ML20153D656
| ML20153D656 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 06/30/1988 |
| From: | Baehr W, Blue L, Gowdy G SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML19297G864 | List: |
| References | |
| NUDOCS 8809020276 | |
| Download: ML20153D656 (15) | |
Text
_ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT P
FOR THE OPERATING PERIOD January 1,1988 - June 30,1988 August 22,1988
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1 dd V. C. SUMMER NUCLEAR STATION SOUTH CAROLINA ELECTRIC AND GAS COMPANY Prepared by:
0 1
G.M/Gowdy,(J Staff Health Physicist Reviewed and a proved by:
Reviewed and approved by:
W3b[_
s
. A. Blue, Manager W. R. Baehr, Manager Corporate Health Physics and Chemistry and Health Physics Environmental Programs 8809020276 000G29 DR ADOCK 050w 5
~. -.
SEMIANNUAL EFFLUENT AND WASTE DISPSSAL REPORT January. Juno,1988 Virgil C. Summer Nuclear Station South Carolina Electrie, & Gas This report is being submitted as a summary of the qJantities 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 assessmect of radiation doses from plant releases.
A brief discussion of the Sup alemental Information and Tables 1 and 3 through 7 is presented in Sections A 11 ough 0. An evaluation of the, radiological impact on man due to operation of the Virgil C. Summer Nuclear Station is presented in Section E and Table 2. Changes made to the Process Control Program are presented in Section F. Corrections to previous reports are given in Section G. Abnormal releases are detailed in Section H.
A.
Supplementalinformation Regulatory limits for doses and maximum permissible concentrations presented in Sup alementalInformation are from the Virgil C. Summer Nuclear Station Technica 5,necifications and 40 CFR 190. Average energy (E) is not applicable to the method for determining release rate limits for fission and activation gaseous effluents; therefore,it has been omitted.
B.
Gaseous Effluents Gaseous effluents released from ground tevel are summarized in Tables 3 and 4. An elevated release pathway does not exist at VirgJ C. Summer Nuclear Station. Cumulative doses are discussed in Section E.
The errors for gaseous effluent 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 1584 has been added to estimate total error.
C.
Liquid Effluents Liquid effluents are summarize:d in Tables 5 and 6.
Estimated total errors are expressed as in Section B sbove.
D.
Solid Waste Shipments Solid waste shipments are summarized in Table 7.
No waste was shipped during this reporting period (also see Table 1).
Table 1 SOLID WASTE SHIPMENTS NO SHIPMENTS WERE M ADE JANUARY 1 - JUNE 31,1988.
Page 1
SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1988 Virgil C. Summer Nuclear Station South Carolina Electric & Gas E.
Radiological Impact on Man Potential doses to the maximum 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 were five (5) waste gas batch releases,5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of Reactor Building aurge releases (6 inch line), releases from PORV's and the Terry Turbine, anc a continuous six month main plant vent release. Doses are summarized in Table 2. The total curies released are presented in Tables 3 and
- 4. Air doses to an individual due to noble gases were 1.37E 2 and 1.43E 2 mrad for gamma and beta respectively. The maximum organ dose attributed to the releases was 2.22E 2 mrem for the six month period Measured plant liquid effluent data was used to calculate estimates of doses to indiviouals in accordance with the Offsite Dose Calculation Manual.
The source term consisted of thc isotopic contents of five (5) Nuclear Slov down, one (1) Condensate Demineralizer Backwash (CDBWT),231 Waste Mor itor Tank liquid effluent batch releases and continuous Turbine Building Sump and Steam Generator Blowdown releases. The CDBWT release was al',1ormal and is detailed in Section H. Doses are summarized in Table 2. The tatal radioactivity released is described in Tables 5 and 6. The total body dose to the maximally exposed individual due to the radioactive liquid released was 1.33E 1 mrem. The maximum organ dose was 1.73E 1 mrem to the Liver.
