ML20029A569
| ML20029A569 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/31/1990 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 91-095, 91-95, NUDOCS 9102250255 | |
| Download: ML20029A569 (27) | |
Text
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YlltOINIA 151.1:0T141(' AND l'OWI:lt COMI'ANY ll ir il M ON il, Yl HO LN I A MllM fil February 18,1991 United States Nuclear Regulatory Commission Serial No.91-095 Attention: Document Control Desk NAPS /JHL Washington, D. C. 20555 Docket Nos. 50 338 50 339 License Nos. NPF 4 NPF 7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPM NORTH ANNA POWER STATION UNIT NOS.1 AND 2 RADIOACTIVE EFFLUENT RELEASE REPORT Pursuant to Technical Specification 6.9.1.9, enclosed is the Radioactive Effluent Release Report for North Anna Power Station Unit Nos.1 and 2 for the reporting period of July 1,1990 to December 31,1990.
If you have any questions or require additionalinformation, please contact us.
Very truly yours,
.)[O-W. L. Stewart Senior Vice Precident - Nuclear cc: U. S. Nuclear Regulatory C ..uission Region 11 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. M. S. Lesser NRC Senior Resident inspector North Anna Power Station m,
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i RADIOACTIVE EFFLUENT RELEASE REPORT NORTil ANNA POWER STATION (JULY 01, 1990 TO DECEMBF.R 31, 1990)
PREPARED QY x_f x r
Supervisor Radiological Analysis REVIEWED BY:
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Supervisor Technical Services APPROVED BY: .-
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Superintendent Radiological Protection
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FORWARD This report is submitted as required by Appendix A to operating License Nos. NPF-4 and NPF-7, Technical Specifications for North Anna Power Station, Units 1 and 2, Virginia Electric and Power Company, Docket Nos. 50-338, 50-339, Section 6.9.1.9.
RADIOACTIVE EFFLL' 2NT RELEASE REPORT r
FOR THE NORTH ANNA POWER STATION (JULY 01, 1990 TO DECEMBER 31, 1990)
INDEX SECTION NO. SUBJECT PAGE 1 PURPOSE AND SCOPE................................ 1 2 DISCUSStON....................................... 2-3 3 SUPPLEMENTAL INFORMATION......................... 4 Attachment 1 Effluent Release Data............................ 5 Attachment 2 Annual and Quarsarly Doses....................... 6 Attachment 3 Revisions to Offsite Dose Calculation Manual JCM)........................................... 7 Attachment 4 Revisions to Process Control Program (PCP)....... 8 Attachment 5 Major changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems. .............. 9 Attachment 6 Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation...... 10 Attachment 7. Unplanned Releases............................... 11 Attachment 8 Lower Limits of Detection (LLD) for Effluent Sample Analysis................................. 12-13
Page 1 1.0 $ PURPOSE AND SCOPE
, , The Radioactive Effluent Release Report includes, in Attachment 1, a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21,
" Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and releases of radioactive Materials in Liquid and Gaseous Effluents of Light-Water-Cooled Nuclear Power Plants," Revision ,
1, June 1974, with data summarized on a quarterly basis following the format of Tables 1, 2 and 3 of Appendix B thereof. The report submitted within 60 days after January 1 of each year includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site during the previous calendar year. The report submitted within 60 days after July 1 of each year has the same sections except for the assessment of radiation doses.
The report also includes a list of unplannned releases during the reporting period, in Attachment 7.
As required by Technical Specification 6.15.c, changes to the Offsite Dose Calculation Manual (ODCM) for the time period covered by this report are included in Attachment 3. Information is provided to suppcrt the changen along with a package of those pages of the ODCM changed.
This report includes changes to the Process Control Program (PCP) with information and documentation necessary to support the rationale for these changes in Attachment 4.
Major changes to radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 5, as required by the ODCM, Section 6.6.2. Information to support the reason (s) for the change (s) and a summary of the 10 CPR 50.59 evaluation are included. In lieu of reporting major changes in this report, major changes % the radioactive waste treatment systems may be submitted as part of the annual FSAR update.
. Page 2 1.0 i PURPOSE AND SCOPH (cont.)
, , As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2.b.3, a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in this report, in Attachment 6.
2.0 DISCUSSION The basis for the calculation of the percent of technical specification for the critical organ in Table 1A of Attachment 1, is the ODCM. The ODCM, Section 6.3.1 requires that the dose rate for Iodine-131, for Tritium, and for all radionuclidos in particulate form with half-lives gr7ater than 8 days shall be less than or equal to 1500 mrem /yr to the critical organ at or beyond the site boundary. The critical organ is the child's thyroid; inhalation pathway.
