0CAN089607, Semi-Annual Radioactive Effluent Release Rept for First & Second Quarters of 1996
| ML20117H208 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/30/1996 |
| From: | Mims D ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 0CAN089607, CAN89607, NUDOCS 9609090154 | |
| Download: ML20117H208 (29) | |
Text
_. - ._ _
h,:-:- ENTERGY c 1.,2y age,.iie... ioc.
=a a m Rcsc0vM AR 72301 l
, Tel 501858K00 )
i l
i August 30,1996 l
OCAN089607 l
U. S. Nuclear Regulatory Conunission Document Control Desk l Mail Station Pl-137 .
Washington, DC 20555
Subject:
Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 and 50-368 1 License Nos. DPR-51 and NPF-6 4
Semi-Annual Radioactive Efiluent Release Report for the First and Second Quarters of1996 ,
)
Gentlemen:
Arkansas Nuclear One, Units 1 and 2 (ANO-1 & 2) Technical Specifications 6.12.2.6 and ;
6.9.3, respectively, require the submittal of a Semi-Annual Radioactive Efiluent Release '
Report. Tlie purpose of this letter is to complete this reporting requirement for the first and i' second quarters of 1996 at ANO. 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.
Should you have any questions regarding this submittal, please contact me.
Very tmly yours, SF,W/4 Dwight C. Mims Director, Nuclear Safety DCM/eas Attachments i
9609090154 960830 3 d
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PDR ADOCK 05000313 l R PDR i l
U. S. NRC
', August 30,1996 0CAN089607 Page 2 cc: Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector :
Arkansas Nuclear One P.O. Box 310 London, AR 72847 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 Mr. Bernie Bevill Arkansas Department ofHealth Division ofRadiation Control and Emergency Management i 4815 West Markham Street Little Rock, AR 72205 l
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Attachment I to l
', OCAN089607 Page1of22 1
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l ARKANSAS NUCLEAR ONE UNIT 1 AND UNIT 2 OPERATING LICENSE NO. DPR-51 AND NPF-6 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1 THROUGII JUNE 30,1996 l
Attachment I to
'. OCAN089607 Page 2 0f 22 TABLE OF CONTENTS Page
- 1. Introduction 3 I i
! 2. - Regulatory Limits 3 I j 3. Summary ofLiquid Effluent Data 5
] 4. Summary ofGaseous Effluent Data 11 i <
- 5. Summary ofRadiation Doses 16 li 6. Summary of Dose to Members of the Public 16 4 7. Historical Effluent Data 16 ;
- 8. Solid Waste Summary 16 !
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) 9. Unplanned Releases 18 1
j 10. Radiation Instmmentation 19 l l 11. Changes to the Process Control Program 21 1
- 12. Changes to the Offsite Dose Calculation Manual 21-
- 13. LLD Levels 21 l 14. Radiological Environmental Monitoring Program 22 A. Changes in Sample Locations 22
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j B. Identificatior. of New Sample Locations 22 l l
- 15. Summary of the Hoorly Meteorological Data 22
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- ' 16. Description of Major Changes to Radioactive Waste Systems 22 I
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! 1. INTRODUCTION
! Arkansas Nuclear One (ANO) is a two unit plant consisting of a Babcock & Wilcox (Unit 1)
- and,a Combustion Engineering (Unit 2) Nuclear Steam Supply System. Both liquid and i gaseous emuents are released in accordance with the technical specifications for each unit.
l This report is a summary of the emuent data in accordance with Unit 1 Technical l Specification 6.12.2.6 and Unit Two Technical Specification 6.9.3. This report provides the following information:
l A. Routine radioactive emuent release reports covering the operation of the units during the reporting period.
j B. Description of unplanned releases to unrestricted areas.
). C. Description of changes to Offsite Dose Calculation Manual (ODCM).
D. Description of changes to Process Control Program (PCP).
I
- j. E. Sumraary of radiation doses due to radiological effluents during the previous j calensr year. This data is provided in the report covering the third and fourth quarters of each year.
i F. Radiation dose to members of the public due to activities inside the site i boundary. This data is provided in the report covering the third and fourth
- quarters of each year.
G. Description of licensee initiated major changes to the radioactive waste systems during the previous calendar year. This data is provided in the report covering the third and fourth quaners of each year.
