ML20082N123
ML20082N123 | |
Person / Time | |
---|---|
Site: | Summer |
Issue date: | 06/30/1991 |
From: | Blue L, Gowdy G, Nettles K SOUTH CAROLINA ELECTRIC & GAS CO. |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
NUDOCS 9109060202 | |
Download: ML20082N123 (21) | |
Text
n o.
rgi C Su er N citar stio K. W. NIttlis
- P.O Bca 88 Gerotsl MInsgir, N
JunMnsulle SC N065 Nuclear Safety SCE&G ggjpjjj;[g AUG 3 01991 i
U. S. Nuclear Regulatory Commission Doctment Control Desk Washington, DC 20555 I Gentlemen:
4
Subject:
VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 SEMI-ANNUAL EFFLUENT AND WASTE DISPOSALREPORT(SA300)
Enclosed is the South Carolina Electric & Gas Company (SCE&G)' Semi-Annual Effluent and Waste Disposal Report as required by 10CFR50.36a and Sections 6.9.1.8 and 6.9.1.9 of the Virgil C. Summer Nuclear Station Technical Specifications.
Should there be any questions, please contact us at your convenien e.
Very truly yours, f
. W. ettles&
CJM:KWN: led Enclosure
.c: 0. W. Dixon Jr. (w/o attachments)
R. R. Mahan (w/o attachments)
R. J. White S. D. Ebneter G. F. Wunder General Managers NRC Resident Inspector J. B. Knotts Jr.
File (818.02-1)
CG0030 9109060202 910630 NUCLEAR EXCELLENCE - A SUMER TRADITION! [off
- )VJ l l
SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT FOR THE OPERATING PERIOD January 1,1991 - June 30,1991 August 1991 S
-[gpmwmw g I l
.J V. C. SUMMER NUCLEAR STATION SOUTH CAROLINA ELECTRIC AND GAS COMPANY Prepared by:
$/ 4 G.M!Gow3y, g Staff Health Physicist Reviewed and ap roved by: Reviewed and approved by:
/ th' W. R. BaeTir, Manager 4..
1 A. Blue, Man 5ger Corporate Health Physics and Chemistry and Health Physics Environmental Programs Reviewed and approved by:
au
'G. G. Hall, Associate Manager Health Physics
, SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1991 Virgil C. Summer Nuclear Station South Carolina Electric & Gas This report is being submitted as a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the Virgil C. Summer Nuclear Station.
This report satisfies the requirements in Sections 6.9.1.8 and 6.9.1.9 of Technical Specifications and 10CFR50.36(a). Also included is an assessment of radiation doses from plant releases.
A brief discussion of the Supplemental Information and Tables 2 through 6 is presented in Sections A through D. An evaluation of the radiologicalimpact on man due to operation of the Virgil C. Summer Nuclear Station is presented in Section E and Table 1. Changes made to previous reports are presented in Section F and Appendix 1.
A. SupplementalInformation Regulatory limits for doses and maximum permissible concentrations prescrited in Supplemental Information are from the Virgil C. Sumnier Nuclear Station Technical Specifications and 40 CFR 190. Average energy (E)is not applicable to the method for determining release rate limits for fission and activation gaseous ef fluents; therefore,it has been omitted.
B. Gaseous Ef fluents Gaseous effluents released from ground level are summarized in Tables 2 and
- 3. An elevated release pathway does not exist at Virgil C. Summer Nuclear Station. Cumulative doses are discussed in Section E.
The errors for gaseous ef fluent totals are given as the square root of the sum of squares of counting errors and flow or volume measurement errors. A systematic error of 15% has been added to estimate total error.
C. Liquid Effluents Liquid effluents are summarized in Tables 4 and 5. Estimated total errors are expressed as in Section B above.
D. Solid Waste Shipments Solid waste shipments are summarized in Table 6. Curie content of radioactive waste packages is determined by dose rates and/or analysis of samples by gamma spectroscopy. The total error for each type of Curie content determination is conservatively estimated to be the sum of a 15% systematic error and a 20% photon response error for the detector used.
E. Radiological Impact on Man Potential doses to the maxirnum exposed individual in the unrestricted area were calculated using measured plant gaseous effluent and meteorological data in accordance with the Offsite Dose Calculation Manual. Included in the source term was one (1) waste gas decay tank (WGDT) batch release and a continuous six month main plant vent release. Doses are summarized in Table
- 1. The total activities released are presented in Tables 2 and 3. Air doses to the Page 1 1
4 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT .
