ML20117G771
| ML20117G771 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 08/29/1996 |
| From: | Hill W NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9609050320 | |
| Download: ML20117G771 (23) | |
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Northem States Power Company Monticello Nuclear Generating Plant 2807 West Hwy 75 Monticello, Minnesota 55362 9637 August 29, 1996 Technical Specification US Nuclear Regulatory Commission Attna Document Control Desk Washington, DC 20555 i
I MONTICELLO NUCLEAR GENERATING PLANT l Docket No. 50-263 License No. DPR-22 Effluent and Waste Disposal Semi-Annual Report for January Throuch June 1996 In accordance with the Monticello Technical Specifications section 6.7.A.4, we are submitting the Effluent and Waste Disposal Semi-Annual Report for the period of January-June 1996 as Attachment A.
In addition, the Effluent and Waste Disposal Semi-Annual Report for the period of July-December 1995 has been updated and is submitted as Attachment B. The reason for the update is that during routine periodic interlaboratory QC l checks it was found that one of the HpGe detectors in the counting laboratory was improperly calibrated. An investigation determined that this miscalibration resulted in gaseous iodine values being conservatively analyzed and reported in our original submittal. One of the follow-up actions from the investigation was to revise the July-December 1995 report and resubmit it. For convenience, the affected iodine values are side-barred in the updated report.
It is noted that there may be insignificant changes to some of the other values as a result of the updating process.
There were no changes to the Offsite Dose Calculation Manual (ODCM) or the Process Control Program (PCP) Manual during the reporting period. Also, there were no milk and vegetable sampling deviations or changes to the Radiation Environmental Monitoring Program during this reporting period.
This letter contains no new NRC commitments, nor does it modify any prior commitments. Please contact Mel Opstad at (612) 295-1653 if you require further information.
/ bin ,/ 'Q.
William J Hill Plant Manager Monticello Nuclear Generating Plant 9609050320 960829 _
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( USNRC NORTHERN STATES POWER COMPANY 1 August 29, 1996 Page 2 l
c: Regional Administrator - III, NRC !
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.NRR Project Manager, NRC l Sr Resident Inspector, NRC State of Minnesota Attna Kris Sanda J Silberg Attachment A Effluent and Waste Disposal Semi-Annual Report, Period January-June 1996 Attachment B Effluent and Waste Disposal Semi-Annual Report, Period July-December 1995 (Updated 8/29/96) l l
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I Fue+ J.WO460mMONTEMAPERIODIC.NPTWFF,RPfl.962
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Attachment A j Effluent and Waste Disposal Semi-Annual Report, Period January-June 1996 ,
(The attached Report contains 9 pages.) ;
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NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1996 Supplemental Information
- 1. Regulatory Limits - Quarterly levels requiring reporting to Nuclear Regulatory Commission A. Noble Gases :
5 mrad / quarter gamma radiation 10 mrad / quarter beta radiation B. Long Lived Iodines, Particulates, and Tritium :
7.5 mrem / quarter dose to any organ C. Liquid Effluents :
1.5 mrem /
5.0 mremquarter
/ quarterdose dosetotoany theorgan total body
- 2. Maximum Permissible Concentrations A. Noble Gases :
10 CFR Part 20, Appendix B, Table II, Column 1 B. Long Lived Iodines, Particulates, and Tritium :
10 CFR Part 20, Appendix B, Table II, Column 1 C. Liquid Effluents :
10 CFR Part 20, Appendix B, Table II, Column 2 2.0 E-4 uci/ml for dissolved and entrained gases
- 3. Average Energy (Not Applicable)
Page 2
' EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1996 Supplemental Information (continued)
- 4. Measurements and Approximations of Total Radioactivty I A. Noble Gases :
Continuous gross activity monitors in Reactor Building Vent and Plant Stack exhaust streams. Weekly isotopic analysis of exhaust streams.
B. Iodines in Gaseous Effluent : !
Continuous monitoring with charcoal cartridges in Reactor Building Vent and Plant Stack exhaust streams with weekly analysis.
