ML20063L653
| ML20063L653 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/31/1993 |
| From: | Bowling M VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 94-107, NUDOCS 9403070249 | |
| Download: ML20063L653 (27) | |
Text
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VIRGINIA Ex.ncruic Axn Pownu Coniwxy it s e n.w on n, VIHOINIA 20261 February 23, 1994 United States Nuclear Regulatory Commission Serial No.94-107 Attention: Document Control Desk NAPS /JHUGSS Washington, D. C. 20555 Docket Nos. 50-338 50-339 License Nos. NPF-4 NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY 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 1,1993 to December 31,1993.
If you have any questions or require additionalinformation, please contact us.
Very truly yours, bV M. L Bowling, M nager l Nuclear Licensing and Programs !
Enclosure cc: U. S. Nuclear Regulatory Commission l Region 11 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 1 Mr. R. D. McWhorter NRC Senior Resident inspector North Anna Power Station 20014 f)
I k
9403o70249 931231 PDR I R
ADOCK 0500o338 PDR p
RADIOACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION (JULY 01, 1993 TO DECENBER 31, 1993) l l
8 PREPARED BY.^ s WJ% W
.A Supervisor Radiological Analysis REVIEWED BY:
- NAT Y
Supervisor Technical Services APPROVED BY: MM Superintendent Radiological Protection
- - - _ _ . ________ _ _ ___a
i PORWARD l
This report is submitted as required by Appendix A to Operating License i
Nos. NPF-4 and NPF-7, Technical Specifications for North Anna Power Station, l Units 1 and 2, Virginia Electric and Power Company, Docket Nos. 50-338, 50-
)
339, Section 6.9.1.9.
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l
f RADIOACTIVE EFFLUENT RELEASE REPORT I FOR THE NORTH ANNA POWER STATION JULY- 01, 1993 TO DECEMBER 31, 1993 l
INDEX l l
Section No. Subject- Page ]
l 1 PURPOSE AND SCOPE..................... 1 -
2 j
l 2 DISCUSSION............................ 2 -
4 j 3 SUPPLEMENTAL INFORMATION.............. 5 )
Attachment 1 -
Effluent Release Data................. 6 Attachment 2 -
Annual and Quarterly Doses............ 7 Attachment 3 -
Revisions to Offsite Dose Calculation Manual (ODCM)......................... 8 Attachment 4 -
Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems............................... 9 ,
l Attachment 5 -
Inoperability of Radioactive Liquid I and Gaseous Effluent Monitoring I Instrumentation....................... 10 Attachment 6 -
Unplanned Releases.................... 11 Attachment 7 -
Lower Limits of Detection (LLD) for Effluent Sample Analysis............. 12 - 13 i
f* 4 1.0 PURPOS'E AND SCOPE l
The Radioactive Effluent Release Report includes, in Attachment 1, a l 1
summary of the quantities of radioactive liquid and gaseous effluents i l
and solid waste as outlined in Regulatory Guide 1.21, " Measuring, l
Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from 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 af ter July 1 of each year has the same sections except for the assessment of radiation doses. The report also includes a list of unplanned releases during the reporting period, in Attachment 6.
As required by Technical Specification 6.15, changes to the Offsite Dose Calculation Manual (ODCM) for the time period covered by this report are .
1 included in Attachment 3. I 1
Major changes to radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, as required by the ODCM, section 6.6.2. Information to support the reason (s) for the change (s) and a i 1
summary of the 10 CFR 50.59 evaluation are included. In lieu of l I
reporting major changes in this report, major changes to the radioactive waste treatment systems may be submitted as part of the annual FSAR update.
1
. = . _ _ - _ .
l.0 PURPOSE AND SCOPE (cont).
As required by the ODCM, sections 6.P. 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 Attachment 5 of this report.
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, section 6.3.1, which requires that the dose rate for iodine-131, for tritium, and for all radionuclides in particulate form with half-lives greater 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 i
- thyroid via the 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, section 6.3.1, which requires that the dose rate for noble gases to areas at or beyond site boundary shall be less than or equal to 500 mrem /yr to the l total body and less than or equal to 3000 mrem /yr to the skin.
I The basis for the calculation of the percent of technical specification in Table 2A in Attachment 1 is the ODCM, section 6.2.1, which states that the concentrations of radioactive material released in l
2 l
I
l
. 1 2.0 DISCUSSION (cont).
liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited l to 2.0E-4 microcuries/ml.
l Percent of technical specification calculations are based on the total l gasoous or liquid effluents released for that respective quarter.
i The annual and quarterly doses, as reported in Attachment 2, were calculated according to the methodology presented in the ODCM. 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 gland. The maximum exposed member of the public from radioactive materials in liquid effluents in unrestricted areas is defined as an adult, exposed by either the invertebrate or fish pathway, with the critical organ being the liver. The total body dose was also determined for this individual.