J:nuary - June,1991 Virgil C. Summer Nuclear Station South Carolina Electric & Gas maximum exposed-individual due to noble gases were 5.19E-3 and 1.28E-2 mrad for gamma and beta, respectively. The maximum organ dose attributed to the releases was 3.73E-3 mrom for the six month period Measured plant liquid effluent data was used to calculate estimates of doses to individuals in accordance with the Offsite Dose Calculation Manual. The source term consisted of the isotopic contents of 227 Waste Monitor Tank batch releases and continuous Turbine Building Sump and Steam Generator Blowdown releases. Doses are summarized in Table 1. The total radioactivity
- released is described in Tables 4 and 5. The total body dose to the maximally exposed mdividual due to the radioactive liquid released was 4,49E-2 mrem.
The maximum organ dose was 5.83E 2 mrem to the thyroid.
Table 1 GASEOUS AND LIQUID DOSES F_irst Quarter,1991 Second Quarter,1991 C
Sect Gaseous Limits Dose Percent Dose Percent of Limit of Limit 3.11.2.2 a,b 5 mrad gamma /qtr. 3.50E-3 mrad 6.99E-2 1.69E-3 mrad 3.38E-2 10 mrad gamma /yr. 3.50E-2 5.19E 2 *
(January-June total gamma air dose: 5.19E-3 mrad) 3.11.2.2a,b 10 mrad beta /qtr. 8.18E-3 mrad 8.18E-2 4.58E-3 mrad 4.58E-2 20 mrad beta /yr. 4.09E-2 6.38 E-2 *
(January-June total beta air dose: 1.28E-2 mrad) 3 11.2.3a,b 7.5 mrem / organ /qtr. 3.08E-3 mrem 4.10E-2 6.56E-4 mrem 8.74E-3 15 mrem / organ /yr. 2.05 E-2 2.49E-2 *
(January June maximum exposed organ dose: 3.73E 3 mrem) l Li_ quid Limits 3.1 1.1. 2 a,b 1.5 mrom/qtr. 4.64E-3 mrem 3.09E-1 4.02E-2 mrem 2.68E0 3.0 mrem /yr. 1.55 E-1 1.50 E0
- l (January-June whole body dose: 4.49E-2 meera) 3.1 1.1.2 a,b 5 mrem / organ /qtr. 1.64E-2 mrem 3.28E-1t 5.09E-2 mrem 1.02 E0 t 10 mrem / organ /yr. 1.64E-1 t 5.83E-1
- t (January-June maximum exposed organ dose 5.83E-2 mremt) l
- Includes contribution from previous quarters.
t Maximum exposed organs first quarter and 6 months- thyroid; second quarter -liver.
Page 2
SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1991 Virgil v iummer Nuclear Station South Carolina Electric & Gas Dose rates and concentrations were below the limits snecified in Supplemental information, Section 2a, b and c during all the of fluent releases.
Radiation doses from radioactive effluents to workers at the Fairfield Hydro Station were calculated to be 7,12E-4 and 1.76E-3 mrad for gamma and beta, respectively.
Radiation doses from nearby uranium fuel cycle sources were not assessed.
Technical Specifications, Section 3/4.11.4, page B 3/411-6 establishes a five (5) mile limit beyond no uranium which fuel cycle doses plants from within nearby a five (plants
- 5) mile radiusare insignificant.
of Virgil There are C. Summer Nuclear Station.
F. Changes to Previous Reports During the affected six month period, a problem was found with computer software determinations of airborne tritium concentrations. A detailed description of the problem is given in LER 91-004, August 1991. Attachment i gives the corrected airborne tritium concentrations and affected doses for previous reports. The increases in maximum exposed organ doses due to tritium in gaseous ef fluents were 2.09E 3, 9.04E-3, 5.00E-5,1.78E-2, 4.94E-2, 3.50E-3 and 7.50E-4 mrem, respectively for 1984 through 1990. The maximum increase of 4.94E-2 mrem in 1988 led to a change in the percent of annual limit from 2,18E-1% to 5.47E-1%. Thus, the overall organ dose effect from the
- tritium problem was minimal, i
l An additional correction to the last report (July - December,1990) also needs to be made. One (1) shipment of five (5) irradiated fuel pins was trucked in September,1990 to Chalk River, Canada for testing. Part B of Table 5 needs to be updated accordingly.
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'SEMlANNUAL EFFLUENT AND WASTE DISPOSAL REPORT l
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January June,1991 Virgil C. SummerNuclearStation South Carolina Electric & Gas ) !
Supplementallnformation - !
