ML20197B224
| ML20197B224 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/31/1985 |
| From: | ALABAMA POWER CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8610280267 | |
| Download: ML20197B224 (230) | |
Text
{{#Wiki_filter:_ _ _ - f u l l 1 1 ALABAMA POWER COMPANY j FARLEY NUCLEAR PLANT UNIT NO. ONE I LICENSE NO. NPF-2 AND FARLEY NUCLEAR PLANT UNIT NO. TWO LICENSE NO. NPF-8 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY 1, 1985 THROUGH DEC. 31, 1985 8610280267 851231 PDR ADOCK 05000348 R PDR
TABLE OF CONTENTS SUBJECT PAGE A. Introduction ~1 B. Supplemental Information for Effluent and Waste Disposal
- 1. Regulatory Limits 2
- a. Fission and Activation Gases
- b. Iodir.e s and Particulates
- c. Liquid Effluents
- 2. Maximum Permissible Concentrations 3
- a. Airborne
- b. Liquid
- 3. Average Energy 3
- 4. Measurements and Approximations of Total 3 Activity
- a. Fission and Activation Gases
- b. Iodines and Particulates
- c. Liquid Effluents
- 5. Batch Releases 6
- a. Liquid
- b. Gaseous
- 6. Abnormal Releases 6
- a. Liquid
- b. Gaseous i
TABLE OF CONTENTS (con't) l SUBJECT PAGE l
- 7. Estimate of Total Error 8
- 8. Solid Waste 9 l
- 9. Radiological Impact on Man 9
- 10. Meteorological Data 11
- 11. Minimum Detectable Concentration (MDC) 11
- 12. Annual Radiation Dose Assessment 11
- 13. Deviations from the Gaseous Waste Release 12 Program
- 14. Deviations from the Liquid Waste Release 13 Program
- 15. Process Control Program 89 11
LIST OF TABLSS TABLE PAGE 1A-1Q3 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES, 15 Farley Unit 1 - 3rd Quarter, 1985 1A-1Q4 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES, 16 Farley Unit 1 - 4th Quarter, 1985 1A-2Q3 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES, 17 Farley Unit 2 - 3rd Quarter, 1985 1A-2Q4 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES, 18 Farley Unit 2 - 4th Quarter, 1985 1B-1Q3 GASEOUS EFFLUENTS--ELEVATED RbLEASE, Farley 19 Unit 1 - 3rd Quarter, 1985 l l 1B-1Q4 GASEOUS EFFLUENTS--ELEVATED RELEASE, Farley 20 l Unit 1 - 4th Quarter, 1985 1B-2Q3 GASEOUS EFFLUENTS--ELEVATED RELEASE, Farley 21 Unit 2 - 3rd Quarter, 1985 1B-2Q4 GASEOUS EFFLUENTS--ELEVATED RELEASE, Farley 22 Unit 2 - 4th Quarter, 1985 1C-1Q3 GASEOUS EFFLUENTS--GROUND RELEASE, Farley 23 Unit 1 - 3rd Quarter, 1985 1C-1Q4 GASEOUS EFFLUENTS--GROUND RELEASE, Farley 24 Unit 1 - 4th Quarter, 1985 1C-2Q3 GASEOUS EFFLUENTS--GROUND RELEASE, Farley 25 Unit 2- 3rd Quarter, 1985 1C-2Q4 GASEOUS EFFLUENTS--GROUND RELEASE, Farley 26 Unit 2 - 4th Quarter, 1985 2A-1 LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES, 27 Farley Unit 1 - 2nd Half, 1985 2A-2 LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES, 28 Farley Unit 2 - 2nd Half, 1985 2B-13 LIQUID EFFLUENTS--BATCH, Farley Unit 1 29 2nd Half, 1985 2B-2B LIQUID EFFLUENTS--BATCH, Farley Unit 2 30 2nd Half, 1985 i t 'i
LIST OF TABLES (cont.) TABLE PAGE 2B-1C LIQUID EFFLUENTS--CONTINUOUS, Farley Unit 1 31 2nd Half, 1985 2B-2C LIQUID EFFLUENTS--CONTINUOUS, Farley Unit 2 32 2nd Half, 1985 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS, 33 2nd Half, 1985 4A-CQ3 CUMULATIVE JOINT FREQUENCY DISTRIBUTION, 35 Continuous Mode - 3rd Quarter, 1985 4A-CQ4 CUMULATIVE JOINT FREQUENCY DISTRIBUTION, 49 Continuous Mode - 4th Quarter, 1985 4A-1BQ3 CUMULATIVE JOINT FREQUENCY DISTRIBUTION, 63 Unit i Batch Mode - 3rd Quarter, 1985 4A-1BQ4 CUMULATIVE JOINT FREQUENCY DESTRIBUTION, 64 Unit i Batch Mode - 4th Quarter, 1985 4A-2BQ3 CUMULATIVE JOINT FREQUENCY DISTRIBUTION, 65 Unit 2 Batch Mode - 3rd Quarter, 1985 4A-2BQ4 CUMULATIVE JOINT FREQUENCY DISTRIBUTION, 66 Unit 2 Batch Mode - 4th Quarter, 1985 4B CLASSIFICATION OF ATMOSPHERIC STABILITY 67 5 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS 68 PROGRAM, Units 1 & 2 6 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS 71 PROGRAM, Units 1 & 2 7 LIQUID DISCHARGES NOT MEETING SPECIFIED DETECTION 74 LIMITS, Units 1 & 2 - 2nd Half, 1985 3-CA CUMULATIVE JOINT FREQUENCY DISTRIBUTION, 75 Continuous Mode - Annual, 1985 iv
INTRODUCTION This semi-annual radioactive release report, for the period July 1 through December 31, 1985, is submitted in accordance with Appendix A of License No.'s NPF-2 and NPF-8. Appendix A will hereinafter be referred to as the Standard Technical Specifications or STS. A single submittal.is "ade for both units which combines those sections that are common. Separate tables of releases and release totals are included where separate processing systems exist. This report includes an annual summary of hourly meteorological data collected over the past year and an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Farley Nuclear Plant site over the same period. Additionally Section 12.d with associated dose contributions to sectors comprises an assessment of radiation doses to the likely most exposed member of the public from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation). All assessments of radiation doses are performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). 1
- 3. SUPPLIMENTAL INFORMAT CN ?CR EFFLUENT AND ~4ASTS DISPCSAL
- 1. Regulatory Limits
- a. Fission and Activation Gases
- 1. The dose rate from the site at any time due to noble gases shall be less than or equal to 500 mrem /yr to the total body and 3000 mrem /yr to the skin.