Presented in Attachment 6 is a list of unplanned gaseous and liquid releases exceeding the ODCM limits of sections 6.3.1 and 6.2.1 respectively.
3
4 2.0 DISCUSSION (cont).
The typical Lower Limit of Detection (LLD) capabilities of the radioactive effluent analysis instrumentation are presented in.
Attachment 7. These LLD values are based upon conservative conditions (i.e., minimum sample' volume and maximum delay time prior to analysis).
Actual LLD values may be lower. If a radioisotope was not detected when effluent samples were analyzed, then the activity of that radioisotope was reported as Not Detectable (N/D) on Attachment 1 of this report. If an analysis for an isotope was not performed, then the activity was reported as Not Applicable (N/A).
I 4
i l
3.0 SUPPT.To(ENTAL INFORMATION l
l As required by the ODCM, section 6.5.2, evaluacion of the Land Use Census is made to determine if new location (s) have been identified for !
the radiological environmental monitoring program pursuant to the ODCM, Section 6.5.2 requirements. Evaluation of the Land Use Census conducted in 1993 identified no change in sample locations for the radiological environmental monitoring program.
Section 6.5.1.b.4 of the ODCM requires identification of the cause(s) for the unavailability of milk or leafy vegetation samples, and the identification of new locations for obtaining replacement samples. Milk samples, as required by the ODCM, section 6.5.1, were available during the time period covered by this report. The leafy vegetation samples for vegetation station 14, 15, 16, 21 and 23 were not collected for the months of November and December 1993 due to seasonal unavailability.
All other samples were obtained and analyzed as required during the time period covered by this report.
i l
l 5
. - . . . . _ . . _ . - - .. ~ . - - .-. . .. . .
l i
ATTACIINENT 1 ;
EFFLUENT RELEASE DATA (07/93 -
12/93) i l
l This attachment includes a summary of the quantities of radioactive liquid l
and gaseous effluents and solid waste, as outlined in Regulatory Guide 1.21, Appendix B.
i 1
6
TABLE 1A -
NORTH ANNA POWER STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RETTASES FOR (07/93 - 12/93) 3rd 4th ESTIMATED TOTAL UNITS OUARTER OUARTER PERCENT ERROR (%i A. Fission and Activation Gases:
- 1. Total Release. Curies 9.46E+1 1.36E+1 1.80E+1
- 2. Averace Release Rate for Period uCi/sec 1.19E+1 1.71E+0 B. Iodines:
- 1. Total Iodine-131 Release. Curies 1.15E-3 2.70E-4 2.80E+1
- 2. Averace Release Rate for Period uCi/sec 1.45E-4 3.40E-5 C. Particulates (Th > 8 days):
- 1. Total Particulate (T > 8 days)
Release Curies 3.78E-5 3.62E-5 2.80E+1
- 2. Averace Release Rate for Period uCi/sec 4.74E-6 4.55E-6
- 3. Gross Aloha Radioactivity Release Curies 1.02E-4 5.85E-5 D. Tritium:
- 1. Total Release Curies 2.37E+1 1.25E+1 3.10E+1
- 2. Averace Release Rate for Period uCi/sec 2.98E+0 1.57E+0 E. Percentace of Technical Specification Limits
- 1. Total Body Dose Rate % 4.72E-3 1.63E-2
- 2. Skin Dose Rate % 1.83E-3 3.98E-3
- 3. Critical Orcan Dose Rate % 3.44E-3 1.32E-3
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TABLE 2A -
N0RTH ANNA POWER STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT PET RASE REPORT LIOUID EFFLUENTS-SUMMATION OF ATT. PET. RASES FOR (07/93 - 12/93) 3rd 4th ESTIMATED TOTAL UNITS OUARTER OUARTER PERCENT ERROR (%)
A. Fission and Activation Products:
- 1. Total release (not including tritium, noble gas, and gross aloha). Curies 1.14E-1 1.15E-1 2.00E+1
- 2. Average diluted concentration durina the ceriod. uCi/ml 1.47E-10 2.01E-10