C. Particulates in Gaseous Effluent :
Continuous monitoring with particulate filters in Reactor Building Vent and Plant Stack exhaust streams with weekly analysis.
1 D. Tritium in Gaseous Effluent : ;
Continous monitoring with silica gel cartridges in Reactor Building Vent and Plant Stack exhaust streams with weekly analysis.
E. Liquid Effluents :
Tank sample analyzed prior to each planned release and continuous !
monitoring of gross activity during planned release, j i
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- 5. Batch Releases i A. Liquid : I
- 1. Number of Batch Releases 0
- 2. Total Time Period for Batch Releases 0.0 min
- 3. Maximum Time Period for a Batch Release 0.0 min
- 4. Average Time Period for a Batch Release 0.0 min :
- 5. Minimum Time Period for a Batch Release 0.0 min 1
- 6. Average River Flow During Release 0.0 cf/sec B. Gaseous : j
- 1. Number of Batch Releases 2
- 2. Total' Time Period for Batch Releases 2617.0 min
- 3. Maximum Time Period for a Batch Release 2240.0 min
- 4. Average Time Period for a Batch Release 1308.5 min
- 5. Minimum Time Period for a Batch Release 377.0 min
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4 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1996 Supplemental Information (continued)
- 6. Abnormal Releases l
A. Liquid :
- 1. Number of Releases 1
- 2. Total Activity Released 6.80E-07 Ci B. Gaseous :
1 1. Number of Releases 0
- 2. Total Activity Released 0.0 Ci l
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Page 4 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1996 Table 1A Gaseous Effluents - Summation of all Releases Units 1st Qtr 2nd Qtr Est. Total Error, %
A. Fission & Activation gases l
- 1. Total Release Ci 1.07E+02 5.24E+01 2.00E+01 l
- 2. Average Release Rate uci/sec 1.37E+01 6.67E+00
- 3. Percent Tech Spec Qtrly Reporting Level l Gamma Radiation % 7.00E-02 2.89E-02 l Beta Radiation % 2.82E-02 8.81E-03 B. Iodines
- 1. Total I-131 Release Ci 1.66E-03 2.34E-03 1.00E+01 l
- 2. Averace I-131 Release Rate uci/sec 2.14E-04 2.97E-04 l
C. Particulates
- 1. Total Particulates Ci 3.70E-04 4.33E-04 3.00E+01 l
- 2. Averace Release Rate uci/sec 4.75E-05 5.51E-05
- 3. Gross Aloha Radioactivity Ci 2.30E-06 5.05E-06 D. Tritium
- 1. Total Release Ci 7.45E+00 5.43E+00 1.00E+01 l
- 2. Averace Release Rate uci/sec 9.58E-01 6.91E-01 E. Percent Qtrly Tech Spec Reporting Levels
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Page 5 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1996 Table 1B Gaseous Effluents - Elevated Releases Continuous Mode Batch Mode Nuclides Released Unit 1st Otr i 2nd Otr 1st Otr I 2nd Otr