Table 2 GASEOUS AND LIQUID DOSES First Quarter,1988 Seccnd Quarter,1988 C
Gaseous Limits ect Percent Percent Dose Dose of Limit of Limit 3.11.2.2o b 5 mrad gamma /qtr 1.22E 2 mrad 2.45E 1 1.46E 3 mrad 1.37 E-1
- 10 mrad gamma /yr.
(January June total gamma air dose: 1.37E 2 mrad) 3.11.2.2a,b 10 mrad beta /qtr.
1.07E-2 mrad 1.07E 1 3.60E-3 mrad 7.13 E-2
- 20 mrad betatyr.
(January June total beta air dose.1.43E 2 mrad) 3.11.2.3 a,b 7 5 mre.m/argan'qtr.
8.26E 4 mrem 1.10 E-2 2.13E 2 mrerr, 1.48E 1
- 15 mrem / organ /yr.
(January-June maximum exposed organ dose: 2.22E 2 mrem)
- Includes contobution from previous quarters.
Page 2
SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January. June,1988 Virgil C. Summer Nuclear Station South Carolina Electric & Gas Table 2 (continued)
First Quarter,1988 Second Quarter,1988 Tech Spec Liould Limits Section Percent Percent Dose Dose of Limit of Limit 3.11.1.2a,b 1.5 mrem /qtr.
5.42E 2 mrem 3.49E0 8.11E 2 mrem 4.45E-2*
3.0 mrem /yr.
(January June whole body dose: 1.33E 1 mrem) 3.11.1.2 a,b 5 mrem / organ /qtr.
6.78E 2 mrem 1.36E0 1.05E-1 mrem 1.73 E-2
- 10 mrem / organ /yr.
(January Juna maximum exposed organ dose: 1./3E 1 mrem)
- Includes contribution from previous quarters.
Dose rates and concentrations were below the limits specified in Supplemental Information, Section 2a, b and c during all the effluent releases.
Radiation doses from radioactive effluents to workers at the Fairfield Hydro Station were determined to be 1.87E 3 and 1.95E 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 3/4116 establishes a five (5) mile limit beyond which doses from nearby plants are insignificant.
There are no uranium fuel cycle plants within a five (5) mile radius of Virgil C.
Summer Nut. lear Station.
F.
Process Control Program The Virgil C. Summer Nuclear Station (VCSNS) Process Control Program (PCP) was modified three (3) times during the affected six month period.
Revision 7 (4/13/88) was used to update the PCP to incorporate the changes to the Chem Nuclear Systams, Inc. (CNSI) attachments made to Revision 6 (and Changes A E) of the manual (detailed in previous reports). CNSI procedures no longer used were deleted from the attachments. Procedures de;eted included those for dewatering a 24 inch demineralizer vessel containing free-standing water, for installing closure cans on 24 incb HIC's, and providing operating guidelines for use of fiberglass reinforced plastic HIC's. In addition, Attach-ment I to the PCP was updated to reflect CNSI operating changes in dewatering for CNSI 14 215 or smaller liners. Revision 7, Change A (5/4/88) l involved replacing PCP Attachment IV with an updated version reflecting the discontinuation of the use of 1/4 inch thread and the change in the butress lid I
rotation from 360 degrees to 180 degrees in polyethylene HIC's. Revision 7 j
Change B (6/29/88) required that PCP Attachmen'. IV, Appendix D be changed Page 3 i.
I L
SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January Jun3,1988 Virgil C. Summer Nuclear Station South Carolina Electric & Gas to reflect a change in the list of materials not compatible with polyethylene HIC's. Also PCP Attachment ll1 was changed to allow for solidificat,on of LOMI i
at VCSNS. The overall conformance of the solidified waste product to existing criteria for solid wastes has not been adversely affected by the changes incorporated in the VCSNS PCP. Per Technical Specification requirement 6.13.2.1.c, the PSRC has reviewed and approved the revisions which are enclosed as Attachment 1. See the changes and each Procedure Development Form - A,Section IX, for the PSRC approval signatures.
G.
