0CAN089306, Ano,Units 1 & 2 Semiannual Radioactive Effluent Release Rept,Jan-June 1993
| ML20056F848 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/30/1993 |
| From: | James Fisicaro ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 0CAN089306, CAN89306, NUDOCS 9308310205 | |
| Download: ML20056F848 (30) | |
Text
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1 August 27,1993 OCAN089306 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555
Subject:
Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Semiannual Radiological Effluent i
Release Report for the First and Second Quarters of 1993 Gentlemen:
e 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 Semiannual Radioactive Effluent Release Report. The purpose of this letter is to complete this reporting requirement for the first and second quarters of 1993 at ANO.
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Should you have any questions regarding this submittal, please contact me.
Very truly yours, au l'.).eaLn
/James J. -isicaro Director, Licensing JJF/JJD Attachment m
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U.S.NRC' August 27,1993 OCAN089306 Page 2 l
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Mr. James L. Milhoan l'
U. S. Nuclear Regulatory Commission l
Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 j
NRC Senior Resident Inspector 2
Arkansas Nuclear One - ANO-l&2 Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. Roby Bevan NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission l
NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Thomas W. Alexion l
NRR Project Manager, Region IV/ANO-2 l
U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 1
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ARKANSAS NUCLEAR ONE UNIT 1 AND UNIT 2 OPERATING LICENSE NO. DPR-51 AND NPF-6 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1,1993 THROUGH JUNE 30,1993 l
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l TABLE OF CONTENTS l
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1.
Introduction l
I 2.
Regulatory Limits 3.
Summary of Liquid Effluent Data 4.
Summary of Gaseous Effluent Data t
5.
Historical Effluent Data 6.
Solid Waste Summary 7.
Unplanned Releases l
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Radiation Instrumentation 9.
Changes to the Process Control Program 10.
Changes to the Offst e Dose Calculation Manual i
11.
LLD Levels 12.
Radiological Environmental Monitoring Program A.
Changes in Sample 1.ocations B.
Identification of New Sample Locations l
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1.
INTRODUCTION I
Arkansas Nuclear One is a two unit plant consisting of a B&W (Unit 1) and CE (Unit 2) design.
i Both liquid and gaseous effluents are released in accordance with the respective units Technical i
Specifications. This report is a summary of the effluent data in accordance with Unit 1 l
Technical Specification 6.12.2.6 and Unit Two Technical Specification 6.9.3.
This report l
provides the following information:
j 1.
Routine radioactive effluent release reports covering the operation of the unit during the previous 6 months of operation.
2.
Description of unplanned releases to unrestricted areas.
3.
Description of changes to ODCM.
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4.
Description of changes to PCP.
5.
Items to be reported in the Semiannual Report per other miscellaneous Technical Specifications.
This report covers the period of January 1,1993 through June 30,1993.
2.
REGULATORY LIMITS The Unit One and Unit Two Technical Specifications contain the limits to which Arkansas i
Nuclear One must adhere. Because of the ALARA philosophy at ANO, an attempt is made to reduce the amount of ra<liation released to the environment to as low as reasonable achievable.
The following are the limits required by the Technical Specifications.
A.
Gaseous Effluents 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.
I 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.
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2.
Dose - Noble Gases Quarterly less than or equal to 5 mrads gamma.
Less than or equal to 10 mrads beta.
Yearly Irss 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 l_ess than or equal to 7.5 mrems to any organ.
Yearly Less than or equal to 15 mrems to any organ.
B.
Liquid Effluents 1.
Concentration The concentration of radioactive material released to the discharge canal shall be limited to the concentration specified in 10 CFR Part 20, 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.
2.
Dose Quarterly Less than or equal to 1.5 mrem total body.
Iess than or equal to 5 mrem critical organ.
Yearly Less than or equal to 3 mrem total body.
Less than or equal to 10 mrem critical organ.
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3.
SUMMARY
OF LIQUID EFFLUENT DATA l
The following data is a summary of releases for both Unit I and Unit 2. These releases occurred f
between January 1,1993 and June 30,1993.
Unit 1 Unit 2 I
Number of releases:
123 82 Total time for all releases (minutes):
17737 23718 i
Maximum time for a release (minutes):
287 2113 l
Average time for a release (minutes):
144 289 l
Minimum time for a release (minutes):
30 102 i
As required by Regulatory Guide 1.21 Rev.1, a summary of the data for liquid releases is to be provided in the semiannual report. One unplanned liquid effluent release from Unit 1 occurred during this period, as discussed in Section 7. The summary ofliquid effluents for both j
Unit I and Unit 2 follows (4 pages):
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Arkansas Nuclear One Unit 1 Page 1 SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER ALL LIQUID EFFLUENTS January 1993 through June 1993 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %
A.
FISSION & ACTIVATION PRODUCTS h
- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA)
CURIES 1.195E_01 2.348E-01 0
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 9.973E-09 1.708E_08
___________-_____________-______________-____________________5.694E+00
- 3. PERCENT OF APPLICABLE LIMIT 3.324E+00 B.
___-_-___________________-_________01 1.125E+02 0
- 1. TOTAL RELEASE CURIES 8.413E+
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 7.021E-06 8.187E-06
________________________________-_______________________01 2.729E-01 l
- 3. PERCENT OF APPLICABLE LIMIT 2.340E-C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 5.222E-02 9.571E-02 0
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.358E-09 6.962E-09
________-________--____-___-_______-_-__________________03 3.481E-03 3.
PERCENT OF APPLICABLE LIMIT 2.179E-r D.