- 2. The air dose from each reactor unit from the site during any calendar quarter due to noble gases shall shall be less than or equal to 5 mrad for gamma radiation and 10 mrad for beta radiation.
- 3. The air dose from each reactor unit from the site during any calendar year due to noble gases shall be less than or equal to 10 mrad for gamma radiation and 20 mrad for beta radiation.
- b. Iodines and Particulates
- 1. The dose rate from the site at any time due to iodines, particulates and radionuclides with half-lives greater than 8 days shall be less than or equal to 1500 mrem /yr to any organ.
- 2. The dose from each reactor unit from the site during any calendar quarter due to iodines, particulates and radionuclides with half-lives greater than 8 days shall be less than or equal to 7.5 mrem to any organ.
- 3. The dose from each reactor unit from the site during any calendar year due to iodines, particulates and radionuclides with half-lives greater than 8 days shall be less than or equal to 15 mrem to any organ,
- c. Liquid Effluents
- 1. The concentration of radioactive materials released in liquid effluents to unrestricted areas from all reactors at the site shall not exceed at any time the values specified in 10 CFR Part 20, Appendix B, Table II, Column 2. The concentration of dissolved or en-trained noble gases, released in liquid effluents to unrestricted areas from all reactors at the site, shall not exceed at any time 2E-4 uCi/ml in water.
- 2. The dose or dose commitment due to liquid effluents released from each reactor unit from the site during any calendar quarter shall be less than or equal to 1.5 mrem to the total body and 5 mrem to any organ.
- 3. The dose or dose commitment due to liquid effluents released from each reactor unit from the site during any calendar year shall be less than or equal to 3 mrem to the total body and 10 mrem to any organ.
2
- 2. Maximum Permissible Concentrations
- a. Airborne - The maximum permissible concentration of radioactive materials in gaseous effluents is limited by the dose rate restrictions of 10CFR20. In this case, the maximum permissible concentrations are actually determined by the dose factors in the ODCM.
- b. Liquid - 10 CFR Part 20, Appendix 3, Table II, Column 2.*
- NOTE: The MPC chosen is the most conservative value of either the soluble or insoluble MFC for each isotope.
- 3. Average Energy Not applicable for Farley's STS.
- 4. Measurements and Approximations of Total Activity The following discussion details the methods used to measure and approximate total activity for the following*
- a. Fission and Activation Gases
- b. Iodines and Particulates
- c. Liquid Effluents Tables 5 and 6 give sampling frequencies and minimum detectable concentration requirements for the analysis of gaseous and liquid effluent streams, respectively.
Values in the attached tables given as zero do not mean that the nuclides were not present. A zero indicates that the nuclide was not present at levels greater than the sensitivity requirements shown in Tables 5 and 6. For some nuclides, lower detection limits than required may be readily achievable; when a nuclide is measured below its stated limit, it is reported.
- a. Fission and Activation Gases The following noble gases are considered in evaluating gaseous airborne discharge:
Kr-87 Xe-133 Kr-88 Xe-135 Xe-133m Xe-138 3
Periodic grab samples from plant effluent streams are analyzed by a computerized pulse height analyzer system utilizing high resolution germanium detectors. (See Table 5 for sampling and analytical requirements). Isotopic values thus obtained are used for release rate calculations as specified in the ODCM. Only those nuclides that are detected are used in this computation. During the period between grab samples, the amount of radio-activity released is based on the effluent monitor readings. Monitors are assigned a calibration factor based upon the last isotopic analysis using the following relationship: CF =A /m , where i i CF = isot.opic calibration factor for isotope 1. i A = concentration of isotope in the grab sample, in i uCi/ml. m = net monitor reading associated with the effluent stream Wese calibration factors along with the hourly effluent monitor readings are inputs to the laboratory computer where the release rates for individual nuclides are calculated and stored. To ensure isotopic distributions do not change significantly during major operational occurrences, the frequency of grab sampling is increased to satisfy the requirements of footnotes b & d of STS Table 4.11-2, " Radioactive Gaseous Waste Sampling and Analysis Program".
- b. Iodines and Particulates The radioiodines and radioactive materials in particulate forms to be considered are:
Mn-54 I-131 Fe-59 I-133 Co-58 Cs-134 Co-60 Cs-137 Zn-65 Ce-141 Sr-89 Ce-144 Sr-90
- H-3 Mo-99 Other nuclides with half-lives greater than 8 days which are identified and measured are also considered. We MDC's will vary and are not required to meet the MDC limits of those isotopes listed specifically.
- Tritium is considered in the gaseous or water vapor form.
4.
Continuous Releases: Continuous sampling is performed on ne continuous release points (i.e. the ?lant Vent Stack, Containment Purge and the Turbine Building 7ent). Particulate material is collected by filtration. Periodically these filters are removed and analyzed on the pulse height analyzer to identify and quantify radioactive materials collected on the filters. Particulate filters are then analyzed for gross alpha and strontium as required. Gross alpha determinations are made using a 2 pi gas flow proportional counter. Sr-89 and 90 values are obtained by chemical separation l and subsequent analysis using 2 pi gas flow proportional counters. Batch Releases: The processing of batch type releases (from Containment or Waste Gas Decay Tanks) is analogous to continuous releases, except that the release is not commenced until samples have been obtained and analyzed.
