ML113190501

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Amend to Effluent & Waste Disposal Semiannual Rept for Jul-Dec 1989, Providing Previously Omitted 4th Quarter Analyses Results of Sr-89 & Sr-90
ML113190501
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 12/31/1989
From:
Northern States Power Co
To:
Shared Package
ML113190500 List:
References
NUDOCS 9009070078
Download: ML113190501 (15)
v • d • e


Text

AMENDMENT to the MONTICELLO Effluent and Waste Disposal Semiannual Report (for the 2nd Half year of 1989)

This report provides the previously omitted 4th quarter analyses results of Sr-89 and Sr-90 9009070078 900829 PDR ADOCK 050*****

RPNU

NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1989 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 lodines, 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
2. Maximum Permissible Concentrations Noble Gases:

10 CFR Part 20, Appendix B, Table II, Column 1 B. Long Lived lodines, 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 : Jul - Dec 1989 Supplemental Information (continued)

4. Measurements and Approximations of Total Radioactivty 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.

D. Tritium in Gaseous Effluent Continuous 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.

5. Batch Releases A. Liquid :
1. Number of Batch Releases 0
2. Total Time Period for Batch Releases NA min
3. Maximum Time Period for a Batch Release NA min
4. Average Time Period for a Batch Release NA min
5. Minimum Time Period for a Batch Release NA min
6. Average River Flow During Release NA cf/sec B. Gaseous
1. Number of Batch Releases 3
2. Total Time Period for Batch Releases 2821.0 min
3. Maximum Time Period for a Batch Release 2160.0 min
4. Average Time Period for a Batch Release 940.3 min
5. Minimum Time Period for a Batch Release 136.0 min

Page 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1989 Supplemental Information (continued)

6. Abnormal Releases A. Liquid :
1. Number of Releases 0
2. Total Activity Released NA Ci B. Gaseous :
1. Number of Releases 0
2. Total Activity Released 0.0 Ci

Page 4 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1989 Table 1A Gaseous Effluents - Summation of all Releases Units 3rd Qtr I 4th Qtr lEst. Total Error, %

A. Fission & Activation gases

1. Total Release Ci 6.85E+02 5.74E+02 5.00E+01
2. Average Release Rate uci/sec 8.61E+01 [ 7.23E+01
3. Percent Tech Spec Qtrly Reporting Level l Gamma Radiation l I 4.09E+00 I 7.92E-01 I Beta Radiation  % 2.45E+00 4.25E-01 B. Iodines
1. Total I-131 Release Ci 2.54E-02 2.95E-03 5.00E+01 I2. Average 1-131 Release Rate uci/sec 3.20E-03 3.71E-04 C. Particulates
1. Total Particulates Ci .03E-0 .1E-03 L.0OE+01
2. Average Release Rate uci/sec 1.29E-03 i.46E-04 l 3. Gross Alpha Radioactivit Ci 2.89E-0 1.54E-05

.ritium

1. Total Release Ci 2.67E+01 1.21E+01 5.OE+01 1 2. Average Release Rate I uci/sec I 3.36E+00 I 1.52E+00 I E. Percent Qtrly Tech Spec Reporting Levels
1. lodines, Particulates, I and Tritium  % I4.74E+00 I 5.26E-01I

Page 5 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period  : Jul - Dec 1989 Table 1B Gaseous Effluents - Elevated Releases I I Continuous Mode I Batch Mode Nuclides Released I Unit I 3rd Qtr I 4th Qtr I 3rd Qtr I 4th Qtr