The basis for the calculation of percent of technical specification for the total body and skin in Table 1A of Attachment 1, is the ODCM. The ODCM, Section 6.3.1, requires that the dorso rate for nobic gases to areas at or beyond site boundary shall be less than or equal to 500 mnem/yr to the total body and less than or equal to 3000 mRom/yr to the skin.
The basis for the calculation of the percent of technical specification in Table 2A of Attachment 1 is the ODCM. The ODCM, Section 6.2.1, states that the concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CPR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shal* be limited to 2.00E-4 microcuries/ml.
Percent of technical specification calculations are based on the total gaseous or liquid effluents released for that respective quarter.
The annual and quarterly doses, as reported in Attachment 2 of the report submitted within 60 days after January 1 of each year, are calculated according to the methodology presented in the ODCM.
Page 3 2.0 , DISCUSSION (cont.)
The beta and gamma air doses due to noble gases released from the site were calculated at site boundary. The maximum exposed member of the public from the releases of airborne Iodine-131, Tritium and all radionuclides in particulate form with half-lives greater than 8 days, is defined as an infant, exposed through the grass-cow-milk pathway, with the critical organ being the thyroid. The maximum exposed member of the public from radioactive materials is liquid effluents in unrestricted areas is defined as an adult, exposed by either the invertebrate or fiah pathway, with the critical organ being the liver. The total body dose was also determined for this individual.
Unplanned releases presented in Attachment 7 are defined according to .the critoria presented in 10 CPR 50.73, as those gaseous radioactive releases that exceed 2 times the applicable concentration limits specified in Appendix D, Table II, of 10 CFR 20, in unrestricted areas, when averaged over a time period of one hour, and/or as those liquid radioactive releases that exceed 2 times the limiting combined Maximum Permissible Concentration (MPC) specified in Appendix B, Table II, of 10 CPR 20, in unrestricted areas, for all radionuclides except Tritium and dissolved noble gases, when averaged over a time period of one hour.
The typical Lower Limit of Detection (LLD) capabilities of the radioactive offluent analysis instrumentation are presented in Attachment 8. These LLD values are based upon conservative conditions (i.e., minimum sample volume and maximum delay time l prior to analysis). Actual LLD values may be lower. If a radioisotope is not detected when analyzing effluent samples, then the activity of that radioisotope will be reported as Not Detectable (N/D) on Attachment 1 of this report. When all radioisotopes listed on Attachment 1 for a particular quarter and release mode are less than the LLD, then the totals for this period will be designated as Not Applicable (N/A).
1
Page 4 3.0 , SUPP11 2 MENTAL IMPORMATIOM As required by the ODCM, evaluation of the Land Use Census is location (s) to be made for identifying the new for the environmental monitoring program pursuant to the ODCM, Section 6.5.2, requirements. No new location (s) for dose calculations and/or environmental monitoring were identified by the evaluation of the Land Use Census conde.teo during 1990.
As required by the ODCM, the identification of the causes of the unavailability of milk or leafy vegetation samples, required by the ODCM, Section 6.5 and Attachment 21, and the identification of the new location (s) for obtaining replacement samples are listed. Milk samples, as required by the ODCM, Section 6.5 and Attachment 21, were available during the time period covered by this report. The leafy vegetation samples for vegetation stations 14, 15, 16, 21 and 23 were not collected for the month of December 1990 due to seasonal unavailability. All other samples were obtained and analyzed as required during the time period covered by this report.
, Page S
, , ,ATTACl! MENT 1 EFFLUENT RELEASE DATA (07/90 - 12/90)
This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste, as outlined in Regulatory Guide 1.21.
