0CAN089510, Semiannual Radioactive Effluent Release Rept for Jan-June 1995

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Semiannual Radioactive Effluent Release Rept for Jan-June 1995
ML20091Q333
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 06/30/1995
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20091Q327 List:
References
0CAN089510, CAN89510, NUDOCS 9509050300
Download: ML20091Q333 (36)
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Text

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. Attachment I to

, OCAN089510 Page1of30 ARKANSAS NUCLEAR ONE UNIT 1 AND UNIT 2 OPERATING LICENSE NO. DPR-51 AND NPF-6 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1

! JANUARY 1,1995 THROUGH JUNE 30,1995 I

i 9509050300 950830 PDR ADOCK 05000313 R . _. .._ PDR

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TABLE OF CONTENTS Section Eagt
1. Introduction 3
2. Regulatory Limits 3
3. Summary ofLiquid Efiluent Data 5 e
4. Summary of Gaseous Effluent Data 12 5.- Summary ofRadiation Doses 17

!- 6. Summary ofDose to Members of the Public 17

7. Historical Effluent Data 17
8. Solid Waste Summary 26 i

i 9. Unplanned Releases 27 1

10. Radiation Instrumentation 28

. 11. Changes to the Process Control Program 28

12. Changes to the Offsite Dose Calculation Manual 28

! 13. LLD Levels 29 i

. 14. Radiological Environmental Monitoring Program 29 IS, Summ- of the Hourly Meteorological Data 30

16. Description of Major Changes to Radioactive Waste Systems 30 4

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1. INTRODUCTION 3 Arkansas Nuclear One (ANO)is a two unit plant consisting of a Babcock and Wilcox (Unit 1) ed a Combustion Engineering (Unit 2) design. Both liquid and gaseous effluents are released in accordance with the technical specifications for each unit. This report is a summary of the effluent data in accordance with Unit 1 Technical Specification 6.12.2.6 and Unit 2 Technical Specification 6.9.3. This report provides the following information:

A. Routine radioactive effluent release reports covering the operation of the units during the reporting period.

B. Description of unplanned releases to unrestricted areas. ,

C. Description of changes to the Offsite Dose Calculation Manual (ODCM).

D. Description of changes to the Process Control Program (PCP).  ;

E. Summary of radiation doses due tn radiological effluents 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 l' boundary. This data is included in the first report of each year.

G. Description of licensee initiated major changes to the radioactive waste systems during the previous calendar year. This data is included in the first report ofeach year.

l H. Items to be reported in the Semiannual Report in accordance with other miscellaneous technical specifications.

This report covers the period ofJanuary 1,1995 through June 30,1995.

2. REGULATORY LIMITS l

l Unit One and Unit Two Technical Specifications contain the limits to which ANO must l 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 ensironment. Liquid and gaseous 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 radioactive effluents have had an overall minimal dose contribution to the surrounding environment. The following are the limits required by the technical specifications.

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A. Gaseous Efiluents  ;

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1. Dose rate due to radioactive materials released in gaseous effluent to unrestricted areas shall be limited to the following:
a. Noble gases Less than or equal to 500 mrem / year to the total body Less than or equal to 3000 mrem / year to the skin
b. Iodine - 131, tritium, and for all radionuclides in particulate form with halflives greater than 8 days Less than or equal to 1500 mrem /yr
2. Dose - Noble Gases 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 Less than or equal to 20 mrads beta
3. Dose - Iodine-131, Tritium, and Radionuclides in Particulate Form Quarterly Less than or equal to 7.5 mrems to any organ Yearly Less than or equal to 15 mrems to any organ l

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. B. Liquid Efiluents i t

i 1. Concentration. i i

The concentration of radioactive material released to the discharge canal shall be limited to the concentration specified in 10CFR20, i Appendix B, Table II, Column 2 for radionuclides other than dissolved

{ or entrained noble gases. For dissolved or entrained noble gases, the j total concentration released shall be limited to 2E-4 microcuries/ml.  !

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2. Dose j

. Quarterly i

! I ess than or equal to 1.5 mrem total body >

Less than or equal to 5 mrem critical organ

. Yearly i

j. Less than or equal to 3 mrem total body ,

4 Less than or equal to 10 mrem critical organ

3.

SUMMARY

OF LIQUID EFFLUENT DATA l The following data is a summary of the number and times of releases for both Unit I and l j Unit 2. These releases occurred between January 1,1995 and June 30,1995.