- 1. Fission Gases KR-85M Ci 0.00E+00 2.25E-01 0.00E+00 0.00E+00 KR-87 Ci 7.95E-01 7.10E-01 0.00E+00 0.00E+00 KR-88 Ci 4.34E-01 7.38E-01 0.00E+00 0.00E+00 KR-89 Ci 2.24E+00 1.16E+00 0.00E+00 0.00E+00 XE-133 Ci 1.97E+01 8.05E+00 0.00E+00 7.08E-03 XE-133M Ci 7.43E-02 0.00E+00 0.00E+00 0.00E+00 XE-135 Ci 2.66E+00 3.59E+00 0.00E+00- 8.75E-03 XE-135M Ci 7.08E+00 4.71E+00 0.00E+00 0.00E+00 XE-137 Ci 4.87E+01 2.07E+01 0.00E+00 0.00E+00 l XE-138 Ci 1.89E+01 9.66E+00 0.00E+00 0.00E+00 i AR-41 Ci 0.00E+00 0.00E+00 0.00E+00 1.18E-02 I Total for Period Ci 1.01E+02 4.96E+01 0.00E+00 2.76E-02
- 2. Iodines l I-131 Ci 1.71E-04 1.01E-03 0.00E+00 0.00E+00 I-133 Ci 1.03E-03 4.44E-03 0.00E+00 0.00E+00 I-135 Ci 1.52E-03 6.87E-03 0.00E+00 0.00E+00 Total for Period Ci 2.72E-03 1.23E-02 0.00E+00 0.00E+00
- 3. Particulates CR-51 Ci 0.00E+00 7.32E-07 0.00E+00 0.00E+00 MN-54 Ci 0.00E+00 4.64E-07 0.00E+00 0.00E+00 CO-58 Ci 0.00E+00 8.73E-08 0.00E+00 0.00E+00 FE-59 Ci 0.00E+00 2.39E-07 0.00E+00 -0.00E+00 CO-60 Ci 3.10E-06 4.65E-06 0.00E+00 0.00E+00 ZN-65 Ci 8.84E-07 3.21E-06 0.00E+00 0.00E+00 SE-75 Ci 0.00E+00 4.49E-07 0.00E+00 0.00E+00 CS-137 Ci 2.30E-05 9.31E-07 0.00E+00 0.00E+00 BA-140 Ci 1.05E-04 4.95E-05 0.00E+00 0.00E+00 SR-89 Ci 4.27E-05 0.00E+00 0.00E+00 0.00E+00 SR-90 Ci 2.30E-07 0.00E+00 0.00E+00 0.00E+00 Total for Period Ci 1.75E-04 6.02E-05 0.00E+00 0.00E+00 Analysis of Sr-89 & 90 for the 2nd Qtr was not completed in time for this report, results will be included with the next semiannual report.
Page 6 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1996 Table 1C Gaseous Effluents - Building Vent Releases Continuous Mode Batch Mode Nuclides Released Unit 1st Otr l 2nd Otr 1st Otr l 2nd Otr
- 1. Fission Gases XE-135 Ci 4.33E+00 2.10E+00 0.00E+00 0.00E+00 XE-135M Ci 1.70E+00 7.57E-01 0.00E+00 0.00E+00 Total for Period Ci 6.03E+00 2.86E+00 0.00E+00 0.00E+00
- 2. Iodines I-131 Ci 1.49E-03 1.33E-03 0.00E+00 0.00E+00 I-133 Ci 1.29E-02 3.49E-03 0.00E+00 0.00E+00 I-135 Ci 3.12E-02 4.02E-03 0.00E+00 0.00E+00 Total for Period Ci 4.56E-02 8.84E-03 0.00E+00 0.00E+00
- 3. Particulates MN-54 Ci 0.00E+00 9.76E-06 0.00E+00 0.00E+00 CO-60 Ci 1.23E-04 1.49E-04 0.00E+00 0.00E+00 ZN-65 Ci 1.03E-05 2.03E-04 0.00E+00 0.00E+00 CS-137 Ci 1.78E-05 1.15E-05 0.00E+00 0.00E+00 BA-140 Ci 3.43E-05 0.00E+00 0.00E+00 0.00E+00 SR-89 Ci 1.01E-05 0.00E+00 0.00E+00 0.00E+00 Total for Period Ci 1.95E-04 3.74E-04 0.00E+00 0.00E+00 Analysis of Sr-89 & 90 for the 2nd Qtr was not completed in time for this report, results will be included with the next semiannual report.
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT )
Period : Jan - Jun 1996 l
l Table 2A Liquid Effluents - Summation of all Releases l Units 1st Qtr 2nd Qtr Est. Total l Error. % J A. Fission & Activation products
- 1. Total Release-(not including tritium, cases, aloha) Ci 0.'00E+00 6.80E-07 0.00E+00
- 2. Ava Diluted Concentration uci/ml 0.00E+00 9.91E-12 B. Tritium
- 1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 l !