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TABLE- lA '
NORTH ANNA POWER STATION
--SENI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUfGEATION OF ALL GASEOUS EFFLUENT RELEASES- FOR 1990 I C
3rd 4th ESTIMATED TOTAL UNITS QUARTER QUARTER PERCENT ERROR (1)
A. Fission and Activati_on Gases:
- 1. Total Release. Curies 4.92E+2 3.02E+1 1.80E+1
- 2. Average Release Rate for: Period. pCi/sec' 6.19E+1 3.80E+0 B. Iodines:
- 1. Total Iodine-131 Release. Curies- 5.52E-3 2.22E-4 2.80E+1
- 2. Average Release Rate for Periodo pCi/sec 6.94E-4 2.79E-5 C. Particulates.(T ' > 8 days):
- 1. Total Particulate (T > 8 days) Release. Curies 2.44E-4 2.80E+1 2 13E-4
- 2. Average Release Rate for Period. pCi/sec 3.07E-5 2.93E-5 ,
- 3. Gross Alpha Radioactivity lease Curies N/D N/D D. Tritium:
- 1. Total Release. Curies- 3.64E+0 6.58E+0 3.10E+1
- 2. Averag Release Rate for Period. pCi/sec 4.58E-1 8.28E-1 E. Percentage of Technicial Specification Limits:
- 1. Total Body Dose Rate. % 2.29E-2 3.94E-3
- 2. Skin Dose Rate. 1 % 1.04E-2 8.90E-4
- 3. Critical Organ Dose Rate. % 6.72E-2 2.80E-3 N/D is Not 7etectable' & N/A is Not Applicable
- a. - - . - . --. :_ - . - _ _
TABLE -IB ' ~
'. -NORTH ANNA POWEn- STATION
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' SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS' EFFLUENT RELEASES FOR- 1990 Page 1 of 2 1
CONTINUOUS MODE BATCH MODE
- I 3rd' 4th 3rd 4th l NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER
[ Fission and Activation Gases:
!. Krypton - 85 Ci N/D N/D 1.46E+1 6.92E+0 l Krypton - 85m C i' N/D N/D N/D N/D Krypton Ci N/D N/D N/D N/D
' Krypton - 88 Ci N/D N/D N/D N/D Xenon - 131m Ci N/D N/D 6.89E+0 9.08E-2 l- ' Xenon - 133 Ci 6.70E+1 9.03E+0 1.92E+2 4.llE-1 j_ Xenon - 133m 'Ci N/D N/D 9.llE-1 N/D
. Xenon --135 Ci 1.05E+0 2.53E-1 8.31E-2 8.91E-2 J con - 135m Ci N/D N/D 2.21E-2 2.21E-2 k .non - 138 Ci N/D N/D _ N/D N/D l Other (Specify)
! Argon - 41 Ci N/D N/D N/D NfD l
Total for Period Ci 6.81E+1 9.28E+0 2.15E+2 7.53E+0 i Iodines:
- i. Iodine - 130 Ci N/D N/D N/A N/A
[ Iodine - 131 Ci 1.62E-5 7.06E-7 N/A N/A I Iodine - 132 Ci- N/D N/D N/A N/A l Iodine - 133 Ci _
4.51E-6 N/D N/A N/A j' Iodine - 134 Ci _
N/D N/D N/A N/A i Iodine - 135 Ci _
N/D N/D N/A N/A i
Total for Period Ci 2.07E-5 7.06E-7 N/A N/A
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Particulates:
Manganese - 54 Ci N/D N/D N/A N/A 4
Iron - 55 Ci 1.18E-6 2.70E-7 N/A N/A Cobalt - 58 Ci N/D N/D N/A N/A
[ Cobalt - 60 Ci 3.50E-6 2.43E-6 N/A N/A i Strontium - 89 Ci N/D N/D N/A N/A l Strontium - 90 Ci N/D N/D N/A N/A
' Silver - 110m Ci N/D N/D N/A N/A Cesium - 134 Ci 9.07E-7 6.27E-7 N/A N/A
- _ Cesium - 136 -Ci N/D N/D N/A N/A i Cesium - 137 Ci 3.04E-6 2.75E-6 N/A N/A l Barium - 140 Ci N/D N/D N/A N/A
! : N/D is Not Detectable Er N/A is Not Applicable
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TAQLE 1C ,
NORTH ANNA POWER STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT !
GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR 1990 Page 1 of 2 CONTINUOUS MODE BATCH MODE
- 3rd 4th 3rd 4th NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fissior and Activation Gases: -
Krypton - 85 Ci N/D 1.22E-1 1.92E+0 1.92E+0 Krypton - 85m Ci 4.26E-2 2.95E-2 3.94E-3 N/D -
Krypton - 87 Ci 6.79E-2 5.40E-2 6.17E-3 N/D Krypton - 88 Ci 9.41E-2 6.92E-2 9.07E-3 N/D Xenon - 131m Ci N/D N/D 9.51E-1 9.50E-1 Xenon - 133 Ci 1.84E+2 2.92E-1 1.92E+1 8.03E+0
, Xenon - 133m Ci 1.06E-2 N/D 3.28E-2 3.08E-2 Xenon - 135 _
Ci 5.07E-1 4.80E-1 1.47E-1 1.75E-7
_ Xenon - 135m Ci 3.45E-1 4.17E-1 7.33E-3 7.33E-4 Xenon - 138 Ci 1.32E-1 1.57E-1 1.72E-2 N/D Other (Specify)
Argon - 41 Ci 7.81E-1 8.59E-1 6.95E-2 N/D Total for Period Ci 1.86E+2 2.48E+0 2.24E+1 1.09E+1
, Iodines:
Iodine - 130 Ci N/D N/D N/D N/D Iodine - 131 Ci 5.50E-3 2.06E-4 1.68E-7 1.53E-5 Iodine - 132 Ci N/D N/D 7.64E-9 5.60E-5 4
Iodine - 133 Ci 5.03E-4 7.14E-5 3.35E-8 9.54E-5
_I_odine - 134 Ci N/D N/D 2.00E-9 4.63E-5 Icdine - 135 Ci N/D N/D 8.95E-9 1.06E-4 i Total for Period Ci 6.00E-3 2.77E-4 2.20E-7 3.19E-4 Particulates:
- Manganese - 54 Ci N/D N/D N/D N/D Iron - 55 Ci 5.65E-5 1.05E-5 N/D N/D j Cobalt - 58 Ci 1.43E-4 1.43E-4 4.34E-8 1.86E-7 Co ba lt. , 60 Ci 1.52E-5 5.20E-5 7.73E-10 1.50E-5 N/D Stror'_ lum - 89 Ci N/D N/D N/D
_Sy Nntium - 90 Ci N/D N/D N/D N/D _
Silver - 110m Ci N/D N/D N/D N/D Cesium - 134 Ci 7.39E-6 N/D 1.66E-8 1.57E-7 Cesium - 136 Ci N/D N/D 2.84E-9 N/D Cesium - 137 Ci 1.26E-5 5.71E-6 1.23E-8 1.20E-7 fBarium - 140 Ci N/D N/D N/D N/D
, N/D is Not Detectable & N/A is Not Applicable
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TABLE 2A ,
NORTH ANNA POWER STATION
-EFFLUENT 'AND WASTE DISPOSAL' SEMI-ANNUAL' REPORT (1990) ' '
. LIQUID EFFLUENTS-SUFWEATION -OF 'ALL RELEASES ,
3rd 4th ESTIMATED TUTAL UNITS QUARTER QUARTER PERCENT ERROR (%)
A. Fission and Activation Products:
- 1. Total release . (not including tritium, - .
gases, alpha). Ci 1.03E-1 2.49E-1 2.00E+1 ;
- 2. Average diluted concentration during period. pCi/ml- 1.51E-10 4.30E-10 ,
i
- 3. Percent of applicable limit (T.S.).- % i- 5.68E-3 7.02E-3 1 ,
i B. Tritium: !
i t j 1. Total release activity. Ci 3.82E+2 3.25E+2 2.00E+1 i
! 2. Average diluted concentration'dur.ing j period. pCi/ml 5.54E-7 5.6}E-7 i
- 3. Percent of' applicable limit (T.S.). % 1.85E-2 1.87E-2 i, C. Dissolved and Entrained Gases:
! 1. Total release activity. Ci 6.33E+0 _
7.15E-1 2.00E+1 i 2. Average diluted. concentration during
! period. pCi/ml 9.19E-9 1.23E-9 '
I
! 3. Percent of applicable limit-(T.S.) t 4.60E-3 6.15E-4 I i
- D. Gross Alpha Radioactivity:
I
- 1. Total release activity. Ci N/D _ _ N/D 2.00E+1 1
- E. Volume of waste released(prior to !
dilution). Liters 8.91E+7 ._ 9.01B+7 3.00E+0
- F. Volume of dilutio'n water used during ..
period. Liters .6.90E+11 5.79E+11 3.00E+0 [
N/D is Not Detectable. & N/A is Not Applicable , (
i t
- i. - - _ _ _ _ _ , _ . . . - - - . _ . - . . _. .