GROSS ALPHA RADIOACTIVITY l
_______-___________________________________-________-___04 0.000E+00 0
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- 1. TOTAL RELEASE CURIES 2.253E-E. WASTE VOL RELEASED (PRE-DILUTION)
LITERS 5.504E+06 5.664E+06 0
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_______________-_____________________________________7E+10 1.373E+10 0
F. VOLUME OF DILUTION WATER USED LITERS 1.19 I
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Arkansas Nuclear One Unit 1 Page 2 SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES REPORT CAT'EGORY TOTALS FOR EACH NUCLIDE RELEASED.
l TYPE OF ACTIVITY
- ALL RADIONUCLIDES QUARTER # 1 AND QUARTER # 2 YEAR 1993 REPORTING PERIOD l CONTINUOUS RELEASES l BATCH RELEASES l
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_______________________________________________l QUARTER 2 l QUARTER 1 l QUARTER 2 UNIT
- QUARTER 1 NUCLIDE l
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ALL NUCLIDES t
_______________________________________________l 0.00E+00 l 2.25E-04 !
0.00E+00 G-ALPHA l
CURIES
] 0.00E+00 XE-133M l
CURIES l 0.00E+00 l 0.00E+00 l 2.43E-04 0.00E+00 BE-7 l
CURIES l 0.00E+00 l*0.00E+00 l 3.36E-04 0.00E+00 SR-90 l
CURIES l 0.00E+00 l 0.00E+00 1 8.05E-04 0.00E+00 l t
NB-97 l
CURIES l 0.00E+00 4 0.00E+00 3.80E-05 8.24E-06 [
0.00E+00 1.52E-05 !
MO-90 l
CURIES l 0.00E+00 0.00E+00 l
ZR-97 l
CURIES l 0.00E+00 0.00E+00 l 0.00E+00 1.64E-05 t
KR-87 l
CURIES l 0.00E+00 0.00E+00 L 0.00E+00 2.29E XE-135M l
CURIES l 0.00E+00 0.00E+00 i 0.00E+00 3.04E-05 i
SN-113 l
CURIES l 0.00E+00 l 0.00E+00 7.46E-05 3.65E-05 8.50E-06 ! 6.34E-05 l NA-24 l
CURIES O.00E+00 l 0.00E+00 i
58-124 l
CURIES 0.00E+00 l 0.00E+00 !
0.00E+00 1.52E-04 I-133 l
CURIES 1 0.00E+00 l 0.00E+00 1 1.03E-04 1.95E-04 I
i LA-140 l
CURIES j 0.00E+00 l 0.00E+00 6.23E-05 l 1.99E-04 CO-57 j
CURIES l 0.00E+00 l 0 00E+00 l 9.64E-04 '
2.64E-04 SR-92 l
CURIES l 0.00E+00 1 0.00E+00 l 1.89E-05 5.10E-04 i
XE-135 j
CURIES l 0.00E+00 1 0.00E+00 l 3.46E-05
( 7.42E-04 SR-89 l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 8.63E-04 SB-125 j
CURIES l 0.00E+00 l 0.00E+00 l 1.67E-03 [ 1.52E-03 :
. NB-95 l
CURIES
] 0.00E+00 l 0.00E+00 l 3.12E-03 l 1.72E-03 l ZR-95 l
CURIES l 0.00E+00 0.00E+00 1.55E-03 !
2.10E-03 l f
I-131 l
CURIES l 0.00E+00 0.00E+00 1.18E-03 2.24E-03 l i
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' 2.65E-03 [
XE-131M l
CURIES l 0.00E+00
, 0.00E+00 1 0.00E+00 CR-51 l
CURIES l 0.00E+00 l 0.00E+00 l 2.12E-03 3.22E-03 l l
MN-54 l
CURIES l 0.00E+00 l 0.00E+00 l 2.19E-03 3.74E-03 CS-134 l
CURIES l 0.00E+00 1 0.00E+00 l 2.28E-03 l 4.70E-03 CS-137 j
CURIES l 0.00E+00 l 0.00E+00 l 7.08E-03 l 1.09E-02 CO-60 l
CURIES l 0.00E+00 l 0.00E+00 l 3.65E-02 l 1.89E-02 i
FE-55 l
CURIES 1 0.00E+00 ] 0.00E+00 l 8.25E-03 l 4.47E-02 l CO-58 l
CURIES l 0.00E+00 l 0.00E+00 l 4.98E-02 l 6.68E-02 1
AG-110M l
CURIES l 0.00E+00 l 0.00E+00 l 1.25E-03 l 7.18E-02 l
XE-133 l
CURIES l 0.00E+00 1 0.00E+00 l 5.19E-02 l 9.22E-02 i
H-3 J
CURIES l 0.00E+00 l 0.00E+00 l 8.41E+01 l 1.12E+02 l l
_____________________________________________0 l 0.00E+00 l 8.43E+01 l 1.12E+02 l l
TOTAL FOR PERIOD l
CURIES l 0.00E+0 I
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Entergy Operations Inc.
Arkansas Nuclear One Unit 2 Page 1 SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER ALL LIQUID EFFLUENTS January 1993 through June 1993 TYPE OF EFFLUENT UNITS QU72TER 1 QUARTER 2 EST. TOT ERROR %
A.