- c. Liquid Effluents The radionuclides listed below ace considered when evaluating liquid effluents:
Mn-54 I-131 Fe-59 Cs-134 Co-58 Cs-137 Co-60 Ce-141 2n-65 Ce-144 Sr-89 Mo-99 Sr-90 Fe-55 H-3 Batch Releases: Representative pre-release grab samples are obtained and analyzed per Table 6. Isotopic analyses are performed using the computerized pulse height analysis system previously described. Aliquots of each pre-release sample proportional to the waste volume released are composited in accordance with requirements in Table 6. Strontium and Iron determinations are made by performing a chemical separation and counting the isotope thus separated using a 2 pi gas flow proportional counter.
- Gross beta and gross alpha determinations are made using 2 pi gas flow proportional counters. Tritium concen-trations are determined by using liquid scintillation techniques. Dissolved gases are determined employing grab sampling techniques and then counting on the pulse height analyzer.
Continuous Releases: Continuous releases (from the Steam Generator Blowdown) are analogous to that of the batch releases except that they are analyzed on a weekly
-composite basis per Table 6.
1 5
.-. . - _ _ - , _ .c - , _ - _ , - . ,, .- -_ . , - -
UNIT # 1 1985
- 5. Batch Release
- a. Liquid Quarter 3 Quarter 4
- 1. Number of batch releases: 77 74
- 2. Total time period for releases: 6550 min. 6044 min.
- 3. Maximum time period for a release: 120 min. 153 min.
- 4. Average time period for a release: 85 min. 82 min.
- 5. Minimum time period for a release: 53 min. 44 min.
- 6. Average stream flow during periods of release of effluent into a *1.15E4 cfs *1.15E4 cfs flowing stream:
- b. Gaseous Quarter 3 Quarter 4
- 1. Number of releases: 0 0
- 2. Total time period for releases: 0 min. O min.
- 3. Maximum time period for a release: 0 min. O min.
- 4. Average time period for a release: O min. O min.
- 5. Minimum time period for a release: 0 min. O min.
- 6. Abnormal Releases i
- a. Liquid
- 1. Number of releases: NONE
- 2. Total activity released: N/A
- b. Gaseous
- 1. Number of releases: NONE
- 2. Total activity released: N/A
- Annual Average River Flow Rate.
6
1 l l UNIT # 2 1985
- 5. Batch Release
- a. Liquid Quarter 3 Quarter 4
- 1. Number of batch releases: 58 53
- 2. Total time period for releases: 5148 min. 4559 min.
- 3. Maximum time period for a release: 162 min. 145 min.
- 4. Average time period for a release: 89 min. 86 min.
- 5. Minimum time period for a release: 65 min. 40 min.
- 6. Average stream flow during periods of release of effluent into a *1.15E4 cfs *1.15E4 cfs flowing stream:
- b. Gaseous Quarter 3 Quarter 4
- 1. Number of releases: 0 0
- 2. Total time period for releases: 0 min. O min.
- 3. Maximum time period for a release: 0 min. O min.
- 4. Average time period for a release: 0 min. O min.
- 5. Minimum time period for a release: 0 min. O min.
- 6. Abnormal Releases
- a. Liquid
- 1. Number of releases: None
- 2. Total activity released: N/A
- b. Gaseous
- 1. Number of releases: None
- 2. Total activity released: N/A
- Annual Average River Flow Rate.
7
- 7. Estimate of Total Error
- a. Liquid
- 1. The maximum error associated with volume and flow measurements, based upon plant calibration practice is estimated to be + or - 10%.
- 2. The average error associated with counting is estimated to be less than + or - 15%.
- b. Gaseous
- 1. The maximum errors associated with monitor readings, sample flow, vent flow, sample collection, monitor calibration and laboratory procedure are collectively estimated to be:
Fission and ,. Activation Gases Iodines Particulates Tritium
~
75% 60% 50% 45%
- 2. The average error associated with counting is estimated to be:
Fission and Activation Gases Iodines Particulates Tritium 6% 18% 19% 12%
- c. Solid Radwaste The error involved in determining the contents of solid radwaste shipments is estimated to be less than + or -
15%. 8
UNIT # 1 1985
- 8. Solid Waste See Table 3
- 9. Radiological Impact On Man
- a. Water Related Exposure Pathways 3rd Quarter 4th Quarter Total Body = 1.6E-03 mrem 1.2E-03 mrem Bone = 8.5E-04 mrem 5.1E-04 mrem Liver = 3.4E-03 mrem 2.1E-03 mrem Thyroid = 6.9E-04 mrem 6.7E-04 mrem Kidney = 8.6E-04 mrem 8.0E-04 mrem -
Lungs = 3.3E-03 mrem 1.9E-03 mrem GI Tract = 4.7E-03 mrem 2.4E-03 mrem
- b. Gaseous Related Exposure Pathways 3rd Quarter 4th Quarter Total Body = 3.4E-02 mrem 1.4E-02 mrem Skin = 8.1E-02 mrem 3.1E-02 mrem
- c. Particulate and Iodine 3rd Quarter 4th Quarter Organ Dose = 1.1E-02 mrem 4.1E-02 mrem 9
UNIT # 2 1985 j d
- 8. Solid Waste See Table 3
- 9. Radiological Impact On Man
- a. Water Related Exposure Pathways 3rd Quarter 4th Quarter Total Body = 9.5E-04 mrem 1.5E-03 mrem Bone = 3.3E-02 mrem 1.9E-04 mrem Liver = 1.1E-03 mrem 1.6E-03 mrem Thyroid = 9.2E-04 mrem 1.3E-03 mrem Kidney = 9.5E-04 mrem 1.4E-03 mrem Lungs = 1.1E-03 mrem 1.6E-03 mrem GI Tract = 3.4E-03 mrem 3.6E-03 mrem 4
- b. Gaseous Related Exposure Pathways 3rd Quarter 4th Quarter Total Body = 1.6E-02 mrem 1.1E-02 mrem Skin = 3.5E-02 mrem 1.6E-02 mrem
- c. Particulate and Iodine 3rd Quarter 4th Quarter Organ Dose = 3.9E-02 mrem 3.2E-02 mrem 4
1 10
- 10. Meteorological Data See Tacle 4A, ' Cumulative Joint- Frequencf Distribution'.