Unit 1 Unit 2

! Number of releases: 494 187 i Total time for all releases (minutes): 87220 58147

Maximum time for a release (minutes)
1261 4422 -

1 Average time for a release (minutes): 176 311 Minimum time for a release (minutes): 1 30 l As required by Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity

! in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Efiluents from  :

Light-Water-Cooled Nuclear Power Plants," Rev.1, a summary of data for liquid releases is to be provided in the Semiannual Report. The following pages provide a summary ofliquid j effluents for both Unit I and Unit 2:

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Attachment I to

, OCAN089510 Page 6 of 30 SEMIANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL LIQUID EFFLUENTS)

January 1,1995 through June 30,1995 Unit 1 Type of Efiluent Units Quarter 1 Quarter 2 Est. Tot Error %

A. Fission and Activation Products

1. Total Release (Not Including Tritium, Curies 6.571E-01 5.146E-01 0 Gases, Alpha)
2. Average Diluted Concentration Ci/ml 2.106E-09 1.394E-09 During Period
3. Percent of Applicable Limit  % 7.021E-01 4.645E-01 B. Tritium
1. Total Release Curies 1.525E+02 7.837E+01 0
2. Average Diluted Concentration Ci/ml 4.889E-07 2.123E-07 During Period
3. Percent of Applicable Limit  % 1.630E-02 7.075E-03 C. Dissolved and Entrained Gases
1. Total Release Curies 2.692E+00 1.830E-02 0
2. Average Diluted Concentration Ci/ml 8.630E-09 5.093E-11 During Period
3. Percent of Applicable Limit  % 4.315E-03 2.546E-05 D. Gross Aloha Radioactivity
1. Total Release Curies 0.000E+00 5.744E-05 0 E. Waste Vol Released (Pre-Dilution) Liters 3.200E+07 3.494E+07 0 F. Volume of Qilulian Water Used Liters 3.119E+11 3.692E+11 0 i

Attachment I to

. OCAN089510 Page 7 of 30 UNIT 1 REPORT CATEGORY  : SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES

TOTALS FOR EACH NUCLIDE RELEASED TYPE OF ACTIVITY  : ALL RADIONUCLIDES REPORTING PERIOD  : QUARTER # 1 AND QUARTER # 2 YEAR 1995 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 TC-99M CURIES 0.00E+00 0.00E+00 9.13E-06 0.00E+00 ZN-65 CURIES 0.00E+00 0.00E+00 1.54E-05 0.00E+00 NB-97 CURIES 0.00E+00 0.00E+00 1.91E-05 0.00E+00 LA-140 CURIES 0.00E+00 0.00E+00 2.98E-05 0.00E+00 SN-ll3 CURIES 0.00E+00 0.00E+00 5.31E-05 0.00E+00 SN-ll7M CURIES 0.00E+00 0.00E4 00 9.23E-05 0.00E+00 SB-122 CURIES 0.00E+00 0.00E+00 3.25E-04 0.00E+00 ZR-95 CURIES 0.00E+00 0.00E+00 4.81E-04 0.00E+00 AG-110M CURIES 0.00E+00 0.00E+00 5.38E-04 0.00E+00 SB-126 CURIES 0.00E+00 0.00E+00 9.00E-04 0.00E+00 NB-95 CURIES 0.00E+00 0.00E+00 1.02E-03 0.00E+00 XE-131M CURIES 0.00E+00 0.00E+00 3.47E-02 0.00E+00 SR-92 CURIES 0.00E+00 0.00E+00 2.53E-05 6.91E-06 I-133 CURIES 0.00E+00 0.00E+00 2.81E-04 9.51E-06 CO-57 CURIES 0.00E+00 0.00E+00 7.10E-04 1.79E-05 I-132 CURIES 0.00E+00 0.00E+00 3.24E-04 3.43E-05 G-ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 5.74E-05 SE-75 CURIES 0.00E+00 0.00E+00 5.27E-05 8.82E-05 XE-135 CURIES 0.00E+00 0.00E+00 3.96E-03 8.91E-05 XE-133M CURIES 0.00E+00 0.00E+00 2.25E-02 1.64E-04 NA-24 CURIES 0.00E+00 0.00E+00 5.09E-04 1.24E-03 MN-54 CURIES 0.00E+00 0.00E+00 4.01E-04 4.64E-03 CS-134 CURIES 0.00E+00 0.00E+00 4.06E-03 4.94E-03 KR-85 CURIES 0.00E+00 0.00E+00 4.52E-02 5.16E-03 I-131 CURIES 0.00E+00 0.00E+00 3.99E-02 5.64E-03 CS-137 CURIES 0.00E+00 0.00E+00 8.85E-03 7.27E-03 CO-60 CURIES 0.00E+00 0.00E+00 2.94E-02 8.76E-03 FE-55 CURIES 0.00E+00 0.00E+00 1.1lE-02 1.20E-02 XE-133 CURIES 0.00E+00 0.00E+00 2.59E+00 1.34E-02 CR-51 CURIES 0.00E+00 0.00E+00 1.47E-02 1.36E-02 SB-124 CURIES 0.00E+00 0.00E+00 3.86E-02 2.69E-02