FISSION & ACTIVATION PRODUCTS
______________________________________________________.e_________________________
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- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA)
CURIES 7.073E-02 2.702E-01 0
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.661E-09 1.405E-08
- 3. PERCENT OF APPLICABLE LIMIT 1.553E+00 4.686E+00 t
B.
___________________________________________________________________________0
- 1. TOTAL RELEASE CURIES 9.494E+00 4.663E+01
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD UCi/ML 6 256E-07 2.425E-06
_______________.________________________________m_______________________________
- 3. PERCENT OF APPLICABLE LIMIT 2.085E-02 8.085E-02 i,
C.
DISSOLVED AND ENTRAINED GASES
___________________________________________________________________________0
- 1. TOTAL RELEASE CURIES 2.900E-03 7.697E-02 j
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD UCi/ML 1.911E-10 4.003E-09
- 3. PERCENT OF APPLICABLE LIMIT 9.557E-05 2.001E_03 D. GROSS ALPHA RADIOACTIVITY
_____________________________e___________________________________________________
- 1. TOTAL RELEASE CURIES 1.815E-04 4.843E-05 0
E. WASTE VOL RELEASED (PRE-DILUTION)
LITERS 3.327E+06 6.673E+06 0
____e.___________________________________________________________________________
F. VOLUME OF DILUTION WATER USED LITERS 1.517E+10 1.921E+10 0
_een__===>___e*_____e.ee__emme=_em________es._eme._e=____e=_e=__==_==_em_e-___e=_a=___==_emmeei-ooem___enn___==_
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Arkansas Nuclear One Unit 2 Page 2 REPORT CATEGORY
- SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES
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- TOTALS FOR EACH NUCLIDE RELEASED.
l TYPE OF ACTIVITY
- ALL RADIONUCLIDES REPORTING PERIOD
- QUARTER # 1 AND QUARTER # 2 YEAR 1993 i
l CONTINUOUS RELEASES l BATCH RELEASES l
I UNIT
- QUARTER 1 ] QUARTER 2 l QUARTER 1 l QUARTER 2 l NUCLIDE l
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j ALL NUCLIDES i
ZR-97 l
CURIES l 0.00E+00 l 0.00E+00 l 8.16E-06 l 0.00E+00 l e
I-134 I
CURIES l 0.00E+00 1 0.00E+00 l 8.83E-06 l 0.00E+00 l NA-24 l
CURIES l 0.00E+00 1 0.00E+00 l 1.37E-04 l 0.00E+00 l I-135 l
CURIES l 0.00E+00 l 0.00E+00 l 1.76E-04 j 0.00E+00 ;
CE-143 l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 8.63E-06 SR-92 l
CURIES l 0.00E+00 l 0.00E+00 [ 0.00E+00 l 4.33E-05 G-ALPHA l
CURIES l 0.00E+00 l 0.00E+00 l 1.81E-04 l 4.84E-05 t
X-133 l
CURIES I 0.00E+00 l 0.00E+00 l 3.94E-04 l 5.43E-05 WB-97 l
CURIES l 0.00E+00 l 0.00E+00 l 9.61E-05 l 7.73E-05 l SE-75 i
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.14E-04 l SN-113 l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.15E-04 l CO-57 l
CURIES l 0.00E+00 1 0.00E+00 l 7.09E-05 l 1.33E-04 l FE-59 l
CURIES l 0.00E+00 1 0.00E+00 l 0.00E+00 l 1.65E-04 l LA-140 l
CURIES I 0.00E+00 l 0.00E+00 l 0.00E+00 l 2.37E-04 l FE-55 l
CURIES l 0.00E+00 l 0.00E+00 l 1.04E-02 l 2.87E-04 l XE-135 l
CURIES i 0.00E+00 l 0.00E+00 l 6.21E-05 L 3.12E-04 l ZR-95 l
CURIES l 0.00E+00 l 0.00E+00 l 1.70E-04 4.88E-04 NB-95 l
CURIES l 0.00E+00 0.00E+00 l 2.95E-04 5.41E-04 l
XE-133M l
CURIES l 0.00E+00 0.00E+00 l 0.00E+00 l 5.63E-04 l SB-126
)
CURIES l 0.00E+00 j 0.00E+00 l 0.00E+00 l 5.92E-04 l SR-89 l
CURIES l 0.00E+00 l 0.00E+00 l 3.11E-04 l 5.99E-04 l SB-122 l
CURIES l 0.00E+00 1 0.00E+00 l 0.00E+00 l 1.00E-03 l i
I-131 l
CURIES l 0.00E+00 l 0.00E+00 l 1.20E-04 l 1.32E-03 l CO-60 l
CURIES l 0.00E+00 l 0.00E+00 l 2.13E-03 l 6.74E-03 l l
CR-51 l
CURIES l 0.00E+00 1 0.00E+00 l 0.00E+00 l 6.80E-03 l l
MN-54 l
CURIES l 0.00E+00 l 0.00E+00 l 1.59E-02 l 8.45E-03 l AG-110M l
CURIES l 0.00E+00 l 0.00E+00 l 6.39E-04 l 9.30E-03 l TE-132 l
CURIES j 0.00E+00 1 0.00E+00 l 0.00E+00 1 1.26E-02 l SB-124 l
CURIES
] 0.00E+00 l 0.00E+00 l 1.00E-03 l 1.55E-02 l I-132 j
CURIES l 0.00E+00 l 0.00E+00 l 5.06E-05 1.85E-02 l CS-134 l
CURIES l 0.00E+00 1 0.00E+00 l 5.53E-03 l 2.41E-02 l CS-137
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CURIES l 0.00E+00 l 0.00E+00 l 7.73E-03 4.23E-02 l CO-58 l
CURIES l 0.00E+00 l 0.00E+00 l 1.58E-02 4.92E-02 l 6
SB-125 l
CURIES l 0.00E+00 l 0.00E+00 l 9.59E-03 7.07E-02 l 7.60E-02 l XE-133 l
CURIES l 0.00E+00 l 0.00E+00 l 2.83E-03
. 4.66E+01 l H-3 l
CURIES l 0.00E+00 l 0.00E+00 l 9.49E+00 l TOTAL FOR PERIOD j
CURIES l 0.00E+00 l 0.00E+00 l 9.56E+00 l 4.69E+01 l
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4.