Continuous Release Mede: 3rd Quarter, 1985 : 4A-CQ3 4th-Quarter, 1985 : 4A-CQ4 Batch Release Mode (Units 1&2): 3rd Quarter, 1985 : 4A-1BQ3 & 4A-2BQ3 4th_ Quarter, 1985 : 4A-1BQ4 & 4A-2BQ4
- 11. Minimum Detectable Concentration (MDC)
Detectable limite for activity analyses are based upon the technical feasibility and on the potential significance in the environment of the quantities released. However, in practice, when an isotope's a posteriori MDC could not be met due to other nuclides being present in much greater concentrations, the a priori MDC as defined in the STS Table 4.11-1 a. is relied upon.
- 12. Annual Radiation Dose Assessment (1985)
- a. Water Related Exposure Pathways i Total Body = 3.2E-02 mrem Bone = 7.5E-02 mrem i Liver = 5.4E-02 mrem Thyroid = 8.7E-03 mrem Kidney = 2.0E-n2 mrem Lungs = 2.2E-02 mrem GI Tract = 6.4E-02 mrem-
- b. Gaseous Related Exposure Pathways Total Body = 1.3E-01 mrem Skin = 3.0E-01 mrem
- c. Particulate and Iodine Organ = 1.8E-01 mrem i
Note: The meteorological conditions concurrent with the
' time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement- outlined in Table 5) have been used for the gaseous pathway doses. The assessment of radiation doses has been performed in accordance with the OFFSITr' DOSE CALCULATION MANUAL (ODCM).
11
- d. Maximum Real Exposure h e maximum real exposure is an assessment of radiation doses to the likely most exposed member of the public from reactor releases and other nearby uranium fuel cycle sources including doses from all primary effluent pathways and direct radiation (liquid pathways are limited to the Chattahoochee River) for the previous 12 consecutive months in conformance with 40 CFR 190.
A tabulation of doses to sixteen 22.5 degree sectors around the plant calculated at the site boundary provides the quarterly and yearly dose for each sector. %e dose or dose commitment to any member of the public due to releases of radioactivity and radiation from uranium fuel cycle ; sources are limited by STS to less than or equal to 25 mrem j to the total body or an organ (except the thyroid which is limited to less than or equal to 75 mrem) over 4 consecutive quarters. This technical specification is provided to meet the dose limitations of 40 CFR 190. Since the Farley Nuclear Plant is the only uranium fuel cycle source within a radius of 50 miles, the dose to any member of the public will be less than the dose in the highest sector. We tabulation below includes the highest organ dose or the whole body dose if greater for each quarter from liquid effluents. We tabulation also includes the quarterly and yearly doses from the highest sector for each of the following:
- 1. Gaseous iodine / particulate
- 2. Noble gases
- 3. Direct radiation (It should be noted that the direct radiation values reported herein include background radiation. Based upon preoperational data, the reported direct radiation doses are essentially all attributable to background radiation.)
i 12.
MAXIMUM
- OFF-SITE DOSES AND DOSE COMMI'IMENTS
'IO MEMBERS OF THE PUBLIC Dose, Millire.M Source 1st Qtr 2nd Qtr 3rd Qtr 4th Otr Year **
Note: Organ LIV G1 BONE G1 BONE Liquid Effluents (1) 3.6E-02 3.3E-02 3.4E-02 6.OE-03 7.5E-02 Airborne Effluents Sector WSW SSW SW WSW WSW Iodines & 8.2E-03 4.4E-03 1.3E-02 2.3E-02 4.7E-02 Particulates (2) Sector S W WSW WSW WSW Noble gases (3) 3.6E-03 3.4E-03 1.3E-02 6.9E-03 2.5E-02 Sector E NE NE SE E Direct Radiation (4) 3.3E 01 2.5E 01 3.7E 01 3.5E 01 9.7E 01
*" Maximum" means the largest fraction of the corresponding 10CFR50 Appendix I dose design objective.
=*" Maximum" dose for the year may not equal the sum of the quarterly maximum doses because the doses may be to different organs or may occur at different places.
Note:
- 1. %e liquid effluent total body and organ doses are determined primarily by the fish pathway. Wese are calculated using the bioaccumulation factors, dose conversion factors and assumptions of Regulatory guide 1.109 (March 1976).
- 2. Airborne effluent iodine and particulate doses are determined through the inhalation pathway using reported isotopic concentrations, atmospheric dispersion assumptions of Regulatory guide 1.111 (March 1976) and inhalation dose factors of Regulatory guide 1.109. Once calculated these doses are multiplied by a constant (238) to convert them to the grass / cow /
milk pathway equivalents in accordance with the OFFSITE DOSE CALCULATION MANUAL ODCM).
- 3. The noble gas doses are determined using the measured isotopic concentrations, the atmospheric dispersion assumptions of Regulatory guide 1.111 and submersion dose factors from Regulatory guide 1.109.