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- 1. Regulatory Limits: i
- a. Fission and Activation Gases:-
The air dose to an individual due to noble gases released in gaseous ;
effluents shall be limited to less than or equal to 5 mrad for gamma i radiation and 10 mrad for beta radiation during any calendar quarter a and 10 mrad for gamma radiation and 20 mrad for beta radiation i during any calendar year (Technical Specifications, Section 3.11.2,2), i t
- b. -lodines, Particulates (half-lives > 8 days) and Tritium: li
-The dose to an individual from radioiodines, tritium and radioactiv i l materials in particulate form with half-lives greater than 8 days in ;
gaseous of fluents shall be limited to less than or equal to 7.5 mrem to !
a
.any duringorgan duringyear any calendar any(Technical calendar5pecifications, quarter andSection 15 mrem to any 3.11.2.3 . org)an t t
- c. Liquid Effluents: l The dose or dose commitment to an individual from radioactive '
materials in liquid effluents released shall be limited to less than or equal to 1.5 mrem to the total body and 5 mrem to any organ during :
4 any calendar quarter and 3 mrem to the total body and 10 mrem to !
any organ during any calendar year (Technical Specifications, Section ;
3.1 1.1.2). !
\
d.
All Sources:
i The annual dose equivalent shall not exceed 25 mrem to the whole l body,75 mrem to the thyroid and 25 mrem to any other organ (40 !
CFR 190). i
- 2. Maximum Permissible Concentrations: i
- a. Fission and Activation Gases: !
The dose rate in unrestricted areas due to radioactive materials released in gaseous effluents shall be limited to less than or equal to ;
500 mrem / year to the total body and less than or equcI to 3000 i mrem / year to the skin (Technical Specifications, Section 3.11.2.1). t
- b. lodines, Particulates (half lives > 8 days) and Tritium: }
t The dose rate in unrestricted areas due to radioactive materials in !
effluents shall be limited to less than or equal to 1500 mrem / year to !
any organ (Technical 5pecifications, Section 3.11.2.1). ;
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SEMIANNUAL EFFLUENr AND WASTE DISPOSAL REPORT January June,1991
- llrgil C. Summer Nuclear Station South Carolina E'lectric & Gas SupplementalInformation
- c. Liquid EIfluents:
The concentration of radioactive materials released from the site shall be limited to the concentrations specified in 10 CFR 20 Appendix B, Table 11, Column 2 for radionuclides other than dissolved or entra;ned noble gases. For dissolved or entrained noble gases, the concentrat%n shall be hmited to 2E 4 pCl/ml total activity (Technical Specifications, Section 3.11.1.1).
- 3. Average Energy:
Not Applicable
- 4. Measurements and Approximations of Total Radioactivity:
- a. Fisuon and activation gases: Gamma spectrometry (Ge(Li) or HPGe]
- b. lodines: Gamma spectrometry (Ge(Li) or HPGe]
- c. Particulates: Gamma spectrometry [Ge(U) or HPGej, beta propor-tional counting, alpha proportional counting
- d. Tritium: Liquid scintillation
- c. Liquid effluents: Gamma spectrometry [Ge(Li) or HPGe], liquid scintillation (H-3), beta proportional counting, alpha proportional counting
- 5. Batch Releases:
- a. Gaseous:
- 1. Number of batch releases: 1
- 2. Total time period for batch releases: 133 min.
3 Maximum time period for a batch release: 133 min.
- 4. Average time period for a batch release: 133 min.
- 5. Minimum time period for a batch release: 133 min.
- b. Liquid:
- 1. Number of batch releases:
107 for first quarter,1991 120 for second quarter,1991 Page 5
SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1991 Virgil C. Surnmer Nuclear Station South Carolina Electric & Gas Supplernentallnformation
- 2. Total time period for batch releases:
/.43E + 3 min. for first quarter,1991 8.84E 4 3 min. for second quarter,1991
- 3. Maxunum time period for a batch release:
8.30E 41 min. for first quarter,1991 1.00E 4 2 min. for second quarter,1991
- 4. Average time period for batch releases:
6.94E + 1 min. for first quarter,1991 7.37E + 1 mm. for second quarter,1991
$. . Minimum time period for a batch release:
1.00E + 0 min, for fitst quarter,1991 4.00E + 1 min fc t second quarter,1991
- 6. Average stream flow during periods of release of effluent into a flowing stream:
2.97E + 6 gpm for first quarter,1991 4.61E + 6 gpm for second quarter,1991
- 6. Abnormal Releases:
- a. Gaseous:
- 1. Number of releases: 0
- 2. Total activity released 0
- b. Liquid:
- 1. Number of releases: 0
- 2. Total activity released: O Page 6
- _ _ _ - - _ _ _ _ - - _ _ _ _ - - _ _ _ _ _ _ - - _ _ _ _ _ _ _ - l
SEMIANNUAL EFFLUENT AND WASTE DISPOSAL WORT January June,1991 Table 2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES First Second Est. Total Quarter Quarter Error, % ;
A. Fission 8 activation gases I
- 1. Total release Ci 4.08E t 1 2.49E + 1 3.38E 41
- 2. Average release rate for period Ci/sec 5.25E 4 0 3.17E 4 0
- 3. Percent of technical specification limit p4 *
- B lodines .