- 2. Ava Diluted Concentration uci/ml 0.00E+00 0.00E+00 C. Dissolved and Entrained' Gases
- 1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 l
- 2. Ava Diluted Concentration uci/ml 0.00E+00 0.00E+00 D. Percent Qtrly Tech Spec Reporting Level
- 1. Whole Body Dose % 0.00E+00 0.00E+00
- 2. Orcan Dose % 0.00E+00 0.00E+00 E. Gross Alpha Radioactivity l 1. Total Release I Ci I'0.00E+00 1 0.00E+00 l 0.00E+00 l )
lF. Volume of Waste Released l Liters I 0.00E+00 l 4.25E+03 1 0.00E+00 l lF. Volume of Dilution Water Used I Liters I 0.00E+00 l 6.86E+07 l 0.00E+00 l Table 2B Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit 1st Otr 2nd Otr 1st Otr 2nd Otr F-18 Ci 0.00E+00 6.80E-07 0.00E+00 0.00E+00
'. ,- j Page 8 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period Jan - Jun 1996 Table 3 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Offsite for Burial or Disposal (not irradiated fuel)
- 1. Type of Waste Units 6-month Est. Total Period Error. %
- a. Spent resins, filter sludges, Cu. Meter 0.00E+00 ,
evaporator bottoms. etc. Ci 0.00E+00 0.00E+00 l
- b. Dry compressible waste, Cu. Meter 8.01E+00 contaminated ecuipment. etc. Ci 2.87E-01 3.50E+01
- c. Irradiated components, Cu. Meter 0.00E+00 control rods, etc. Ci 0.00E+00 0.00E+00 i
- d. Otber (describe) Cu. Meter 0.00E+00 1 Ci 0.00E+00 0.00E+00 l
- 2. Estimate of ma:ior nuclide composition (by type of waste)
Type A Type B Type C Type D j Nuclide cercent oercent percent percent 1 H-3 2.58E-01 l C-14 3.85E-02 Mn-54 4.57E+00 l Fe-55 5.16E+01 l Co-57 1.47E-01 i Co-58 2.19E-01 Fe-59 5.97E-01 Co-60 2.33E+01 Ni-63 1.56E+00 Zn-65 1.56E+01 Sr-89 1.94E-02 Sr-90 3.57E-02 Tc-99 2.16E-03 Sb-125 3.41E-02 I-129 6.15E-03 Cs-134 7.34E-02 Cs-137 1.53E+00 '
Ce-144 6.44E-02 Pu-238 5.55E-02 Pu-239 3.00E-02 Am-241 2.36E-02 Pu-241 1.44E-01 Cm-242 1.29E-02 Pu-242 5.98E-02 Cm-243 8.02E-03 I
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Page 9 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1996 j Table 3 Solid Waste and Irradiated Fuel Shipments
- 3. Solid waste disposal Number of Mode of Destination Shioments Transoortation n 25 Truck Chem-Nuc Inc., Barnwell, SC.
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- 1. Disposition i Number of Mode of Destination Shioments Transportation None This Period l
l C. Shipping Container and Solidification Method No. Volume Activity Type of Container Solidification M3 Ci Waste Code Code I S464f 6.51E-01 1.26E-03 B L N !
