ML20114C779

From kanterella
Revision as of 03:27, 17 May 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
VC Summer Nuclear Station Semiannual Effluent & Waste Disposal Rept for Operating Period 920101 Through 920630
ML20114C779
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 06/30/1992
From: Gowdy G, Rollins E, Gabe Taylor
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9209030215
Download: ML20114C779 (15)
v • d • e


Text

r.

. South Carolina Electric G Gas Company

. Virg!1 C. Summer Nuclear Station. Gary J. ?Oylof P.C. bon 68 General Menoger JenbnsvWe. 50 2906$ Nuclear operations SCE&G' lljjslsU me , -,-

August 31, 1992 U.-S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

Subject:

VIRGIL C. SUMMER NUCLEAR STATION DOCKET N0. 50/395 OPERATING LICENSE NO. NPF-12

. SEMI-ANNUAL EFFLUENT AND WASTE O!SPOSAL REPORT (SA 300)

Enclosed b the South Carolina Electric & Gas Company (SCE&G) Semi-Annual Effluent and Waste Disposal Report as required by 10CFR50.36a, Sections 6.9.1.8 and 6.14.2 of the Virgil C. Summer Nuclear Stat 9: Technical Specifications, anc Ection 1.6.2 of the Offsite Case Calculation Manual (00CM).

Should there be any questions, please contact us at your convenience.

Very truly yours, b'\U h 5k GaryJ. Taylor')DL t' id:lcd Enclosure

l. c: 0.--W. Dixon (w/o attachments)

R. R. Mahan.(w/o attachments)

-R. J. White S. D. Ebneter-G. F..Wunder General Managers NRC Resident Insoector J. B. Knotts-Jr.

HSRC RTS (SA 300) cile (818.02-1)-

l 1-

-- 300(19 -

NUCLEAR EXCELLENCE - A SUMMER TRADITION! l(

9209030215 920630

=

PDR ADOCK 05000395 I

-R PDR

l l

l SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT FOR THE OPERATING PERIOD January 1,1992 - June 30,1992 August 1992

/ _

s SCE&G g )j l

J V. C. SUMMER NUCLEAR STATION SOUTH CAROLINA ELECTRIC AND GAS COMPANY.

Prepared by:

$// OYW (J

,t -

~G.

Staff M/Gowdy,hysicist Health P i Reviewed and approved by: Reviewed and approved by:

lindwhb tal f'b D E Rolliris' . G. G. Hall, Associate Manager-Sr. aff Health Physicist Health Physics i Reviewed and approved by:

lIhulbst l W. R. Baehr, Manager .

Chemistry and Health Physics i._

.- - .- .- - - . -- - . - -. ~ -

SEMIANNUAL EFFLUEleT AND WASTE DISPOSAL REPORT January - June,1992 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 6.14.2 of Technical Specifications, Section 1.6.2 of the Offsite Dose Calculation Manual (ODCM) ar'd 10CFR50.36(a). Alsoincluded is an assessment of radiation doses from plant releases.

A brief discussion  ? Supplemental information and Tables 2 through 6 is presented in Sectio. . aough D. An evaluation of the radiologicalimpact on man due to operation of the ,ogil C. Summer Nuclear Station is presented in Section E and

- Table 1. Changes made to previous reports are presented in Section F and Appendix l.

A. SupplementalInformation Regulatory limits for doses and maximum permissible concentrations presented in Supplemental Information are from the Virgil C. Sum _mer Nuclear Station Technical Specifications and 40 CFR 190. As erage 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 Effluents 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. The errors for gaseous effluent totals are given as the sc,uare root of the sum of squares of counting errors ar.d flow or volume measurement errors.

A systematic error of 15% has been added to estimate total error. Cumulative doses are discussed in Section E.