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, l CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 CO-58 CURIES 0.00E+00 0.00E+00 1.86E-01 9.73E-02 SB-125 CURIES 0.00E+00 0.00E+00 3.19E-01 3.32E-01 i

H-3 CURIES 0.00E+00 0.00E+00 1.53E+02 7.84E+01 Total for Period CURIES 0.00E+00 0.00E+00 1.56E+02 7.89E+01 e

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Attachment I to

, OCAN089510 Page 9 of 30 SEMIANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL LIQUID EFFLUENTS)

January 1,1995 through June 30,1995 Unit 2 Type of Efiluent Units Quarter 1 Quarter 2 Est. Tot Error %

A. Fission and Activation Products

1. Total Release (Not Including Tritium, Curies 1.031E-01 5.748E-02 0 4 Gases, Alpha)
2. Average Diluted Concentration Ci/mi 3.304E-10 1.557E-10 During Period
3. Percent of Applicable Limit  % 1.101E-01 5.189E-02 B. Ilitium
1. Total Release Curies 2,455E+02 6.797E+01 0
2. Average Diluted Concentration Ci/ml 7.871E-07 1.841E-07 During Period
3. Percent of Applicable Limit  % 2.624E-02 6.137E-03 C. Dissolved and Entrained Gases
1. Total Release Curies 8.937E+00 1.398E+00 0
2. Average Diluted Concentration pCi/ml 2.865E-08 3.787E-09 During Period
3. Percent of Applicable Limit  % 1.432E-02 1.893E-03 D. Gross Alpha Radioactivity
1. Total Release Curies 0.000E+00 0.000E+00 0 E. Waste Vol Released (Pre-Dilution) Liters 1.548E+07 5.796E+06 0 F. Volume of Dilution Water Used Liters 3.119E+11 3.692E+11 0

4 Attachment I to

, OCAN089510 Page 10 of 30 UNIT 2 REPORT CATEGORY  : SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES

TOTALS FOR EACII NUCLIDE RELEASED TYPE OF ACTIVITY  : ALL RADIONUCLIDES REPORTING PERIOD  : QUARTER # 1 AND QUARTER # 2 YEAR 1995 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 I-134 CURIES 0.00E+00 0.00E+00 8.68E-06 0.00E+00 SB-126 CURIES 0.00E+00 0.00E+00 3.00E-05 0.00E+00 AR 41 CURIES 0.00E+00 0.00E+00 4.72E-05 0.00E+00 LA-140 CURIES 0.00E+00 0.00E+00 6.13E-05 0.00E+00 CS-136 CURIES 0.00E+00 0.00E+00 1.01E-04 0.00E+00 BE-7 CURIES 0.00E+00 0.00E+00 1.09E-04 0.00E+00 FE-59 CURIES 0.00E+00 0.00E+00 1.49E-04 0.00E+00 LA-142 CURIES 0.00E+00 0.00E+00 1.75E-04 0.00E+00 NB-95 CURIES 0.00E+00 0.00E+00 2.55E-04 0.00E+00 ZR-95 CURIES 0.00E+00 0.00E+00 2.97E-04 0.00E+00 MN-54 CURIES 0.00E+00 0.00E+00 3.55E-04 0.00E+00 l M O-99 CURIES 0.00E+00 0.00E+00 4.18E-04 0.00E+00 SR-89 CURIES 0.00E+00 0.00E+00 4.21E-04 0.00E+00 I-135 CURIES 0.00E+00 0.00E+00 4.46E-04 0.00E+00 ;

SN-117M CURIES 0.00E+00 0.00E+00 4.47E-04 0.00E+00 TC-99M CURIES 0.00E+00 0.00E+00 6.52E-04 0.00E+00 TE-132 CURIES 0.00E+00 0.00E+00 9.39E-0/ 0.00E+00 I I-132 CURIES 0.00E+00 0.00E+00 2.20E-03 0.00E+00 KR-85 CURIES 0.00E+00 0.00E+00 2.43E-02 0.00E+00 I-133 CURIES 0.00E+00 0.00E+00 3.52E-03 4.86E-08 I-131 CURIES 0.00E+00 0.00E+00 1.32E-02 4.19E-05 AG-110M CURIES 0.00E+00 0.00E+00 8.20E-04 1.40E-04 CS-134 CURIES 0.00E+00 0.00E+00 1.70E-03 1.50E-04 CO-60 CURIES 0.00E+00 0.00E+00 2.25E-03 3.40E-04 CS-137 CURIES 0.00E+00 0.00E+00 3.74E-03 5.41E-04 XE-135 CUIUES 0.00E+00 0.00E+00 4.75E-04 1.73E-03 FE-55 CUPdES 0.00E+00 0.00E+00 0.00E+00 1.99E-03 CR-51 CURIES 0.00E+00 0.00E+00 3.85E-02 2.43E-03 CO-58 CURIES 0.00E+00 0.00E+00 1.25E-02 5.1lE-03 SB-124 CURIES 0.00E+00 0.00E+00 4.02E-03 5.26E-03 XE-133M CURIES 0.00E+00 0.00E+00 6.58E-02 1.16E-02