SUMMARY
OF GASEOUS EFFLUENT DATA I
As required by Regulatory Guide 1.21'Rev.1, a summary of the data for gaseous releases is to l
be provided in the semiannual report. This summary covers releases during January 1,1993 and l
June 30,1993. The summary of gaseous effluents for both Unit I and Unit 2 is as follows-i Unit 1 Unit 2 Number of releases:
61 102 Total time for all releases (minutes):
425259 596411 l
Maximum time for a release (minutes):
10198 10393 l
Average time for a release (minutes):
7088 5847 Minimum time for a release (minutes):
16 3
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i The Unit I gaseous releases consisted of:
i 5 emergency feedwater (EFW) pump releases - These releases were a result of i
surveillances to the steam driven EFW pump.
2 waste gas decay tank releases.
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i 52 weekly vent releases.
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2 unplanned reieases, j
t The Unit 2 gaseous releases consisted of:
14 emergency feedwater (EFW) pump releases - These releases were a result of surveillances to the steam driven EFW pump.
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I reactor building purge.
8 8
I 2 volume control tank (VCT) releases.
84 weekly vent releases.
1 unplanned release.
The three unplanned gaseous releases are discussed in more detail in Section 7.
Additional gaseous effluent data is contained in the following summaries (4 pages):
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Arkansas Nuclear One Unit 1 Page 1 1
SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER j
ALL AIRBORNE EFFLUENTS i
January 1993 through June 1993 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT t
ERROR %
1 ____________________________________________________________________.___________
A.
FISSION & ACTIVATION PRODUCTS i
1.
TOTAL RELEASE CURIES 7.683E-03 3.691E-03 0
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 9.881E-04 4.695E-04
- 3. PERCENT OF APPLICABLE LIMIT 1.383E-05 6.573E-06 4
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4 B.
RADIOIODINES 1
- 1. TOTAL IODINE-131 CURIES 4.462E-06 4.356E-07 0
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.738E-07 5.541E-08 3 ________________________________________________________________________________
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- 3. PERCENT OF APPLICABLE LIMIT 1.606E-06 1.551E-07 g
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C.
PARTICULATES i
- 1. PARTICULATES(HALF-LIVES >8 DAYS)
CURIES 2.046E_07 3.488E-07 0
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- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.632E-08 4.436E-08
- 3. PERCENT OF APPLICABLE LIMIT 7.369E-08 1.242E-07 4.
GROSS ALPHA RADIOACTIVITY CURIES 0.000E+00 0.000E+00 D.
TRITIUM t
- 1. TOTAL RELEASE CURIES 3.592E+00 3.242E+00 0
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.620E-01 4.124E-01 3.
PERCENT OF APPLICABLE LIMIT 6.468E-04 5.774E-04 i
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Arkansas Nuclear One Unit 1 Page 2 SEMIANNUAL AIRBORNE GROUND LEVEL CONTINUOUS AND REPORT CATEGORY l
- BATCH RELEASES. TOTALS FOR EACH NUCLIDE RELEASED.
TYPE OF ACTIVITY
- FISSION GASES, IODINES, AND PARTICULATES REPORTING PERIOD
- QUARTER # 1 AND QUARTER # 2 YEAR 1993 l
CONTINUOUS MODE l
BATCH MODE l
1
_____________________-_-_-_______________________________-__--_-___1 l QUARTER 2 UNIT
- QUARTER 1 l QUARTER 2 l QUARTER NUCLIDES RELEASED l
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FISSION GASES
-_-____________----_______--_-_---_-___1.27E-03 0.00E+00 l XE-133 l
CURIES l 0.00E+00 0.00E+00 l KR-85 l
CURIES l 0.00E+00 0.00E+00 l 6.41E-03 3.69E-03 l l
-_____________-_______-____________--________---__-_--_--____68E-03 l 3.69E-03 l I
TOTAL FOR PERIOD l
CURIES l 0.00E+00 1 0.00E+00 l 7.
i IODINES
-________________---_______________________--__-_-_-________-_12E-06 l 0.00E+00 l i
I-133 l
CURIES l 0.00E+00 l 0.00E+00 l 2.
