical SrM' *+6.12.2.6 and Unit Two i L Technical Speci6 cation 6.9.3. This report provides the following information.

A. Routine radioactive efBuent release reports covering the operation of the units -

l during the reporting period B. Description ofunplanned releases to unrestricted areas  !

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C. Description of changes to Offsite Dose Calculation Manual (ODCM). l D. Description of changes to Process Control Program (PCP).

E. Summary of radiation doses due to radiological efBuents during the previous calendar year. This data is included in the first report of each year.

F. Radiation dose to members of the public due to their activities inside the site boundary. This data is included in the first report of each year.

G. Description of licmsee initiated major ch= ages to the radioactive waste systems during the previous calendar year. This data is included in the first report ofeach year.

H. Items to be reported in the Semiannual Report per other miscellaneous Technical Specifications.

This report covers the period from July 1 through December 31,1994.

2. REGUIATORY LIMITS Unit One and Unit Two Technical Specifications contain the limits to which ANO must adhere. Because of the "as low as reasonably achievable" (ALARA) philosophy at ANO, an attempt is made to reduce the amount of radiation released to the environment. Liquid and gaseous release data show that the dose from both ANO-1 and ANO-2 is generally a factor of 100 below the technical specification limits This data reveals that the radioactive efBuents have an overall minimal dose contribution to the surrounding environment. The following are the limits required by the technical specifications.

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,W.- ' 0CAN029514 Page 4 of37 _,

A. Gaseous EfBuents .

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1. Dose rate due to radioactive materials released in gaseous efBuent to l

' unrestricted areas shall be limited to the following:

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a. Noble gases l

Less than or equal to 500 mrem / year to the total body  ;

Less than or equal to 3000 mrem / year to the skin .

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b. Iodine-131, tritium, and for all radionuclides in particulate form

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with halflives greater than 8 days -  :

Less than or equal to 1500 mrem /yr

2. Dose-Noble Gases i

Quarterly  !

Less than or equal to 5 mrads gamma  ;

Less than or equal to 10 mrads beta  !

Yearly Less than or equal to 10 mrads gamma l Less than or equal to 20 mrads beta l t

3. Dose - Iodine-131, Tritium, and Radionuclides in Particulate Form i I

Quarterly t

Less than or equal to 7.5 mrems to any organ ,

i Yearly i Less than or equal to 15 mrems to any organ [

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i Attachment' I to

-e> OCAN029514 Page 5 of 37 B. - Liquid Effluents

l. Concentration j 4

The concentration of radioactive material released to the discharge .

canal shall be limited to the concentration specified in 10CFR20, [

Appendix B, Table II, Column 2 for radionuclides other than dissolved  :

or entrained noble gases For dissolved or entrained noble gases, the ~  !

total concentration released shall be limited to 2E-4 microcuries/ml.  ;

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2. Dose j L Quarterly )

Ims than or equal to 1.5 mrem total body [

Less than or equal to 5 mrem critical organ '

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- Less than or equal to 3 mrem total body Less than or equal to 10 mrom critical organ

3.

SUMMARY

OF LIQUID EFFLUENT DATA ,

The following data is a summary of the number and times of releases for both Unit I and Unit 2. These releases occurred between July 1 and December 31,1994.

Unit 1 Unit 2 Number ofreleases: 586 195 Total time for all releases (minutes): 97365 54002 Maximum time for a release (minutes): 466 1050 t Average time for a release (minutes): 166 277 Minimum time for a release (minutes): 5 32 As required by Regulatory Guide 1.21, Rev.1, a summary of data for liquid releases is to be provided in the Semiannual Report. The following five pages provide a summary ofliquid effluents for both Unit I and Unit 2:

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  • OCAN029514 Page 6 of 37

~ SEMIANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL LIQUID EFFLUENTS)

July 1 through December 31,1994 ,

Unit 1 Type ofEffluent Units Quarter 3 Quarter 4 Est. Total Error %

A. Fission and Activation Products

1. TotalRelease(NotIncluding Curies 8.063E-2 7.675E-2 0 Tritium, Gases, Alpha)
2. Average Diluted Concentration Ci/mi 2.115E-10 2.347E-10 During Period
3. Percent of Applicable Limit  % 7.049E-2 7.823E-2 B. Tritium 4
1. TotalRelease Curies 1.293E+2 1.364E+2 0
2. Average Diluted Concentration Ci/mi 3.391E-7 4.170E-7 During Period
3. Percent of Applicable Limit  % 1.130E-2 1.390E-2 C. Dissolved and Entrained Gases
1. TotalRelease Curies 1.693E-1 1.994E+0 0
2. Average Diluted Concentration Ci/mi 4.440E-10 6.096E-9
3. Percent of Applicable Limit  % 2.220E-4 3.048E-3 D. Gross Alpha Radioactivity
1. TotalRelease Curies 2.204E-3 0.000E+0 0 i E. Waste Vol Released (Pre-Dilution) Liters 3.604E+7 3.277E+7 0 F. Volume ofDilution Water Used Liters 3.812E+11 3.270E+11 0

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.. OCAN029514 l Page 7 of 37 -

UNIT 1 REPORT CATLGORY  : SEMIANNUAL IJQUID CONTINUOUS AND BATCH RELEASES

TOTALS POR EACH NUCLIDE RELEASED TYPE OF ACTIVITY ': ALLRADIONUCLIDES REPORTING PERIOD  : QUARTER # 3 AND QUARTER # 4 YEAR 1994  ;

CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 2 QUARTER 4 SN-113 CURIES 0.00E+00 0.00E%0 3.26E-06 0.00E+00 ZR-97 CURIES 0.00E MO 0.00E@0 1.72E 05 0.00E@0 NB-97 CURIES 0.00E+00 0.00E+00 1.85E-05 0.00E+00 CE-141 CURIES 0.00E+00 0.00E40 2.69E-05 0.00E+00 SB-124 CURIES 0.00E+00 0.00E+00 2.74E-05 0.00E+00 G-ALPHA CURIES 0.00E+00 0.00E+00 2.20E-03 0.00E+00 TC-99M CURIES 0.00E+00 0.00E+00 1.76E-05 1.10E-05 AR-41 CURIES 0.00E+00 0.00E+00 0.00E+00 1.23E-05 l SR-92 CURIES 0.00E+00 0.00E+00 0.00E+00 1.33E-05 SB-122 CURIES 0.00E+00 0.00E+00 0.00E+00 1.74E-05 CS-138 CURIES 0.00E+00 0.00E+00 0.00EM0 3.04E-05 KR-85M CURIES 0.00E+00 0.00E+00 2.07E-05 3.14E-05 I-133 CURIES 0.00E+00 0.00EM0 3.56E-05 5.44E-05 CR-51 CURIES 0.00E+00 0.00E+00 1.85E-04 1.27E-04 KR-88 CURIES 0.00E+00 0.00E+00 0.00E+00 1.36E-04 ZR-95 CURIES 0.00E+00 0.00E+00 1.29E-04 1.60E-04 MN-54 CURIES 0.00E+00 0.00E400 6.39E-04 3.43E-04 CO-57 CURIES 0.00E+00 0.00E+00 4.21E-04 4.98E NB-95 CURIES 0.00E+00 0.00E+00 6.42E-04 5.56E-04 AG-110M CURIES 0.00E+00 0.00E+00 1.69E-03 7.69E-04 SR-89 CURIES 0.00E+00 0.00E+00 0.00E+00 1.14E-03 I-131 CURIES 0.00E+00 0.00E+00 1.llE-03 1.29E-03 NA-24 CURIES 0.00E+00 0.00E400 3.79E-03 1.41E-03 CS-134 CURIES 0.00E+00 0.00E+00 2.75E-03 1.43E-03 XE-135 CURIES 0.00E+00 0.00E+00 1.60E-04 3.85E-03 +

CS-137 CURIES 0.00E+00 0.00E+00 8.43E-03 5.31E-03 ,

CO-58 CURIES 0.00E+00 0.00E+00 - 1.27E-02 8.33E-03 l XE-133M CURIES 0.00E+00 0.00E+00 1.25E-03 1.01E-02 FE-55 CURIES 0.00E+00 0.00E+00 4.08E-03 1.09E-02 SB-125 CURIES 0.00E+00 0.00E+00 2.70E-02 2.21E-02 CO-60 CURIES 0.00E+00 0.00E+00 1.69E-02 2.22E-02 i

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CONTINUOUS RELEASES BATCH RELEASES i NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 '

XE-131M- CURIES 0.00E+00 0.00E+00 2.42E-03 3.41E-02 KR-85 CURIES 0.00E+00 0.00E+00 1.20E-02 1.07E-01 XE-133 CURIES 0.00E+00 0.00E+00 1.53E-01 1.84E+00 H-3 CURIES 0.00E+00 0.00E+00 1.29E+02 1.36E+02 Total for CURIES 0.00E+00 0.00E+00 1.30E+02 1.38E+02 Period t

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l 4 Attachment I to l "7 OCAN029514 l Page 9 of 37 SEMIANNUAL SUMMATION FOR ALL RELEASES BY QUARTER  ;

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(ALL LIQUID EFFLUENTS)

July 1 through December 31,1994 j Unit 2 -

Type ofEffluent Units Quarter 3 Quarter 4 Est. Total Error %  ;

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- A. Fission and Activation Products

1. TotalRelease(NotIncluding Curies 3.871E-2 4.334E-2 0 Tritium, Gases, Alpha) i
2. Average Diluted Concentration Ci/ml 1.015E-10 1.325E-10 During Period
3. Percent of Applicable Limit  % 3.385E-2 4.418E-2 B. Tritium
1. TotalRelease Curies 9.163E+1 1.609E+2 9
2. Average Diluted Concentration pCi/ml 2.403E-7 4.920E-7 During Period
3. Percent of Applicable Limit  % 8.01IE-3 1.640E-2 C. Dissolved and Entrained Gases
1. TotalRelease Curies 2.017E-2 1.516E+0 0
2. Average Diluted Concentration pCi/ml 5.291E-11 4.6376E-9
3. Percent of Applicable Limit  % 2.645E-5 2.319E-3 D. Gross Alpha Radioactivity
1. TotalRelease Curies 3.622E-3 4.526E-4 0 ,

i E. Waste Vol Released Pre-Dilution) Liters 6.949E+6 8.905E+6 0 F. Volume ofDilution Water Used Liters 3.812E+11 3.270E+11 0

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, OCAN029514 Page 10 of 37 UNIT 2 REPORT CATEGORY  : SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES

TOTALS FOR EACH NUCLIDE RELEASED.

TYPE OF ACTIVITY  : ALL RADIONUCLIDES REPORTING PERIOD  : QUARTER # 3 AND QUARTER # 4 YEAR 1994 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 NB-95 CURIES 0.00E+00 0.00E+00 1.98E-05 0.00EM0 -

ZR-95 CURIES 0.00E%0 0.00E40 2.28E-05 0.00E+00 NA-24 CURIES 0.00E+00 0.00E+00 2.45E-05 0.00E+00 I-133 CURIES 0.00E40 0.00E40 5.64E-05 0.00E+00 Y-91M CURIES 0.00E+00 0.00E+00 8.37E-05 0.00E+00 CR-51 CUPJES 0.00E+00 0.00E+00 6.24E-04 0.00E+00 SN-113M CURIES 0.00E+00 0.00E@0 0.00E+00 4.95E-06 I-134 CURIES 0.00E+00 0.00E%0 0.00E+00 7.25E-06 CO-57 CURIES 0.00E%0 0.00E+00 5.77E-05 8.30E-05 SB-124 CURIES 0.00E+00 0.00EN)0 1.54E-03 1.08E-04 XE-135 CURIES 0.00E%0 0.00E+00 1.10E-04 2.62E-04 AG-110M CURIES 0.00E+00 0.00E+00 2.41E-04 3.03E-04 G-ALPHA CURIES 0.00E+00 0.00E40 3.62E-03 4.53E-04 CS-134 CURIES 0.00E+00 0.00E+00 6.14E-04 1.57E-03 FE-55 CURIES 0.00E+00 0.00E+00 5.24E-03 3.01E-03 MN-54 CURIES 0.00E+00 0.00E+00 1.75E-03 3.29E-03 CO-60 CURIES 0.00E+00 0.00E+00 1.35E-03 3.53E-03 ,

I-131 CURIES 0.00E+00 0.00E+00 1.72E-03 4.55E-03 l CS-137 CURIES 0.00E+00 0.00E+00 2.00E-03 5.09E-03 l SB-125 CURIES 0.00E40 0.00E40 1.12E-02 6.55E-03 I I

XE-133 CURIES 0.00E+00 0.00E+00 0.00E+00 7.97E-03 CO-58 CURIES 0.00E+00 0.00E+00 1.21E-02 1.52E-02 XE-131M CURIES 0.00E+00 0.00E+00 0.00E+00 1.84E-02 l XE-133 CURIES 0.00E%0 0.00E40 2.01E-02 1.49E+00 H-3 CURIES 0.00E+00 0.00E+00 9.16E%1 1.61E+02 l Total for CURIES 0.00E%0 0.00E+00 9.17E+01 1.62E%2 Period i

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. OCAN029514 Page 11 of37

4.