C. Liquid Ef fluents liquid effluents are summarized in Tables 4 and S. 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. RadiciogicalImpact on Man Potential doses to the maximum exposed individual in the unrestricted area were calculated using measured plant gaseous effluent and meteorological cata in accordance with the Offsite Dose Calculation Manual. The source term included four (4) waste gas decay tank (WGDT) batch releases,1.45 days of 6-inch and 4.77 days of 36-inch Reactor Building purge releases and a

, continuous six month main piant 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

SEMIANNUAL EFFLUENT AND WASTE DISPGSAL REPORT January - June,1992 Virgil C Summer Nuclear Station South Carolina Electric & Gas maximum exposed individual due to noble gases were 2.09E-2 and 5.41E-2 mrad for gamma und beta, respectively. The maximum organ dose attributed to the releases was 3.66E-3 mrom for the six month ceriod.

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 201 Waste Monitor Tank batch releases,34.3 days of Steam Generator Blowdown release and a continuous Turbine Building Sump release. Doses are summarized in Table 1 and total radioactivity released is described in Tables 4 and 5. The total body dose to the maximally exposed individual due to the release of radioactive liquid was 1.08E-2 mrem. The maximum organ dose was 3.01E-2 mrem to the thyroid during the six month period.

Table 1 GASEOUS AND LIQUID EFFLUENT DOSE

SUMMARY

First Quarter,1992 Second Quarter,1992 O M Gaseous Limits Se t on P

  • I'* ".t Percen,t Dose Dose of Limit of Limit 1.2 3.la,b 5 mrad gan.ma/qtr. 6 76E-3 mrad 1. 35 E- 1 1.41E-2 mrad 2.82 E- 1 10 mrad gamma /yr. 6.76E-2 2. 09 E- 1 *

(January-June total gamma air dose: 2.09E-2 mrad) 1.2.3 t a,b 10 mrad na/qtr 1.61 E-2 mrad 1.61 E- 1 3.80E-2 mrad 3.80E-1 20 mrad betalyr. 8 05E-2 2.71 E-1 *

(January-June total beta air dose: 5.41 E-2 thrad) 1.2.4. l a,b 7 5 mrem /orgars/qtr 7.93E-4 mrem 1.06E-2 2.87E-3 mrem 3 83E-2 15 mrem / organ /yr. 5.29E-3 2.44 E-2 *

(January-June maximum exposed organ dose: 3.66E-3 mrem)

Liquid Limits 1.1.3. la b 1.5 mrem /qtr. 1.89E 3 mrem 1.26E-1 8 93E-3 mrem 5.96E-1 3.0 mrem /yr. 6.30E-2 3.61 E-1 *

(January-June whole body dose: 1.08E-2 mrem) 1.1.3 la,b 5 mrem / organ /qtr. 6 97E-3 mremt 1.39E 1 2.32E-2 mremt 4 63E-1 em/ organ /yr. 6 97E-2 3.01E 1 *

(January-June maximum exposed organ dose: 3.01E-2 mremt)

!

  • Includes contribution from previous quarters.

t Maximum organ dose for quarters 1 and 2 was to the thyroid.

Page 2 i

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1992 Virgil C. Summer Nuclear Station South Carolina Electric & Gas Dose rates and concentrations were below the limits specified in Supplemental information, Section 2a, b and c during all the ef fluent releases.

Radiation doses from radioactive effluents to workers at the Fairfield Hydro Station were calculated for the six-month period to be *,.90E-3 and 4.88E-3 mrad for gamma and beta, respectively.

Radiation doses from nearby uranium fuel cycle sources were not assessed.

ODCM, Sections 1.3.1 and B/1.3 establish a five (5) mile limit beyond vs hich doses from nearby plants are insigr.'ficant. There are no uranium fuel c/cle plants within a five (S) mile radius of Virgil C. Sumnier Nuclear Station.