9464g 2.83E-03 8.91E-04 B L N 9602a .1.67E-01 2.45E-03 B L N 9602b 2.38E-01 3.72L-03 B L N 9602c 9.63E-02 2.59E-03 B L N 9602d 3.96E-02 1.14E-03 B L N 9602e 3.68E-02 1.47E-03 B L N 9602f 1.42E-02 1.18E-02 B L N 9602g 1.70E-02 2.02E-02 B L N j 9602h 2.83E-02 5.92E-03 B L N -
9605a 3.14E-01 9.36E-03 B L N 9605b 6.51E-02 2.40E-03 B L N 9605c 8.50E-03 4.93E-02 B L N 9605d 9.06E-01 2.60E-02 B L N 9627a 2.27E-01 2.88E-03 B L N 9627b 2.44E-01 2.91E-03 B L N l 9627c 8.58E-01 9.74E-03 B L N 9627d 3.68E-01 2.99E-03 B L N l 9627e 1.04E+00 7.71E-03 B L N :
l 9627f 1.42E-01 1.37E-03 B L N I 9638a 4.93E-01 1.83E-02 B L N l
9638b 7.84E-01 3.97E-02 B L N 9638c 8.95E-01 5.66E-02 B L N 9642a 3.79E-01 6.14E-03 B L N 9464h 2.83E-03 2.67E-04 B L N
! Container Codes : Solidification Codes :
L - LSA C - Cement
{ A - Type A. U - Urea Formaldehyde B - Type B D - Dewatering Q - Large Quantity N - Not Applicalble
..... . . . . . .- -. .. - . . . . . . . . . . . . - . . . - . . ~ - . . - . - . - - . . . _ _ . . _ . .
j- a 1 A
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. Attachment B Effluent and Waste Disposal Semi-Annual Report, i
Period July-December 1995 (Updated 8/29/96) i i
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! (The attached Report contains 10 pages.) i i
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NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1995 Supplemental Information
- 1. Regulatory Limits - Quarterly levels requiring reporting to Nuclear Regulatory Commission A. Noble Gases :
5 mrad / quarter gamma radiation 10 mrad / quarter beta radiation B. Long Lived Iodines, Particulates, and Tritium :
7.5 mrem / quarter dose to any organ C. Liquid Effluents : )
1.5 mrem / quarter dose to the total body 5.0 mrem / quarter dose to any organ i
- 2. Maximum' Permissible Concentrations A.' Noble Gases : l l
10 CFR Part 20, Appendix B, Table II, Column 1 j j
B. Long Lived Iodinec, Particulates, and Tritium : )
10 CFR Part 20, Appendix B, Table II, Column 1 C. Liquid Effluents : l l
10 CFR Part 20, Appendix B, Table II, Column 2 !
2.0 E-4 uci/ml for dissolved and entrained gases
- 3. Average Energy (Not Applicable) ;
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8/29/96 )
EFTLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l Period : Jul - Dec 1995 Supplemental Information (continued)
- 4. Measurements and Approximations of Total Radioactivty A. Noble Gases :
i Continuous gross activity monitors in Reactor Building Vent and Plant l Stack exhaust streams. Weekly isotopic analysis of exhaust streams.
B. Iodines in Gaseous Effluent : j Continuous monitoring with charcoal cartridges in Reactor Building Vent and Plant Stack exhaust streams with weekly analysis.
C. Particulates in Gaseous Effluent : I Continuous monitoring with particulate filters in Reactor Building Vent and Plant Stack exhaust streams with weekly analysis.
D. Tritium in Gaseous Effluent :
Continous monitoring with silica gel cartridges in Reactor Building Vent and Plant Stack exhaust streams with weekly analysis.
l E. Liquid Effluents : j Tank sample analyzed prior to each planned release and continuous monitoring of gross activity during planned release.