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Attachment I to

. OCAN089510 Page11of30 CONTINUOUS RELEASES BATCH RELEASES i NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 l XE-131M CURIES 0.00E+00 0.00E+00 3.34E-02 1.59E-02 SB-125 CURIES 0.00E+00 0.00E+00 1.57E-02 4.15E-02 1 XE-133 CURIES 0.00E+00 0.00E+00 8.81E+00 1.37E+00 H-3 CURIES 0.00E+00 0.00E+00 2.46E+02 6.80E+01 Total for Period CURIES 0.00E+00 0.00E+00 2.55E+02 6.94E+01 6

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4.

SUMMARY

OF GASEOUS EFFLUENT DATA As required by Regulatory Guide 1.21, Rev.1, a summary of data for gaseous releases is ,

provided in the Semiannual Report. This summary covers releases from January 1 through June 30,1995. The summary of gaseous effluents for both Unit I and Unit 2 is as follows:

Unit 1 Unit 2 i Number of releases: 83 91

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Total time for all releases (minutes): 517457 534897 Maximum time for a release (minutes): 10534 11089 ,

Average time for a release (minutes): 6234 5943 Minimum time for a release (minutes): 2 1 The Unit I gaseous releases consisted of:

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

8 waste gas decay tank releases.

3 reactor building purge releases. ,

57 vent releases.

3 make-up/ quench rank releases.

2 secondary steam releases.

The Unit 2 gaseous releases consisted of:

14 emergency feedwater (EFW) pump releases - These releases were a result of ,

I surveillances to the steam driven EFW pump.

1 waste gas decay tank release.

I reactor building purge release.

73 vent releases.

1 volume control tank release.

I secondary steam release.

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Attachm:nt I to

. OCAN089510 Page 13 of 30 SEMIANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL AIRBORNE EFFLUENTS)

January 1,1995 through June 30,1995 Unit 1 Type of Efiluent Units Quarter 1 Quarter 2 Est. Tot Error %

A. Fission and Activation Products

1. Total Release Curies 3.858E+01 4.768E+00 0
2. Average Release Rate For Period Ci/Sec 4.961E+00 6.064E-01
3. Percent of Applicable Limit  % 6.946E-02 8.490E-03 B. Radiciodines
1. Total Iodine-131 Curies 1.207E-04 1.458E-05 0
2. Average Release Rate For Period pCi/Sec 1.553E-05 1.854E-06
3. Percent of Applicable Limit  % 4.347E-05 5.191E-06 C. Particulates
l. Particulates (Half-Lives > 8 Days) Curies 7.052E-06 6.345E-07 0
2. Average Release Rate For Period Ci/Sec 9.068E-07 8.070E-08
3. Percent of Applicable Limit  % 2.539E-06 2.259E-07
4. Gross Alpha Radioactivity Curies 0.00E+00 1.782E-06 D. Tritium
1. Total Release Curies 2.188E+00 2.036E+00 0
2. Average Release Rate For Period Ci/Sec 2.814E-01 2.589E-01
3. Percent of Applicable Limit  % 3.940E-04 3.625E-04 l

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UNIT 1 REPORT CATEGORY  : SEMIANNUAL AIRBORNE GROUND LEVEL

CONTINUOUS AND BATCH RELEASES
TOTALS FOR EACH NUCLIDE RELEASED TYPE OF ACTIVITY  : FISSION GASES, IODINES, AND PARTICULATES REPORTING PERIOD  : QUARTER # 1 AND QUARTER # 2 YEAR 1995 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 Fission Gases XE-133M CURIES 0.00E+00 0.00E+00 1.01E-01 0.00E+00 XE-135 CURIES 0.00E+00 0.00E+00 4.68E-02 1.04E-06 XE-131M CURIES 0.00E+00 0.00E+00 3.40E-01 1.01E-02 KR-85 CURIES 0.00E+00 0.00E+00 7.20E+00 8.92E-01 XE-133 CURIES 0.00E+00 0.00E+00 3.09E+01 3.87E+00 Total for Period CURIES 0.00E+00 0.00E+00 3.86E+01 4.77E+00 Iodines I-133 CURIES 0.00E+00 0.00E+00 9.05E-07 8.16E-07 I-131 CURIES 0.00E+00 0.00E+00 1.21E-04 1.46E-05 j Total for Period CURIES 0.00E+00 0.00E+00 1.22E-04 1.54E-05 Particulates CO-58 CURIES 0.00E+00 0.00E+00 6.35E-06 0.00E+00 CS-137 CURIES 0.00E+00 0.00E+00 0.00E+00 6.34E-07 Total for Period CURIES 0.00E+00 0.00E+00 6.35E-06 6.34E-07 Other SR-89 CURIES 0.00E+00 0.00E+00 7.03E-07 0.00E+00 G-ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 1.78E-06 H-3 CU. RIES 0.00E+00 0.00E+00 2.19E+00 2.04E+00 Total for Period CURIES 0.00E+00 0.00E+00 2.19E+00 2.04E+00