Corrections to Previous Reports in the last Semiannual Effluent and Waste Disposal Report (July December,1987),
one revision to the PCP was inadvertently omitted. Revision 6, Change E (11/25/87) involved adding CNSI procedure FO-OP 014, Rev. F as Attachment IX to the PCP. This procedure provides guidelines for installing closure cans on 24 inch diameter fiberglass reinforced plastic High Integrity Containers. This attachment and the Proceeure Development Form A containing the PSRC approval signature (Section IX) are exhibited in Attachment ll. No other sections of the report are affected by these changes.
H.
Abnormal Release On June 9,1988 an Auxiliary Building operator pumped 7430 gallons of water and resin from the Condensate Demineralizer Backwash Receiver Tank (CDBWT) to the Alum Sludge Lagoon prior to issuance of the release permit. Note that this is a normal release path but a release permit is required before discharge can occur. Analyses of the CDBWT contents before and after the release indi:ated the presence of H 3 at a concentration of 3.9 t 2.2E 6 pCi/ml. The previous quarterly Fe-55 analysis of CDBWT contents also indicated the presence of Fe 55 at a concentration of 4.110.6E-7 pCi/ml. Total activity released was 109 pCi H 3 and 12 pCi Fe 55. Doses to the publicwere calculated to be 3.4E-exposed individual.y and 1.3E 7 mrem to the critical organ (bone) of the maximum 8 mrem whole bod data for this report.
r l
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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REP 8RT January June,1988 Virgil C. Summer Nuclear Station South Carolina Electric & Gas SupplementalInformation 1.
Regulatory Limits; 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 radiation and 10 mrad for beta radiation during any calendar quarter and 10 mrad for gr.mma radiation and 20 mrad for beta radiation during any calendar year (Technical Specifications, Section 3.11.2.2).
b.
lodines, Particulates (half. lives > 8 days) and Tritium:
The dose to an individual from radioiodines, tritium and radioactive materials in particulate form with half lives greater than 8 days in gaseous effluents shall be limited to less than or equal to 7.5 mram to any organ during any calendar quarter and 15 mcem to any organ c' aring any calendar year (Technical Specifications, Section 3.11.2.3).
c.
Liquid Effluents:
Tl e dose or dose commitment to an individual from radioactive materials illiquid effluents released shall be limited to less than or ec ual to 1.5 mrem to the total body and 5 mrem to any organ during any ca endar quarter and 3 mrem to the total body and 10 mrem to any organ during any calendar year (Technical Specifications, Section 3.11.1.2).
d.
All Sources:
The annual dose equivalent shall not exceed 25 mrem to the whole body,75 mrem to the thyroid and 25 mrem to any other organ (40 CFR 190).
2.
Maximum Permissible Concentrations:
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 e skin (Technical Specifications, Section 3.11.2.1) qual to 3000 mrem / year to the b.
todines, Particulates (half-lives > 8 days) and Tritium:
The dose rat s in unrestricted areas due to radioactive materials in effluents shall be limited to less than or equal to 1500 mrem / year to any l
organ (Technical Specifications, Section 3.11.2.1).
PageS
SEMIANNUAL EFFLUENT AND WASTE DISPSSAL REPORT January June,1988 Virgil C. Summer Nuclear Station South Carolina Electric & Gas Supplementallnformation C.
Liquid Effluents:
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 entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 uCi/ml total activity (Technical Specifications, Section 3.11.1.1).
3.
Average Energy:
Not Applicable 4.
Measurements and Approximations of Total Radioactivity:
2.
Fission and activation gases: Gamma spectrometry (Ge(Li) or HPGe]
b.
todines: Gamma spactrometry (Ge(Li) or HPGe]
c.
Particulates.
Gamma spectrometry [<a(Li) or HPGe], beta propor-tionalcounting, alpha,.oportionalcounting d.
Tritium: Liquid scintillation Liquid effluents. Gamma spectrometry [Ge(Li) or HPGe), liquid e.
scintillation (H 3), beta proportional counting, alpha proportional counting 5.
Batch Releases:
a.
Liquid:
1 Number of batch releases:
116 for first quarter,1988 121 for second quarter,1988 2.