H. Items to be reported in the Semi-Annual Report per other miscellaneous technical specifications.
This report covers the period from January 1 through June 30,1996. !
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- 2. REGULATORY LIMITS i
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 l 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. The following are i the limits required by the technical specifications.
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Attachment 1 to
. OCAN089607 Page 4 of 22 A. Gaseous Efiluents
.l. 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 i
Less than or equal to 15 mrems to any organ
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B. Liquid Effluents
- 1. Concentration The concentration of radioactive material released to the discharge canal shall be limited .to the concentration specified in 10CFR20, Appendix B, Table II, Colmnn 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the i
total concentration released shall be limited to 2E-4 microcuries/ml.
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, OCAN089607 Page 5 of 22
- 2. Dose
- Quarterly
,. Less than or equal to 1.5 mrem total body l Less than or equal to 5 mrem critical organ Yearly Less than or equal to 3 mrem total body l' Less than or equal to 10 mrem critical organ
- 3. .
SUMMARY
OF LIQUID EFFLUENT DATA- 1 As required by Regulatory Guide 1.21, Rev.1, Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liauld and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants. a summary of data for liquid releases is provided in the Semi-Annual Report. :
This summary covers releases from January 1 through June 30,1996. The summary ofliquid l effluents for both Unit 1 and Unit 2 is as follows: l Unit 1 Unit 2 Number of releases: 535 181 Total time for all releases (minutes): 89673 297266 Maximum time for a release (minutes): 458 14210.
Average time for a release (minutes): 168 1642 Minimum time for a release (minutes): 14 94 The Unit I liquid releases consisted of:
532 Normal Releases 132 Neutralization Tank 54 Treated Waste Monitor Tanks i 1 Laundry Drain Tanks !
345 Turbine Building Sump 3 Non-routine Releases 3 Condenser Reject to Flume l
0 Unplanned Releases l
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Attachment 1 to I
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The Unit 2 liquid releases consisted of: !
l 181 Normal Releases 9 Boric Acid Condensate Tanks 145 Regenerative Waste Tanks 27 Turbine Building Sump l 0 Non-routine Releases 0 Unplanned Releases l
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Attachment I to
'. OCAN089607 l Page 7 of 22 !
SEMI-ANNUAL SUMMATION FOR ALL RELEASES B*? QUARTER (ALL LIQUID EFFLUENTS)
January 1 through June 30,1996 i Unit 1 i
Type ofEfiluent Units Quarter 1 Quarter 2 Est. Total j Error % ;
A. Fission and Activation Products ,
i
- 1. TotalRelease(NotIncluding Curies 9.907E-02 9.652E-02 0 ;
Tritium, Gases, Alpha)
- 2. Average Diluted Concentration Ci/ml 3.487E-10 2.710E-10 During Period
- 3. Percent of Applicable Limit % 1.162E-01 9.033E-02 :
B. Tritium
- 1. TotalRelease Curies 1.885E+02 2.584E+02 0 l l
- 2. Average Diluted Concentration Ci/ml 6.634E-07 7.255E-07 During Period
- 3. Percent of Applicable Limit % 2.211E-02 2.418E-02 C. Dissolved and Entrained Gases
- 1. TotalRelease Curies 8.525E-01 3.231E+00 0
- 2. Average Diluted Concentration pCi/ml 3.000E-09 9.071E-09 ,
During Period
- 3. Percent of Applicable Limit % 1.500E-03 4.536E-03 D. Gross Aloha Radioactivity
- 1. TotalRelease Curies 7.250E-05 2.850E-03 0 E. Waste Vol Released (Pre-Dilution) Liters 3.095E+07 3.105E+07 0 l