- 4. Direct radiation was assessed using thermal luminescent dosimetry. Two dosimeters containing three LiF TLD chips each were placed at selected locations within each of 16 sectors around the plant. %ese chips were collected and read quarterly and annually.
13.
- 13. Deviations from the Gaseous Waste Release Program.
No deviaions from the Gaseous Waste Release Program occurred.
- 14. Deviations from the Liquid Waste Release Program.
A review of the liquid effluent software program at FNP revealed an error in the code which calculated the total dilution water released from each unit. We liquid effluent software is designed to cover three modes of radiological liquid release: steam generator blowdown, waste monitor tank, and turbine building sump. Steam generator blowdown is in near continual release with a volume of dilution water attributed to the entire period of steam generator blowdown discharge. As a result, the volume of dilution water associated with steam generator blowdown closely approximates the total dilution water released from each unit. Additionally, waste monitor tanks and turbine building sumps have a volume of dilution water attributed to each batch release and these releases may, and normally do, occur simultaneously with steam generator blowdown releases. We computer code, when calculating the total dilution volume failed to recognize the fact that the dilution volume was being duplicated when a waste monitor tank or turbine building sump batch release overlapped a steam generator blowdown release. hus, this failure results in a over quantification of total dilution volume. We double accounting of dilution volume in no way invalidates the dose calculations since the dose calculated for each release is based on the dilution water discharged at the time of the release. he only inaccuracy resulting from this accounting error is the reported total dilution volume and the concentration-at-discharge values reported . in the Reg. Guide 1.21, " Semi-Annual Effluent Relaase Report". An accurate method for determining total dilution volume has been implementted and the values reported herein are valid. However, since ENP's Technical Specifications are " dose based" and no error occurred in dose calculations, no attempt will be made to correct previously submitted
" Semi-Annual Effluent Release Report" data. To prevent recurrence of this arror, INP has implemented a reasonableness check for total dilution flow for future reporting.
14. J
TA3LE LA-103 GASECUS I??LUENTS--5UMMATION CF ALL RELEASES Farley Unit 1 - 3rd Quarter, 1985 UNITS' QTR 3 Est Error A. Fission & activation gases:
- 1. Total release Ci 5.38E 02 1.41E 01
- 2. Average release rate uCi/sec 6.77E 01
- 3. % of Technical Specification % 1.27E-03*
% 2.67E-03*w
- 3. Iodines
- 1. Total iodine-13L Ci 1.23E-05 5.45E-06
- 2. Average release rate uCi/sec 1.55E-06
- 3. % of Technical Specification % 4.71E-09***
( , C. Particulates
- 1. Particulates with T1/2>8 days Ci 0.00E 00 0.00E 00
- 2. Average release rate uCi/sec 0.00E 00
- 3. % of Technical Specification % 0.00E 00**w
- 4. Gross alpha radioactivity Ci 0.00E 00 D. Tritium
- 1. Total release Ci 2.80E 01 2.39E-01
- 2. Average release rate uCi/sec 3.52E 00
- 3. 4 of Technical Specification % 3.26E-07xw=
*: ~4 hole body limit (<500 mrem /yr)
**: Extrem. limit.(<3000 mrem /yr) ww*: % of 1500 mrem /yr for all la isotope
't i l 15
TABLE 1A-1Q4 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES Farley Unit 1 - 4th Quarter, 1985 UNITS QTR 4 Est Error A. Fission & activation gases:
- 1. Total release Ci 1.49E 02 9.09E 00
- 2. Average release rate uCi/sec 1.87E 01
- 3. % of Technical Specification % 4.70E-04*
% 9.70E-04**
B. Iodines
- 1. Total iodine-131 Ci 2.11E-05 6.66E-06
- 2. Average release rate uCi/sec 2.66E-06
- 3. % of Technical Specification % 8.09E-09***
C. Particulates
- 1. Particulates with T1/2>8 days Ci 0.00E 00 0.00E 00
- 2. Average release rate uCi/sec 0.00E 00
- 3. 4 of Technical Specification % 0.00E 00***
- 4. Gross alpha radioactivity Ci 0.00E 00 D. Tritium
- 1. Total release Ci 6.95E 01 3.36E-01
- 2. Average release rate uCi/sec 8.74E 00
- 3. 4 of Technical Specification % 8.10E-07***
*: Whole body limit (<500 mrem /yr)