Attachment I to

. . OCAN089510 Page 15 of 30 SEMIANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL AIRBORNE EFFLUENTS)

January 1,1995 through June 30,1995 Unit 2 Type of Efiluent Units Quaner 1 Quaner 2 Est. Tot Error %

A. Fission and Activation Products

1. Total Release Curies 1.887E+03 4.054E+02 0
2. Average Release Rate For Period Ci/Sec 2.427E+02 5.157E+01
3. Percent of Applicable Limit  % 3.398E+00 7.220E-01 B. R_adigiodines
1. Total Iodine-131 Curies 7.443E-04 7.301E-07 0
2. Average Release Rate For Period pCi/Sec 9.571E-05 9.286E-08
3. Percent of Applicable Limit  % 2.680E-04 2.600E-07 C. Particulates
1. Particulates (Half-Lives > 8 Days) Curies 1.255E-05 0.000E+00 0
2. Average Release Rate For Period Ci/Sec 1.614E-06 0.000E+00
3. Percent of Applicable Limit  % 4.519E-06 0.000E+00 t
4. Gross Alpha Radioactivity Cuties 1.515E-06 1.496E-06 D. Tritium
1. Total Release Curies 9.171E+00 2.050E+00 0
2. Average Release Rate For Period Ci/Sec 1.179E+00 2.608E-01
3. Percent of Applicable Limit  % 1.651E-03 3.651E-04

Attachment I to

. . OCAN089510 Page 16 of 30 UNIT 2 REPORT CATEGORY  : SEMIANNUAL AIRBORNE GROUND LEVEL

CONTINUOUS AND BATCH RELEASES
TOTALS FOR EACH NUCLIDE RELEASED TYPE OF ACTIVITY  : FISSION GASES, IODINES, AND PARTICULATES REPORTING PERIOD  : QUARTER # 1 AND QUARTER # 2 YEAR 1995 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 Fission Gases KR-87 CURIES 0.00E+00 0.00E+00 6.70E-08 0.00E+00 XE-133M CURIES 0.00E+00 0.00E+00 8.80E+00 0.00E+00 XE-131M CURIES 0.00E+00 0.00E+00 9.89E+00 0.00E+00 KR-85 CURIES 0.00E+00 0.00E+00 1.19E+01 0.00E+00 KR-85M CURIES 0.00E+00 0.00E+00 1.83E-01 8.51E-07 XE-135 CURIES 0.00E+00 0.00E+00 4.16E+01 4.18E+01 XE-133 CURIES 0.00E+00 0.00E+00 1.81E+03 3.64E+02 Total for Pedod CURIES 0.00E+00 0.00E+00 1.89E+03 4.05E+02 Iodines I-131 CURIES 0.00E+00 0.00E+00 7.44E-04 7.30E-07 Total for Period CURIES 0.00E+00 0.00E+00 7.44E-04 7.30E-07 Particulates CO-58 CURIES 0.00E+00 0.00E+00 3.22E-07 0.00E+00 CS-134 CURIES 0.00E+00 0.00E+00 4.35E-06 0.00E+00 CS-137 CURIES 0.00E+00 0.00E+00 7.33E-06 0.00E+00 Total for Period CURIES 0.00E+00 0.00E+00 1.20E-05 0.00E+00 l Other SR-89 CURIES 0.00E+00 0.00E+00 5.61E-07 0.00E+00 ,

G-ALPHA CURIES 0.00E+00 0.00E+00 1.55E-06 1.50E-06 j H-3 CURIES 0.00E+00 0.00E+00 9.17E+00 2.05E+00 Total for Period CURIES 0.00E+00 0.00E+00 9.17E+00 2.05E+00 I

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. . OCAN089510 Page 17 of 30

5.

SUMMARY

OF RADIATION DOSES Annual data is provided in the first report submitted each year.

6.

SUMMARY

OF DOSE TO MEMBERS OF TIIE PUBLIC Annual data is provided in the first report submitted each year.