- 5. Batch Releases A. Liquid :
- 1. Number of Batch Releases 0
- 2. Total Time Period for Batch Releases 0.0 min
- 3. Maximum Time Period for a Batch Release 0.0 min
- 4. Average Time Period for a Batch Release 0.0 min
- 5. Minimum Time Period for a Batch Release 0.0 min
- 6. Average River Flow During Release 0.0 cf/sec B. Gaseous :
- 1. Number of Batch Releases 0
- 2. Total Time Period for Batch Releases 0.0 min
- 3. Maximum Time Period for a Batch Release 0.0 min
- 4. Averace Time Period for a Batch Release 0.0 min
- 5. Minimum Time Period for a Batch Release 0.0 min l
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1995 Supplemental Information (continued)
- 6. Abnormal Releases A. Liquid :
- 1. Number of Releases 0
- 2. Total Activity Released 0.0 Ci ,
D. Gaseous :
- 1. Number of Releases 0
- 2. Total Activity Released 0.0 Ci 1
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i Table 1A Gaseous Effluents - Summation of all Releases Units 3rd Qtr 4th Qtr Est. Total Error. %
l A. Fission & Activation gaees
- 1. Total Release Ci 1.27E+02 1.08E+02 2.00E+01 l
- 2. Average Release Rate uci/sec 1.60E+01 1.36E+01
- 3. Percent Tech Spec Qtrly Reporting Level Gamma Radiation % 7.88E-02 7.80E-02 l
Beta Radiation % 3.25E-02 2.80E-02 B. Iodines
- 1. Total I-131 Release Ci 8.66E-04 9.21E-04 1.00E+01 l
- 2. Average I-131 Release Rate uci/sec 1. 0 9E- 04 1.16E-04 C. Particulates
- 1. Total Particulates Ci 4.82E-04 3.66E-04 3.00E+01 l l 2. Average Release Rate uci/sec 6.07E-05 4.60E-05
- 3. Gross Aloha Radioactivity Ci 7.08E-06 I 3.20E-06 D. Tritium l
- 1. Total Release Ci 1.16E+01 6.96E+00 1.00E+01 l
- 2. Averace Release Rate uci/sec 1.46E+00 8.76E-01 E. Percent Otrly Tech Spec Reporting Levels
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1 Page 5 8/29/96 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l Period . Jul - Dec 1995 l Table 1B Gaseous Effluents - Elevated Releases Continuous Mode Batch Mode ,
Nuclides Released Unit 3rd Otr l 4th Otr 3rd Otr l 4th Otr {
- 1. Fission Gases KR-85M Ci 1.15E+00 8.31E-01 0.00E+00 0.00E+00 KR-87 Ci 1.70E+00 1.08E+00 0.00E+00 0.00E+00 KR-88 Ci 2.79E+00 1.44E+00 0.00E+00 0.00E+00 XE-133 Ci 2.61E+01 2.80E+01 0.00E+00 0.00E+00 !
XE-133M Ci 1.69E-01 2.03E-01 0.00E+00 0.00E+00 l XE-135 Ci 1.61E+01 1.34E+01 0.00E+00 0.00E+00 XE-135M Ci 7.55E+00 5.31E+00 0.00E+00 0.00E+00 XE-137 Ci 4.24E+01 3.41E+01 0.00E+00 0.00E+00 XE-138 Ci 2.15E+01 1.53E+01 0.00E+00 0.00E+00 AR-41 Ci 6.66E-02 8.62E-02 0.00E+00 0.00E+00 Total for Period Ci 1.19E+02 9.97E+01 0.00E+00 0.00E+00
- 2. Iodines I-131 Ci 2.75E-04 1.79E-04 0.00E+00 0.00E+00 I-133 Ci 1.72E-03 1.03E-03 0.00E+00 0.00E+00 I-135 Ci 2.51E-03 1.55E-03 0.00E+00 0.00E+00 Total for Period Ci 4.50E-03 2.77E-03 0.00E+00 0.00E+00
- 3. Particulates MN-54 Ci 0.00E+00 3.79E-08 0.00E+00 0.00E+00 CO-60 Ci 3.26E-06 2.62E-06 0.00E+00 0.00E+00 CS-137 Ci 2.73E-06 1.37E-06 0.00E+00 0.00E+00 BA-140 Ci 1.37E-04 1.03E-04 0.00E+00 0.00E+00 SR-89 Ci 1.17E-04 7.62E-06 0.00E+00 0.00E+00 SR-90 Ci 2.58E-07 2.66E-07 0.00E+00 0.00E+00 Total for Period Ci 2.60E-04 1.15E-04 0.00E+00 0.00E+00 SR-89 results decreased due to lower results for 1st quarter of 1996 which includes the last two weeks of this reporting period.