I-131 l
CURIES l 0.00E+00 l 0.00E+00 l 4.46E-06 l 4.35E-07 l
_-____________________________________---_-____-____----_-_-__58E-06 l 4.35E-07 l TOTAL FOR PERIOD l
CURIES l 0.00E+00 l 0.00E+00 l 6.
i PARTICULATES l
__-_________________---________________________________________0E+00 l 9.05E-09 CS-137 l
CURIES j 0.00E+00 l 0.00E+00 l 0.0 CO-58 l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 3.39E-07
____________________________-_-_---_____-____________--_______00E+00 l 3.48E-07 l TOTAL FOR PERIOD l
CURIES 1 0.00E+00 1 0.00E+00 [
0.
OTHER
_________________--______-_________________________--_-__-____04E-07 0.00E+00 l SR-89 l
CURIES l 0.00E+00 l 0.00E+00 l 2.
3 H-3 l
CURIES l 0.00E+00 l 0.00E+00 l 3.59E+00 3.24E+00 l
______--__-______________________________--_--_____-_-______3.59E+00 l 3.24E+00 l TOTAL FOR PERIOD l
CURIES l 0.00E+00 1 0.00E+00 l r
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Arkansas Nuclear One Unit 2 Page 1 SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER ALL AIRBORNE EFFLUENTS January 1993 through June 1993 i
TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %
A.
FISSION & ACTIVATION PRODUCTS
_____----_-_---__-_-_-__-__-______---_______--_________00 1.587E+01 0
- 1. TOTAL RELEASE CURIES 0.000E+
____-_-___-_______________________________0 2.018E+00
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.000E+0
___-______________-______________________________________-___2.825E-02
- 3. PERCENT OF APPLICABLE LIMIT 0.000E+00 B.
RADIOIODINES
_______--__-_--_____________-----_____-----______-______________90E-08 0
- 1. TOTAL IODINE-131 CURIES 8.138E-08 6.1
_________-____-_-__-____-____-___________________________________3E-09
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.046E-08 7.87
__-_-_-____________-__2.204E-08
- 3. PERCENT OF APPLICABLE LIMIT 2.930E-08 l
C.
PARTICULATES
\\
-__________________4.634E-07 0
- 1. PARTICULATES(HALF-LIVES >8 DAYS)
CURIES 0.000E+00
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.000E+00 5.895E-08
____---_________-____---__________________650E-07
- 3. PERCENT OF APPLICABLE LIMIT 0.000E+00 1.
_-__-__-_--_-________________---____--____---__________________000E+00 4.
GROSS ALPHA RADIOACTIVITY CURIES 0.000E+00 0.
l l
D.
TNITIUM
_________________~______________-__---_-____--_--_------------535E+00 0
- 1. TOTAL RELEASE CURIES 2.738E+00 1.
_-______________-_____-_-_-_-----------------------------------52E-01
- 2. AVERAGE RELEASE RATE FOR PERIOD UCi/Sec 3.521E-01 1.9
~~~~---~~~~
_______________________-----__------------------ --------------33E-04 i
- 3. PERCENT OF APPLICABLE LIMIT 4.929E-04 2.7 l
l 1
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Ent,ergy' Operations Inc.
Arkansas Nuclear One Unit 2 Page 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 1993 l
CONTINUOUS MODE l
BATCH MODE l
UNIT
- QUARTER 1 lQUARTER 2 l QUARTER 1 QUARTER 2 l NUCLIDES RELEASED
]
l l
l l
FISSION GASES XE-133M l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 2.19E-04 1
XE-131M l
CURIES l 0.00E+00 1 0.00E+00 l 0.00E+00 8.
3E-04 XE-135 l
CURIES l 0.00E+00 1 0.00E+00 1 0.00E+00 1.49E-01 XE-133 l
CURIES l 0.00E+00 l 0.00E+00 1 0.00E+00 l
- 1. 8.' E+ 0 0 l KR-85 l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.384+01 l TOTAL FOR PERIOD l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.58E+01 l TODINES X-131 l
CURIES l 0.00E+00 l 0.00E+00 l 8.13E-08 l 6.19E-08 l 1-133 l
CURIES l 0.00E+00 0.00E+00 l 4.93E-08 1.54E-07 l I-132 l
CURIES l 0.00E+00 0.00E+00 l 0.00E+00 7.26E-06 l
)
TOTAL FOR PERIOD l
CURIES l 0.00E+00 l 0.00E+00 l 1.30E-07 l 7.47E-06 l PARTICULATES j
CO-58 l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 7.21E-09 l CS-137 l
CURIES l 0.00E+00 l 0.00E+00 1 0.00E+00 l 2.61E-08 l CO-57 l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l B.18E-08 ]
BA-133 l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 3.48E-07 l 7
TOTAL FOR PERIOD l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 4.63E-07 l l
OTHER H-3 l
CURIES l 0.00E+00 l 0.00E+00 l 2.73E+00 l 1.53E+00 l l
TOTAL FOR PERIOD l
CURIES l 0.00E+00 1 0.00E+00 l 2.73E+00 l 1.53E+00 l
5.
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 first six months of 1993.
Graph 1 - Unit 1 Gaseous Effluents Total Curies Released.
Graph 2 -Unit 1 Liquid Effluents Total Curies Released.
Graph 3 - Unit 2 Gaseous Ef0uents Total Curies Released.
Graph 4 - Unit 2 Liquid Effluents Total Curies Released.
Graph 5 - Unit 1 Liquid Effluents Total Volume.