7. HISTORICAL EFFLUENT DATA The following graphs show the historical release data for both units on a yearly basis. These graphs compare data from 1988 through 1995 (data for 1995 is based on the first six months of the year).

. Attachment I to

, , OCAN089510 Page 18 of 30 UNIT 1 LIQUID EFFLUENTS Fission and Activation Products l 1E+002 1E+001 -

U 5

0 1E+000 -

1 E-001 1988 1989 1990 1991 1992 1993 1994 1995 YEAR UNIT 1 LIQUID EFFLUENTS Tritium 1E+004 1E+003 -

- i 1988 1989 1990 1991 1992 1993 1994 1 1995 YEAR

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UNIT 1 LIQUID EFFLUENTS Dissolved and Entrained Gases 1E+003 1E+002 r E.lill. ai 1988 1989 1990 1991 YEAR 1992 1993 1994 1995 UNIT 1 LIQUID EFFLUENTS Total Volume Released 1E+008

':::: IIIIh 1988 1989 1990 1991 YEAR 1992 1993 1994 1995

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, UNIT 2 LIQUID EFFLUENTS Fission and Activation Products 1E+002 1E+001 -

m a

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1E+000 1E 001 1988 1P89 1990 1991 1992 1993 1994 1995 YEAR UNIT 2 LIQUID EFFLUENTS Tritium l 1E+004

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k l 1E+003 -

@ /

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1E+002 '

1988 1989 1990 1991 1992 1993 1994 1995 YEAR

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Attachment I to OCAN089510 Page 21 of 30 UNIT 2 LIQUID EFFLUENTS Dissolved and Entrained Gases 1E+003 1E+002 -

1 E+001 -

Elh l' d 1 E-001 1988 1989 1990 1991 YEAR 1992

.1993 1994 1995 I UNIT 2 LIQUID EFFLUENTS t

Total Volume Released 1E+008 1E+007 -

,E.00, b 1988 1989 1990 1991 1992 1993 1994 1995 l YEAR l

89510 i

.' Page 22 of 30 UNIT 1 GASEOUS EFFLUENTS  :

Fission and Activation Products 1E+004 1E+003 1E+002 -

1E+001 -

lM 1E+000 1988 1989 1990 1991 1992 1993 1994 1995 YEAR UNIT 1 GASEOUS EFFLUENTS Tritium i j 1E+002 i

2 1 E+001 - -

1E4000 - -

1988 1989 1990 1991 1992 1993 1994 1995 YEAR

.' OC 510 J Page 23 of 30 UNIT 1 GASEOUS EFFLUENTS Radiolodines 1 E-002 1988 1989 1990 1991 1992 1993 1994 1995 YEAR UNIT 1 GASEOUS EFFLUENTS Particulates 1E 001 ,

1E-002 =

1E 003 r

_ dd 1988 1989 1990 1991 1992 1993 aa 1994 1995 YEAR

/

~

8 510

/ Page 24 of 30 UNIT 2 GASEOUS EFFLUENTS Fission and Activation Products 1E+004 1E+003 r N:

1E+002 r 1988 1989 1990 1991 1992 1993 1994 1995 YEAR UNIT 2 GASEOUS EFFLUENTS Tritium 1E+002 l

l L::::iIdh_Ii 1988 1989 1990 1991 YEAR 1992 1993 1994 1995

~

OC 89510 Page 25 of 30 UNIT 2 GASEOUS EFFLUENTS Radioicdines

~

1E 002 1 E-003 =

j m 1 E-004 =

1E-005 e i 1E 006 r 1 E-007 1988 1989 1990 1991 1992 1993 1994 1995 YEAR UNIT 2 GASEOUS EFFLUENTS Particulates 1E-001 -

1E-002 =

1E 003 -

5 U

1 E-004 r > -

/

og A 1988 1989 1990 1991 1992 1993 1994 1995 i YEAR I

Attachment I to

, , OCAN089510 Page 26 of 30

8. SOLID WASTE

SUMMARY

The following is a summary of the solid wastes shipped offsite during the first six months of 1995. l l

REGULATORY GUIDE 1.21 REPORT WASTE DISPOSAL SEMIANNUAL

SUMMARY

REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY l THROUGH JUNE 30,1995 A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel) 6 Month Est. Total

1. Type of Waste Unit Period Error (%) ,
a. Spent resins, filter sludges, m' O.00E+00 evaporator bottoms, etc. Ci 0.00E+00 0.00E+00
b. Dry compressible nste, m' O.00E+00 contaminated eqtup., etc. Ci 0.00E+09 0.00E+00
c. Irradiated components, control m' O.00E+00 rods, etc. Ci 0.00E+00 0.00E+00
d. Other (describe) m' O.00E+00 Ci 0.00E+00 0.00E+00
2. Estimate of Major Nuclide Composition (by Type of Waste) i
a. N/A
b. N/A j c. N/A
d. N/A ,
3. Solid Waste Disposition
Number of Shiomen_1s . Mode of Transportation Destination l 6 Unshielded Vanffruck Oak Ridge, TN

Attachment I to

. . OCAN089510 Page 27 of 30 B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination N/A N/A N/A

9. UNPLANNED RELEASES During the six month period from January 1,1995 through June 30, 1995 there was one unplanned release.