- 3. Percent of acclicable limit (T.S.) % 1.76E-3 4.80E-4 B. Tritium:
- 1. Total release activity. Curies 1.70E+2 1.98E+2 2.00E+1
- 2. Average diluted concentration durina the ceriod. uCi/ml 2.20E-7 3.46E-7
- 3. Percent of acolicable limit (T.S.) % 7.31E-3 1.15E-2 C. Dissolved and Entrained Gases:
- 1. Total release activity. Curies 2.96E-3 2.03E-4 2.00E+1
- 2. Average diluted concentration durina the ceriod. uCi/ml 3.82E-12 3.54E-13
- 3. Percent of acolicable limit (T.S.) % 1.91E-6 1.77E-7 D. Gross Alpha Radioactivity:
- 1. Total release activity. Curies 1.08E-4 5.91E-4 2.00E+1 E. Volume of waste released: (prior to dilution). Liters 6.85E+7 6.02E+7 3.00E+0 F. Total volume of dilution water used durina the period. Liters 7.74E+11 5.73E+11 3.00E+0 l
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c 8 0 - 1 3 3 3 3 4 - 4 - 1 1 7 5 - P P 5 6 1 1 1 1 1 1 1 - e - - 1 5 6 m
- & e 5 mm - m m p 9 m 5 - u m 3 r S n e s 5 - - uu u- - - - - - u - y S y m 5 u - 6 - - i u 1 o E o n - t t it it m i n n ( n u i m t i 1 f D i a un r e e m m ma m o l l n n i e e n n u u u h u m oi r m m
- n m - u o u i t l e n l e n e - l I s a n a a o o b h v i i i i i t i i ei o n ci c d ak h h a L s n o bb r r o t l d d s s r n r t h t r o r d n o b c c t n t C i a r o o t t i u i ooeeaa en t n h ri n i h oi eui o U
N FMICCSS N R S I I C C B L C A O A C I Z I Z R C N T R T T
2 f 6 o D -
2 x D / D D D D D E h r / N / / / / / 2 e tT N N N N N N 2 g 4R .
- r. A 2 P U E O D
O M
H C
T A 6 6 B x D - -
d r D / E D D E D D rT / 7 / /
3RA / N 5 7 N/ N 5 N N N . .
T R
U O
1 1 O 3 P 9 E /
R 2 1
E - 4 4 2 4 S x - - + -
A E 3 h E tT D D / D D E E E 8
E 9
/ N / / 3 3 N L 9/ E 4RA N N N 0 0 9 8 O E 7 D . . . .
I R 0 O U 2 2 1 5 T M O A
T T R S N O S E F U U O B RL U 2 E F S N W F O E E I 2 4 S T 3 5 5 3 E P A Nd x - - - - + -
L O rT r E D / E D E E E E B E E C 3R 7 9 / 9 6 0 8 A A VL 8 N 0 N 5 9 7 0 TN I E A U
N TR 2 6 2 2 1 1 A C O A T O
H I N T D r RA u O R FL S N F T i i i i i i i i L E I : CCCC N s C C C C A
U D U e N I s N a AU Q G
I I e ML l b
E S o N
d e
n i
D a E
S r d t ) o A n v i F .
E f r T mi e E & 3 m 3 5 5c P a P 3 3 3 3 e 1 h d 1 1 1 1o 4 r o e S o l S A E lv - - - -(
- f m u
D o n n n nr n l i s I s o o o oe o a t s L s n n n nh c t i o C i e e e et r o r r U T T G N D X X X XO A
TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SIIIPMENTS FOR 07-01-93 TIIROUGII 12-31-93
[ Pace 1 of 2 Ao SOLID WASTE SIIIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-Month Estimated Total
- 1. Type of Waste Unit Period Percent Error (%)
- a. Spent resins, filter m8 8.05E+1* 2.50E+1 sludges, evaporator Ci 7.83E+1 2.50E+1 bottoms.etc.
- b. Dry compressible waste, m8 4.23E+2** 2.50E+1 contaminated equipment, Ci 5.59E0 2.50E+1 etc.
- c. Irradiated components, m2 0.00E0 0.00E0 control rods, etc. Ci 0.00E0 0.00E0
- d. Other (describe) m8 1.54E+1*** 2.50E+1 Waste Oil / Sludge Ci 1.36E-2 2.50E+1
- 2. Estimate of major nuclide composition (by type of waste)
- a. Fe-55 % 3.61E+1 2.50E+1 Co-60 % 1.55E+1 2.50E+1 Ni-63 % 1.70E+1 2.50E+1 Mn-54 % 1.06EO 2.50E+1 Co-58 % 2.84E+1 2.50E+1 Cs-137 % 1.75E0 2.50E+1
- b. Fe-55 % 1.86E+1 2.50E+1 Co-60 % 1.15E+1 2.50E+1 Cs-137 % 1.35EO 2.50E+1 Ni-63 % 2.67E0 2.50E+1 Co-58 % 1.33E+1 2.50E+1 Ce-144 % 1.85E0 2.50E+1 Zr-95 % 1.71E+1 2.50E+1 Nb-95 % 3.37E+1 2.50E+1 G-
t TABLE 3 HORTH ANNA POWER STATION RADIOACTIVE EFPLUENT RELEASE REP _QRT SIIMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS POR 07-01-93 THROUGH 12-31-93 Paae 2 of 2
- 2. Estimate of major nuclide composition (by type of 6-Month Estimated Total waste) (cont.)