SUMMARY

OF GASEOUS EFFLUENT DATA As required by F-h*=y Guide 1.21, Rev.1, a summary of data for gaseous releases is '

provided in the. Semiannual Report. This summary covers releases from July 1 to December 31,1994. The summary of gaseous effluents for both Unit I and Unit 2 is as ,

' follows:

Unit 1 Unit 2 Number ofreleases- 56 87 Total time for all releases (minutes): 448012 468284 t

Merimum time for a release (minutes): 10295 10619 e Average time for a release (minutes): 8000 5321 i Minimum time for a release (minutes): 57 2 The Unit 1 gaseous releases consisted of:

7 emergency feedwater (EFW) pump releases - These releases were a result of surveillances to the steam driven EFW pump.

49 vent releases ,

The Unit 2 gaseous releases consisted of: j 10 emergency feedwater (EFW) pump releases - These releases were a result of surveillances to the steam driven EFW pump.

77 vent releases I

' Attachment I to

.- OCAN029514 Page 12 of 37 l SEMIANNUAL SUMMATION FOR ALL RELEASES BY QUARTER j (ALL AIRBORNE EFFLUENTS) J July 1 through December 31,1994  :

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Unit 1 Type ofEffluent Units Quarter 3 Quarter 4 Est. Total Error % ,

A. Fission and Advation Products

1. TotalRelease Curies 0.000E+0 1.101E+1 0
2. Average Release Rate for Period pCi/Sec 0.000E+0 1.385E+0
3. Percent of Applicable Limit  % 0.000E+0 1.938E-2 B. Radioiodines
1. TotalIodine-131 Curies 0.000E+0 'E-7 0
2. Average Release Rate for Period Ci/Sec 0.000E+0 -

c.E-7

3. Percent of Applicable Limit  % 0.000E+0 3.215E-7 C. Particulates
1. Particulates (Half-Lives > 8 Days) Curies 4.118E-9 8.550E-7 0
2. Average Release Rate for Period Ci/Sec 5.181E-10 1.076E-7
3. Percent of Applicable Limit  % 1.451E-9 3.012E-7
4. Gross AlphaRadioactivity Curies 1.907E-6 1.703E-6 D. Tritium
1. TotalRelease Curies 1.257E+0 4.588E+0 0
2. Average Release Rate for Period pCi/Sec 1.581E-1 5.773E-1
3. Percent of Applicable Limit  % 2.214E-4 8.082E-4 I

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.- OCAN029514  ;

Page 13 of37 l

UNIT 1 REPORT CATEGORY  : SEMIANNUAL AIRBORNE GROUND LEVEL i

CONTINUOUS AND BATCH RELEASES l
TOTALS FOR EACH NUCLIDE RELEASED TYPE OF ACTIVITY  : FISSION GASES, IODINES, AND PARTICULATES REPORTING PERIOD.  : QUARTER # 3 AND QUARTER # 4 YEAR 1994 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 Fission Gases XE-133 CURIES 0.00E+00 0.00E400 0.00E+00 1.10E+01 Total for CURIES 0.00E+00 0.00E+00 0.00E+00 1.10E+01 Period Iodines 1-131 CURIES 0.00E+00 0.00E+00 0.00E+OO 9.13E-07 I-133 CURIES 0.00E+00 0.00E+00 0.00E+00 2.53E-06 Total for CURIES 0.00E+00 0.00E400 0.00E400 3.44E-06 Period Particulates NB-95 CURIES 0.00E+00 0.00E400 0.00E+00 5.13E-07 Total for CURIES 0.00E+00 0.00E+00 0.00E+00 5.13E-07 Period Other SR-89 CURIES 0.00E+00 0.00E+00 4.12E-09 3.42E-07 G-ALPHA CURIES 0.00E+00 0.00E+00 1.91E-06 1.70E-06 H-3 CURIES 0.00E+00 0.00E+00 1.26E+00 4.59E+00 Total for CURIES 0.00E+00 0.00E+00 1.26E+00 4.59E+00 Period l

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Page 14 of 37.

SEMIANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL AIRBORNE EFFLUENTS)

July 1 through December 31,1994 Unit 2 Type ofEffluent Units Quarter 3 Quarter 4 Est. Total Error %

A.' Fission and Activation Products

1. TotalRelease Curies 5.316E+1 3.201E+2 0
2. Average Release Rate for Period Ci/Sec 6.688E4 4.027E+1
3. Percent of Applicable Limit  % 9.364E-2 5.638E-1 B. Radioiodines
1. TotalIodine-131 Curies 7.059E-8 5.257E-7 0
2. Average Release Rate for Period pCi/Sec 8.881E-9 6.614E-8
3. Percent of Applicable Limit  % 2.487E-8 1.852E-7 C. Particulates I
1. Particulates (Half-Lives > 8 Days) Curies 1.113E-8 3.807E-7 0
2. Average Release Rate for Period pCi/Sec 1.400E-9 4.790E-8
3. Percent of Applicable Limit  % 3.921E-9 1.341E-7 l
4. Gross AlphaRadioactivity Curies 1.71IE-10 2.682E-6 D. Tritium
1. TotalRelease Curies 1.502E+0 3.324E% 0
2. Average Release Rate for Period pCi/Sec 1.889E-1 4.181E-1
3. Percent of Applicable Limit  % 2.645E-4 5.854E-4 l l
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. OCAN029514 Page 15 of37 UNIT 2 REPORT CATEGORY  : SEMIANNUAL AIRBORNE GROUND LEVEL *

CO TINUOUS AND BATCH RELEASES
TOTALS FOR EACH NUCLIDE RELEASED TYPE OF ACTIVITY  : FISSION GASES, IODINES, AND PARTICULATES REPORTING PERIOD  : QUARTER d *, AND QUARTER # 4 YEAR 1994 CONTINUOUS RELEASES BATCH REI. EASES NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 Fission Gases XE-135 CURIES 0.00E400 0.00E+00 9.98E+00 1.20E+01 XE-133 CURIES 0.00E+00 0.00E+00 4.32E401 3.08E+02 Total for CURIES 0.00E+00 0.00E+00 5.32E+01 3.20E+02 Period Iodines i I

I-133 CURIES 0.00E400 0.00E+00 3.48E-08 2.36E-07 I-131 CURIES 0.00E+00 0.00E+00 7.06E-08 5.26E-07 I-134 CURIES 0.00E+00 0.00E400 0.00E+00 3.39E-05 l Total for CURIES 0.00E+00 0.00E+00 1.05E-07 3.47E-05 Period Particulates i Total for CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Period 1

i Other SR-89 CURIES 0.00E+00 0.00E400 1.10E-11 0.00E400 .