F. Volume of Dilution Water Used Liters 2.841E+11 3.561E+11 0 !
1 Attachment I to 0CAN089607 Page 8 of 22 UNIT 1 REPORT CATEGORY : SEMI-ANNUAL LIQUID CONTINUOUS AND BATCH RELEASES l
- TOTALS FOR EACH NUCLIDE RELEASED TYPE OF ACTIVITY : ALL RADIONUCLIDES REPORTING PERIOD : QUARTER # 1 AND QUARTER # 2 YEAR 1996 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 SR-92 CURIES 0.00E+00 0.00E+00 1.05E-05 0.00E+00 l NB-97 CURIES 0.00E+00 0.00E+00 3.24E-05 0.00E+00 1 CE-144 CURIES 0.00E+00 0.00E+00 1.17E-04 0.00E+00 Y-91M CURIES 0.00E+00 0.00E+00 1.57E-04 0.00E+00 l
Y-91 CURIES 0.00E+00 0.00E+00 7.53E-04 0.00E+00 i NB-94 CURIES 0.00E+00 0.00E+00 0.00E+00 7.47E-06 I-133 CURIES 0.00E+00 0.00E+00 2.75E-05 9.45E-06 ZR-95 CURIES 0.00E+00 0.00E+00 0.00E+00 2.66E-05 KR-85M CURIES 0.00E+00 0.00E+00 0.00E+00 3.06E-05 NB-95 CURIES 0.00E+00 0.00E+00 6.97E-05 6.15E-05 AG-110M CURIES 0.00E+00 0.00E+00 2.89E-05 6.89E-05 MN-54 CURIES 0.00E+00 0.00E+00 1.79E-04 1.13E-04 SN-117M CURIES 0.00E+00 0.00E+00 0.00E+00 1.28E-04 SB-124 CURIES 0.00E+00 0.00E+00 2.12E-04 3.15E-04 i XE-135 CURIES 0.00E+00 0.00E+00 5.57E-04 4.23E-04 CO-57 CURIES 0.00E+00 0.00E+00 8.90E-04 4.48E-04 I-131 CURIES 0.00E+00 0.00E+00 4.91E-04 1.55E-03 CR-51 CURIES 0.00E+00 0.00E+00 5.97E-04 2.45E-03 G-ALPHA CURIES 0.00E+00 0.00E+00 7.25E-05 2.85E-03 NA-24 CURIES 0.00E+00 0.00E+00 2.04E-03 2.99E-03 CS-134 CURIES 0.00E+ 00 0.00E+00 1.35E-03 4.25E-03 CO-58 CURIES 0.00E+00 0.00E+00 2.53E-02 6.65E-03 CS-137 CURIES 0.00E+00 0.00E+00 8.71E-03 1.20E-02 XE-133M CURIES 0.00E+00 0.00E+00 2.12E-03 1.27E-02 !
CO-60 CURIES 0.00E+00 0.00E+00 2.36E-02 1.37E-02 KR-85 CURIES 0.00E+00 0.00E+00 0.00E+00 2.06E-02 SB-125 CURIES 0.00E+00 0.00E+00 3.45E-02 5.17E-02 XE-131M CURIES 0.00E+00 0.00E+00 1.57E-02 6.19E-02 XE-133 CURIES 0.00E+00 0.00E+00 8.34E-01 3.14E+00 H-3 CURIES 0.00E+00 0.00E+00 1.88E+02 2.58E+02 Total for CURIES 0.00E+00 0.00E+00 1.89E+02 2.62E+02 Period
Attachment 1 to
. OCAN089607 Page 9 of 22 SEMI-ANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL LIQUID EFFLUENTS)
- January 1 through June 30,1996
, Unit 2 Type ofEffluent Units Quaner 1 Quarter 2 Est. Total l Error %
A. Fission and Activation Products
- 1. TotalRelease(NotIncluding Curies 1.595E-02 4.851E-02 0 Tritium, Gases, Alpha)
- 2. Average Diluted Concentration pCi/ml 5.614E-11 1.362E-10 During Period
- 3. Percent of Applicable Limit % 1.871E-02 4.540E-02 B. Tritium
- 1. TotalRelease Curies 1.402E+01 3.037E+01 0
- 2. Average Diluted Concentration Ci/ml 4.935E-08 8.527E-08 During Period
- 3. Percent of Applicable Limit % 1.645E-03 2.842E-03 C. Dissolved and Entrained Gases
- 1. TotalRelease Curies 2.968E-03 2.632E-04 0
- 2. Average Diluted Concentration Ci/ml 1.044E-11 7.391E-13 During Period
- 3. Percent of Applicable Limit % 5.222E-06 3.695E-07 D. Gross Alpha Radioactivity
- 1. TotalRelease Curies 3.446E-03 1.790E-02 0 E. Waste Vol Released (Pr.:-Dilution)
. Liters 1.535E+07 1.623E+07 0 F. Volume of Dilution Water Used Liters 2.841E+11 3.561E+11 0
Attachment I to OCAN089607 I Page 10 of 22 l l UNIT 2
- REPORT CATEGORY
- SEMI-ANNUAL LIQUID CONTINUOUS AND BATCH l RELEASES TOTALS FOR EACH NUCLIDE RELEASED l TYPE OF ACTIVITY : ALL RADIONUCLIDES l REPORTING PERIOD : QUARTER # 1 AND QUARTER # 2 YEAR 1996 CONTINUOUS RELEASES BATCH RELEASES !
l NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 MN-54 CURIES 0.00E+00 0.00E+00 7.29E-06 0.00E+00 NA-24 CURIES 0.00E+00 0.00E+00 3.06E-04 0.00E+00 CO-57 CURIES 0.00E+00 0.00E+00 0.00E+00 3.23E-06 ZR-97 CURIES 0.00E+00 0.00E+00 0.00E+00 1.90E-05 CE-143 CURIES 0.00E+00 0.00E+00 0.00E+00 2.18E-05 FE-55 CURIES 0.00E+00 0.00E+00 0.00E+00 1.27E-04 I-131 CURIES 0.00E+00 0.00E+00 1.79E-04 2.026-04 l XE-133 CURIES 0.00E+00 0.00E+00 2.97E-03 ' 2.63E-04 i CO-60 CURIES 0.00E+00 0.00E+00 1.82E-04 3.07E-04 I CS-134 CURIES 0.00E+00 0.00E+00 6.04E-04 3.26E-04 l l
AG-110M CURIES 0.00E+00 0.00E+00 3.65E-04 5.85E-04 CS-137 CURIES 0.00E+00 0.00E+00 1.01E-03 7.1lE-04 )
SR-89 CURIES 0.00E+00 0.00E+00 2.82E-05 1.15E-03 l CR-51 CURIES 0.00E+00 0.00E+00 6.29E-04 1.57E-03 ;
CO-58 CURIES 0.00E+00 0.00E+00 1.94E-03 2.00E-03 I SB-124 CURIES 0.00E+00 0.00E+00 9.51E-04 3.03E-03 G-ALPHA CURIES 0.00E+00 0.00E+00 3.45E-03 1.79E-02 SB-125 CURIES 0.00E+00 0.00E+00 9.75E-03 3.85E-02 H-3 CURIES 0.00E+00 0.00E+00 1.40E+01 3.04E+01 Total for CURIES 0.00E+00 0.00E+00 1.40E+01 3.04E+01 Period l
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Attachment I to
". OCAN089607 i Page 11 of 22
- 4.
SUMMARY
OF GASEOUS EFFLUENT DATA As required by Regulatoy Guide 1.21, Rev.1, a summary of data for gaseous releases is provided in the Semi-Annual Report. This summary covers releases from January 1 through June 30,1996. The summary of gaseous effluents for both Unit I and Unit 2 is as follows:
l Unit 1 Unit 2 Number of releases: 60 83 i Total time for all releases (minutes): 326173 526101 Maximum time for a release (minutes): 10615 10321 ,
Average time for a release (minutes): 5436 6339 Minimum time for a release (minutes): 18 2 The Unit 1 gasecus releases consisted of:
46 Routine vent releases 18 FuelHandling Area 27 Radwaste Area i 1 Hydrogen Purge Emergency Penetration Room ]
l 3 Routine tank releases !
l 3 T18, Waste Gas Decay Tank 9 Non-routine releases:
8 Steam-driven emergency feedwater (EFW) pump 1 Steam safeties 2 Unplanned releases 2 Steam safeties / atmospheric dump valves i
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Attachm:nt I to )
.. OCAN089607 1 l
Page 12 of 22 The Unit 2 gaseous releases consisted of:
73 Routine vent releases l r
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15 Auxiliary Building Extension i 13 Fuel Handling Area l 2 Hydrogen Purge Emergency Penetration Room 12 Low Level Radwaste Building 4 - Post Accident Sampling System 27 Radwaste Area
! 10 Non-routine releases: I 10 Steam driven emergency feedwater (EFW) pump i
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Attachment I to OCAN089607 i Page 13 of 22 l SEMI-ANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL AIRBORNE EFFLUENTS) 1 January 1 through June 20,1996 !