- 1. Totat iodine-131 Ci 1.68E 5 3.15E 5 3.60E 41
- 2. Average release rate for period pCi/sec 2.16E 6 4.01 E-6 ,
- 3. Percent of '.echnical specification limit % ** **
C. Particulates $
- 1. Particulates with half-lives > 8 days Ci 0 1.55E 6 3.32E 41
- 2. Average release rate for period pCi/sec 0 1.97E 7
- 3. Percent of technical specification limit % ** **
- 4. Gross alpha radioactivity Ci 0 0 D. Tritium r
- 1. Total release Ci 8.21E 4 0 0 2.65E 41-
- 2. Average release rate for penod pCi/sec 106E 4 0 0
- 3. Percent of technical specification limit % ** **
Calculated as a percent of dose limits found in SupplementalInformation, Section 1a First quarter values were 6.99E-2% and 3.50E-2% of the quarterly and cnnulative annual gamma dose limits, respectively and 8.18E-2% and 4.09E-2% of the quarterly and cumulative annual beta dose limits, respectively. Second quarter values were 3.38E 2% and 5.19E-2%1 of the quarterly and cumulative annual gamma dose limits, respectively, and 4.58E-2% and 6.38E 2%1 of the quarterly and cumulative annual beta dose limits, respectively.
Calculated as a percent of dose limits found in SupplementalInformation, Section 1b. The sum of these values for the first quarter was 4.10E 2% and 2.05E-2% of the quarterly and cumulative annual organ dose limits, respectively. The sum of these values for the second quarter was 8.74E 3% and 2.49E 2%t of the quarterly and cumulative annual organ dose ,
hmits, respectively.
1 Note: Secend quarter values are the sum of the first and second quarter values compared to annual dose limits.
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L M p. y ,_9.- m..,__-._.my , . - . _ -, p2.r ,v -
-. . . . - - - . ,--_g --.--,y.
. SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1991 Table 3 GASEOUS EFFLUENTS GROUND LEVEL RELEASES Continuous Mode Batch Mode first Second First Second Nuclides Released Unit Quarter Quarter Quarter Quarter
- 1. Fission gases Krypton 85 C 0 0 6.7/E 2 0 Krypton 85ni Ci 0 0 0 0 Krypton 87 Ci 0 0 0 0 Krypton-88 Ci 0 0 0 0 Xenon 133 Ci 3.66E + 1 2 41 E + 1 1.89 E - 5 0 Xenon-135 Ci 4.10E + 0 8.05E 1 2.16E-6 0 Xenon-13 5m Ci 0 -
0 0 0 Xenon 138 Ci 0 0 0 0 Others: Ci 0 0 0 0 Unidentified Ci 0 0 0 0 Total for period Ci 4 07E + 1 2 49E + 1 6 78E-2 0
- 2. lodines lodine-131 Ci 1.bSL-5 ~
3.15t 5 0 0 iodine 13? Ci 9 83E-7 1.70E 5 0 0 todine 133 Ci 5.48E-5 5.67E 5 0 0 lodine-134 Ci 0 0 0 0 lodme-135 Ci 0 0 0 0 Total for period Ci 7.26E-5 1.0 5 E -4 0 0
- 3. Particulates Strontium 89 Ci 0 0 0 0 Strontium-90 Ci 0 0 0 0 tesium 134 Ci 0 1.10 E-6 0 0 Cesiurn-137 Ci 0 3.62 E-7 0 0 Barium-Lanth.-140 Ci 0 0 0 0 Others: Co 57 Ci 0 8.39E-8 0 0 ~
Rb-88 Ci 2.78E 2 2.51 E-3 0 0 Tc 99m Ci 2.19E 6 0 0 0 Cs-138 Ci 1.89 E-2 6.39 E-3 0 0 Unidentified Ci 0 0 0 0 Total for period Ci 467E-2 8.90E 3 0 0 1
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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1991 Table 4 LIQUID EFFLUENTS. SUMMATION OF ALL RELEASES First Second Est. Total Quarter Quarter Error, %
A. Fission & activation products
- 1. Total release (not including tritium, gases, Ci 1.20E-1 1.58E 1 1.92E + 1 alpha)
- 2. Average diluted concentration during pCi/mi 1.94 E-10 2.39E 10 period
- 3. Percent of applicablelimit $4 B. Tritium
- 1. Total release Ci 2.29E 4 2 2.90E 4 2 1.84E 41
- 2. Average diluted concentration during pCi/ml 3.70E 7 4.39E 7 period
- 3. Percent of applicable limit *
- C. Dissolved and entrained gases
- 1. Total release Ci 4.98E 3 1.67E 2 1.86E 41
- 2. Average diluted concentration during pCi/ml 8.08E 12 2.52E 11 period
- 3. Percent of applicable limit * *
$4 D. Gross alpha radioactivity
- 1. Total release Ci 0 0 N/A E. Volume of waste released (prior to dilution) liters 7.05E 4 7 7.71E 4 7 3.00E 4 0 1 Volume of dilution water used during period liters 6.17E + 11 6.61 E + 11 4.30E 4 0
- See following page.