. l ILR95-0193 - Neutralizing Tank Release Release start time  : March 14,1995 at 0957 Release stop time  : March 14,1995 at 1042  :

Release volume :3600 gallons Release duration :45 minutes Total Body Dose :2.96E-06 mrem - Percent of yearly limit < 0.01  !

Critical Organ Dose :3.57E-06 mrem - Percent of yearly limit < 0.01 A. Description of Occurrence On March 14,1995, a Unit 1 operator began a planned neutralizing tank release, but failed to log the release in accordance with procedures. Approximately 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> later, after a shift turnover, a second operator commenced backwashing of a ,

condensate polisher. In accordance with procedures, this water is to be sent to the Unit I neutralizing tank for sampling and analysis prior to release. However, since a ,

neutralizing tank release was already in progress (anknown to the second operator due to the logging failurc), the water from the backwashing operation was added directly to the release without sampling or modification of the release permit. After commencing the backflush, the second operator was notified that the neutralizing tank release had been secured; at this time the unplanned release was realized.

B. Cause for Exceeding Limits No limits were exceeded due to this release.

C. Corrective Actions Taken to Mitigate Occurrence When the neutralizing tank isolation valve was secured, the release was terminated.

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Attachment I to

, . OCAN089510 Page 28 of 30 ,

D. Actions Taken to Prevent Recurrence

1. Procedure 1106.024, " Condensate Demineralizer System Operation and Regeneration," was revised to require verification that a neutralizing tank release is not in progress prior to transferring resin from an exhausted polisher to the regeneration receiving tank.
2. Operations personnel were briefed on the circumstances leading to the unplanned release.

E. Consequences of the Unplanned Release The Unit I neutralizing tank is a normal release tank for radioactive and non-radioactive emuents generated by the ' secondary systems. Samples from this unplanned release revealed that the contents discharged to the flume were consistent with previous tanks of effluents released by this pathway. Because the release pathway and effluent activities were consistent with previous planned releases, no abnormal consequences would be expected to occur due to this release. See data ,

above for dose contribution from this release.

- 10. RADIATION INSTRUMENTATION f As required by Unit I and Unit 2 Technical Specifications, any radioactive effluent instrumentation inoperable for more than 30 days shall be reponed in the next Semiannual Radioactive Effluent Release Report. During the first and second quarters of 1995, no instrumentation was inoperable longer than 30 days.

11. CHANGES TO THE PROCESS CONTROL PROGRAM L

As required by Unit I and Unit 2 Technical Specifications, a description of changes made to r the Process Control Program (PCP) during the reporting period shall be included in the next 3 Semiannual Radioactive Efiluent Release Report. No changes were made to the PCP during i

the first and second quarters of1995. i l

12. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL

[ During the first and second quarters of 1995, the following changes were made to the Offsite

[

Dose Calculation Manual (ODCM):

! A. Sample Station Number 29, used as an alternate location to obtain a milk sample, was deleted because the dairy ceased to function. This change is

, reflected on pages 37 and 41 of the ODCM.

J t

, = - ,. = _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ . _ . . _ _ _ _ _ _ _ _ _ _ _ . _ - _ _ _ . - . _ _ _ . _ . _ ._

_ _ _ _ . _ _ _ _ . ..__m . . _ . _ . _ . _ _ _ _ . _ _ . _ _ _ __. _._

- Attachment I to

, , OCAN089510 l,' Page 29 of 30 B. Sample Station Number 41, used to obtain a milk sample, was deleted because

the dairy ceased to function. This change is reflected on pages 37 and 43 of  ;

the ODCM. j i  !

1

! C. New Sample Station Number 49 was added to rcplace Sample Station Number

41. This change is reflected on pages 37 and 44 of the ODCM.

4 These changa do not reduce the accuracy or reliability of dose calculations or setpoint

, determinations. Revised pages for the ODCM are included. in Attachment 2. The l circumstances necessitating these changes are discussed in Section 14.

i

13. LLD LEVELS i

l 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 Effluent j Release Report. During the reporting period, there, were no LLDs higher than required.

i

14. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 4

! The three environmental sample location changes discussed in Section 12 were the only I changes to the Radiological Environmental Monitoring Program (REMP) during the reporting period. ,

i The following summary describes the circumstances which caused technical specification

{

required samples not to be taken and the modifications to the REMP identified in Section 12 l to be necessary.