**: Extrem. limit (<3000 mrem /yr)
***: 4 of 1500 mrem /yr for all 18 isotopes 16
TABLE 1A-2Q3 GASEOUS EFFLUENTS--SUMMATION OF ALL' RELEASES Farley Unit 2 - 3rd Quarter, 1985 UNITS QTR 3 Est Error A. Fission & activation gases:
- 1. Total release Ci 2.19E 02 1.38E 01
- 2. Average release rate uCi/sec 2.76E 01
- 3. 4 of Technical Specification % 7.84E-04*
% 1.45E-03**
B. Iodines
- 1. Total iodine-131 Ci 2.86E-05 5.29E-06
- 2. Average release rate uCi/sec 3.60E-06
- 3. % of Technical Specification % 1.10E-08***
C. Particulates
- 1. Particulates with T1/2>8 days Ci 0.00E 00 0.00E 00
- 2. Average release rate uCi/sec 0.00E 00
- 3. % of Technical Specification % 0.00E 00***
- 4. Gross alpha radioactivity Ci 0.00E 00 D. Tritium
- 1. Total release Ci 8.80E 01 5.41E-01
- 2. Average release rate uCi/sec 1.11E 01
- 3. % of Technical Specification % 1.03E-06***
*: Whole body limit (<500 mrem /yr)
**: Extrem. limit (<3000 mrem /yr)
***: % of 1500 mrem /yr for all 18 isotopes 1
17
TABLE 1A-2Q4 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES Farley Unit 2- 4th Quarter, 1985 UNITS QTR 4 Est Error < A. Fission & activation gases:
- 1. Total release Ci 1.08E 02 8.57E 00
- 2. Average release rate uCi/sec 1.36E 01
- 3. % of Technical Specification % 6.11E-04*
% 1.03E-03**
B. Iodines
- 1. Total iodine-131 Ci 8.80E-07 1.49E-07
- 2. Average release rate uCi/sec 1.11E-07
- 3. % of Technical Specification % 3.37E-10***
C. Particulates
- 1. Particulates with T1/2>8 days ci 0.00E 00 0.00E 00
- 2. Average release rate uCi/sec 0.00E 00
- 3. % of Technical Specification % 0.00E 00***
- 4. Gross alpha radioactivity Ci 0.00E 00 D. Tritium
- 1. Total release Ci 7.66E 01 4.75E-01
- 2. Average release rate uCi/sec 9.64E 00
- 3. % of Technical Specification % 8.93E-07***
*: Whole body limit (<500 mrem /yr)
**: Extrem. limit (<3000 mrem /yr)
***: % of 1500 mrem /yr for all 18 isotopes 18
7A37I 13-103 3ASICUS EEFLUENTS--ELEVATED ?.ELIASE Farley Uni: 1 - 3rd Quarter, 1985 CCNTINUCUS SATCE Mode Mode Nuclides Released Unit QTR# 3 Q"'R# 3
- 1. Fission gases Ar-41 Ci 8.07E 00 0.00I 00 Xe-138 Ci 0.00E 00 0.00E 00 Ci 2.50E-02 0.00E 00 Kr-87 Ci 3.76E-02 0.00E 00 Kr-85M Ci 2.14E 01 0.00E 00 Xe-135 0.00E 00 Xe-133M Ci 3.22E 00 Ci 1.30E-01 0.00E 00 Kr-88 Ci 4.83E 02 0.00E 00 Xe-133 Total for period Ci 5.16E 02 0.00E 00
- 2. Iodines ,
I-133 Ci 3.68E-06 0.00E 00 Ci 1.18E-05 0.00E 00 I-131 Total for period Ci 1.55E-05 0.00E 00
- 3. Particulates
- Mo-99 Ci 0.00E 00 0.00E 00 Co-60 Ci 0.00E 00 0.00E 00 Ci 0.00E 00 0.00E 00 Zn-65 C i' O.00E 00 0.00E 00 Fe-59 Ci C.00E 00 0.00E 00 Mn-54 -
0.00E 00 Co-56 Ci 0.00E 00 Ci 0.00E 00 0.00E 00 Cs-137 0.00E 00 Cs-134 Ci 0.00E 00 Ci 0.00E 00 0.00E 00
- I-133 Ci 0'.00E 00 0.00E 00 I-131 Ci 0.00E 00 0.00E 00 Ce-141 0.00E 00 Ce-144 Ci 0.00E 00 Ci 0.00E 00 0.00E 00 Sr-89 0.00E 00 Sr-90 Ci , 0.00E 00 Total for period Ci 0.00E 00 0.00E 00
* !sotope with half-life less than 8 days L9
TABLE 13-1Q4 GASECUS EFFLUENTS--ELEVATED RELEASE Farley Unit 1 - 4th Quarter, 1985 CONTINUOUS BATCH Mode Mode Nuclides Released Unit QTR# 4 QTR# 4
- 1. Fission gases Ar-41 Ci 2.48E 00 0.00E 00 Xe-138 Ci 0.00E 00 0.00E 00 Kr-87 Ci 0.00E 00 0.00E 00 Kr-85M Ci 1.95E-02 0.00E 00 Xe-135 Ci 1.94E 01 0.00E 00 Xe-133M Ci 0.00E 00 0.00E 00 Kr-88 Ci 1.80E-01 0.00E 00 Xe-133 Ci 1.20E 02 0.00E 00 Total for period Ci 1.43E 02 0.00E 00
- 2. Iodines I-133 Ci 3.60E-06 0.00E 00 I-131 Ci 1.99E-05 0.00E 00 Total for period Ci 2.36E-05 0.00E 00
- 3. Particulates
- Mo-99 Ci 0.00E 00 0.00E 00 Co-60 Ci 0.00E 00 0.00E 00 2n-65 Ci 0.00E 00 0.00E 00 Fe-59 Ci 0.00E 00 0.00E 00 Mn-54 Ci 0.00E 00 0.00E 00 Co-58 Ci 0.00E 00 0.00E 00 Cs-137 Ci 0.00E 00 0.00E 00 Cs-134 Ci 0.00E 00 0.00E 00
- I-133 Ci 0.00E 00 0.00E 00 I-131 Ci 0.00E 00 0.00E 00 Ce-141 Ci 0.00E 00 0.00E 00 Ce-144 Ci 0.00E 00 0.00E 00 Sr-89 Ci 0.00E 00 0.00E 00 Sr-90 Ci 0.00E 00 0.00E 00 Total for period Ci 0.00E 00 0.00E 00
- Isotope with half-life less than 8 days 20
TABLE 13-203 GASEOUS EFFLUENTS--ELEVATED RELEASE Farley Unit 2- 3rd Quarter, 1985 CONTINUOUS BATCH Mode Mode Nuclides Released Unit QTR# 3 QTR# 3
- 1. Fission gases Ar-41 Ci 1.01E 01 0.00E 00 Xe-138 Ci 0.00E 00 0.00E 00 Kr-87 Ci 0.00E 00 0.00E 00 Xe-135 Ci 7.59E 00 0.00E 00 Xe-133M Ci 0.00E 00 0.00E 00 Kr-89 Ci 2.43E-02 0.00E 00 Kr-88 Ci 0.00E 00 0.00E 00 Xe-133 Ci 1.95E 02 0.00E 00 Total for period Ci 2.13E 02 0.00E 00
- 2. Iodines .