Graph 6 - Unit 2 Liquid Effluents Total Volume.
i 1
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UNIT 1 GASEOUS EFFLUENTS i
i i
TOTAL CURIES RELEASED 1
l 10000 r
I 1000 4
I 100 g
y c.
1 l
10 l
v>
9 5
l h
~
i; f,w O
J O
- r.,
O.1 r
i l'
r
[
=.
7, E
m
'1
)
0.01 r
a
=-.
95 5
l y
m e
.+
g
.. g g
e 0.001 [
- p M
"4
-h j dh 4
l 0.0001 1988 1989 1990 1991 1992 1993 YEAR M Ts Tiuu R FISSION AND 2 IODINES C 'd PARTICULATE ACTIVATION i
I I
UNIT 1 LIQUID EFFLUENTS i
TOTAL CURIES RELEASED i
i f
l 1000:
4 100[
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,0 'r r.-.
e a
u>
s.z w
M m I E
);.
=
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- 1 c..
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a
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l
,, d l
0.01 1988 1989 1990 1991 1992 1993 YEAR i
M TRITIUM FISSION AND C GASES j
ACTIVATION j
i
UNIT 2 GASEOUS EFFLUENTS TOTAL CURIES RELEASED i.-
i 1E+04 1E+03 2'
1E+02-g 7
t l.,
R L
1 E+ 01 w
j i
g 1E+00 r
h L
1 E-01 r
f I
l Sl
- g 1 E-02 r
i E
B
[
4 7
1 E-03 M L d
. i_5 Nd r
l e
j a
j
,g,g,
1988 1989 1990 1991 1992 1993 YEAR l
E TRITIUM R FISSION Ar4D th IODINES LEEl PARTICULATE ACTIVATION i
UNIT 2 LIQUID EFFLUENTS TOTAL CURIES RELEASED j
1000g t
i l
1988 1989 1990 1991 1992 1993 l
YEAR M TRITIUM M FISSION AND E GASES 4
I UNIT 1 LIQUID EFFLUENTS TOTAL VOLUME 1E+08 l
I t
b 1E+07 :
1 E+ 06 -
l 1988 1989 1990 1991 1992 1993 YEAR E TOTAL GALLONS L
UNIT 2 LIQUID EFFLUENTS I
TOTAL VOLUME 1E+07 l
E 6E+06 -
s EME E
1E+06 q
1988 1989 1990 1991 1992 1993
}
YEAR l
i i
E TOTAL G ALLON S i
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J 6.
SOLID WASTE
SUMMARY
i i
The following is a summary of the solid wastes shipped offsite during the first six months of 1993 (2 pages).
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- REGULATORY GUIDE 1.21 REPORT ***
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1993)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS ARKANSAS NUCLEAR ONE ROUTE 3 BOX 137G RUSSELLVILLE, AR 72801 JANUARY 1, 1993 THROUGH JUNE 30, 1993 A.
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 6-month Est. Total
- 1. Type of waste Unit Period Error, %
3 a.
Spent resins, filter sludges, m
4.12E+00 evaporator bottoms, etc.
Ci 1.45E+01 2.93E+00 3
- b. Dry compressible waste, contaminated m
3.16E+01 equip, etc.
Ci 1.77E+00 1.51E+00 3
c.
Irradiated components, control m
0.00E-00 rods, etc.
Ci 0.00E-00 0.00E-00 3
- d. Other (describe) m 0.00E-00 Ci 0.00E-00 0.00E-00 2.
Estimate of major nuclide composition (by type of vaste)
- a. NI 63 50.6 %
7.20E+00
+/- 5.39 %
CO 58 15.8 %
2.25E+00
+/- 5.39 %
FE 55 12.7 %
1.81E+00
+/- 5.39 %
CO 60 5.7 %
8.16E-01
+/- 5.39 %
SB 125 5.2 %
7.39E-01
+/- 5.39 %
NB 95 4.3 %
6.08E-01
+/- 5.39 %
2R 95 2.2 %
3.12E-01
+/- 5.39 %
CS 137 1.6 %
2.23E-01
+/- 5.39 %
SR 89 1.2 %
- 1. 71E-01
+/- 5.39 %
TE 125m 0.6 %
8.21E-02
+/- 5.39 %
~
31.2 %
5.53E-01
+/- 3.47 %
3.43E-01
+/- 3.47 %
CO 58 18.4 %
3.27E-01
+/- 3.48 %
NI 63 11.0 %
1.95E-01
+/- 3.47 %
FE 55 9.4 %
1.67E-01
+/- 3.47 %
I CO 60 7.6 %
1.34E-01
+/- 3.47 %
SB 125 1.7 %
2.99E-02
+/- 3.47 %
C 14 1.1 %
1.94E-02
+/- 3.47 %
TE 125m 0.1 %
1.27E-03
+/- 3.46 %
SR 89 0.1 %
1.06E-03
+/- 3.49 %
c.
E
+/-
ll d.
E
+/-
i 3.
Solid Waste Disposition Fumber of Shipments Mode of Transportation Destination 3
Unshielded Van / Truck Oak Ridge, TH 1
Cask Shipment (Type A)
Barnwell, SC B. IRRADIATED FUEL SHIPMENTS (Dispositon)
Number of Shipments Mode of Transportation Destination i
e 7.