Unit 1 Type ofEffluent Units Quarter 1 Quarter 2 Est. Total Error % j A. Fission and Activation Products
- 1. TotalRelease Curies 4100E+01 3.955E+01 0
- 2. Average Release Rate for Period Ci/Sec 5.342E+00 5.030E+00
- 3. Percent of Applicable Limit % 7.479E-02 7.042E-02
)
l B. Radiciodines
- 1. Totallodine-131 Curies 4.653E-06 2.613E-05 0
- 2. Average Release Rate for Period pCi/Sec 5.918E-07 3.323E-06
- 3. Percent of Applicable Limit % 1.657E-06 9.304E-06 C. Particulates
- 1. Particulates (Half-Lives > 8 Days) Curies 0.000E+00 0.000E+00 0
- 2. Average Release Rate for Period Ci/Sec 0.000E+00 0.000E+00
- 3. Percent of Applicable Limit % 0.000E+00 0.000E+00
- 4. Gross Alpha Radioactivity Curies 0.000E+00 1.793E-07 D. Tritium
- 1. TotalRelease Curies 5.984E+00 1.502E+00 0
- 2. Average Release Rate for Period Ci/Sec 7.61lE-01 1.91IE-01
- 3. Percent of Applictible Limit % 1066E-03 2.675E-04
1 Attachmsnt I to OCAN089607 Page 14 of 22 UNIT 1 REPORT CATEGORY : SEMI-ANNUAL AIRBORNE GROUND LEVEL
- CONTINUOUS AND BATCII RELEASES
- TOTALS FOR EACH NUCLIDE RELEASED TYPE OF ACTIVITY : FISSION GASES, IODINES, AND PARTICULATES REPORTING PERIOD : QUARTER # 1 AND QUARTER # 2 YEAR 1996 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 Fission Gases XE-131M CURIES 0.00E+00 0.00E+00 2.56E-02 3.58E-04 KR-85 CURIES 0.00E+00 0.00E+00 9.66E-02 1.63E-02 XE-135 CURIES 0.00E+00 0.00E+00 9.03E-06 3.93E+00 XE-133 CURIES 0.00E+00 0.00E+00 4.19E+01 3.56E+01 Total for CURIES 0.00E+00 0.00E+00 4.20E+01 3.95E+01 Period Iodines I-133 CURIES 0.00E+00 0.00E+00 5.21E-07 1.37E-06 I-131 CURIES 0.00E+00 0.00E+00 4.56E-06 2.61E-05 Total for CURIES 0.00E+00 0.00E+00 5.17E-06 2.75E-05 Period Particulates l
Total for CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Period Other G-ALPHA CURIES 0.00E+00 ' O.00E+00 0.00E+00 1.79E-07 H3 CURIES 0.00E+00 0.00E+00 5.98E+00 1.50E+00 Total for CURIES 0.0i+E+00 0 00E+00 5.98E+00 1.50E+00 l Period l
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Attachment I to
. . OCAN089607 Page 15 of 22 SEMI-ANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL AIRBORNE EFFLUENTS)
January 1 through June 30,1996
, Unit 2 Type of EfIluent Units Quarter 1 Quarter 2 Est. Total
- Error %
A. Fission and Activation Products
- 1. TotalRelease Curies 0.000E+00 0.000E+00 0
- 2. Average Release Rate for Period Ci/Sec 0.000E+00 0.000E+00
- 3. Percent of Applicable Limit % 0.000E+00 0.000E+00 B. Radiciodines
- 1. TotalIodine-131 Curies 4.396E-07 1.316E-07 0
, 2. Average Release Rate for Period Ci/Sec 5.591E-08 1.674E-03 4
- 3. Percent of Applicable Limit % 1.565E-07 4.688E-08 i C. Paniculates
- 1. Particulates (Half-Lives > 8 Days) Curies 1.105E-06 0.000E+00 0 4
1 2. Average Release Rate for Period Ci/Sec 1.405E-07 0.000E+00
- 3. Percent of Applicable Limit % 3.935E-07 0.000E400
- 4. Gross Alpha Radioactivity Curies 4.728E-07 5.398E-07 D. Tritium
- 1. Total Release Curies 4.228E+00 2.021E+00 0
- 2. Average Release Rate for Period Ci/Sec 5.378E-01 2.571E-01
- 3. Percent of Applicable Limit % 7.529E-04 3.599E-04
Attachment 1 to
', OCAN089607 Page 16 of 22 UNIT 2 REPORT CATEGORY : SEMI-ANNUAL 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 1996 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 Fission Gases Total for CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Period Iodines l I-131 CURIES 0.00E+00 0.00E+00 4.40E-07 1.32E-07 Total for CURIES 0.00E+00 0.00E+00 4.40E-07 1.32E-07 Period Particulates ,
l Total for CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Period I
Other SR-89 CURIES 0.00E+00 0.00E+00 1.10E-06 0.00E+00 G-ALPHA CURIES 0.00E+00 0.00E+00 4.73E-07 5.40E-07 H-3 CURIES 0.00E+00 0.00E+00 4.23E+00 2.02E+00 Total for CURIES 0.00E+00 0.00E+00 4.23E+00 2.02E+00 Period i
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Page 17 of 22 i
- 5.