SR-90 CURIES 0.00E+00 0.00E+00 1.11E-08 3.81E-07 l' G-ALPHA CURIES 0.00E+00 0.00E+00 1,71E-10 2.68E-06 H-3 CURIES 0.00E+00 0.00E400 1.50E400 3.32E+00 Total for CURIES 0.00E+00 0.00E+00 1.50E+00 3.32E+00 Period i

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. Page 16 of 37

5.

SUMMARY

OF RADIATION DOSES The following is a summary of the annual radiation doses due to radiological effluents during 1994 calculated in accordance with the Offsite Dose Calculation Manual.

UNIT 1' Liquid Radwaste Effluents Dose Limits (mrem): Total Body = 1.5/Qtr 3Nr, Other Organs = 5/Qtt 10Nr Organ _QLL1  % _Q1L2  % .Q1L1  % .Qtr_4  % XcK  %

TBody 0.0072 0.48 0.0141 0.94 0.0054 0.36 0.0036 0.24 0.0302 1.01 Bone 0.0068 0.14 0.0126 0.25 0.0047 0.09 0.0032 0.06 0.0274 0.27 Liver 0.0099 0.20 0.0200 0.40 0.0076 0.15 0.0050 0.10 0.0424 0.42 Thyroid 0.0001 0.00 0.0013 0.03 0.0047 0.01 0.0008 0.02 0.0029 0.03 Kidney 0.0033 0.07 0.0069 0.14 0.0026 0.05 0.0018 0.04 0.0147 0.15 Lung 0.0012 0.02 0.0025 0.05 0.0010 0.02 0.0007 0.01 0.0055 0.05 GI-LLI 0.0023 0.05 0.0109 0.22 0.0066 0.13 0.0066 0.13 0.0264 0.26 Gaseous Radwaste Effluents Iodine, H-3, and Particulate (ITP) - Dose Limits (mli:=) =- 7.5/Qtr 15Nr DIgan Q1L1  % _Q1L2  % _Qtti  % .QLL4  % XcK  %

TBody 0.0024 0.03 0.0017 0.02 0.0008 0.01 0.0028 0.04 0.0077 0.05 Bone 0.0001 0.00 0.0000 0.00 0.0000 0.00 0.0000 0.00 0.0001 0.00 Liver 0.0024 0.03 0.0017 0.02 0.0008 0.01 0.0028 0.04 0.0077 0.05 Thyroid 0.0024 0.03 0.0017 0.02 0.0008 0.01 0.0030 0.04 0.0079 0.05 Kidney 0.0024 0.03 0.0017 0.02 0.0008 0.01 0.0028 0.04 0.0077 0.05 Lung 0.0024 0.03 0.0017 0.02 0.0008 0.01 0.0028 0.04 0.0077 0.05 GI-LLI 0.0024 0.03 0.0017 0.02 0.0008 0.01 0.0028 0.04 0.0077 0.05 Noble Gas Air Dose Limits (mrad) = Gamma S/Qtr 10Nr, Beta 10/Qtr 20Nr Ist Q1L1  % Q1L2  % Q1L1  % .Q1L4  % Xsat  %

Gamma 0.0000 0.00 0.0000 0.00 0.0000 0.00 0.0003 0.01 0.0003 0.00 Beta 0.0000 0.00 0.0000 0.00 0.0000 0.00 0.0010 0.01 0.0010 0.01

i i

+ Attachment I to

'. OCAN029514. s l

Page 17 of37 j UNIT 2  ;

Liquid Radwaste EfBuents '

Dose Limits (mrem): Total Body = 1.5/Qtr 3Nr, Other Organs = 5 /Qtr 10Nr  !

Ot8an Qttl  % QlL2  % .Q1tl  % Q1[.1  % Xsat .% ] :

TBody 0.0016 0.11 0.0019 0.13 0.0016 0.11 0.0036 0.24 0.0088 0.29 j Bone 0.0016 0.03 0.0012 0.02 0.0028 0.06 0.0030 0.06. 0.0087 0.09 . l Liver 0.0020 0.04 0.0026 0.05 0.0031 0.06 0.0051 0.10 0.0127 0.13  !

Thyroid 0.0048 0.10 0.0011 0.02 0.0028 0.02 0.0022 0.04 0.0089. 0.09 -l Kidney 0.0018 0.04 0.0008 0.02 0.0007 0.01 0.0018 0.04 0.0052 0.05 l Lung 0.0004 0.01 0.0003 0.01 0.0010 0.02 0.0008 0.02 0.0024 0.02 l GI-LLI 0.0213 0.43 0.0221 0.44 0.0013 0.03 0.0009 0.02 0.0455 0.46  :

Gaseous Radwaste Effluents j lodine, H-3, and Particulate - Dose Limits (mrem) = 7.5/Qtr 15Nr j Organ Q1ti  % .Q1t.2  % .Q1tl  % .Q1L4  % Xsat  %  !

TBody 0.0023 0.03 0.0012 0.02 0.0009 0.01 0.0021 0.03 0.0065 0.04 Bone 0.0001 0.00 0.0000 0.00 0.0000 0.00 0.0002 0.00 0.0003 0.00 ,

Liver 0.0023 0.03 0.0012 0.02 0.0009 0.01 0.0020 0.03 0.0065 0.04 Thyroid 0.0023 0.03 0.0012 0.02 0.0009 0.01 0.0022 0.03 0.0066 0.04 Kidney 0.0023 0.03 0.0012 0.02 0.0009 0.01 0.0020 0.03 0.0065 0.04 ,

Lung 0.0023 0.03 0.0012 0.02 0.0009 0.01 0.0020 0.03 'O.0064 0.04 GI-LLI 0.0023 0.03 0.0012 0.02 0.0009 0.01 0.0020 0.03 0.0065 0.04 Noble Gas Air dose Limits (mrad) = Gamma S/Qtr 10Nr, Beta 10/Qtr 20Nr  !