UNPLANNED RELEASES Unplanned releases are defined as any release of radioactive material that is released to the environment that do not meet the following criteria:
A.
Sample analysis prior to release.
B.
Release calculations performed prior to release.
During the first and second quarters of 1993, there were three gaseous and one liquid unplanned releases (IGR93-023, IGR93-046,2GR93-077 and ILR93-075). The following is a summary of the unplanned releases.
1GR93-023 - Release through Door 493 Release start time:
February 23,1993 at 1003 Release stop time:
February 23,1993 at 2005 Release volume:
1.806E6 cubic feet Release duration:
602 minutes Gamma Air Dose:
0.00E+0 mrad - Percent of yearly limit = 0.00 Beta Air Dose:
0.00E+0 mrad - Percent of yearly limit = 0.00 ITP':
2.70E-7 mrem - Percent of yearly limit = 1.80E-6
'ITP = Iodine-131, Tritium and Particulates 2
A.
Description of Occurrence 1
On February 23, 1993, an Unit 1 Auxiliary Operator (AO) found Door 493 opened. Upon discovery of the open door, the Unit 1 AO tried to secure Door 493 with no success. It was then determined that the door would not close due to pressure on the backside of door.
Door 493 is a pressure relief door that exhausts from the Emergency Piping Penetration Room (EPPR) to the Old Startup Boiler room. The most probable reason for the pressure buildup on the back side of Door 493 was the inadvertent closing of BDD-12 damper. BDD-12 is a High Energy Line Break (HELB) damper. The function of this damper is to close on a high energy line break to protect equipment in the electrical penetration rooms. BDD-12 will isolate the EPPR room from the exhaust fans upon closing causing a pressure buildup due to the VEF-7 supply fans. This pressure buildup will cause Door 493 to open allowing flow from the EPPR to the Start-up Boiler to atmosphere.
B.
Cause for Exceeding Limits No limits were exceeded due to this release.
I
~
C.
Corrective Actions Taken to Mitigate Occurrence Upon discovery of Door 493 being opened the Unit 1 Operations personnel initiated an investigation of the system and discovered that BDD-12 was closed.
j BDD-12 was opened and negative pressure was established in the EPPR room.
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D.
Actions Taken to Prevent Recurrence 1.
A review of the BDD-12 design was completed to verify the actuation j
setpoint was adequate.
i 2.
A visual inspection was performed to verify that all HELB dampers were properly set.
l 3.
All HELB dampers will be re-inspected eight months after the initial inspection to determine if the Constant Force Springs have drifted off the Lever Arm Stop Bolts. (ongoing) l l
4.
Training for operators will be provided on the HELB dampers, and the l
proper method to reset these dampers after being tripped. (ongoing)
{
E.
Summary of Consequences of Occurrence The Unit I auxiliary building atmosphere has the potential to contam j
radioactivity. The contents of the building are pulled through a filter and j
charcoal system designed to hold-up and/or remove radioactivity from the effluent. Due to Door 493 being open, air was allowed to flow from the EPPR
)
room to atmosphere without treatment. Upon discovery, the EPPR air was j
sampled for determination of a radioactive release. Sample results indicated that l
tritium was the only radionuclide present at the time of release. The dose from this release is listed above and is low in comparison to the limit of the Technical i
Specification and the yearly dose from Unit 1 gaseous effluents. No abnormal consequences would be expected to occur due to this release. See data above for dose contribution due to this release.
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l 1GR93-046 - Unit 1 Reactor Trio Release start time:
March 5,1993 at 1400 Release stop time:
March.5,1993 at 1403 Release volume:
5.9135E6 cubic feet Release duration:
3 minutes Gamma ' Air Dose:
0.00E+0 mrad - Percent of yearly limit = 0.00 Beta Air Dose:
0.00E+0 mrad - Percent of yearly limit = 0.00 ITP:
1.1IE-5 mrem - Percent of yearly limit = 7.4E-5
.1
I-
)
i A.
Description of Occurrence i
On March 5,1993, the Unit I reactor tripped due to generator lockout. Due to the presence of tritium in the secondary system, a radioactive steam release occurred when the main steam safeties lifted. The main steam was sampled and the radioactivity accounted for in release IGR93-046.
B.
Cause for Exceeding Limits No limits were exceeded due to this release.
C.
Corrective Actions Taken to Mitigate Occurrence Reactor was reduced to Hot Shutdown which alleviated the need to release steam through the safeties.
l D.
Actions Taken to Prevent Recurrence l
i l
A steam release will occur from reactor trips at power. ANO has taken actions to reduce the number of reactor trips and to reduce the potential for primary to i
secondary leakage.
i E.
Summary of Consequences 31 Occurrence This release is the result of a reactor trip. Due to the presence of tritium in the secondary system a radioactive release resulted. Sample analysis of the main steam showed that tritium was the only radionuclide to be released to the atmosphere in measurable quantities. The dose due to this release is low in comparison to the limit of the Technical Specification and the yearly dose from j
Unit 1. No abnormal consequences would be expected to occur due to this release. See data above for dose contribution due to this release.
l j
2GR93-077 - Release of Auxiliary Buildine Atmosphere via CA-2 and Roof Hatch Release start time:
April 18,1993 at 1500 i
Release stop time:
April 22,1993 at 1723 i
Release volume:
1.0625E8 cubic feet l
Release duration:
5903 minutes Gamma Air Dose:
0.00E+0 mrad - Percent of yearly limit = 0.00 Beta Air Dose:
0.00E+0 mrad - Percent of yearly limit _ = 0.00 ITP:
1.04E-5 mrem - Percent of yearly limit = 6.93E-5 l
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1 A.