SUMMARY
OF RADIATION DOSES Annual data is provided in the report covering the third and fourth quarters of each year.
- 6.
SUMMARY
OF DOSE TO MEMBERS OF THE PUBLIC Annual data is provided in the report covering the third and fourth quarters of each year.
- 7. HISTORICAL EFFLUENT DATA Annual data is provided in the report covering the third and fourth quarters of each year.
- 8. SOLID WASTE
SUMMARY
As required by Regulatory Guide 1.21, Rev.1, Radioactivity in Solid Wastes and Reieases of Radioactive Materials in Liauid and Gaseous Efiluents from Light-Water-Cooled Nuclear Power Plants. a summary of data for solid wastes shipped offsite is provided in the Semi-Annual Report. This summary covers shipments from January 1,1996 through June 30,1996.
The summary for solid waste shipments is as follows:
l REGULATORY GUIDE 1.21 REPORT WASTE DISPOSAL ANNUAL
SUMMARY
REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY l THROUGH JUNE 30,1996 j 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 sludge, m3 0.00E+00 evaporator bottoms, etc. Ci 0.00E+00 0.00E+00
- b. Dry compressible waste, m3 3.04E+00 contaminated equipment, Ci 4.34E-01 9.73E-01 etc.
- c. Irradiated components, m3 0.00E+00 control rods, etc. Ci 0.00E400 0.00E+00 l
! m3 0.00E+00
- d. Other(describe)
Ci 0.00E+00 0.00E+00 i
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, ', . Attachment 1 to l
. OCAN089607 Page 18 of 22 l 2. Estimate ofMajor Nuclide Composition (by Type of Waste)
- a. ' CS-137 0.00 0.00E+00 CS-134 0.00 0.00E+00 NI-63 0.00 0.00E+00 FE-55 0.00 0.00E+00 l CO-60 0.00 0.00E+00 CO-58 0.00 0.00E+00 l AG-110M 0.00 0.00E+00 C-14 0.00 0.00E+00 ,
- b. FE-55 24.0 1.04E-01 CS-137 17.3 7.52E-02 CO-60 15.7 6.84E-02 CO-58 14.3 6.19E-02 NI-63 9.9 4.32E-02 CS-134 ' 5.9 2.57E-02 i SB-125 4.7 2.05E-02 AG-110M 2.6 1.12E-02 i MN-54 1.6 7.13E-03 l CR 1.5 6.48E-03 I
- c. N/A N/A N/A i d. N/A N/A N/A i
- 3. Solid Waste Disposition Number of Shioments Mode ofTransportation Destination 1 Unshieldcd Vanfiruck Oak Ridge, TN B. Irradiated Fuel Shipments (Disposition) l Number of Shioments Mode ofTransportation Destination 0 N/A N/A ,
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Attichment I to
'. OCAN089607 Page 19 of 22
- 9. UNPLANNED RELEASES An unplanned release is defined as any release of radioactive material to the environment that does not meet the following criteria:
A. Sample analysis prior to release, and B. Release calculations perfonned prior to release.
During *.he first and second quarters of 1996, there were two unplanned releases (1GR90-0076 and IGR96-0077). The following is a summary of the unplanned releases:
1GR96-0076 - Release of Main Steam via Main Steam Safety Valves Release start time : May 19,1996 at 0312 Release stop time : May 19,1996 at 0330 Release volume : 6.7953E+6 cubic feet .