Tynn Qtti  % Q1I.2  % .Q1tl  % .Q1L4  % Xsat  %

Gamma 0.0002 0.00 0.0000 0.00 0.0031 0.06 0.0117 0.23 0.0149 0.15 Beta 0.0005 0.01 0.0000 0.00 0.0062 0.06 0.0313 0.31 0.0380 0.19

(

l'

C Attachment I to  ;

~

OCAN029514 Page 18 of 37 4

6.

SUMMARY

OF DOSE TO MEMBERS OF THE PUBLIC i The following is a summary of the annual radiation dose to % of the public due to activities inside the site boundary. ,

UNIT I -

110NE LIVER TBODY THYROID KIDNEY GIIII LUNG SKIN Gaseous Effluent ITP 4.81E-5 3.38E-3 3.38E-3 3.47E-3 3.38E-3 3.38E-3 3.38E-3 Noble Gas 8.84E-5 2.09E-4 ,

Liquid Effluent Fish 2.74E-2 4.24E-2 3.02E-2 2.85E-3 1.47E-2 5.46E-3 2.64E-2 -

Sediment 1.35E-3 1.59E-3 ,

Unit 1 Total 2.75E-2 4.57E-2 3.37E-2 6.32E-3 1.81E-2 8.83E-3 2.98E-21.79E-3 UNIT 2 Daseous Effluent ITP 1.41E-4 2.82E-3 2.85E-3 2.88E-3 2.82E-3 2.82E-3 2.82E-3 Noble Gas 3.93E-3 9.1IE-3 Liquid Effluent Fish 8.67E-3 1.27E-2 8.78E-3 8.93E-3 5.22E-3 2.42E-3 4.55E 2 Sediment 4.19E-4 4.92E-4 Unit 2 Total 8.82E-3 1.55E-2 1.56E-2 1.18E-2 8.04E-3 5.24E-3 4.84E-2 9.60E-3 3.63E-2 6.13E-2 4.93E-2 Site Total 1.81E-2 2.61E-2 1.41E-2 7.82E-21.14E-2 Limit (40CFR190) 25 25 75 25 25 25 25 25

% Limit 1.45E-1 2.45E-1 6.57E-2 7.25E-2 1.04E-1 5.63E-2 3.13E-14.56E-2 I

l l

~

c Attachment I to'

.,, . OCAN029514 Page 19 of37

7. HISTORICAL EFFLUENT D4l'A The following graphs show the historical raense data for both units on a yearly basis. These graphs compare data from 1988 through 1994.

UNIT 1 GASEOUS EFFLUENTS CRITICAL ORGAN DOSE

~

1E+002 1E+001 =

1E+000 r 8

1 E-004 1988 1989 1990 1991 1992 1993 1994 YEAR UNIT 1 GASEOUS EFFLUENTS TOTAL BODY DOSE 1E+002 1E+001 =

9 1E+000 r 4

l $ 1 E-001 r t.

1 E-002 r 1E 004 1988 1989 1990 1991 1992 1993 1994 YEAR

i

~~

o A**-h I to ~

.OCAN029514 k, Page 20 of37 l 7; ; . t '

UNIT 1 GASEOUS EFFLUENTS GAMMA DOSE i 1E+002 1E+001 1E+000 r 2, 1 E-001 -

2 1 E-002 r 1 E-003 1988 1989 1990 1991 1992 1993 1994 YEAR UNIT 1 GASEOUS EFFLUENTS BETA DOSE 1E+002 1E+001

- 1E+000 r 1E 001 r  ;

1 E-002 r d d d EE

'" ~ '

i 1988 1989 1990 1991 1992 1993 1994 YEAR

. Attachment I to .

L Pag 1of37 UNIT 1. GASEOUS EFFLUENTS ,

Fission and Activation Products

< 10000 1988 1989 1990 1991 1992 1993 1994 YEAR UNIT 1 GASEOUS EFFLUENTS >

Tritium 100

e I to

- Page 22 of 37? 'i UNIT 1 GASEOUS EFFLUENTS Radiolodines 1 E-002 1E 003 r m 1E-004 r '

i 1 E-005 r 1 E-006 r

$d E .

1988 1989 1990 1991 1992 1993 1994 YEAR UNIT 1 GASEOUS EFFLUENTS Particulates 1E 001 1 E-002 -

1 E-003 r 1 E-006 lE 1988 1989 1990 1991 YEAR 1992 1993 1994

. Attachment I to i L ,

OCAN029514 -

1 Pagt 23 of37 UNIT 1 LIQUID EFFLUENTS CRITICAL ORGAN DOSE )

1E+002  !

1E+001 -

@ 1E+000 r ,

9 1 E 001 r 1 E-002 r l 2 ,

, IE 003 r 1E-004 1988 1989 1990 1991 1992 1993 1994 YEAR UNIT 1 LIQUID EFFLUENTS  !

TOTAL BODY DOSE-  ;

1E+001 ,

k p 1E+000 -

1E 003 1908 1989 1990 1991 1992 1993 1994 i YEAR

i[ -

i. Attachment I to OCAN029514 Page 24 of37 UNIT 1 LIQUID EFFLUENTS  !

Dissolved and Entrained Gases 1E+002- - - -- '

[

1E+001 -

1E+000 -

1E-001 --

1988 1989 1990 1991 1992 1993 1994 YEAR UNIT 1 LIQUID EFFLUENTS TRITIUM I 1E+004 i I

i 1E+003 -

O t 1E+002 1988 1989 1990, 1991 1992 1993 1994 YEAR l

l

~

., 1 Page 25 of37 )

UNIT 1 LIQUID EFFLUENTS {

FISSION AND ACTIVATION PRODUCTS 1E+002 -

1E+001 -

1E 00 1988 1989 1990 1991 1992 1993 1994 YEAR UNIT 1 LIQUID EFFLUENTS TOTAL VOLUME RELEASED 1E+008 1E+007 -

7

,E 0ee 1988 1989 1990 1991 1992 1993 1994 YEAR

J; -

i-' ,

s. Attachment I to  !