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a SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1991 [
Table 4 1 LlQUID EF5LUENTS SUMMATION OF ALL RELEASES r
- Calculated as a percent of dose limits found in SupplementalInformation, Section 1c. The .
sum of these values for the first quarter was 3.09E-1% and 1.55E 1% of the respective quarterly and cumulative annual whole body dose lint ts i and 3.28E-1% and 1.64E-1% of the respective quarterly and cumulative annual organ dose limitt. The sum of these values for ,
the second quarter was 2.68% and 1.50%1 of the tespective quarterly and cumulative annual whole body dose limits and 1.02% and 5.83E 1% t of the respective quarterly and .
cumulative annual organ dose limits. Dose to the thyroid was the most limiting organ dose for the first quarter and six (6) months of 1991. Dose to the liver was most limiting during the second quarter of 1991.
1 Note: Second quarter valuas are the sum of the first and second quarter values compared to !
annual dose limits.
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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT l January June,1991 l Table 5 l LIQUID EFFLUENTS f Continuous Mode Batch Mode j nrst be(ond hrst Second i f Nuclides Released Unit Quarter Ovarter Quarter Quarter !
Strontium-89 Ci 0 0 5.15 E-4 4.57E-4 Strontium-90 Ci 0 0 8.59E-4 8.24E-4 ;
Cesium-134 Ci 0 :1.91 E-3 1.88 E-4 9.39 E -4 !
Cesium 137 Ci 0 2.92 E - 3 2 61E-4 9.87 E -4 !
lodine 131 Ci ' 21 E-3 1.21 E -2 106E-4 9.54E 4
" Cobalt 58 Ci 0 1.45E 5 7. 78 E -4 3.94L 4 Cobalt-60 Ci 0 0 1.25E-2 1.3 6 E -2 Iton 59 Ci 0 0 0 0 Zinc 65 Ci 0 0 3.86E-5 3.22E 5 Manganese 54 Ci 0 0 3.0 3 E-3 3.29E-3 !
Shromium 51 Ci 0 0 1.7 2 E -5 0 ;
Zirconium Niobium 95 Ci 0 0 7 60E-5 2.32 E 6 [
Molybdenum 99 C# 0 5 02EI 4 3.49E 5 1.17 E- 5 i Technetium 99m Ci 0 4.26E-5 3.95E 5 1.0 5 E -4 I
Barium-Lanth.-140 Ci 0 4.50E-4 0 1.4 2 E-6 Cerium-141 Ci 0 0 1. 70 E - 6 6.33E 7 j Other: F - 18 Cl 8.62 E -3 8.69E-3 0 0 i Na-24 Ci 0 0 1.38E 5 3.81E 6 -
Fe 55 Ci 0 0 2.18 E -2 2.59F-4 {
Co 57 Ci 0 0 2.105-5 187E-5 Rb-88 Ci 0 0 2.00E-5 0 R u- 106 Ci 0 0 6.15 E-4 6.96E 4 Aq-110m Ci 0 0 2.62E-5 2.72E-5 !
Sb 125 Ci 0 0 2.80E-3 1 56E-3 !
~~
Te-132 Ci 0 0 9.90E-7 0 !
l-132 Ci 1.56E 2 2.12 E 2 5.78E-6 0 ~~ I l-133 Ci 1.71 E-2 2.86E-2 1.30E 4 4.2404 :
1134 Ci 1.02E 2 1.44 t -2 0 0 i l 1-135 Ci 2.17 E -2 3.30E 2 5.12 E -5 4 49E 5 !
I Cs- 136 Ci 0 6.84E 4 0 2.04E 5 !
Cs 138 Ci 1.7 7 E-3 5.71 E-3 0 0 !