TABLE 23- ,
NCn7H ANNA- POWER STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ~
- IQUID a EFFLUENT RELEASES FOR 1990 Page_i of*2 CONTINUOUS PK;OE _ _
BA'NJi MODE 3rd 4th 3rd 4th UNITS QUARTER QUARTER QUARTER QUARTER NUCLIDES RELEASED -
Fission and Activation Products:
Manganese - 54 Ci N/D 4.69E-4 N/D N/A Iron - 55 Ci N/D ,N/D N/D . N/A
- Cobalt - 58 Ci 2.64E-2 _
. 41E-1 1.64E-5 N/A N/A Cobalt '
Ci 3 . _6 5 E-2 4.34E-2 5.91E-6 Strontium - 89 Ci N/D' l N/D N/D N/A
' Strontium - 90 Ci N/D N/D N/D N/A ,
Silver - 110m Ci 2.83E-3 2.28E-3 N/D N/A Iodine - 131 'Ci 7.89E-3 3.21E-3 2.39E-5 N/A Iodine - 132 Ci N/D 4.91E-4 N/D N/A Iodine - 133 Ci 1.06E-2 2.54E-2 N/D N/A Iodine - 134 Ci N/D 3.99E-5 N/D N/A
' Iodine - 135 Ci 1.32E-4 3.27E-3 N/D N/A Cesium - 134 Ci 1.65E-3 4.74E-4 2.78E-5 N/A Cesium - 136 ' Ci 1.02E-4 N/D N/D N/A Cesium - 137 Ci 3.10E-3 2.20E-3 3.28E-5 N/A Barium - 140 Ci 2.20E-4 N/D N/D N/A Other (specify)
Chromium - 51 Ci- 1.01E-3 1.67E-3 N/D N/A Cobalt - 57 Ci N/D 1.52E-4 N/D N/A Iron - 59 Ci 8.50E-4 1.96E-4 N/D N/A Strontium - 85 Ci 8.80E-4 1.82E-4 1.02E-5 N/A Zirconium - 95 Ci N/D 1.04E-3 N/D N/A Cadrium - 109 C
_i N/D N/D 6.98E-5 N/A Antimony - 124 _ Ci 6.60E-4 1.92E-3 N/D N/A Antimony - 125 Ci 8,37E-3 1.67E-2 N/D N/A Sodium - 24 (T < 8 dayc) Ci c/D N/D N/D N/A Rubidium - 88 (T < 8 days) _Ci _ _ N/D N/D 9.57E-5 N/A Niobium - 95 (TS < 8 days) Ci 5.02E 4.29E-3 N/D N/A Technetium - 99m (T < 8 days) Ci N/D N/D N/D N/A Antimony - 122 (T < 8 days) Ci N/D N/D 1.39E-6 N/A Cesium - 138 (Th < 8 days) Ci N/D N/D 4.4SE-5 N/A 3 Barium - 139 (T < 8 days) Ci 2.10E-3 2.74E-4 N/D N/A Lanthanum - 140 (T < 8 days) Ci N/D N/D N/D N/A Total for Period Ci 1.03E-1 2.49E-1 3.29E-4 N/A ,
'N/D is Not Detectable -& N/A is Not Applie=b3e
~
R -
~
E -
2 hT A A A A A A A A A A A tR ///// / // / / /
. f 4A N N N N N N N N N N N o U -
E Q -
2 D -
O e M -
g a
P H C
T ;
A B R 4 5 6 3 3 2 E - - - - - -
dT D E D E D E E D E E D rR / 9 / 9 / 7 7 / 3 3 /
3A N 8 N 5 N 8 3 N 9 7 N U . .
Q 4 6 3 2 2 3 -
T R -
O _
P I E ~ -
R 0
E 9 R 3 1 3 2 4 4 2 1 2 S 19 E - - - - - - - - +
A hT E E E E E E E D E E D E E tR 1 4 1 2 1 9 0 / 5 5 / -
D 4A
.N L R 0 5 2 3 6 0 2 N 1 2 N
.O E O O U I R M Q 2 6 3 1 6 1 4 7 3 T F A S T T S N S U E E O U S U -
B R L A N 2 E F E I W F E L T O E R N R 1 0 2 2 4 5 1 4 0 2 .
E P O E - + - - - - - - + +
L C dT E E E E E E E E E E D rR B E S 9 9 1 l 6 3 9 3 2 / _
A A V T 3A 2 8 2 7 l 1 0 4 3 8 N T N I N E
.U Q 1 5 4 6 1 3 2 1 6 3 .
N T U .
A C L e A F l O
H I F b T D E a c
R A i _
O R D l N I S p _
L U T p _ _
A Q I N
i i i i i C C C C C i, . i C C C i
C i
C i
C A
U IL U t N
N o _
A :
N s _
I e s M s i E a _
S G A _
/
e N l
b o K r
N D d e E e l
$ n b A i a E a t L r d c E t ) o e R n y i t E f m r - e m m m i 5 5 e D S & 1 3 3 5 5 c 8 8 P A E 3 3 3 3 3 e 1 H t D d 1 1 1 1 1 p 4 - - r P o I e s o L N L v - - - - - ( - nn f M A C l oo U s U o n n n n n r n t t l I S i N s s
o o o o o e o py yp n n n n n h g a T S t I O D i e e e e e t r r r o R R /
D X X X X X O A K K T T G N lll ,
- g. .. . . . . . ~ , . -- - - . - - - - = ~ . . . . ~ .