Total time period for batch releases:
l 6.59E3 min. for first quarter,1988 7.54E3 min, for second quarter,1988 3.
Maximum time period for a batch release:
l 75 min. for first quarter,1988 1
75 min. for second quarter,1988 l
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1 1
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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1988 Virgil C. Summer Nuclear Station South Carolina Electric & Gas Supplementallnformation 4.
Average time period for batch releases:
57 min. for first quarter,1988 62 min. for second quarter,1988 5.
Miriimum time period for a batch release:
13 min. for first quarter,1988 45 min. for second quarter,1988 6.
Average stream flow during periods of release of effluent into a flowing stream:
3.38E + 6 gpm for first quarter,1988 3.72E + 6 gpm for second quarter,1988 b.
Gaseous:
1.
Number of batch releases: 5 2.
Total time period for batch releases: 7253 min.
3.
Maximum time period for a batch release: 1815 min.
4.
Average time period for a batch release: 1451 min.
Minimum time period for a batch release: 990 min.
2.
6.
Abnormal Releases:
a.
Uquid:
1.
Number of releases:
1 2.
Total activity re! eased: 1.2F 1 mci b.
Gaseous:
1.
Number of releases 0
2 Total activity released: 0 1
Page 7 l
SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1988 Table 3 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES First Second Est. Total Quarter Quarter Error, 86 A. Fission & activation gases
- 1. Total release Ci 3.68E + 1 1.86E + 1 1.71 E + 1
- 2. Average release rate for period uCi/sec 4.66E0 2.23E0
- 3. Percent of technical specification limit 86 B. lodines
=
1.Totaliodine 131 Ci 4.90E 5 1.48E 3 1.73E + 1
- 2. Average release rate for period uCi/sec 6.20E 6 1.78E 4
- 3. Percent of technical specification limit C. Particulates
- 1. Particulates with half-lives > 8 days Ci 1.10E 9 3.28E 5 1.80E + 1
- 2. Average release rate for period uCi/sec 1.39E-10 3.94E 6
- 3. Percent of technica',pecification limit 86
- 4. Gross alpha radioactivity Ci 0
0 D. Tritium
- 1. Totai release Ci 1.40E 1 1.31 E0 2.22E + 1
- 2. Average release rate for penod uCi/sec 1.77E 2 1.57E 1
- 3. Percent of technical specificatier limit Calculated as a percent of dose limits found in Su aplementalinformation, Section la. First quarter values were 2.45E 1*i, and 1.22E 1% o" the quarterly and cumulative annual gamma dose limits, respectively and 1.07E 186 and 5.35E 2% of the quarterly anc cumula-tive annual beta dose limits, respectively. Second quarter values were 2.92E-2% and 1.37E-18 of the quarterly and cumulative annual gamma dose limits, resnectively, and 3.60E 2%
and 7.13E 2ao of the quarterly and cumulative annual beta dose limits. respectiveiy.
Calculated as a percent of cose limits found in SupplementalInformation, Section 1b. The sum of these values for the first quarter was 1.10E 2% and 5.50E 3% of the quarterly and cumulative annual organ dose limits, respectively. The sum of these values for the second quarter was 2.84F 1% arid 1.48E-186 of the quarterly and cumulative annual organ dose limits, respectively.