F. Offsite Dose Calculation Manut.l The ODCM was not revised during the affected six month period.

l Page 3

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1992 Virgil C. Summer Nuclear Station South Carolina Electric & Gas SupplementalInformation

1. Regulatory Limits;
a. Fission and Activation Gases:

The air dose in individual due to noble gases teleased in gascous effluents shall be liniited to less than or equal to 5 mrad for gamma radiation and 10 mrad for beta radiation durino any calendar quarter and 10 mrad for gamma radiation and 20 mrad for beta radiation during any calendar year (ODCM, Scction 1.2.3.1).

b lodines, Particulates (half-lives > 8 days) and Tritium:

The dose to an individual from radiciodines,intium and radioactive materials in particulate form with half-lives greater than 8 days in gaseous of fluents shall be limited to less than or eciual to 7.5 mrem to any organ during any calendar quarter and 15 mrem to any organ during any calendar year (ODCM, Section 1.2.4.1).

c. Liquid Effluents:

/

The dose or dose commitment to an individuct from radinactive materials in liquid effluents released shall be !!mited to less than or equal to 1.5 mrem to the total body and 5 mrem to any organ during ariy calendar qucrter and 3 mrem to the total body and 10 mrem to any organ during any calendar year (ODCM, Section 1.1.3.1),

d. All Sources:

7 j'- The annual dose equivalent shall not exceed 25 mrem to the whole body,75 mrem to tne thyroid and 25 mrem to any other organ (40 CFR 190).

2. Maximum Permissible Concentrations:
a. Fissior 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 equal to 3000 mrem / year to the skin (ODCM, Section 1.2.2.1).

lodines, Particulates (half-lives > 8 days) and Tritium:

The dose rate in unrestricted areas due to radioactive maxrials in

,; eifluents shall be limited to less than or equal to 1500 mrem / year to any organ (ODCM, Section 1.2.2.1).

Page 4

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1992 Virgil C. Summer Nuclear Station South Carolina Electric & Gas Supplementalinformation

c. Liquid Effluents:

The concentration of radioactive materials released from the site shall be limited to the concentrations specified ?n 10 CFR 20,-

Appendix B, Table 11, Column-2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be timited to 2E-4 pCi/ml total activity (ODCM, Section 1.1.2.1).

3. Averaoe Energy:

Not Applicable

4. Measurements and Approximations of Total Radioactivity:
a. Fission and activation gases: Gamma spectrcmetry [Ge(Li) or HPGe]

! b lodines: Gamma spectrometry [Ge(Li) or HPGe]

L

c. Particulates: Gamma spectrometry [Ge(Li) or HPGe], beta propor-tional counting, elpha proportional counting
d. Tritium: Liquid ;cintillation
e. Liquid effluents: Gamma spectrometry [Ge(Li) or HPGe], liquid scintillation (H-3), beta proportional counting,
alpha proporttonal counting
5. Batch Releases:
a. Gaseous:

l

1. Number of batch releases: 4

?. Total time period for batch releases: 1.02E + 3 min.

3. Maximum time period for a batch release: 3.97E + 2 min.
4. Average time period for a betch release: 2.54E + 2 min.

S. Minimum time period for a batch release: 1.50E + 1 min.

b. Liquid:
1. Number of batch releases:

98 for first quarter,1992 103 for second quarter,1992 PageS l

SEMlANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1992 Virgil C Summer NuclearStation South Carolina Electric & Gas Supplementallnformation

2. Total time period for batch releases:

7.27E + 3 min. for fi6st quartc r,1992 7.88E + 3 min.for second qua rter,1992 1

3. Maximum time period for a batch release: I 8.80E + 1 min. for first quarter,1992 l 9.60E & 1 min for second quarter,1992 l
4. Average time period for batch releases:

7.42E + 1 min. for first quarte,,1992 7.65E + 1 min for second quarter,1992

s. Minimum time period for a batch release:

4.50E + 1 min, for first quarter,1992 5.40E + 1 min, for second quarter,1992

6. Average stream' flow during periods of release of effluent into a lowing stream:

2.85E + 6 gpm.for first quarter,1992 3.51E + 6 gpm for second quarter,1992

6. Abnormal Releases.
a. Gaseous:
1. Number of releases: 0
2. Total activity released: 0
b. Liquid:
1. Numberof releases: 0
2. Total activity released: 0 i

Page 6 l-

, SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1992 Table 2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES First Second Est. Total Quarter Quarter Error, %