Ce-144 Ci 0 0 5.59 E -4 2.71 E-4 I Unidentified Ci l 0 0 l 0 l 0 f Total for period (above) l Ci l 7.52E 2 l 133E-1 l 4.4 5 E -2 l 2.49E-2 l t
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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT i January June,1991 Table 5 (continued)
LlQUID EFFLUENTS Continuous Mode Batch Mode First Second First Second tNuclides Released Unit Quarter Quarter Quarter Quarter Xenon 133 Cl 1.14E 3 2.58E-3 2.29E 3 1.24E 2 Xenon 135 C: 1.50 E ~, 1.59E 3 3.85E-5 7.32E 5 Other: Kr 85m Ci 0 0 0 1.71E 6 Kr 87 Ci 0 0 0 3.30E 6 Kr-88 Ci 0 0 1.88E 6 0 Xe-131m Ci 0 0 1.53E 5 2.63E 5 Xe-133m Ci 0 0 0 2.79E 5 Total entrained gases C# 2.64 E-3 4.17 E-3 2.34E 3 1.2 5 E-2 t Tritium not included. See Table 4 for tritium numbers.
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l SEMlANNUAL EFFLUENT AND WASTE DISPOSAL REPORT l January June,1991 !
Table 6 i SOLID WA5TE AND 1RRADIATED FUEL SHIPMENTS l A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated f uel) !
6 month Est. Total
- 1. Type of waste Unit Period Error,% (
- a. $ pent resins, filter sludges, evaporator m 3 9./3L 4 0 bottoms, etc. Ci 1.05E 4 2 3 50E 41 }
- b. Dry compressible waste, contan'iinated m8 6.57E 4 0 !
equip,, etc. Ci 3,43E - 1 3.50E 41 !
I
- c. Irradiated components, control rods, etc. m' 0 !
Ci 0 N/A !
d.Other (describe) m' 0 I Ci 0 N/A !
- 2. Estimate of major nuclide composition (by type of waste)
- a. Fe 55 % 2.95E + 1 ;
,Ni 63 % l 946 ' I , f Cs-137 % 1.82 E + 1 l Co 60 % 1.66E v 1 Cs-134 % 1.04E i 1 ,
Mn 54 % 2.16E + 0 [
Co 58 % !
1:77h ' U
- b. Fe 55 % 4.12E i 1 j Co 60 46 1.99E e 1 i Cs-137 % 1.39E 4 1
(
Cs 134 % 8.29E + 0 !
~
Ni 63 % 6.90E 4 0 l Mn-54 % 2,69ti + 0
{
H3 % 1.60E + 0 !
- Co-58 % 1.57E 4 0 !
l c. None _
% N/A f
d, None % N/A !
' All nuclides with concentrations above 1.0% are listed in descending order by activity level.
- 3. Solid Waste Disposition (6 month period) ,
Number of Shipments Mode of Transportation Destination !
1/t Truck Barnwell, SC t
1 Note: 15 of these are partial shipments of DAW from waste processor to Barnwell, SC.
{
B. Irradiated Fuel Shipments (Disposition) l Numberof Shipments Mode of Transportation Destination None N7A N/A f l
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ATTACHMENT I i
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i V. C. SUMMER NUCLE AR STATION !
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Corrections to Previous Reports -
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Corrections to Table 1: Gaseous a'nd Liquid Doses ,
l ! First Quarter j Second Quarter l Third Quarter Fourth Quarter j -
Year Gaseous Limits Dose Percent Dose Percent j Dose Percent i Dose Percent !
(mrem) of Limit , (mrem) of Limit j (mrem) of Limit ! (mrem) of Limit 1984 l 7.5 miem! organ!otr 8 46E-5' i 13E-3t 3 25E-5' 4 33E-4' 1 57E-3 2. 09E-2 1 5 57E-4 7 43E-3 j 15 mrem / organ /yr l 5 64E-4* 7. 81 E-d' * , t 12E-2* f 1 50E-2*
- (January - June maximum execsed organ c ose. 1.17 E-4 mremt)
(July - December maximum exposed organ dose: 2.13E-3 mrem)
(January - December maximum exposed organ dose: 2.24E-3 mrem) l: .
l First Quarter Second Quarter Third Quarter l:
Fourth Quarter j Year l Gaseous L.imits l Dose Percent Dose Percent Dose Percent Dose Percent i ! (mrem) of Limit (mrem) , of Limit (mrem) of Limit l (mrem)
. of Limit 1985 l 7 5 mrem /organiqtr i 1 01 E- 5' 1 3 5 E-4* 1 13E-4 1 SiE-3 ! 8 98E-3 120E-1 4 37E-4 5 83E-3 4
l 15 mrem /orgar>yr j 6 73E l 8 21 E-4*
l 6 07E-2* 6.36E-2*
- (January - June maximdin exposed organ dose
- 1.23 E-4 mrem) 4 (July - December maximum exposed organ dose: 9.42E-3 mrem) j (January - December maximum exposed organ dose: 9.54E-3 mrem) i l j j First Quarter l Second Quarter l Third Quarter l Fourth Quarter l l Year ! Gaseous Limits .: Dese Percent ! Dose Percent - 4 Dose Percent Dose Percent i ! j (mrem) of Limit I (mrem)' of Limit l (mrem) of Limit il (mrem) of Limit .