On March 20, 1995, Entergy Operations determined that the Radiological l Environmental Monitoring Program was not being conducted in accordance w:ra the j requirements of the ANO Units 1 and 2 Technical Specifications. During the months i of December 1994 through February 1995, only three milk samples were collected, while the ANO Technical Specifications require four samples. This condition was

~

initiated due to the cessation of operation of one milk sample station (dairy) in

. December 1994. Due to an improper interpretation of the technical specification requirements, it was decided that the sample station did not need to be replaced since ,

! no other milk samples could be obtained within five miles of ANO. The improper j interpretation was identified during review of. the draft Annual Radiological Environmental Repon. The condition was corrected in March 1995, when a new milk

! sample station was identified and collection of samples began. Further details may be found in Licensee Event Report 50-313/95-003-00, dated April 14, 1995 (0CAN049511). i i <

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Attachment I to

~

, . OCAN089510 Page 30 of 30 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 IIOURLY METEOROLOGICAL DATA Annual data is provided in the first report submitted each year.

16. DESCRIPTION OF MAJOR CIIANGES TO RADWASTE SYSTEMS i

Annual data is provided in the first report submitted each year.

1 a

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ATTACHMENT 2 OFFSITE DOSE CALCULATION MANUAL

REPLACEMENT PAGES 1

4 4

4 5

1

-.. 4- an, LICENSE.075 Pag 31 Res.5 VO OFFSITE DOSE CALCULATION MANUAL FOR ARKANSAS NUCLEAR ONE REVISION 05

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LICENSE.075 I

P ge 41 Rev.5

) TABLE 4-1 Environmental Sampling Stations - Radiological Sample Station Number 14 Approximate Direction and Distance from Plant: 70* - 5.3 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 (Flat 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 Approximate Direction and Distance from Plant: 95* - 5.1 miles Sample Types 1) Milk

., fg 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 miles. The sample station is on the ". eft at the Arkansas Tech Dairy.

-O

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LICENSE.075 l

? .

Pags 43  :

, Rev.5  ;

,~ ,

i TABLE 4-1 l Environmental Sampling Stations - Radiological I l

Sample Station Number: 38 Approximate Direction and Distance from Plant: 314* - 2.4 miles Sample Types Food products (alternate) samtl e Station Location: l Fres west junction of Highway 64 and Highway 333 in London, AR, go approximately 0.4 ndles west on Highway 64. Turn right at Hornet Estate and go approximately 0.1 ndles. Turn lef t and go approximately 0.1 ndles.

The sample station is on the left at Ronnie Jones' residence.

Sample Station Number: 40 Approximate Direction and Distance from Plant: 119' - 2.2 miles Sample Types : 1) Foods products Sample Station Location:

From junction on Highway 64 and Highway 326 (Marina Road), go approximately 2.0 miles on Marina Road. The sample station is on the left at Horace Hollis' residence just prior to curve.

Sample Station Number: 42 Approximate Direction and Distance from Plant: 73 * - 12. 4 ndles Sample Types: 1) Milk f-~g Sample Station Location:

b From junction of Highway 124 and Highway 326 in Gum Log, AR, go approximately 1.1 miles northeast on Highway 124. Turn left onto Gravel Hill Road and go approximately 0.6 miles. Turn right onto Hudson Loop and go approximately 0.3 miles. The sample station is on the left at the Hudson Dairy.

Sample Station Number: 45 Approximate Direction and Distance from Plant: 90* - 0.9 miles Sample Types 1) Broad leaf vegetation Sample Station Location:

I The sample station is located near mouth of intake canal.

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LICENSE.075 Page 44 Rev.5

, TABLE 4-1

\ Environmental Sampling Stations - Radiological 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.

Sample Station Number: 48 Approximate Direction and Distance from Plant: 316' - 2.2 ndles Sample Types: 1) Food Products Sample Station Location:

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

Sample Station Number: 49 Approximate Direction and Distance from Plant: 338' - 9.0 miles Sample Types: 1) Milk Sample Station Location:

' k//'}

m IF traveling from London, T5EN take Hwy. 333 N. to Augsburg community. Turn left (west) at the Augsburg Church. Travel west on County Road 81 for 3.2 miles. Hylee Dairy on right (north) side of County Road 81.

1 4

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:

IF traveling from Highway 333, THEN turn south onto Flatwood Road and go approximately 0.4 ndles. The sample station is on the right.

IF traveling north on Flatwood Road, THEN go approximately 0.4 ndles from sample station 109. The sample station is on the left.

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