A. Fission & actiaation gases

1. Totai release Ci 8.12 E + 1 1.96E + 2 2.92 E + 1 2.' Average release rate for period pCi/sec 1.01E + 1 2.50E + 1 l3. Percent of technical speafication limit  %

B. lodines

1. Total iodine-131 Ci 4.12 E-5 1.45E-4 2.66E + 1
2. Average release rate for period pCi/sec 5.30E-6 1.84 E-5
3. Percent of technical specification limi; ** **

C. Particulates .

1. Particulates with half-lives > 8 days Ci 0 0 N/A 2 Average release rate for period pCi/sec 0 0
3. Percent of technical specification limit  % ** **
4. Gross alpha radioactivity Ci 0 0 D. Tritium L 1. Total release Ci 0 2.4 /E-1 3.09E + 1
2. Avarage re! ease rate for period pCi/sec 0 3.14 E-2
3. Percent of technical specification limit  % ** **

Calculated as a percent of dose limits found in SupplementalInformation, Section la. First c uarter values were 1.35E-1% and 6.76E-2% of the quarterly and cumulative annual gamma c ose limits, respectively and 1.61E-1% and 8.0SE-2% of the quarterly and cumulative annual beta dose limits, respectively. Second quarter values were 2.82E-1% and 2.09E-1%t of the quarterly and cumulative anr.ual gamma dose limits, respectively, and 3.80E-1% and

. 2.71E-1%t of the quarterly and cumulative anneal beta dose limits, respectively.

Calculated as a percent of dose limits found in SupplementalInformation, Section 1b. The l sum of these values for the first quarter was 1.06E-2% and S.29E-3% of the quarterly and cumulative annual organ dose limits, respectively. The sum of these values for the second quarter was 3.83E-2% and 2.44E-2%t of the quarterly and cumulative annual organ dose limits, respectively.

t . Note: Second quarter values are the sum of the first and second quarter values compared L to annual dose limits.

L

~

p Page 7 l

3 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1992 Table 3 CASEOUS EFFLUENTS-GROUND LEVEL RELEASES Continuous Mode Batch Mode First Second First Second Nuclidas Released Unit Quarter Quarter Quarter Quarter

1. Fission gases Krypton-85 Ci 0 0 1.05 E- 1 7.73 E- 1 Krypton-85m

~

Ci 0_ .

5.17 E-2 0 0 Krypton-87 Ci 0' 0 0 0 Krypton-88 Ci 0 1.18 E-3 0 0 Xenon-133 Ci 7.37E + 1 ' 85E + 2

. 2.12 E-4 2.09E-1 Xenon-135 C:' 7.41 E + 0 7.77E + 0 7.74E 6 5.13 E-5 Xenon-135m C 'O ') 0 0 Xenon-138 Ci ~ ~ ' ' '

0 0 0 0 Others: Ar-41. Ci O 1.64 E-2 0 0 Xe-131m Ci 0 9.00E-1 0 1.3 5 E-2 ~

Xe-133 n Ci 0 1.62E + 0 0 1.83 E-4 Unidentified Ci 0 0 0 0 Total for period Ci 8.11 E + 1 1.95E + 2 1.05 E-1 9.95 E- 1

~

2. lodines lodine-131 1-Ci 4.12 C-5 1.45 E-4 0 0 lodine-132 - ~

Ci 0 0 0 0 t lodine 133 Ci 1.43 E-6 1.38 E-5 0 0 l lodine-134 Ci 0 0 0 0 lodine-135 Ci 0 0 0 0 Total for period Ci 4.2 6 E-5 1.59 E-4 0 0

3. Peruculates 1 ontium-89 Ci o 0 l 0 0 Strontium-90 ~

1 Ci 0

~

0 0 0 Cesium 134 Ci 0 0 0 0 Cesium-137 Ci 0 0 0 0 Barium-Lanth.-140 Ci 0 0 0 0 Others: Br 82 Ci 0 330E-7 0 0 Rb-88 Ci 0 5.23 E-6 0 0

Unidentified Ci 0 0 0 0 Total for period l Ci 0 5.61 E-6 0 0 l

l-Pege 8

~ ,. - - - -- .- -- . .- _ _. .