-d 1986 ! 7 5 rnrem/ organ /qtr ! 5 03E-5 6.71 E-4 j 1.53E-4t 2.04E-3t 7.56E-St 1.01 E-3t 2.85E-4' 3 80E-3?
j 15 mrem / organ /yr j 1 36E-3
- 1.86E-3
- 3 76E-3*
{ 3 35E-4 l (January - June maximum exposed organ oose: 2.03E-4 mrem)
(July - December maximum exposed organ dose: 3.61 E-4 mremt)
(January - December maximum exposed organ dose: 5 64E-4 mrem) a
~
q ; First Quarter j Second Quarter l Third Quarter i Fourth Quarter Year l Gaseous Limits i Dose Percent i Dose Percent Dose Percent Dose Percent
= } ! (mrem) of Limit j (mrem) of Limit (mrem) of Limit ll (mrem) of Limit 1
j 1987 7.5 mrem / organ!qtr 2 28E-2 3.04E-1 3 25E-3 4 33E-2 l 2.01 E-5 2 68E-4 0? Ot 1 i 15 mrem! organ /yr 1 52E-1 1 74E-1
- i 1. 74E-1
- 1 74E-1
- l 4
(January -June maximum exposed organ oose: 2.61E-2 mrem)
(July - December maximum exposed organ dose: 2.01E-5 mrem)
(January - December maximum exposed organ dose: 2.61E-2 mrem) 4 4
l
Corrections to Table 1: Gaseous and Liquid Doses (continued)
Year I
Gaseous Limits l{ ^
First Quarter Dose Percent l Second Quarter Dose j
Percent ! Dose
. Third Quarter Percent j Fourth Quarter Dose Percent l l (mrem)' of Limit (mrem) of Limit J (mrem) of Limit (mrem) of Limit i 1988 7.5 mrem /orgarvqtr 5 42E '7 23E-2 6 43E-2 8.57E-1 l 4 72E-3 6.29E-2 7.67E-3 1.02 E-1
- 15 mrem / organ /yr 3 61E-2 4 65E-1* l 4 96E-1* 5 47E-1*
l (January - June maximum exposed organ c ose: 6.97E-2 mrem)
- (July - December maximum exposed organ dose
- 1.24E-2 mrem)
(Jar uary - December maximum exposed organ dose: 8.21E-2 mrem) 4 4
l t
l First Quarter l Second Quarter ; Third Quarter l Fourth Quarter j Year Gaseous Limits Dose ! Percent i Dose Percent i Dose Percent Dose Percent i l (mrem)! of Limit
{ (mrem) of Limit ! (mrem) of Limit (mrem) of Limit 1989 7.5 mrem / organ /otr l 126E-3 168E-2 8 615E-3 8 20E-2 } i 08E 1 44E-1 8 2SE-3 1.10E-1 j 15 mrem / organ /yr l 8 40E-3 f 4 94E-2* i 1 21 E-1
- ll 1 76E-1 *
(January- June maximum exposed organ dose: 7.41 E-3 mrem)
(July - December maximum exposed organ dose: 1.91E-2 mrem) i (January - December maximum ex osed organ dose: 2.65E-2 mrem)
I
! First Quarter l Second Quarter Third Quarter l Fourth Quarter {
i Year I Gaseous Limits i Dose Percent . Dose I Percent i Dose l Percent i Dose Percent p
) l (mrem) of Limit j - (mrem) l of Limit ! (mrem) of Limit l (mrem) of Limit l 1990 " 7.5 mremio gan/att j 4 60E-3 613E-2 ,
192E-3 2 56E-2 i 3 04E4' 4 05E-3? 3 49E-4* 4 65E i 15 mrem / organ /yr j 3 07E-2 { 435E-2' ! 4 55E-2* 4 78E-2*
j' (January - June maximum exposed organ c ose: 6.52E-3 mrem)
! (July - December maximum exposed organ dose: 6.53E-4 mrem *)
i (January - December maximum exposed organ dose: 717E-3 mrem) 1-i
- No corr ection needed.
l
- Includes contribution from previous quarters.
l i
}
I k
..- ,--,,,--.- -._ - -.-.,_.~.- -.--.., . -, _ ..m...-.---,,_ - ,_.--.,_. _,_ _ _ - ,. , ,.--, _ _ -.,._ - - - --- - , , _ _
i Correctionsto Table 2: Gaseous Effluents-Summation of All Releases .