Page 6 8/29/96 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1995 Table 1C Gaseous Effluents - Building Vent Releases Continuous Mode Batch Mode i Nuclides Released Unit 3rd Otr l 4th Otr 3rd otr I 4th Otr
- 1. Fission Gases XE-135 Ci 7.01E+00 5.36E+00 0.00E+00 0.00E+00 XE-135M Ci 8.55E-01 3.17E+00 0.00E+00 0.00E+00 1
Total for Period Ci 7.86E+00 8.53E+00 0.00E+00 0.00E+00
I-133 Ci 4.63E-03 6.18E-03 0.00E+00 0.00E+00 I-135 Ci 5.95E-03 1.09E-02 0.00E+00 0.00E+00 Total for Period Ci 1.12E-02 1.78E-02 0.00E+00 0.00E+00 1
- 3. Particulates j l
MN-54 Ci 3.36E-06 0.00E+00 0.00E+00 0.00E+00 j CO-60 Ci 1.54E-04 1.94E-04 0.00E+00 0.00E+00__ i ZN-65 Ci 2.29E-05 3.44E-06 0.00E+00 0.00E+00 I CS-137 Ci 3.20E-05 1.21E-05 0.00E+00 0.00E+00 BA-140 Ci 0.00E+00 3.07E-05 0.00E+00 0.00E+00 SR-89 Ci 1.01E-05 9.82E-06 0.00E+00 0.00E+00 Total for Period Ci 2.22E-04 2.51E-04 0.00E+00 0.00E+00 I
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Table 2A Liquid Effluents - Summation of all Releases Units 3rd Qtr 4th Qtr Est. Total i Error, % I A. Fission & Activation products
- 1. Total Release (not including 1 tritium, cases, alpha) Ci 0.00E+00 0.00E+00 0.00E+00
- 2. Ava Diluted Concentration uci/ml 0.00E+00 0.00E+00 B. Tritium l
- 1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 l
- 2. Ava Diluted Concentration uci/ml 0.00E+00 0.00E+00 1
C. Dissolved and Entrained Gases '
i
- 1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 l
- 2. Ava Diluted Concentration uci/ml 0.00E+00 0.00E+00 ,
D. Percent Qtrly Tech Spec Reporting Level
- 1. Whole Body Dose % 0.00E+00 0.00E+00
- 2. Organ Dose % 0.00E400 0.00E+00 E. Gross Alpha Radioactivity l 1. Total Release l Ci l 0.00E+00 l 0.00E+00 1 0.00E+00 l lF. Volume of Waste Released i Liters l 0.00E+00 l 0.00E+00 1 0.00E+00 l l
lF. Volume of Dilution Water Used l Liters l 0.00E+00 1 0.00E+00 l 0.00E+0_0_l l 1
Table 2B Liquid Effluents Continuous Mode Batch Mode Nuclides Re? eased Unit 3rd Otr I 4th Otr 3rd Otr I 4th Otr None Released This Period l
Page 8 8/29/96 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1995 j Table 3 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Offsite for Burial or Disposal (not irradiated fuel)
- 1. Type of Waste Units 6-month Est. Total Period Error, %
- a. Spent resins, filter sludges, Cu. Meter 5.25E+01 .