1. Fission Gases KR-85 Ci 1.46E+01 1.50E+01 0.00E+00 0.00E+00 KR-85M Ci 8.92E-01 i.48E+00 00+ 0 0.OOE+00 KR-87 C1 4.33E+00 9.17E+00 0.00E+00 0.00E+00 KR-88 Ci 3.05E+00 4.28E+00 0.00E+00 0.OOE+00 KR-89. Ci 8.34E+01 1.32E-02 0.00E+ 0.00E+00 KR-90 Ci 2.83E+00 4.49E-04 0.00E+00 0.00E+00 XE-131M Ci 8.48E-01 6.37E-02 0.OOE+00 0.OOE+00 XE-133 Ci 2.11E+02 3.78E+01 0.0OE+00 0.OOE+00 XE-133M Ci 1.55E+00 8.96E-01 0.00E+00 0.00E+00 XE-135 Ci 4.65E+00 3.58E+01 0.00E+00 0.00E+00 XE-135M Ci 6.43E+O 4.13E+01 0.OOE+00 0.OOE+00 XE-137 1.09E+02 1.76E+02 0.OOE+00 0.OTE+00 XE-138 Ci 8.68E+01 1.18E+02 0.OOE+00 0.OOE+00 XE-139 Ci 8.41E+00 1.33E-03 0.00E+00 0.00E+00 Total for Period 1Ci 5.38E+02 4.40E+02 0.00E+00 0.00E+00 Iodines d -I- 3l Ci 6.09E-03 1.49E-03 0.OOE+00 0.OOE+0 I-133 Ci 1.10E-02 5.85E-03 0.OOE+00 0.OOE+00 I-135 Ci 8.09E-03 .77E-03 .OOE+ 0.00E+00 Total for Period Ci 2.52E-02 1.41E-02 0.OOE+0 0.00E+00
3. Particulates CR-51 Ci 0.OOE+00 7.96E-07 0.OOE+00 0.0oE+00 MN-54 Ci 5.47E-06 8.70E-06 0.OOE+00 0.OOE+00 CO-58 Ci 1.39E-06 .72E-07 0.OOE+00 0.OOE+00 FE-59 Ci 0.OOE+00 1.iOE-06 0.OOE+00 0.OOE+00 CO-60 Ci 3.78E-05 2.58E-05 0.00E+00 O.OOE+00 ZN-65 Ci 2.74E-06 1.87E-06 0.OOE+00 0.OOE+00 CS-134Ci 1.08E-06 4.03E-07 0.OOE+00 0.O0E+00 CS-137 Ci 3.02E-05 1.27E-05 0.OOE+00 0.OOE+00 BA-140 Ci 2.70E-04 3.94E-04 0.00E+00 0.00E+00 CE-141 Ci 9.30E-07 1.81E-07 0.OOE+00 0.OOE+00 CE-144 Ci 0.OOE+00 3.56E-07 0.OOE+00 0.OOE+00 SR-89 Ci 3.41E-04 2.27E-04 0.OOE+00 0.0OE+00 SR-90 Ci 3.30E-06 1.38E-06 0.OOE+00 0.00E+00 Total for Period _Ci 6.94E-04 6.75E-04 0.00E+00 0.OOE+00

Page 6 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - 'Dec 1989 Table 1C Gaseous Effluents - Building Vent Releases I Continuous Mode Batch Mode Nuclides Released Unit 3rd Qtr l 4th Qtr 3rd Qtr l 4th Qtr

1. Fission Gases KR-85 Ci 5.58E-03 4.52E+01 0.OOE+00 0.00E+00 I KR-85M Ci 4.23E-01 3.61E-03 0.00E+00 0.00E+00 KR-87 Ci 2.07E+00 1.79-02 0.OOE+00 0.00E+00 KR-88 Ci 1.44E+00 1.22-02 0.00E+0 0.OOE+00 KR-89 Ci 3.94E+01 3.34E-01 0.OOE+00 0.00E+00 KR-90 Ci 1.33E+00 1.13E-02 0.OOE+00 0.OOE+00 XE-131M Ci 5.64E-04 1.65E-01 0.00E+00 0.0OE+00 XE-133 Ci 2.53E-01 1.49E+01 3.85E-01 0.00E+00 XE-133M Ci 1.01E-02 8.71E-05 00+ 0.00E+00 XE-135 Ci 2.00E+00 2.84E+01 2.38E-01 6.1-E-04 XE-135M Ci 3.04E+00 4.42E+01 0.OOE+00 0.OOE+00 XE-137 Ci 5.15E+01 4.39E-01 0.OOE+00 0.00E+00 I XE-138 Ci 4.08E+01 3.46E-01 0.OOE+00 0.00E+00 I XE-139 Ci 3.97E+00 3.37E-02 0.00E+00 0.00E+00 Total for Period Ci 1.46E+02 1.34E+02 6.23E-01 6.31E-04 Iodines 1-131 Ci 1.93E-02 1.45E-03 1.30E-05 0.OOE+ 0 I I-133 Ci 2.90E-02 1.26E-02 0.00E+00 0.00E+00 I-135 Ci 3.27E-02 1.44E-02 0.00E+ 0.00E+0 Total for Period Ci 8.10E-02 2.83E-02 1.30E-05 0.00E+00
3. Particulates CR-51 Ci 9.52E-04 0.OOE+00 0.OOE+00 0.OOE+00 MN-54 Ci 7.04E-05 i.99E-05 0.OOE+00 0.00E+00 CO-58 Ci 8.75E-05 0.00E+00 0.00E+00 0.00E+00 CO-60 Ci 1.63E-03 2.42E-04 0.OOE+00 0.00E+00 ZN-65 Ci 6.42E-03 1.47E-05 0.OOE+00 0.00E+00 I RU-103 Ci 2.61E-05 0.OOE+00 0.OOE+00 0.OOE+00 I CS-134 Ci 0.OOE+00 2.96E-06 0.00E+ 0.00E+00 I CS-137 Ci 5.48E-05 7. 4E-05 0.OOE+00 0.00E+00 1 BA-140 Ci 2.87E-04 9.17E-05 0.OOE+00 0.OOE+00 I CE-141 Ci 2.06E-06 3.94E-06 0.00E+00 0.OOE+00 SR-89 Ci 3.79E-05 3.56E-05 0.OOE+00 0.0OE+00 SR-90 Ci 1.50E-06 0.OOE+00 0.OOE+00 0.00E+00 Total for Period Ci 9.57E-03 4.86E-04 0.OOE+00 0.OOE+00