I

~

. SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT 4 January - June,1992 Table 4 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES First Second Est. Total A. Fission & activation products

1. Total release (not including tritium, gases, Ci 7.04E-2 7.14 E-2 1.83E 1

-alpha) u

2. Average diluted concentration / ing pCi/mi 1.91 E-10 1.68 E-10 period
3. Percent of applicable limit  % * *
8. Tritium
1. Total release Ci 6.50E + 1 l 1.41 E + 2 1.86E + 1
2. Average diluted concentration during pCi/mi 1.76E 7 3.31 E-7 period 3.PC cent of applicablelimit  % *
  • C. Dissolved and entnined gases
1. Total release Ci 2.92E-2 2.31 E- 1 1.81 E + 1
2. Average diluted concentration during pCi/mi 7.93 E-11 5.44 E- 10 period
3. Percent of applicable limit  % *
  • D. Gross alpha radioactivity
1. Total release - Ci 0 0 N/A E. Volume of waste released (prior to dilution) liters 2.04E + 7 4.28E + 7 3.00E + 0 F. Volume of dilution water used during

- period liters 3.68E + 11 4.25E + 11 4.30E + 0 l: ' See following page.

Page 9

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1992 Table 4 LIQUID EFFLUENTS-5UMMATION OF ALL RELEASES Calculated as a percent of dose limits found in Supplemental in,ormation, Section 1c. The sum of these values for the first quarter was 1.26E-1% and 6.30E-2% of the respective i-quarterly and cumulative annual whole body dose limits and 1.39E 1% and 6.97E-2% of the respective quarterly and cumulative annual organ dose limits. The sum of these values for the second quarter was 5.96E-1% and 3.61E 1%1 of the respective qua.terly and cumulative annual whole body dose limits and 4.63E-1% and 3.01E 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, second quarter and first six (6) months of 1992, t

Note: Second quarter values are the sum of the first and second quarter values compared to

annual dose hmits n

z_ _

Page 10 L . _ . _ . ._ - - - - - --- - - ~ - - - - - - - - -

- ~

  • SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1992 Table 5 j LIQUID EFFLUENTS l Continuous Mode Batch Mods First Second First Second tNuclides Released Unit Quarter Quarter Quarter Quarter 4

Strontium 89 Ci 0 0 5.71E-7 1.00E-5 Strontium-90

~

Ci 0 0 S.28E-7 9.24 E-6 Cesium 1.,4 Ci 0 1.68 E-4 3.71 E-4 2.55E-3 Cesium-137 Ci 0 4.12 E-4 5.43E-4 4.38E-3 lodine-131 Cl 1.77 E-3 8.72 E- 3 3.94 E-3 5.51 E-3 ~l Cobalt-58 Ci 0 0 3.33 E-2 9. 38 F- 3 Cobalt-60 Ci 0 0 1.3 8 E-2

~

1.1 IET~

Iron-59 Ci 0 ___

C 1. 72 E-4 4.04E-6 Zinc-65 C 0 0 0 4.00E-5 Manganese-54 Ci 0 0 1:,sa-3 1.41 E-3 Chromium 51 Ci 0 0 l S.3 3 E-4 1.86 E-4

' Zirconium Niobium-95 Ci 0 0 8.93 E-4 1.22 E -3 Molybdenum 99 Ci a 0 0 2. 20E-5 7echnetium-99m Ci 0 0 3 23E-5 ' 1.67 E-4 Barium-Lanth.140 Ci 0 ~0 1.80E-5 2.36E-5 Cerium-141 Ci 0 0 0 0 Other: F- 18 Ci 1.08 E-3 4. 'i 3 E-3 0 0 Na-24 Ci 4. 79 E-4 3.06E-3 4.68E-5 1'. 67 E -4 Fey 5 C 0 0 4.18E-4 139E-3 Co-57 Ci 0 0 1.99E-4 9.98E-5 2n-69m Ci 0 0 2.43 E-6 0 As-76 Ci 0 0 0 3.15 E-6