-y: ' OCAN029514 l

- Page 26 of37 UNIT 2 GASEOUS EFFLUENTS '

CRITICAL ORGAN DOSE i 1E+002 1E+001 =

1E+000 r s  :

h 1E 001 r 1E-002 -

1 E-003 -

1 E 004 / A 1988 1989 1990 1991 1992 1993 1994  ;

YEAR ,

UNIT 2 GASEOUS EFFLUENTS TOTAL BODY DOSE 1E+002 1E+001 =  !

Y '

1E+000 r a r 1E-001 - -'

t i 1 E-002 r ,

p^ / /

1E-004 ' -

1988 1989 1990 1991 1992 1993 1994 YEAR

i Attachment I to -

, _ OCAN029514 Page 27 of37 UNIT 2 GASEOUS EFFLUENTS GAMMA DOSE 1E+002 1E+001 =

7 _1E+000 -

9, 1 E-001 -

0 2 1 E-002 r -

1 E-003 r 1E-004 '

1988 1989 1990 1991 1992 1993 1994 YEAR UNIT 2 GASEOUS EFFLUENTS BETA DOSE 1E+002 1E+001 =

1E+000 r 1 E-001 r

{

1 E-002 r 1988 1989 1990 1991 1992

/,

1993 l

1994 YEAR

t

'. I to g Page 28 of37 UNIT 2 GASEOUS EFFLUENTS Fission and Activation Products 10000

+

1000 r-1988 1989 1990 1991 1992 1993 1994 YEAR UNIT 2 GASEOUS EFFLUENTS ,

Tritium 100 g 10 -

/

1988 1989 1990 1991 1992 1993 1994 I

.g , 7 1 to .

Page 29 of37 UNIT 2 GASEOUS EFFLUENTS Radiolodines 1 E-002 1E-003 =

m- 1E-004 e 1E-005 -

e 1 E-006

~~'~^

1E 007 1988 1989 1990 1991 1992 1993 1994 YEAR UNIT 2 GASEOUS EFFLUENTS Particulates 1E-001 1E 002 =

g 1E 003 r 1 E-004 =

1E-005 = : , ,

y' z 1988 1989 1990 1991 1992 1993 1994 YEAR

. Attachment I to

y. . OCAN029514 ~  !
Page 30 of 37: -

UNIT 2-LIQUID EFFLUENTS l' CRITICAL' ORGAN DOSE 1E+002 1E+001 =

7 ,

@ 1E+000 r >

8 1 E 001 r 1E-002 - -

1 E-003 r I E-004 1988 1989 1990 1991 1992 1993 1994 YEAR '

UNIT 2 LIQUID EFFLUENTS  :

TOTAL BODY DOSE 1E+001  !

p 1E+000 g .

N ',

$ 1E-001  :

b '

/

3 g go3 1988 1989 1990 1991 1992 1993 1994 l

YEAR

~ ' . Attachment I to 7_ # OCAN029514 ~

' Page 31 of37 UNIT 2 LIQUID EFFLUENTS ,

Dissolved and Entrained Gases 1E+003 f

1E+002 r i

g 1E+001 r O

1E+000 r 1E 001 '

W 1988 1989 1990 -1991 1992 1993 1994  ;

YEAR UNIT 2 LIQUID EFFLUENTS TRITIUM 1E+004 g 1E+003 -

1 0

1E+002 1988 1989 1990 1991 1992 1993 1994 YEAR ,

e' Attachment I to

. . ~ OCAN029514 Page 32 of37L UNIT 2 LIQUID EFFLUENTS FISSION AND' ACTIVATION PRODUCTS '

1E+002 1E+001 -

I a

1E+000 -

  • 1E 001 1988 1989 1990 1991 1992 1993 1994 YEAR UNIT 2 LIQUID EFFLUENTS TOTAL VOLUME RELEASED ,

1E+008 z

h 1E+007 -

.c -

ie.000 1988 1989 1990 1991 1992 1993 1994 YEAR

,, f 1

' . , ~J.. Attachment I to-

^

, LOCAN029514

-Page 33 of 37 ~ , i

8. SOLID WASTE

SUMMARY

The following is a summary of the solid wastes shipped offsite, both annually and during the last six months of1994.

i REGULATORY GUIDE 1.21 REPORT i WASTE DISPOSAL ANNUAL

SUMMARY

REPORT .

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY THROUGH DECEMBER 1994  !

A. Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiatad Fuel) 12-Month ~ Est. Total

1. Type ofWaste Unit Period ' Error, % .
a. Spent resins, filter sludges, m3 3.38E+01 evaporator bottoms, etc. Ci 4.52E+02 3.77E%0
b. Dry compressible waste, m3- 1.34E+02 contaminated equip, etc. Ci 9.41E+00 9.42E ,

i

c. Irradiated components, m3 0.00E+00 control rods, etc. Ci 0.00E %0 0.00E+00
d. Other(describe) m3 0.00E%0 j Ci 0.00E+00 0.00E+00 J
2. . Estimate of Major Nuclide Composition (by Type of Waste)

% Cdu J

a. CS-137 61.6 2.78E+02 I i

CS-134 33.2 1.50E+02 NI-63 2.8 1.28E+01 ,

FE-55 1.0 4.38E+00 CO-60 0.6 2.50E+00  ;

CO-58 0.4 1.95E+00 .i AG-110m 0.2 1.00E+00 C-14 0.1 4.07E-01 1

b. CS-137 34.7 3.26E400 CO-58 28.9 2.72E+00 I CS-134 14.0 1.32E+00 FE-55 8.6 8.13E-01

_- ._ - _ _ ._ _ _. ___ _ ~.__ _

. Attachment 1 to

,- ,- OCAN029514 Page 34 of 37 NI-63 8.1 7.60E-01 CO-60 2.8 2.62E-01 l NB-95 1.0 9.29E-02 MN-54 1.0 9.15E-02 ZR-95 0.6 5.41E-02

c. N/A
d. N/A l
3. Solid Waste Disposition '

Number of Shipments Mode ofTransportation Destination 2 Unshielded Van / Truck Oak Ridge, TN 10 Unshielded VanfTnick Wampum, PA 1 Cask Shipment (Type B) Barnwell, SC -

B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode ofTransportation Destination N/A N/A N/A l