evaporator bottoms, etc. Ci 3.16E+02 3.70E+01 l
- b. Dry compressible waste, Cu. Meter 9.63E+00 i contaminated eauiDment, etc. Ci 5.46E-01 3.50E+01 I
- c. Irradiated components, Cu. Meter 0.00E+00 control rods, etc. Ci 0.00E+00 0.00E+00 i
- d. Other (describe) Cu. Meter 0.00E+00 )
Ci 0.00E+00 0.00E+00 '
- 2. Estimate of ma?or nuclide composition (by type of waste) l Type A Type B Type C Type D I Nuclide percent percent percent percent E-3 5.03E-02 2.66E-01 C-14 7.57E-02 4.92E-02 Mn-54 1.44E+00 5.29E+00 I Fe-55 1.48E+01 4.92E+01 ,
Co-58 1.36E-01 3.58E-01 i Fe-59 2.03E+00 '
Ni-59 4.81E-03 Co-60 1.58E+01 1.80E+01 Ni-63 4.28E-01 4.27E+00 Zn-65 5.88E+01 1.92E+01 Sr-89 9.17E-02 1.79E-02 Sr-90 1.90E-02 3.50E-02 Nb-94 3.42E-06 Tc-99 6.37E-08 1.17E-06 Cd-109 1.69E-08 i I-129 7.84E-07 3.92E-06 I-131 2.85E-01 Cs-134 7.34E-02 3.74E-02 Cs-137 7.73E+00 4.98E-01 1 Ba-140 1.02E-01 !
La-140 7.76E-11 Ce-141 9.15E-02 1.38E-10 Ce-144 1.27E-02 3.39E-02 Eu-154 3.39E-Oe Pu-238 3.93E-04 2.65E-01 Pu-239 1.85E-04 1.28E-01 Am-241 1.71E-03 1.48E-02 Pu-241 1.38E-02 7.02E-02 Cm-242 1.27E-03 4.57E-02 Pu-242 2.08E-01 Cm-243 1.12E-03 4.14E-03
Page 9 8/29/96 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1995 Table 3 Solid Waste and Irradiated Fuel Shipments
- 3. Solid waste disposal Number of Mode of Destination Shioments Transportation 30 Truck Chem-Nuc Inc., Barnwell, SC.
1 1
B. Irradiated Fuel Shipments
- 1. Disposition Number of Mode of Destination Shioments Transoortation None This Period i
C. Shipping Container and Solidification Method No. Volume Activity Type of Container Solidification M3 Ci Waste Code Code 95-15 5.83E+00 1.86E+01 A A D 95-16 5.83E+00 6.74E+01 A A D 95-18 5.83E+00 6.64E+01 A A D 95-21 5.83E+00 4.61E+01 A A D )
95-22 5.83E+00 2.77E+01 A A D 95-23 5.83E+00 1.71E+01 A A D 95-20 5.83E+00 2.09E+01 A A D 1 95-24 5.83E+00 4.72E+01 A A D 95-37 5.83E+00 4.51E+00 A A D 9378a 5.04E-01 7.90E-06 B L N 9378b 3.96E-01 1.06E-05 B L N 9379a 1.35E+00 1.03E-05 B L N 9379b 7.50E-01 9.60E-06 B L N 9410a 1.70E-02 4.69E-05 B L N 9446a 5.15E-01 2.02E-03 B L N 9446b 8.78E-02 9.23E-02 B L N 9446c 1.09E+00 3.94E-02 B L N 9446d 3.26E-01 3.37E-03 B L N 9446e 5.10E-01 1.02E-03 B L N 9464a 9.63E-01 7.37E-02 B L N 9464b 4.11E-01 2.04E-01 B L N 9464c 1.56E-01 2.07E-04 B L N 9464d 5.38E-02 1.37E-02 B L N 9464e 2.83E-03 2.59E-04 B L N 9471a 8.55E-01 3.11E-02 B L N 9471b 1.27E-01 5.16E-02 B L N 9471c 2.69E-01 1.25E-03 B L N 9471d 8.16E-01 1.82E-02 B L N J
Page 10 8/29/96 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1995 C. Shipping Container and Solidification Method (Cont.)
No. Volume Activity Type of Container Solidification M3 Ci Waste Code Code 9471e 1.70E-01 6.24E-03 B L N 9471f 2.61E-01 8.05E-03 B L N Container Codes -
Solidification Codes :
L- LSA C- Cement A - Type A U - Urea Formaldehyde !
B- Type B D - Dewatering l 0 - Large Quantity N - Not Applicalble 1 1