Description of Occurrence I
On April 18,1993, the Unit 2 I&C technicians performed maintenance on a Dow j
transmitter in the auxiliary building ventilation system. This flow transmitter controls the blade pitch on the 2VEF-8 fans which controls the discharge flow of I
the exhaust fans. During the performance of the procedure, a system constant l
was entered incorrectly. The result of this was that the fan controller had indication that the exhaust fans were exhausting at 54000 CFM when in reality l
they were exhausting at only 38000 CFM. During this time the 2VSF-7's (auxiliary building supply fans) continued to supply normal ventilation to the auxiliary building. This resulted in a positive pressure in the auxiliary building.
With a positive pressure, the contents of the auxiliary building were being released through the roof hatch and the Controlled Access #2 entrance.
B.
Cause for Exceeding Limits No limits were exceeded due to this release.
C.
Corrective Actions Taken to Mitigate Occurrence Upon discovery of positive pressure in the auxiliary building, one of the supply fans was secured to bring the auxiliary building atmosphere back to a negative pressure.
D.
Actions Taken to Prevent Recurrence The applicable procedure was revised to correct the flow transmitter calibration i
constants.
i E.
Summary of Consequences of Occurrence c
The Unit 2 auxiliary building atmosphere has the potential to contain radioactivity. The building is under negative pressure to ensure that the contents being released will be drawn through the filtering system, designed for radionuclide removal and decay. Because of the positive pressure, the contents of the auxiliary building were released without being treated by the filtering system. The auxiliary building air was sampled prior to entering the filtering system to determine the contents of this release.
Tritium was the only radionuclide determined to be present at the time of release. The dose due to this release is low in comparison to the limits of the Technical Specifications and the yearly dose from Unit 2 gaseous effluents. No abnormal consequences would be expected to occur due to this release. See data above for dose contribution due to this release.
1LR93-075 - Inadvertent Release of T16A Release start time:
April 28,1993 at 0920 Release stop time:
April 28,1993 at 1100 Release volume:
8000 gallons Release duration:
100 minutes Total Body Dose:
5.90E-4 mrem - Percent of yearly limit = 0.02 Critical Organ Dose:
8.09E-4 mrem - Percent of yearly limit = 0.01 A.
Description of Occurrence On April 28,1993, the Unit 1 Control Room received a release permit for the T16B Treated Waste Monitor Tank. The Unit 1 Control Room informed the Waste Control Operator (WCO) that the permit to release T16B was ready. The WCO commenced releasing the tank and notified the Control Room that the tank was being released. Approximately I hour and 40 minutes later, the Control Room noticed that the T16B tank level was not decreasing and that the T16A tank level had decreased. The T16A had been misaligned to the discharge path instead of the T16B. The release was terminated and T16A sampled for analysis.
B.
Cause for Exceeding Limits No limits were exceeded due to this release.
C.
Corrective Actions Taken to Mitigate Occurrence Upon discovery of the release of T16A the release was terminated and the tank sampled for analysis.
i D.
Actions Taken to Prevent Recurrence 1
1.
Applicable procedures have been revised to clarify the correct sequence of actions to be taken.
j i
2.
Operators were briefed on lessons learned from the event.
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E.
Summary of Consequences of Occurrence a
The Unit 1 Treated Waste Monitor Tanks are the normal release tanks for liquid d
effluent system. These tanks contain water that has been processed through the filter and deionization system. The activity released from the T16's is consistent in concentration from tank to tank. This would indicate that the release from the T16A would be consistent with previous releases and the sample taken from the tank after release verified that there were no unexpected radionuclides present.
Because this is the normal release pathway and activities were consistent with
}
previous releases, no abnormal consequences would be expected to occur due to this release. See data above for dose contribution due to this release.
)
8.
RADIATION INSTRUMENTATION As required by Unit 1 and Unit 2 Technical Specifications, any radioactive effluent instrumentation inopemble for more than 30 days shall be reported in the next Semiannual Radioactive Effluent Release Report.
During the first and second quarters of 1993, no instrumentation was inoperable longer than 30 days.
l 9.
CHANGES TO THE PROCESS CONTROL PROGRAM 1
5 As required by Unit I and Unit 2 Technical Specifications, a description of changes made to the Process Control Program (PCP) during tiie reporting period shall be included in the next Semiannual Radioactive Effluent Release Report. During the first and second quarters of 1993, the PCP was revised as follows:
{
l A.
The PCP was revised to be a station-wide procedure rather than a departmental
)
procedure. This caused overall administrative responsibility for the PCP to be l
changed from the Manager, Radiation Protection and Radwaste to the Vice i
President, Operations.
l 4
B.
The sampling program for radioactive waste solidification was modified to require 1
l sampling of each batch, instead of every tenth batch, to increase assurance of solidification.
i.
10.
CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL During the first and second quarters of 1993, no changes were made to the Offsite Dose Calculation Manual.
J 11.
LLD LEVELS f
During the report period, there were no LLD's higher than required.
)
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l 12.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i
A.
There were no environmental sample location changes during the repordng l
period.
4 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.
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