Page 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1989 Table 2A Liquid Effluents - Summation of all Releases l Units 3rd Qtr 4th Qtr lEst. Totall I Error, % I A. Fission & Activation products l 1. Total Release (not includingI I I l tritium, gases, alpha) Ci 0.OOE+00 0.OOE+00 0.0OE+00 l 2. Avg Diluted Concentration uci/ml I 0.00E+00 0.00E+00 B. Tritium

1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00
2. Avg Diluted Concentration uci/ml I 0.00E+00 I 0.OOE+00_1 C. Dissolved and Entrained Gases
1. Total Release Ci 0.OOE+0 0.0E+00 0.OOE+00 I
2. Avg Diluted Concentration l uci/ml 0.OOE+00 I 0.00E+00 I D. Percent Qtrly Tech Spec Reporting Level l . Whole Body Dose  % 0.OOE+00 0.OOE+00 I

. Organ Dose  % 0.00E+00 I 0.00E+-00 I Gross Alpha Radioactivity l 1. Total Release - Ci 0.00E+0 0.O0E+00 l.OE+00 IF. Volume of Waste Released I Liters l .- 0E+00 0.00E+0 0.00E+00 I IF. Volume of Dilution Water Used Liters l 0.OOE+00 0.OOE+00 l0.0E+00 I Table 2B Liquid Effluents I I Continuous Mode Batch Mode Nuclides Released Unit I 3rd Qtr l 4th Qtr 3rd Qtr l 4th Qtr None Released This Period

Page 8 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1989

  • 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 I6-month lEst. Totall I Period Error, %_

A. Spent resins, filter sludges, Cu. Meter 2.57E+01 I evaporator bottoms, etc. Ci 3.52E+02 5.00E+01 I B. Dry compressible waste, Cu. Meter 1.68E+02 I contaminated equipment, etc. Ci I 6.17E+00 5.OOE+01 I C. Irradiated components, Cu. Meter 0.00E+00 control rods, etc. Ci 0.OOE+00 5.OOE+01 D. Other (describe) Cu. Meter 0.00E+00 Ci 0.OOE+00 5.OOE+01

2. Estimate of major nuclide Nuclide I Percent I composition (by type of waste)

A l Mn-54 5.14E+00 l Fe-55 2.55E+01 l Co-58 1.14E+00 l Fe-59 2.91E-01 l Co-60 l 5.54E+01 Zn-65 l 5.75E+00 I Sr-89 l 4.03E-01 I Sr-90 l 1.67E-01 l Zr-95 I 2.45E-02 l Ru-103 1.23E-01 l 1-131 l 8.35E-02 I Cs-134 I 9.12E-01 Cs-137 l 3.67E+00 I Ba-140 l 8.87E-02 l Ce-141 l 1.34E-01 II_________________

B l Cr-51 I 2.56E+00 I Mn-54 I 1.12E+01 I Fe-55 l 3.07E+01 Co-58 l 5.68E-01 l Fe-59 l 7.70E-01 l Co-60 l 3.19E+01 l Zn-65 j 3.15E+00 l Sr-89 1.03E+00 l Sr-90 j 3.49E-01 l Cs-134 1.44E+00 Cs-137 l 4.75E+00 Ba-140 l 4.44E-01 l La-140 l 4.38E-01

Page 9 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1989 Table 3 Solid Waste and Irradiated Fuel Shipments

3. Solid waste disposal Number of l Mode of l Destination Shipments Transportation 3 Truck Chem-Nuc Inc., Barnwell, SC.

3 Railway Chem-Nuc Inc., Barnwell, SC.

7 Truck US Ecology, Richland, WA.

B. Irradiated Fuel Shipments

1. Disposition Number of Mode of Destination Shipments Transportation None This Period C. Shipping Container and Solidification Method Volume Activity Type ot Container Solidification M3 Ci Waste Code Code