Page 8
SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1988 Table 4 GASEOUS EFFLUENTS GROUND LEVEL RELEASES Continuous Mode Batch Mode First Second First Second Nuclides Released Unit Quarter Quarter Quarter Quarter I. Fission gases Krypton-85 Ci 0
1.24E 1 4.71 E 2 0
Krypton 85m Ci 1.66E0 1.13E 2 1.12 E 3 0
Krypton 87 C
0 5.89E-4 7.17E 5 0
Krypton 88 Ci 2.55E0 9.85E 3 1.19E 3 0
Xenon 133 Ci 1.50E + 1 170E + 1 4.28E0 0
Xenon 135 Ci 1.31 E + 1 1.24 E0 2.00E 2 0
Xenon 135m Ci 0
0 0
0 Xenon 138 Ci 0
0 0
0 Others. Argon 41 Ci 0
1.04E 2 0
0 Xenon 131m Ci 0
9.20E-2 7.42E 2 0
Xenon 133rn C
0 8.71 E-2 2.63E 2 0
Unidentified Ci 0
0 0
0 Total far period Ci 3.23E + 1 186E + 1 4.45 E0 0
- 3. lodines l
lodine-131 Ci 4.90E 5 1.48E 3 0
0 lodine 132 Ci 1.28E 5 1.73E 4 0
0 lodine 133 Ci 8.12 E 5 7.35E 4 0
0 To"8Ine 134 Ci 0
2.10E 6 0
0 lodine-135 Ci 0
3.20E 6 0
0 Total for period C
1.43E 4 2.39E 3 0
0
- 3. Particulates 5trontium-89 C.:
0 0
0 0
Strontium-90 Ci 0
0 0
0 l
Cesium 134 Ci 6.82E 10 3.46E 6 0
0 Cesium 137 Ci 4.21E 10 2.25E 5 0
0 TaITum Lanth -140 Ci 0
0 0
0 Others:
Rb 88 Ci 8.44E 3 1.15E 6 0
0 I
Cs 136 Ci 0
6.90E 6 0
0 Cs 138 Ci 2.755 4 0
0 0
Ci 0
0 0
0 i
Unidentified Ci 0
0 0
0 Total for period Ci 8.7 2 E -3 3.40E 5 0
0 Page 9
SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1988 Table 5 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 1.06E 1 1.89E 1 1.80E + 1 alpha)
- 2. Average diluted concentration during uCi/ml 1.77E 10 3.90E 10 period
- 3. Percent of applicable limit B. Tritium
- 1. Totai release Ci 1.82E + 2 2.92E + 2 1.85E + 1
- 2. Average diluted concentration during uCi/ml 3.04E 7 6.03E 7 period
- 3. Percent of applicable limit i
C. Dissolved and entrained gases
- 1. Total release Ci 8.95E 2 6.98E-1 1.80E + 1
- 2. Average diluted concentration during uCi/ml 1.50E 10 1.44 E-9 petiod
- 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 8.52E + 7 7.08E + 7 3.00E + 0 i
~
F. Volume of dilution water used during period liters 5.98E + 11 4.85E + 11 4.30E + 0 See following page.
Page 10 1
SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPSRT k
January June,1988 Table 5 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Calculated as a percent of dose limits found in Su0piementalInformation, Section ic. The sum of these values for the first quarter was 3.49 4 and 1.75 % of the respective quarterly I
I and cumulative annual whole bod:.e dose limits and 1.36 % and 6.80E 1 % of the respective I
quarterly and cumulative annual o'rgan dose limits. The sum of these values for the second quarter was 5.40 % and 4.45 % of the respective quarterly and cumulative annual whole body dose limits and 2.10 % and 1.73 % of the respective quarterly and cumulative annual organ dose limits. Dose to the Liver was the most limiting organ dose for the first and i
l second quarters of 1988.
l Page 11
SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1988 Table 6 LIQUID EFFLUENTS Continuous Mode Batch Mode First Second First Second tNuclides Released Unit Quarter Quarter Quarter Quarter 5trontium 69 Ci 0
0 0
0 Strontium 90 Ci 0
0 0
0 Cesium 134 Ci 2.74E 3 2.63E 3 2.01E 2 4.70E 2 Cesium 137 Ci 1.70E 3 1.49E 3 1.42E 2 3.22E 2 lodine 131 Ci
- 8. 38 E-3 1.15E 2 1.58E 3 1.03E 2 Cobalt 58 Ci 2.26t-4 0
.10E-2 3.93t 3 Cobalt 60 C
0 0
1.67E 2 2.09E 2 tron 59 Ci 0
0 0
6.59E 5 Zinc 65 Ci 0
0 0
0 Manganese 54 Ci 0
0 3.70E 3 2.03 E-3 Chromium 51 Ci 0
0 2.65E 5 4.64E 5 Zirconium Niobium 95 Ci 0
0
- 3. / 9 E-b 5.Olt-6 Molybdenum-99 Ci 0
0 2.63E 5 0
Technetium 99m Ci 0
4.91E 5 2.41E 4 2.48E 4 Barium Lanth.140 Ci 0
0 0
3.13 E-4 Terium 141 Ci 0
0 3.61 E-6 0
Other.