Release duration : 18 minutes Gamma Air Dose : 0.000E+0 mrad - Percent of yearly limit < 0.01 Beta Air Dose : 0.000E+0 mrad - Percent ofyearly limit < 0.01 ITP Dose : 2.970E-5 mrem - Percent of yearly limit < 0.01 1GR96-0077 - Release of Main Steam via Atmosoheric Dumo Valves Release start time : May 19,1996 at 0348 i Release stop time : May 19,1996 at 0549 Release volume : 9.3737E+6 cubic feet l Release duration : 60 minutes i Gamma Air Dose : 0.000E+0 mrad - Percent ofyearly limit < 0.01 )
Beta Air Dose : 0.000E+0 mrad - Percent of yearly limit < 0.01 l ITP Dose : 4.096E-5 mrem - Percent ofyearly limit < 0.01 l
A. Description ofEvent and Equipment Involved On May 19,1996, ANO-1 experienced a reactor trip on high reactor coolant system pressure. The pressure increase was caused by reduced main feed water (MFW) flow originating from a component failure affecting controls of one of the operating MFW pumps. After the reactor trip, the other MFW pump tripped on high discharge pressure.
Emergency feed water automatically actuated. As expected, several main steam safety l valves (MSSVs) opened following the reactor trip. One MSSV failed to re-seat. This led ,
to the manual start of one high pressure injection pump because of reduced pressurizer level and manual actuation of main steam isolation of the affected Once Through Steam Generator.
. _ . .I
Attachment I to
'. OCAN089607 Page 20 of 22 B. Cause(s) for the Unplanned Release The MSSV failed to re-seat because inadequate engagement between the valve release l nut and a cotter pin used to lock it in place allowed the nut to rotate and engage the manual lift top lever. This incident resulted in the release of steam from the main '
steam system to the atmosphere via the main steam safety valves and the atmospheric l dump valves (ADVs). l l
C. Actions Taken to Prevent Recurrence l The open MSSV was gagged shut. A modification was made to the MSSVs (other than the one gagged) to minimize the possibility of future inadequate pin engagement.
The MSSV that is gagged shut will be modified similar to the other MSSVs during the next refueling outage which is scheduled for September 1996.
D. Consequences of the Unplanned Release The Unit I secondary system is designed to release steam to the atmosphere whenever the turbine trips. However, due to a small primary to secondary leak (< 0.01 gpm),
the contents of this release contained radioactivity. Sample results revealed that the steam contained H-3 in levels above minimum detectable concentrations. The dose due to this release is low in comparison to the yearly limits specified in the Unit 1 Technical Specifications. No abnormal consequences would be expected to occur due to this release. See data above for dose contribution from this release.
- 10. RADIATION INSTRUMENTATION As required by Unit I and Unit 2 Technical Specifications (TS), any radioactive effluent instmmentation inoperable for more than 30 days shall be reported in the next Semi-Annual Radioactive Efiluent Release Report. During the first and second quarters of 1996, one flow meter was found to be inoperable for longer than 30 days:
A. 2FT-4423 ANO-2 Operations personnel discovered that the 18-month channel calibration test had not been performed as required by TS for the flow monitor in the regenerative waste system (RWS). At the time the TS became effective on January 1,1985, the RWS was not being used to process radioactive liquids, and its operating procedure did not have provisions for radioactive releases. When the system operating procedure i was changed in 1990 to allow release of radioactive liquids, the flow monitor became a radioactive liquid effluent monitoring instrument subject to TS 3.3.3.10 and associated
)
surveillance requirements. The procedure change did not adequately consider impact upca the surveillance program. The root cause of this condition has been attributed to inadequate change management. Enhancements to the procedure change administration process implemented subsequent to this condition's origin have been judged to be adequate to minimize the probability of a similar future occurrence. The flow monitor was declared inoperable until a calibration procedure was prepared and
Attachment I to
. OCAN089607 Page 21 of 22 3 ,
the calibration successfully completed. This condition did not cause release of radioactive liquids in excess of any limit.
- 11. CHANGES TO THE PROCESS CONTROL PROGRAM As required by Unit I and Unit 2 Technical Specifiestions, a description of changes made to the Process Control Program (PCP) during the reporting period shall be included in the next Semi-Annual Radioactive Efiluent Release Report. No changes were made to the PCP during the first and second quarters of1996.
- 12. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL l l
In accordance with Unit I and Unit 2 TS, changes to the Offsite Dose Calculation Manual (ODCM) shall be documented in the next Semi-Annual Radioactive Efiluent Release Report.