I I

I l

i l

)

l l

l

. Attachment I to I

o OCAN029514 Page 35 of 37 j REGULATORY GUIDE 1.21 REPORT WASTE DISPOSAL ANNUAL

SUMMARY

REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JULY I THROUGH DECEMBER 31,1994 A. Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel)

1. Type ofWaste Unit 6-Month Est. Total Period Error, %
a. Spent resins, filter sludges, m3 0.00E+00 evaporator bottoms, etc. Ci 0.00E+00 0.00E+00
b. Dry compressible waste, m3 0.00E+00 contaminated equip, etc. Ci 0.00E+00 0.00E+00
c. Irradiated components, m3 0.00E+00 control rods, etc. Ci 0.00E+00 0.00E+00
d. Other(describe) m3 0.00E400 Ci 0.00E+00 0.00E+00
2. Estimate of Major Nuclide Composition (by Type of Waste)
a. N/A
b. N/A I
c. N/A j
d. N/A l l
3. Solid Waste Disposition Number of Shioments Mode ofTransportation Destination 1 Unshielded Vanfiruck Oak Ridge, TN B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode ofTransoortation Destination I N/A N/A N/A

C Attachment 1 to

^

,; OCAN029514 Page 36 of 37
9. UNPLANNED RELEASES No unplanned releases occurred during the third and fourth quarters of 1994.

l

10. RADIATION INSTRUMENTATION As required by Unit I and Unit 2 Technical Specifications, any radioactive effluent instrumentation inoperable for more than 30 days shall be reported in the next Semiannual Radioactive Efiluent Release Report. During the third and founh quarters of 1994, no instrumentation was inoperable longer than 30 days.
11. CHANGES TO THE PROCESS CONTROL PROGRAM As required by Unit 1 and Unit 2 Technical Specifications, a description of changes made to the Process Control Program (PCP) during the reporting period shall be included in the next Semiannual Radioactive Efiluent Release Report. No changes were made to the PCP during the tidrd and fourth quarters of1994.
12. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL During the third and fourth quarters of 1994, the following changes were made to the Offsite Dose Calculation Manual (ODCM).

A. Editorial change to page 15, Section 3.2.1.a.

B. Editorial change to page 41, sample station number 29.

C. Deleted " Food Products" samples from sample station number 32, page 42.

D. Editorial change to page 42, sample station number 33.

E. Changed the designation " Settling Pond" to " Wastewater Holding Pond" on page 42, sample station number 36.

F. Editorial change on page 42, sample station 37.

G. Added new sample station number 48 on page 44.

H. Changed the alternate food1 ,roducts sample point to a regular food products sample point for sample station number 108, page 44.

1. Editorial change to page 50, sample station number 129.

J. Added sample station number 48 to Figure 4-1, page 37.

Revised pages for the ODCM are included in Attachment 2.

.* Attachment I to 1

.' OCAN029514 I Page 37 of 37

13. LLD LEVELS In accordance with Unit I and Unit 2 Technical Specifications, lower limits of detection (LLDs) higher than required shall be documented in the Semiannual Radioactive EfBuent Release Report. During the reporting period, there were no LLDs higher than required.
14. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM A. There were three environmental sample location changes during the reporting period.

The following is a description and reason for each change:

1. Samole Station Number 32 - Food products for this sample point were deleted.

This sample was moved to sample station number 48. The garden at sample station number 32 no longer exists.

2. Samole Station Number 48 - This sample station was added to the environmental monitoring program to replace the food products sample deleted from sample station number 32.
3. Sample Station Number 108 - The food products sample for this saanple station became a regular sample, as opposed to an alternate sample, in order to increase sampling quantity and food diversity.

B. During the reporting period, there were no sampling locations identified which would yield a calculated dose commitment greater than the values currently being calculated.

15.

SUMMARY

OF HOURLY METEOROLOGICAL DATA In accordance with ANO-1 and 2 Technical Specification 6.12.2.6(e) and 6.9.3.4.1, respectively, in lieu ofincluding a summary of the meteorological data in this report, the 1994 data is retained at ANO. This data is available for NRC review.

16. DESCRIPTION OF MAJOR CHANGES TO RADWASTE SYSTEMS During 1994, no major changes were made to the liquid or gaseous radwaste systems for either unit.

I

p- ,..s

.e l I i

ATTACHMENT 2 I OFFSITE DOSE CALCULATION MANUAL REPLACEMENT PAGES

in ' ,

  • LICENSE.075

" Pcge 1 f

Y

/i iv ,

OFFSITE DOSE CALCULATION MANUAL FOR APJCANSAS NUCLEAR ONE REVISION 4 O

O

m

= . -

_7

-LICENSE.075 k r '. : *T i

,, . ,7f LPsgs 15 i REV. 4 i

p where: ~j

,h'i' 2.8E-6 ' = the annual _ average gaseous dispersion 1

factor (corrected for radioactive decay) as defined in Section 2.3 of the ANO-2 SAR; and ,

TMPC = total MPCs at site boundary.-

-3.2' Airborne Release Dose Rate Effects 3.2.1 Noble Gas Release Rate-3.2.1.a To_ calculate the noble gas release d'ose~ rate, the average ground-level concentration of radionuclide-

"i" at the receptor location must first be determined from the following equation.

(See Regulatory Guide 1.109-20 equation B-4).

xg (0)'= 3.17 x'10'

  • Qg
  • D1X/Q(0) ,

where:

+ xg (0) =averagegroundlevelconcentrationin pCi/m of nuclide "i"' at the user-specified controlling distance in sector 8 (1.05km); _;

O (0) = one of the sixteen 22.5' sectors surrounding the -reactor site, designated N, .l

-NNE, NE, ... etc. (WNW)*

1 i

3.17x10"= number. of pCi per Ci divided by the number of seconds / year; i i

Qg = release rate of nuclide "i" in curies /yr and -i D1X/Q(0) = annual average gaseous dispersion factor  ;

(corrected for radioactive decay) in the sector at angle "0" at the receptor  :

s location in sec/m .- This value is  ;

2.8E-6 sec/m* for short _ term releases. .