1
,_ , TABLE 3
. NORTH ANNA POWER STATION i t , RADIOACTIVE EFFLUENT RBLEASE REPORT
. SUMMATION OF SOLID RADIOACTIVE ^
WASTE AND IRRADIATED FUEL SHIPMENTS 'i POR 07-01-90 THROUGH 12-31-90_
I Page 1 of 2 i
A. SOLID WASTE SHIPPED t<FSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-MONTH ESTIMATED TOTAL
- 1. . Type of Waste UNIT PERIOD PERCENT ERROR ,
(%)
-a. ; Spent resins, filter m3 3.65E+1 2.50E+1 sludges, evaporator Ci 4.05E+2 2.50E+1 bottoms,-etc.
- b. Dry compressible waste, m' 5.19E+2* 2.50E+1 4
. contaminated equipment, Ci 1.31E+1 2.50E+1 1 etc. .;
-- c . Irradiated' components, m 3 0.00E0 0.00E+0 control rods,' etc. Ci 0.00E0 0.00E+0
_d. Other (describe) m' 7.r.:uo** 2.50E+1 011' Ci 0.54E-5 2.50E+1
- s. _
- 2. Estimate of major nuclide composition (by type of waste) a.' Ni-63 '
% 2.81E+1 2.50E+1 Co -% 2.45E+1 2.50E+1
, Co-60 % 2.06E+1 2.50E+1 j Fe-55 % 1.42E+1 2.50E.l Cs-137 % 4.90E0 2.50E+1 Cs-134 % 2.90E0 2.50E+1
.Mn-54 ~'% 1.10E0 2 . 50Y)
- b. Co-58 % -3.15E+1 2. ~ ;+1
~
-Fe-55 -% 2.62E+1 2 . 5'O E+1 Co % 1.37E+1 _2.50E+1' ,
Cs-137 % 8.40E0= 2.50E+1 i Zr-95 % 5.20E0 2-50E+1
~~
Nb-95 % 3.80E0 2.50E+1 Ni-63= '% 3.40E0- 2.50E+1 Cr-51' % 2.80E0 '
2.50E+1 Cd-134 % 1.60E0 ~
2.50E+1 Mn-54 % -1.50E0- _
2.50E+1
,. _ - . _ . . _. . - - _ _ ... . ._ - - - _ . _ _ _. ~. .,m .
- . ? -- , ,
l'
^ '
TABLE 3T NORTH ANNA POWER STATION ;
RADIOACTIVE EFFLUENT RELEASE REPORT
~ SUMMATION'OF SOLID RADIOACTIVE WAGTE AND IRRADIATED FUEL SHIPMENTS FOR 07-01 THRO' UGH 12-31-90 1 Page 2 of 2
-2.- Estimate of-major 6-MONTH ESTIMATED TOTAL
- nuclide'comnosition UNIT -PERIOD PERCENT ERROR (by type of waste)- (%)
(cont.)
_c. NONE w
- d. Cs-137 % 5.18E+1 2 . 5'0 E+1
- Cc-60 % 2.58E+1 2.50E+1 Cs-134 % 1.88E+1 2.50E+1 '
-Co-58 % 3.50E0 2.50E+1 .
1
-i e ,
L _.
1 i
i 3. Solid Waste Disposition
-Number:of" Shipments- Mode of Transportation Destination '
10 Truck Barnwell,S.C.
11 Truck- Oak Ridge,T.N.-
(SEG) 1 1- Truck Oak-Ridge,T.N.
(Quadrex)'
- B. IRRADIATED-FUEL SHIPMENTS (Disposition)
Number of' Shipments Mode of Trar.sportation ' Destination
.0 -N/A N/A
'* .lL shipments of Dry-:ompressible waste were shipped from North Anna' 1
1;' to?ailicensediwaste processor for volume. reduction. : Therefore the.
volume 'ast listed" for this itype. is 'not representative of the actual <
f* volume buried. =The totalivolume buried for this reporting period Ewas: 90.86 m . 2
-**: --l' shipment- of oll was shipped from North Ar.1:a to a licensed waste :
processor-for c incineration. Ti'erefore the volume as listed for this
- waste' type-is not representativ.3 of the actual volume buried.- The Ltotalo volumelburied for this rcporting period was 0.
s s
e -e- d er g. -mm.., - c-w w - -ea-v., e,5,-w e- w ow r e a y e, y f.-mmA#-39,*-+-+ -+y,m--w,- m e97, ------st- y..,w e ,c a y g- , < e r e y% 7*ws,-y
Page 6 ATTACllMENT _2 AMNUAL AND QUARTERLY DOSES (07/90 -
12/90)
An asseastaent of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of this report, along with an annual total of each effluent pathway, wi.L1 be made pursuant to the ODCM, Section 6.6.2 requirements.