'~

Ru-103 Ci 0 0 0 7.95 E-7 Ru-106 Ci 0 0 8.44E-6 0 Aq-110m Ci 0 0 7.21 E-6 1.34 E -4 Sn-113 Ci 0 0 9.60E-6 9.09E-6 Sb-124 C 0 0 1.92 E-4 7.64E-6 S b-125 Ci 0 0 7.46E-3 4.74E-3

~

1 132 Ci 5 62E-4 1.915-3 0 0 1-1.3 Ci 1.8 5 E-3 6.24E-3 1.73 E-4 2.26E-4 l

  • 34 Ci 1.66E-4 6.23 E-4 0 0 1-135 Ci 8.51 E-4 3.

2.26E ? '

O O Cs-136 Ci 0 9.9 7 E-5 0 5.46E-6 Cs-138 Ci 4.90E-6 2.3 7 E-4 0 0 Ce-144 Ci 0 0 4.17 E-6 1.84E-5 Unidentified Ci 0 0 0 0 Total for period (above) Ci 6.77E-3 2.79E-2 6.37E-2 4.3 5 E-2 Fage 11

, , SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June - 1992 Table 5 (continued)

LIQUID EFFLUENTS C intinuous gde Batch Mode First Seco.d First Second

-TNuclides Released Unit Quarter Quarter Quarter Quarter Xenon-133 Ci 3.43E-3 1.62 E-3 2.51 E-2 2.24E-1 Xenon-135 Ci 5.32 E -4 3.2 8 E-4' 1.18E-5 1.56E-5

,e Other: t' r-8 5 m C 4.62 E-5 0 9.3?C 7 2.01 E-5 Xe-131m Ci 0 0 6.47E-5 d.'66E-3 Xe-133m Ci 0 0 1.11 E-5 6.40E-4 Total entrained gases Ci 4.01E 3 1.95 E-3 -

2.52 E-2 2.29E-1 i Tritium not included. See Table 4 for truium numbers.

r l

Page 12

~. . , .,. ..

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT l

l January - Ju ne,1992 Table 6 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid Waste Shipped Of fsite for Burial or Disposal (Not irradiated fuel)

1. Type of waste Unit 6 month Est. Total Penod Error,%
a. Spent resins, hite. sludges, evaporator m' 6.92 E + 1 bottoms, etc. Ci 1.94E + 2 3.50E + 1
b. Dry compressible waste, contaminated m' 1.24E +I equip , etc. Ci 8.07E 1 3.50E + 1
c. Irradiated components, control rods, etc. m' O Ci 0 N/A d.O the,- (d escribe) m3 0 Ci 0 N/A
2. Estimate of major nuclide composition (by type of waste)
a. Fe-55  % 2.20E + 1 Cs-137 1.7 E + 1 Ni-63  % 1.62 E + 1 Cs-134  % 1.51 E + 1 Co-60  % 1.43 E + 1 Co-58  % 1.03 E + 1 Mr54  % 2.60E + 0
b. Fe SS  % 4.12 E + 1 Co-60  % 1.99E + 1 5 -137  % 1.39 E 1 Cs-134  % 8.29E + 0 Ni-63  % 6.90E + 0 Mn-54  % 2.69E + 0 H-3  % 1.60E + 0 Co-58  % 1.57E + 0
c. None  % N/A
d. None  % N/A
  • All nuclides with concentrations above 1.0% are listed in descending order by activity level.
3. Solid V.'a$te Disoosition (6 month oeriod)

Number of Shipments Mode of Transportation Destination

~

451 Truck Barnwell, SC tNote: 38 of these are partial shipments of DAW from waste processor to Barnwell, SC.

B. Irraciated Fuel Shipments (Discosition)

Number of Shipments Mode of Transportation Destination None N/A N/A Page 13

___ - _-_ - ___ - __ ____-. - - - - - _ _ _

Retrieved from "https://kanterella.com/w/index.php?title=ML20114C779&oldid=2810103"