I-133 Ci 2.07E-06 0.00E 00 I-131 Ci 2.75E-05 0.00E 00 Total for period Ci 2.96E-05 0.00E 00
- 3. Particulates
- Mo-99 Ci 0.00E 00 0.00E 00 Co-60 Ci 0.00E 00 0.00E 00 Zn-65 Ci 0.00E 00 0.00E 00 Fe-59 Ci 0.00E 00 0.00E 00 Mn-54 Ci 0.00E 00 0.00E 00 Co-58 Ci 0.00E 00 0.00E 00 Cs-137 Ci 0.00E 00 0.00E 00 Cs-134 Ci 0.00E 00 0.00E 00
- I-133 Ci 0.00E 00 0.00E 00 I-131 Ci 0.00E 00 0.00E 00 Ce-141 Ci 0.00E 00 0.00E 00 Ce-144 Ci 0.00E 00 0.00E 00 Sr-89 Ci 0.00E 00 0.00E 00 Sr-90 Ci 0.00E 00 0.00E 00 Total for period Ci 0.00E 00 0.00E 00
- Isotope with half-life less than 8 days 21
TABL2 13-2Q4 GASECUS IFFLUENTS--ELEVATED RELEASE Farley Unit 2 - 4th Quarter, 1985 CONTINUOUS BATCH Mode Mode Nuclides Released Unit QTR# 4 QTR# 4
- 1. Fission gases Ar-41 Ci 1.05E 01 0.00E 00 Xe-138 Ci 0.00E 00 0.00E 00 Kr-87 Ci 0.00E 00 0.00E 00 Xe-135 Ci 3.84E 00 0.00E 00 Xe-133M Ci 0.00E 00 0.00E 00 Kr-88 Ci 0.00E 00 0. 00E '00 Xe-133 Ci 9.10E 01 0.00E 00 Total fer period Ci 1.05E 02 0.00E.00
- 2. Iodines
~
I-133 Ci 2.46E-10 0.00E 00 I-131 Ci 8.50E-07 0.00E 00 Total for period Ci 8.50E-07 0.00E 00
- 3. Particulates
- Mo-99 Ci 0.00E 00 0.00E 00 Co-60 Ci 0.00E 00 0.00E 00 Zn-65 Ci 0.00E 00 0.00E 00 Fe-59 Ci 0.00E 00 0.00E 00 Mn-54 Ci 0.00E 00 0.00E 00 Co-58 Ci 0.00E 00 0.00E 00 Cs-137 Ci 0.00E 00 0.00E 00 Cs-134 Ci 0.00E 00 0.00E 00
- I-133 Ci 0.00E 00 0.00E 00 I-131 Ci 0.00E 00 0.00E 00 Ce-141 Ci 0.00E 00 0.00E 00 Ce-144 Ci 0.00E 00 0.00E 00 Sr-89 Ci 0.00E 00 0.00E 00 Sr-90 Ci 0.00E 00 0.00E 00 Total for period Ci 0.00E 00 0.00E 00
- Isotope with half-life less than 8 days 22
I TABLE 1C-1Q3 GASEOUS ZFFLUENTS--GROUND RELEASE Farley Unit 1 - 3rd Quarter, 1985 CONTINUOUS BATCH Mode Mode Nuclides Released Unit QTR# 3 QTR# 3
- 1. Fission gases Ar-41 Ci 2.70E-01 0.00E 00 Xe-138 Ci 0.00E 00 0.00E 00 Kr-87 Ci 1.80E-03 0.00E 00 Kr-85M Ci 1.92E-03 0.00E 00 Xe-135 Ci 8.58E-01 0.00E 00 Xe-133M Ci 1.22E-01 0.00E 00 Kr-88 Ci 2.28E-03 0.00E 00 Xe-133 Ci 2.11E 01 0.00E 00 Total for period Ci 2.23E 01 0.00E 00
- 2. Iodines I-133 Ci 7.47E-08 0.00E 00 I-131 Ci 4.51E-07 0.00E 00 Total for period Ci 5.26E-07 0.00E 00
- 3. Particulates
- Mo-99 Ci 0.00E 00 0.00E 00 Co-60 Ci 0.00E 00 0.00E 00 Zn-65 Ci 0.00E 00 0.00E 00 Fe-59 Ci 0.00E 00 0.00E 00 Mn-54 Ci 0.00E 00 0.00E 00 Co-58 Ci 0.00E 00 0.00E 00 l Cs-137 Ci 0.00E 00 0.00E 00 l Cs-134 Ci 0.00E 00 0.00E 00
- I-133 Ci 0.00E 00 0.00E 00 I-131 Ci 0.00E 00 0.00E 00 Ce-141 Ci 0.00E 00 0.00E 00 Ce-144 Ci 0.00E 00 0.00E 00
( 0.00E 00 Sr-89 Ci 0.00E 00 Sr-90 Ci 0.00E 00 0.00E 00 Total for period Ci 0.00E 00 0.00E 00
- Isotope with half-life less than 8 days i
23
TABLE 1C-1Q4 GASEOUS EFFLUENTS--GROUND RELEASE Farley Unit 1- 4th Quarter, 1985 CONTINUOUS BATCH Mode Mode Nuclides Released Unit QTR# 4 QTR# 4 I
- 1. Fission gases Ar-41 Ci 1.10E-01 0.00E 00 l Xe-138 Ci 0.00E 00 0.00E 00 Kr-87 Ci 0.00E 00 0.00E 00 Kr-85M Ci 3.74E-04 0.00E 00 Xe-135 Ci 8.32E-01 0.00E 00 Xe-133M Ci 0.00E 00 0.00E 00 Kr-88 Ci 9.40E-03 . 0.00E 00 Xe-133 Ci 5.26E 00 0.00E 00 Total for period Ci 6.21E 00 0.00E 00
- 2. Iodines I-133 Ci 4.78E-08 0.00E 00 I-131 Ci 1.16E-06 0.00E 00 Total for period Ci 1.20E-06 0.00E 00