The annual dose to the total body and skin due to i noble gas can be. calculated according to Sections '

3.2.1.b and 3.2.1.c..

r 3.2.1.b Annual Total Body Dose Rate  ;

The annual average total body dose rate to the  :

maximally exposed individual is calculated as  ;

follows D (0) = RBPF*SF*Zi (0)*DFB f l

1 m _ _ . . .. . , - . ,

AgeSi'suMD lWe r- WW' ; e r ~

,m n 1.sgeiA;pKMfe9.;g&$@T.Ajij kjjlp!Ui$! ~

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. LICENSE.075

  • Pcgs 41 j REV. 4 g

TABLE 4-1 Environmental Sampling Stations - Radiological

^

/

j -

wl Sample Station Number: 14 Approximate Direction and Distance from Plant: 70' - 5.3 miles Sample Types: 1) Drinking water Sample Station Location:

From junction of Highway 7 and Water Works Road, go approximately 0.8 miles west on Water Works Road. The sample station is on the left at the intake to the Russellville city water system from the Illinois Bayou.

Sample Station Number: 16 Approximate Direction and Distance from Plant: 290' - 5.9 miles Sample Types: 1) Shoreline sediment Sample Station Location:

From junction of Highway 64 and Highway 359 (Fist Rock Piney Bay Recreational Area turnoff), go approximately 0.7 miles west on Highway 64. The sample station is at the Piney Creek area on Lake Dardanelle.

Sample Station Number: 19

,o Approximate Direction and Distance from Plant: 95' - 5.1 miles Sample Types: 1) Milk Sample Station Location:

Turn from Highway 7 onto Harrell Drive in Russellville, AR and go approximately 0.1 miles. Turn right and go approximately 0.25 miltis. The sample station is on the left at the Arkansas Tech Dairy.

Sample Station Number: 29 Approximate Direction and Distance from Plant: 24' - 6.9 miles Sample Types: 1) Milk (alternate)

Sample Station Location:

Turn south from Highway 333 onto County Road 141 and go approximately 0.55 miles. Turn left and go approximately 0.6 miles. Turn left and go approximately 0.05 miles. The sample station is on the right at the Harold Steuber Dairy.

A

-

  • LICENSE.075 P gs 42 REV. 4 g

TABLE 4-1 Environmental Sampling Stations - Radiological .

Sample Station Number: 32 Approximate Direction and Distance from Plant: 132* - 0.9 miles  :

Sample Types: 1) Ground water Sample Station Location:

From bridge over intake canal, go south approximately 0.25 miles. Turn left and go approximately 0.25 miles. Turn left on Bunker Hill Lane and go approximately 0.05 miles. The sample station is on the right at Clifton Stewart's residence.

i Sample Station Number: 33 Approximate Direction and Distance from Plant: 94' - 3.8 miles Sample Types: 1) Ground water Sample Station Location:

From junction of Highway 64 and Highway 326 (Dike Road), go approximately 0.3 miles east on Dike Road. The sample station is on the left at the Duita Lake Recreation Area on the Illinois Bayou.

i S Sample Station Number: 36 Approximate Direction and Distance from Plant: 140' - 0.05 miles ,

Sample Types: 1) Pond water

2) Pond sediment Sample Station Location:

The sample station is at the Wastewater Holding Pond on the ANO site east of i the discharge canal.

Sample Station Number: 37 i Approximate Direction and Distance from Plant: 0' - 7.5 miles Sample Types: 1) Milk Sample Station Location:

H traveling north on Highwey 333, IEN go approximately 3.5 miles from junction of Highway 333 and Mill Creek Road on Highway 333. Turn left and go approximately 0.1 miles. The sample station is on the left at the Lawrence Steuber Dairy.

E traveling from junction of Highway 7 and Highway 333, IEN go approximately 6.0 miles west on Highway 333. Turn right and go approximately 0.1 mile. The sample station is on the left at the Lawrence Steuber Dairy.

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TABLE 4-1 i O Environmental Sampling Stations - Radiological . !

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Sample Station Number: 45 Approximate Direction-and Distance from Plant: 90' - 0.9 miles -

Sample Types: 1) Broad leaf vegetation Sample Station Location:

The sample station is located near mouth of intake canal.

Sample Station Number: 46 Approximate Direction and Distance from Plant: 295' - 4.1 miles Sample Types: 1) Food products Sample Station Location:

From west junction of Highway 64 and Highway 333 in London, AR, go west on ,

Highway 64 approximately 2.4 miles. Turn right onto Scottie Lane and go approximately 0.1 miles. The sample location is on the right at Dewey Gregory's residence.

F Samole Station Number: 48 Anororfmate Direction and Distance from Plant: 316* - 2.2 miles Samnie Tvoes: 1) Food Products Samnie Station Location:

R. J. Cochran residence, No. 26 Hwy 64 London West, directly North (across from) London Volunteer Fire Dept.

Sample Station Number: 108 Approximate Direction and Distance from Plant: 301' - 0.9 miles Sample Types: 1) Direct radiation  :

2) Food Products Sample Station Location:  ;

f IE traveling from Highway 333, IHEN turn south onto Flatwood Road and go approximately 0.4 miles. The sample station is on the right.

IE traveling north on Flatwood Road, IHEN go approximately 0.4 miles from sample station 109. The sample station is on the left.

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-TABLE 4-1 O Environmental Sampling Stations - Radiological -

Sample Station Number: 127 Approximate Direction and Distance from Plant: 102' - 5.6 miles j Sample Types: 1) Direct radiation l Sample Station Location:  ;

The sample station is located on the Arkansas Tech Campus on West 0 Street on j a security light pole in front of Bryan Hall, which is the first building on i the left when traveling from North Arkansas on West 0 Street.

Sample Station Number: 128 i Approximate Direction and Distance from Plant: 113' - 8.6 miles  ;

Sample Types: 1) Direct radiation l Sample Station Location: j The sample station is on a utility pole inside the security fence near the  !

Russellville Airport Office. 'The airport is located off of East 16th Street ,

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Sample Station Number: 129 t

Approximate Direction and Distance from Plant: 118' - 7.3 miles i O Sample Types: 1) Direct Sample Station Location:

radiation ~!

- t The sample station is on a utility pole north of the Russellville High School {

sign, which is in front of the high school on east side of Highway 7T.

' Sample Station Number: 130 Approximate Direction and Distance from Plant: 245' - 4.6 miles i Sample Types: 1) Direct radiation l Sample Station Location At junction of Highway 7 and Highway 22 in Dardanelle, AR, take Highway 22 ~;

.toward Delaware, AR. Go approximately 0.4 miles west of Delaware Recreation j Area turnoff. The sample station is on a utility pole on the right in ,

1 Delaware, AR near Shirley's Beauty Salon.  :

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