Liquid Lifluents:
~
1st 2nd 3rd 1 4th Annual Otarter Quarter Quarter ' Quarter Total Total Body Dose (mrem) 1.63E-1 1.58E-3 1.81E-1 1.31E-1 6.33E-1 Critical Organ Dose-(mrem) 1.69E-1 1.76E-1 2.13E-1 1.50E-1 7.08E-1 Gaseous Ef[luents:-
1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Noble Gas
_ Gamma Dose (mrad) 8.08E-3 7.61E-3 2.89E-2 4.97E-3 4.96E-2 Noble Gas Beta Dose (mrad) 1.46E-2 1.64E-2 7.83E-2 6.73E-3 1.16E-1 Critical Organ Dose.for I-131, H-3 Particulates with T > 8 days (mrem)- 1.61E-2 1.11E-2_
2.54E-1 1.06E-2 2.92E-1 l
l l
Page 7 ATTACIIMENT 3 (07/90 -
12/90)
REVISIONS TO OFFSITE DOSE CALCULATIOM MANUAL (ODCM)
As required by Technical Specification 6.15, revisions to the ODCM for the time period covered by this report are synopsized below. Supporting documentation and affected pages of the ODCM are attached, if applicable.
No ravisions to the Off < ite Dose Calculation Manual (ODCM) were required foi the time period covered by this report.
i.
i
t .
Page 8 I
1 l l ATTACHMENT 4 L
(07/90 -
12/90)
REVISIONS TO PROCESS CONTHOL PROGRAM (PCP}
E 1 l-Revision to the Process Control Program (PCP) for the time period j covered by this report are synopsized below.. Supporting documentation and affected pages of the PCP are attached, if applicable, i
l No revision to the Process Control Program (PCP) were required for the l time period covered by this report.
l.
1 I
l l
l l
1 l
Page 9 m .
t ATTACHMENT 5 (07/90 -
12/90)
MAJOR CIIANGES TO RADIOA.CT.TVE LIQUID, GASEOUS, AND SOLID WASTE REATMENT SYSTEMS As required by the ODCM, Section 6.6.2, major changes to radioactive liquid, gaseous and solid waste treatment systems for the time period covered by this report are reported below.
Supporting information as to the reason (s) for the change (s) and a summary of the 10 CPR 50.59 evaluation are included, as applicable.
No major changes to the radioactive liquid, gaseous, and solid
- aste treatment systems were made for the time period covered by this report.
Page 10
-6
. ATTACHMENT 6 107/90 - 12/90)
IbiOPERABILITY OP RADIOACTIVE: LIQi"D AND GASEOUS
, EFFLUENT INSTRUMENTATION As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2.b.3, a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in this report.
4 t 1. Licruid Effluent Monitorina Instrumentation
- a. Proportional Sampling System The proportional sample flow metering valve, 1-LW-1130, was declared inoperable .on three occasions, with one extended period of
~
inoperability from August to November 1990. This inoperability was due largely to effluent flow transmitter, 1-LW-FT-104, being out of service for replacement. The remaining eight days of inoperability during the period were attributed to crud buildup and subsequent
-flow restrictions of the metering valve. For the short term, the valve continues to be flushed manually on a routine basis to limit crud buildup. EWR E90-330B, issued January 10, 1991, provides- the methods and components for periodic flushing of the valve using instrument air . across the valve seat.- In addition, the effluent flow. transmitter, 1-LW-FT-104, was replaced and has thus far proved more reliable than in the past.
- b. Effluent Plow Monitoring Device The- liquid effluent flow transmitter /totaiizer, 1-LW-FT-104, was remos.ed- from service in August 1990 and replaced with a new t i rinsmitter/ totalizer. The new 1-LW-FT-104 was returned to service
~in November 1990 and has thus far incurred no additional problems.
- 2. Gaseous Effluent Monitoring Instrumentation No extended periods of inoperability occurred with any of the G.seous l
Effluent Monitoring Instrumentation for the period of concern.
Page 11
, , ATTACHMENT 7 (07/90 -
12/90)
. uni <LANNED RELEASES l i
As required by the ODCM, Section 6.6.2, a list of unplanned l l
releases,.as' defined by the criteria presented in 10 CFR 50.73, ;
from the site to unrestricted areas, of radioactive material in gaseous and liquid effluents occurring during.the reporting period, is made below.
No unplanned releases, as defined by the criteria presented in 3 0 CFR- Part 50.73, occurred during the time period covered by this report.
1 t -
~
m - 4 l
Q T' + w '"Of v ?