Unit Period Percent Error (%)
- d. Co-60 % 1.43E+1 2.50E+1 Fe-55 % 1.22E0 2.50E+1 Co-58 % 1.02E0 2.50E+1 Ni-63 % 1.20E0 2.50E+1 Ce-144 % 4.10E+1 2.50E+1 Cs-137 % 2.59E+1 2.50E+1 Cs-134 % 3.25EO 2.50E+1 Sr-90 % 8.83E0 2.50E+1
- 3. Solid Waste Disposition i
Humber of Shipments Mode of Transnortation Destination 10 Truck Barnwell, SC 13 Truck Oak Ridge, TN (SEG) ,
2 Truck Oak Ridge, TN l (Quadrex)
B. Irradiated Fuel Shipments (Disposition)
Number of Shipments Mode of Transportation Destination N/A N/A N/A 3 shipments of resin were shipped from North Anna to a Licensed Waste Processor for volume reduction. Therefore, the volume listed for this type is not representative of actual volume buried. The total volume buried for this reporting period was 39.36 m , a 12 shipments of dry compressible waste / contaminated equipment were shipped from North Anna to a Licensed Waste Processor for volume reduction. Therefore, the volume listed for this type is not representative of the actual volume buried. The total volume buried for this reporting period was 79.16 m8 3 shipments of waste oil / sludge were shipped from North Anna to a Licensed Waste Processor for incineration and volume reduction.
Therefore, the volume listed for this type is not representative of the actual volume buried. The total volume buried for this reporting period was 2.0 m2
1 Attachment 2 j l
l Annual and Ouarterly Dogga (07/93 - 12/93) l l
An assessment 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 the report along with an annual total of each effluent pathway will be made pursuant to ODCM 6.6.2.
Liould Effluents:
1st 2nd 3rd 4th Annual Ouarter Ouarter Ouarter Ouarter Total Total Body Dose (mrem) 1.46E-1 7.13E-2 1.43E-1 7.91E-2 4.39E-1 Critical Organ Dose (mrem) 1.91E-1 7.75E-2 1.81E-1 8.84E-2 5.38E-1 fagaeous Effluents:
1st 2nd 3rd 4th Annual Ouarter Ouarter Ouarter Ouarter Total Noble Gas Gamma Dose (mrad) 5.81E-3 1.41E-3 7.04E-3 2.15E-2 3.58E-2 Noble Gas Beta Dose (mrad) 1.70E-2 3.38E-3 1.93E-2 7.90E-3 4.76E-2 Critical Organ Dose for I-131, H-3, Particulates 4.03E-2 7.04E-3 5.40E-2 1.31E-2 1.14E-1 with T < 8 days (mrem) l
_ - - = - . . - . ..
ATTACHMENT 3 REVISIONS TO OFFSITE DOSE CAIfULATION NANUAL (ODCM) ,
(07/93 -
12/93)
As required by Technical Specification 6.15, changes to the ODCM effective
.for the time period covered by this report, are summarized in this attachment.
There were no changes to the ODCM during this reporting period. All references to ODCM sections in this report are to Revision 4.
I l
8
4 A'I"PACHMENT 4 MAJOR CHANGES TO RADIOACTIVE LIOUID, CASEOUS. AND SOLID l
WASTE TREATMENT SYSTEMS l 1
t 1
(07/93 -
12/93)
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 synopsized in this attachment. Supporting information as to the reason (s) for the change (s) and a summary of the 10 CFR 50.59 cvaluation are included, as applicable.
No major changes to the radioactive gaseous and solid waste treatment systems were made for the time period covered by this report.
l l
l i
l 1
9 1
I
ATTACHMENT 5 INOPERABILITY OF RADIOACTIVE LIOUID AND CASEOUS EFFLUENT __ MONITORING._lMSTRUMENTATION (07/93 - 12/93) l 1
l As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2.b.3, a list and explanation for extended inoperability of radioactive liquid and/or gaseous affluent monitoring instrumentation is provided in this attachment.