Section D -Tritium ,
l First Second Third Fourth -
l Quarter Quarter Quarter Quarter
~
1984 1. Total release Ci 1.60E - 1t O' 4.70E + 0 1.67E + 0
- . 2. Average release rate for period pCi/sec 2.04 E - 2t Ot 5.91 E - 1 2.10E - 1
- 3. Percent of quarterly limit % 1.13 E - 3 r 4.33 E - 4* 2.09 E - 2 7.43 E - 3 Percentof annuallimit % j 5.64 E - 4t 7.81 E - 4*
- 1.12 E - 2 * ;
1.50E - 2
- 1985 1. Total release Ci l 0* 3.39E - 1 2.68E + 1 4.35E - 1
- 2. Average release rate for period pCi/sec j Ot ;. 4.31 E - 2 3.37E + 0 5.47E-2
^
- 3. Percent of quarterly limit % 1.3 5 E - 4+ ! 1.51 E - 3 1.20 E - 1 5.83E-3 ,
Percentof annuallimit % 6.73 E - St j 8.21 E - 4
- 6.07E - 2
- l 6.36E - 2 *
! t
] 1986 1.' Total release Ci 1.51 E - 1 0* Ot Ot
- 2. Averace release rate for period pCi/sec 1.94E - 2 Ot Ot 0+
- 3. Percen't of quarterlylimit % 6.71 E - 4 2.04E - 3t 1.01 E-3t 3.80E Percent of annaullimit
% 3.35E - 4 1.3 6E - 3
- 1.86 E-3
- 3.76E - 3
- 1987 j 1. Total release Ci 4.63E + 1 7.97E + 0 5.79E - 2 0*
i
- 2. Average release rate for period pCi/sec 5.95E + 0 1.01 E + 0 7.28E - 3 Ot !
- 3. Percent of quarterly limit % 3.04E - 1 4.33 E - 2 2. 68E - 4 0- .
Percent of annuallimit % 1.52E - 1 1.74E - 1
- 1.74E - 1
- 1.74 E - 1
- t 1988 1. Total release n Ci 1.40E + 1 1.31 E + 2 1.60E + 0 !
3.93E + 0 i a
- 2. Average release rate for period pCi/sec 1.78E + 0 1.67E + 1 2.01 E - 1 4.94E - 1 i
, 3. Percent of quarterly limit % 7.23 E - 2 8.57E - 1 6.29 E - 2 1.02 E - 1 l
Percent of annuallimit l % 3.61 E - 2 4.65E - 1
- 4 4.96E - 1
- 5.47E - 1
- 1989 1. Total release Ci 2.30E + 0 2.74E + 0 I 4.94E - 1 4.96E + 0
- 2. Average release rate for period pCi/sec 2.96E - 1 3.48E - 1 6.21 E - 2 6.24E - 1 l
! 3. Percent of quarterly limit % 1.68E - 2 8.20 E - 2 1.44E - 1 1.10 E - 1
{ Percentof annuallimit j % 8.40 E - 3 4.94E - 2
- 1.21 E - 1
- 1.76E - 1 *
} 1990 1 Totalrelease . Ci 1.21E + 0 1.07E + 0 Ot 0+
! 2. Average release rate for period pCi/sec 1.56E - 1 1.36E - 1 Ot 0+ j
{ 3. Percent of quarterly limit % 6.13 E - 2 2.56E - 2 4.05E - 3* 4.65 E - 3t ,
! Percentof annuallimit % 3.07E - 2 4.35 E - 2
- 4.55E - 2
- j 4.78 E -2
- i tNo correction needed.
- Includes contribution from previous quarters. ;
I
, , , , - , , , _ . . . , , , . . - - . . - . - , . _ . . . . . _ _ . _ . . , , , , . . , _ _ - . - , _ . - . _ _ . . . ~ - . - - _ . , . . , . . . , , _ , . - - . _ . , . . . - , . . _ . _ - - _ - _ , _ . - - - . - . . , . . - - - _ _ , _ - - , - . - ,
l i
Corrections to Maximum Organ Dose, Paragraph 1, j Section E, Radiologicallmpact on Man ;
e i
I Dose Firs' Dose Second - Cummutative i Six Montas Six Months Annual Dose :
Year (mrem) ! (mrem) (mrem) !
t 1984 1.17E 4' 2.13 E - 3 2.24E - 3 1985 1.23E - 4 9.42 E - 3 9.54E - 3 1986 2.03E - 4 3.61 E - 4' 5.64 E - 4 1987 2.61 E - 2 2.01 E - 5 2.61 E - 2 1988 6.97 E - 2 1.24E - 2 8.21 E - 2 1989 7.41 E - 3 1.91E 2 2.65E - 2 1990 6.52E 3 6.53E 4' 7.17 E - 3 tNo correction needed.
,- - - , - ~ _ . - - , .r-.w,4 .--re-r-n--