-~ I. I - t PF- 24 5.83E+00 2.29E+Ul A A D 89-26 3 . 41E+00 1. 33E+02 A A D 89-34 3.81E+01 1.14E+00 B L N 89-40 3. 55E+00 7 .32E+01 A A C 89-47 3. 55E+00 2. 23E+01 A A C 89-57 1.70E+01 5.85E-01 B L N 89-61 1.70E+01 7 . 79E-01 B L N 89-52 3. 55E+00 8.71E+00 A A C 89-74 1.70E+01 5.60E-01 B L N 89-91 3. 79E+01 1. 84E+00 B L N 89-92 5.83E+00 9.11E+01 A A D 89-99 2.40E+01 6. 24E-01 B L N 89-88 1.70E+01 6 .50E-01 B L N

.1. U a 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

PCP 3.0 Revision 8 Page 1 of 4 PROCESS CONTROL PROGRAM PCP 3.0 ABSORPTION OF LIQUID WASTES Prepared by: Date S17/e7 Reviewed by: / Vj~r> Date // 9 f User Review by: Z- I Date QA Review: Revision 7 Date 5/2/88 Q.A. Revision Review Required: Yes No X ALARA Review: Revision 7 Date 5/17/88 ALARA Revision Review Required: Yes No X Operations Committee Final Review: Meeting Number: 1I7 Date (f (3obIL?

Op. Com. Revision Review Required: Yes X No Approved by: Date /Z,2 P WP/djj

PCP 3.0 Revision 8 Page 2 of 4 3.0 ABSORPTION OF LIQUID WASTES Table of Contents Section Section Title Page PCP 3.1 Purpose 3 PCP 3.2 Applicability 3 PCP 3.3 Description of Operation 3 PCP 3.4 Operation 3 PCP 3.5 Verification of Absorption 3 PCP 3.6 Sample Absorption of Liquid Wastes 3 WP/djj

PCP 3.0 Revision 8 Page 3 of 4

. 3.0 ABSORPTION OF LIQUID WASTES 3.1 Purpose To establish the process parameters which provide reasonable assurance of complete absorption of liquid wastes.

3.2 Applicability This section of the PCP is applicable to the manual absorption of liquid wastes with approved absorbent material. Waste liquids which may be absorbed include:

A. Oils B.. Chemical Waste C. Laundry Waste 3.3 Description of Operation The absorbent of liquid waste is a manual process in which the waste and absorbent are repetitively layered, absorbent-waste-absorbent-waste, in an approved container. Approved absorbent materials are listed in the current revisions of the site license or site criteria. The specific absorbent material will be assigned to the project by the Radioactive Material Shipping Coordinator (RMSC) after checking the site requirements.

The drums are then capped and stored awaiting shipment to the approved burial site.

3.4 Operation A representative sample of each type of waste is to be sampled and analyzed for isotopic content. After sampling, the waste is to be layered with absorbent into an approved shipping container starting with absorbent. The drum is then inspected, capped and stored.

3.5 Verification of Absorption Each container is to contain twice the amount of absorbent required for absorption, as determined prior to the full-scale absorption.

If absorption fails to take place, the process shall be suspended until the cause is determined and remedies are defined.

3.6 Sample Absorption of Liquid Wastes 3.6.1 Sampling Requirements Each type of waste to be absorbed is to be sampled.

WP/djj

PCP 3.0 Revision 8 Page 4 of 4 3.6.2 Prerequisites Before drawing a sample of waste, the waste must be adequately mixed to achieve a representative sample.

3.6.3 Sample Preparation Obtain a speciman of each waste in the required volume.

The volume required will normally be 1000 ml.

3.6.3.1 Transfer 250 ml of samples to 2-liter containers for each type of waste. Record the sample number.

Note: Label container and sample with same number.

3.6.3.2 Add approximately 500 ml of absorbent material to each container and mix for a minimum of 30 seconds.

3.6.3.3 Record results.

3.6.3.4 Add approximately 50 ml absorbent material to each container, and record results.

3.6.3.5 Continue to add about 50 ml of absorbent material and record results until some uncoated absorbent remains.

Note: Acceptable ratio is approximately 3 to 1.

3.6.4 Sample Acceptance Criteria 3.6.4.1 Visual inspection after mixing will confirm that there is some uncoated absorbent material.

3.6.4.2 If no uncoated absorbent remains refer to 3.6.3.5.

WP/djj

Process Control Program Revision Summary

1. Description of Change:

Section 3.0, Absorption of Liquid Wastes, was revised to incorporate a clarification on the method used to absorb liquid waste. Words were added to make it clear that waste and absorbent are repetitively layered, absorbent-waste-absorbent.

The revision was prompted by comments contained in an NRC review of Revision 4 of the PCP.

2. The change does not reduce the overall conformance of the solidified waste product to existing criteria.
3. The change was reviewed and found acceptable by the Operations Committee in meeting #1697, November 30, 1989.
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