'F-18 Ci 0
9 b/t-b 0
0 Na 24 Ci 5.23E 5 8.23E 6 9.40E 5 2.41 E-6 Fe 55 Ci 0
1.80E 3 8.25E-3 6.50E 3
'Co 57 Ci 0
0 1.81 E 4 6.79E 5 Rb 88 Ci 3.21E 3 0
1.52E 5 6.15E 5 Ru 103 Ci 0
0 0
1.62 E-6 Ru 105 C
0 0
3.14 E-6 2.51E 5 Ag 110m Ci 0
0 0
1.51 E-5
'5n 113 Ci 0
0 0
, 6.26E-6
'5b 124 Ci 0
0 6.07E-6 2.26E-5
'5b 125 Ci 0
0 1.52 E-3 5.77E 4 l-130 C
8.89E 5 1.67 E -4 0
0 1132 Ci 2.59E 3 9.21E 3 0
0 1-133 Ci 6.26E 3 1.71E 2 1.07E 6 3.56E-4 1 134 Ci 2.84E 4 4.22E 3 0
0 1135 Ci 1.68 E-3 1.46E 2 0
2.06E 5 Cs-136 Ci 5.80E 4 4.52E 4 7.8 5 E-4 6.70 E -4 Cs-138 Ci 0
7.00E 4 0
0 C e-144 Ci 0
0 4.34E 6 0
Totai for pened (above)
Ci 2./St 2 6 39t-2 7 S4E-2 1.2 5 t 1 Page 12
SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT 3
January June,1988 Table 6 (continued)
LIQUID EFFLUENTS Continuous Mode Batch Mode First Second First Second t Nuclides Released Unit Quarter Quarter Quarter Quarter Xenon 13.3 Ci 4.85E 4 5.72E 4 8.61E 2 6.77E 1 Xenon 135 Ci 2.28E 4 2.51E 4 2.43E 5 2.66E-3 Other:
Kr 85 C
0 0
0 2.04E 4 Kr 85m Ci 5.22E 6 0
0 9.71E 5 Kr 88 Ci 0
0 0
3.95E 5 Xe 131m Ci 0
0 2.43E 3 1.09E 2 Xe 133m C
0 0
2.25E 4 6.22E 3 Total entrained gases Ci "i.18E 4 8.23E 4 8.88E 2 6.97 E-1 t Tritiurr not included. See Table 5 for tritium numbers.
- Dose factors for these trace radionuclides are not included in the ODCM or Regulatory Guide 1.109, consequently the cumulative dose attributed to these isotopes is not reported. The c;uantity of these isotopes compriced only 9.4E 4 % and 2.3E 4 % of the total curies released (including tritium) during the first and second quarter, respectively.
1 4
l
)
+
I i
l i
Page 13 l
SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1988 Table 7 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel) 6 month Est. Total
- 1. Type of waste Unit Period Error,9 a
- a. 5 pent resins, filter sludges, evaporator m'
0 bottoms, ett-Ci 0
N/A
- b. Dry compressible waste, contaminated m3 0
equip., etc.
Ci 0
N/A
- c. Irradiated components, control rods, m'
0 etc.
Ci 0
N/A 3
d.Other (describe) Process I.iters m
0 Ci 0
N/A
- 2. Estimate of major nuclide composition (by type of waste)
- a. None to N/A 6
N/A
- b. None
_- So N/A
- c. Nore 9b N/A
- d. None
- 3. Solid Waste Disposition (6 month period)
Number of Shipments Mode of Transportation Destination None N,A N/A B. trradiated Fuel 5hipments (Disposition)
Number of Shipments Mode of Transportation Destination None N/A N/A Page la