During the first and second quarters of 1996, one change was made to the ODCM:
Revision 6 This revision deleted milk sample station number 42 due to the fact that the dairy had gone out of business. Milk sample station number 50 was added as a replacement to Figure 4-1 and Table 4-1. !
, The associated station environmental sampling procedure was changed and approved on December 20, 1995, as allowed by technical specifications. The changes were submitted as " draft" in the 1995 3rd & 4th quarter Semi-Annual Report since the new 1 milk sample location was already in use, but the associated ODCM change had not yet been approved. The ODCM was revised on June 13, 1996. These changes do not reduce the accuracy or reliability of dose calculations or setpoint determinations. The affected pages are included in Attachment 2.
- 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 Semi-Annual Radioactive Effluent I Release Report. During the reporting period, there were no LLDs higher than required.
l Attachment I to
', OCAN089607 Page 22 of 22 l
- 14. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM A. Changes in Sample Locations In accordance with Unit I and Unit 2 TS, unavailability of milk or fresh, leafy vegetable samples, or an increase in an envirormental sample location's calculated dose commitment must be identified in the Semi-Annual Radioactive Efiluent Release Report. During the reporting period, there were no environmental sampling location changes and there were no environmental sampling locations identified which would yield a calculated dose commitment greater than the values currently being calculated.
B. Identification ofNew Sample Locations No sample locations were added during the reporting period.
- 15.
SUMMARY
OF HOURLY METEOROLOGICAL DATA Annual data is provided in the report covering the third and fourth quarters of each year.
- 16. DESCRIPTION OF MAJOR CHANGES TO RADIOACTIVE WASTE l SYSTEMS j Annual data is provided in the report covering the third and fourth quarters of each year.
1
1 Attachment 2 to
, . OCAN089607 Pagelof5 j
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1 OFFSITE DOSE CALCULATION l
- MANUAL CHANGES
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Attachment 2 to LICENSE.075
- OCAN089607 Page 1 Page 2 Of 5 R0v. g ,
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1 Attaclunent 2 to LICENSE.075 0C/09089607 P ga 43 Page 4 of 5 Rev.6 TABLE 4-1 Environmental Sampling Stations - Radiological i 1 Sample Station Number: 38 Approximate Direction and Distance from Plants 314* - 2.4 miles Sample Types: Food products (alternate)
- Sample Station Location
From west junction of Highway 64 and Highway 333 in London, AR, go 3 approximately 0.4 miles west on Highway 64. Turn right at Hornet Estate and go approximately 0.1 miles. Turn left and go approximately 0.1 ndles. The sample station is on the left at Ronnie Jones' residenc'e. i Sample Station Number: 40
- Approximate Direction and Distance from Plant: 119' - 2.2 miles 4
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. I 1 1
- Sample Station Number
- 45 Approximate Direction and Distance from Plant: 90* - 0.9 miles Sample Types 1) Broad leaf vegetation Sample Station Location:
't j The sample station is located near mouth of intake canal. i s
, Attachm:nt 2 to UCENSE.075 0C/04089607 Pag) 44 Page 5 of 5 Rev.6 , l 1 i TABLE 4-1 Environmental Sampling Stations - Radiological ; i l Sample Station Numbers 46 : Approximate Direction and Distance from Plant: 295* - 4.1 ndles i Sample Types: 1) Food products l i 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. i i l Sample Station Number 48 l Approximate Direction and Distance from Plant: 316* - 2.2 miles Sample Types: 1) Food Products Sample Station Location: 1 1 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 ndles ; Sample Types : 1) Milk l Sample Station Location:
, 1 IF traveling from London, l THEN take Hwy. 333 N. to Augsburg community. Turn left (west) at the Augsburg Church. Travel west on County Road 81 for 3.2 miles. Rylee Dairy on right (north) side of County Road 81.
Sample Station Number: 50 Approximate Direction and Distance from Plant: 47' - 10.8 ndles Sample Types: 1) Milk Sample Station Location: Take State Highway 7 north to Dover. Turn right (east) on State Highway 27. Go approximately 1.6 miles. Dairy is located on left (north) side of State Highway 27. 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 miles. The sample station is on the right. IF traveling north on Flatwood Road, THEN go approximately 0.4 miles from sample station 109. The sample station is on the left.}}