No extended periods of inoperability occurred with any of the Liquid or Gaseous Effluent Monitoring Instrumentation specified in the ODCM, Attachments 2 and 15, for the time period covered by this report.
l l
1 I
i l
l 10 j i
1
4 ATTACHMENT 6 UNPLANNED DET. EASES
!O7/93 - 12/93)
As required by the ODCM, Section 6.6.2, a list of unplanned releases, from the site to unrestricted areas, of radioactive material in gaseous and liquid offluents occurring during the reporting period, is made in this attachment.
No unplanned releases, as defined by the criteria presented in the ODCM, Scction 6.6.2, occurred during the time period covered by this report.
i i
11
ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (07/93 - 12/93)
Gageous Effluents:
Required L.L.D. Typical L.L.D.
Radioisotope fuCi/ml) (uCi/ml)
Kryoton - 87 1.00E-4 3.53E-7 -
4.34E-7 Krypton - 88 1.00E-4 4.79E-7 -
6.28E-7 Xenon - 133 1.00E-4 2.76E-7 -
3.89E-7 Xenon - 133m 1.00E-4 1.15E-6 -
1.51E-6 Xenon - 135 1.00E-4 1.40E-7 -
1.78E-7 Xenon - 135m 1.00E-4 5.34E-7 -
7.54E-7 Xenon - 138 1.00E-4 1.17E-6 -
1.96E-6 Iodine - 131 1.00E-12 5.34E 7.59E-14 Mancanese - 54 1.00E-11 3.64E 5.32E-14 Cobalt - 58 1.00E-11 4.05E 5.21E-14 Iron - 59 1.00E-11 7.70E 1.01E-13 Cobalt - 60 1.00E-11 5.66E 1.52E-13
~ Zinc - 65 1.00E-11 1.01E 1.19E-13 Strontium - 89 1.00E-11 4.00E 5.00E-15 Strontium - 90 1.00E-11 7.00E 1.00E-15 l
Molybdenum - 99 1.00E-11 2.72E 3.47E-13
__._ Cesium - 134 1.00E-11 1.03E 1.61E-13 Cesium - 137 1.00E-11 4.70E 5.77E-14 Cerium - 141 1.00E-11 4.54E 6.79E-14 Cerium - 144 1.00E-11 ,04E 3.22E-13 Gross Aloha 1.00E-11 6.90E 1.20E-14 Tritium 1.00E-6 1.12E-7 -
1.37E-7 12
ATTACHKEITP 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (07/93 -
12/93)
Licuid Effluents:
Required L.L.D. Typical L.L.D.
Radioisotope fuci/ml) (uCi/ml)
Kryoton - 87 1.00E-5 6.07E-8 -
7.29E-8 Kryoton - 88 1.00E-5 8.85E-8 -
1.16E-7 Xenon - 133 1.00E-5 6.08E-8 -
8.83E-8 Xenon - 133m 1.00E-5 2.04E-7 -
2.69E-7 Xenon - 135 1.00E-5 2.50E-8 -
3.14E-8 Xenon - 135m 1.00E-5 8.95E-8 -
1.19E-7 Xenon - 138 1.00E-5 2.17E-7 -
3.41E-7 Iodine - 131 1.00E-6 2.63E-8 -
3.43E-8 Manaanese - 54 5.00E-7 2.45E-8 -
3.93E-8 Iron - 55 1.00E-6 4.00E-7 -
8.00E-7 Cobalt - 58 5.00E-7 2.61E-8 -
3.25E-8 Iron - 59 5.00E-7 4.85E-8 -
5.86E-8 Cobalt - 60 5.00E-7 3.23E-8 -
8.43E-8 Zinc - 65 5.00E-7 5.81E-8 -
6.83E-8 Strontium - 89 5.00E-8 3.00E-8 -
5.00E-8 Strontium - 90 5.00E-8 5.00E-9 -
1.00E-8 Molybdenum - 99 5.00E-7 1.82E-7 -
2.31E-7 Cesium - 134 5.00E-7 5.84E-8 -
1.00E-7 Cesium - 137 5.00E-7 3.32E-8 -
3.79E-8 Cerium - 141 5.00E-7 4.07E-8 -
5.47E-8 Cerium - 144 5.00E-7 1.81E-7 -
2.63E-7 Gross Alpha 1.00E-7 2.15E-8 -
3.72E-8 Tritium 1. o o t- 5 2.78E-6 -
3.32E-6 13
_ _ _ - _ - _ _ - _ - _ _ - _ .