Page 12 ATTACllMENT 8 O LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (07/90 - 12/90)
Gaseous Effluents:
~~
Required L.L.D. Typical L.L.D.
Radioisotope (pC1/ml) (pCi/ml)
Krypton - 87 1.00E-4 1.96E-7 -
2.56U-6 __
Krypton - 88 1.00E-4 1.87E-7 -
2.26E-6 Xenon - 133 1.00E-4 1.89E-7 -
2.04E-6 Xenon - 133m 1.00E-4 6.76E-7 -
2.05E-6 Xenon ,. 135 1.00E-4 6.90E-8 -
2.llE-6 Xenon - 135m 1.00E-4 3.18E-7 -
6.19E-6 Xenon - 138 1.00E-4 7.75E-7 -
5.65E-6 4). _
06_ne .;jl 1.00E-12 3.25E-14 -
8.06E-14 ,,_
Manganese - 54 1.00E-ll 2.26E 4.69E-14 Cobalt - 58 1.00E-ll 2.93E 5.48E-14 Iron - 59 1.00E-ll 6.02E 1.10E-13 Cobalt - 60 1.00E-ll 3.47E-14 -
8.54E-14 Zinc - 65 1.00E-ll 6.15E 1.27E-13 Strontium - 89 1.00E-ll ___
3.00E 5.00E-15 Strontium - 90 1.0CE-11 7.00E 1.00E-15 Molybdenum - 99 1.00E-11 2.28E 3.88E-13 Cesium =- 134 1.00E-ll 2.36E-14 -
6.18E-14 Cesium - 137 1.00E-11 2.90E 6.33E-14 Cerium - 141 1.00E-ll 2 43E 6.19E-14 Cerium - 144 1.00E-ll __
8.65E 2.47E-13 Gross Alpha 1.00E-ll 1.94E 2.00E-14 Tritium 1.00E-6 1.31E-7 _
. _ . , , .~, .. n. - . - . . .. - -
i o ;-s -a Fage 13-
^
- U!
ATTACHMENT- ' 8 -l 7 ' LOWER ' LIMITS' OF DETECTION ~ POR' EFFLUENT- SAMPLE ANALYSIS ;
=(07/90 - 12/90)
~ '
(cont.)
9--
(Liquid- i Effluent _s_
~
m i
l- Required L.L.D. Typical- L.L.D.
- Radioisotope (pCi/ml) (pCi/rd )
g Krypton - 87 1.00E-5 3.57E-8 -
8.34E-8'
, - Krypton - 8 8 1.00E-5 3.62E-8 -
9.93E48 f
' Xenon"- 133- 1.00E-5 '5.12E-8 =-
7.93E-8
' Xenon - 133ni 1.00E-5 1.26E-7 --
2.71E-7 i
'Xebon?- 135 'l.00E-5 1 26E-8 -
3.44E-8-- !
p
' Xenon "135m. 1.00E-5 _ .
6'.12E-8 -=-
1.48E-7=
Xenons- L138 1.00E-5 1.'41E-7 -
3.95E-7' t.
Ibdine - 1314 1.00E-6 1.39E-8
=
3'.-36E-8 1
'Manaanese '.5.00E-7 1.82E-8 -
- 2.88E-8 Iron - 55' _
l'.00E-6 18.00E-7 -
1'.00E-6
-Cobalti :58 5.00E-72 ~1.76E --
3.2SE-8
,u Iron '59 -5.00E-7 3.31E-8 ~~ 6.27E-8 5'.00E-7i
~
- Cobalt - 60: 1.'86E --4.48E-8 S
Zinc 1- 65 5.0'0E-7 -3.37E-8'"- 7.02E-8
& t. . ..
0 Strontium = L89- 00E-8 13;00E-8 -
5.00E-8 m ~
Stront ium E- 90 5.00E-8 5.00E-9 -
8 00E-9: i 4
Molybdenum--'99 5'.'00E-7 l.'4 2 E - 7 - - 2 '. 31 E-7 ;j
-Cesiu.m'~---L134- 5.C,03-7 1.42E-8 '
3.65E-8-' a
' Ceshinr - L137- 5.00E-7 1,88E-8 -
4.15E-8~
= Cerium - 141- '5.00E-7 ^1.89E-b -
4.79E-8
, 2 Cerium?- 144 5.00E-7 6.95E-8 -
1.95E ..
g ,
.i
- -Gross' Alpha ~ -l.00E-7 1.12E -
1.15E-8 Tritium ~~ 1.00E-E 3.61E-6 g
.- 4 ._. . . .. . . , - . . ~ , - , -