- 3. Particulates
- Mo-99 Ci 0.00E 00 0.00E 00 Co-60 Ci 0.00E 00 0.00E 00 Zn-65 Ci 0.00E 00 0.00E 00 Fe-59 Ci 0.00E 00 0.00E 00 Mn-54 Ci 0.00E 00 0.00E 00 Co-58 Ci 0.00E 00 0.00E 00 Cs-137 Ci 0.00E 00 0.00E 00 Cs-134 Ci 0.00E 00 0.00E 00
- I-133 Ci 0.00E 00 0.00E 00 I-131 Ci 0.00E 00 0.00E 00 Ce-141 Ci 0.00E 00 0.00E 00 Ce-144 Ci 0.00E 00 0.00E 00 Sr-89 Ci 0.00E 00 0.00E 00 _
Sr-90 Ci 0.00E 00 0.00E 00 Total for period Ci 0.00E 00 0.00E 00
- Isotope with half-life less than 8 days 24
TABLE 1C-2Q3 GASECUS E77LUENTS--GROUND RELEASE Farley Unit 2- 3rd Quarter, 1985 CONTINUOUS BATCH Hode Mode Nuclides Released Unit QTR# 3 QTR# 3
- 1. Fission gases Ar-41 Ci 3.31E-01 0.00E 00 Xe-138 Ci 0.00E 00 0.00E 00 Kr-87 Ci 0.00E 00 0.00E 00 Xe-135 Ci 2.11E-01 0.00E 00 l Xe-133M Ci 0.00E 00 0.00E 00 l Kr-89 Ci 4.15E-05 0.00E 00 Kr-88 Ci 0.00E 00 0.00E 00 Xe-133 Ci 5.50E 00 0.00E 00 Total for period Ci 6.04E 00 0.00E 00 2 Iodines I-133 Ci 8.78E-08 0.00E 00 I-131 Ci 1.06E-06 0.00E 00 Total for period Ci 1.14E-06 0.00E 00
- 3. Particulates
- Mo-99 Ci 0.00E 30 0.00E 00 Co-60 Ci 0.00E 00 0.00E 00 2n-65 Ci 0.00E 00 0.00E 00 Fe-59 Ci 0.00E 00 0.00E 00 Mn-54 Ci 0.00E 00 0.00E 00 Co-58 Ci 0.00E 00 0.00E 00 Cs-137 Ci 0.00E 00 0.00E 00 Cs-134 Ci 0.00E 00 0.00E 00
- I-133 Ci 0.00E 00 0.00E 00 I-131 Ci 0.00E 00 0.00E 00 Ce-141 Ci 0.00E 00 0.00E 00 Ce-144 Ci 0.00E 00 0.00E 00 Sr-89 Ci 0.00E 00 0.00E 00 Sr-90 Ci 0.00E 00 0.00E 00 Total for period Ci 0.00E 00 0.00E 00
- Isotope with half-life less than 8 days 25
TA3LE 1C-2Q4 GASEOUS EFFLUENTS--GROUND RELEASE Farley Unit 2 - 4th Quarter, 1985 CONTINUOUS BATCH Mode Mode Nuclides Released Unit QTR# 4 QTR# 4
- 1. Fission gases Ar-41 Ci 2.27E-01 0.00E 00 Xe-138 Ci 0.00E 00 0.00E 00 Kr-87 Ci 0.00E 00 0.00E 00 Xe-135 Ci 9.35E'02 0.00E 00 Xe-133M Ci 0.00E 00 0.00E 00 Kr-88 Ci 0.00E 00 0.00E 00 Xe-133 Ci 2.24E 00 0.00E 00 Total for period Ci 2.56E 00 0.00E 00
- 2. Iodines I-133 Ci 7.67E-12 0.00E 00 I-131 Ci 3.02E-08 0.00E 00 Total for period Ci 3.02E-08 0.00E 00
- 3. Particulates
- Mo-99 Ci 0.00E 00 0.00E 00 i Co-60 Ci 0.00E 00 0.00E 00 Zn-65 Ci 0.00E 00 0.00E 00 Fe-59 Ci 0.00E 00 0.00E 00 -
i Mn-54 Ci 0.00E 00 0.00E 00 Co-58 Ci 0.00E 00 0.00E 00 Cs-137 Ci 0.00E 00 0.00E 00 Cs-134 Ci 0.00E 00 0.00E 00
- I-133 Ci 0.00E 00 0.00E 00 I-131 Ci 0.00E 00 0.00E 00 Ce-141 Ci 0.00E 00 0.00E 00 Ce-144 Ci 0.00E 00 0.00E 00 Sr-89 Ci 0.00E 00 0.00E 00 Sr-90 Ci 0.00E 00 0.00E 00 Total for period Ci 0.00E 00 0.00E 00
- Isotope with half-life less than 8 days l
l 26
TABLE 2A-1 LIQUID EFFLUENT--SUMMATION OF ALL RELEASES Farley Unit 1 - 2nd Half, 1985 UNIT Qtr 3 Qtr 4 A. Fission and Activation Products
- 1. Total release Note (1) Ci 3.63E-03 3.70E-03
- 2. Average diluted concentration during period Note (2) uCi/ml 2.41E-10 2.19E-10
- 3. Percent of applicable limit during Period Note (2) % 1.64E-04 1.81E-04 B. Tritium
- 1. Total release Note (1) Ci 1.05E 02 1.29E 02
- 2. Average diluted concentration during period Note (2) uCi/ml 7.00E-06 7.66E-06
- 3. Percent of applicable limit during period Note (2) % 2.33E-01 2.55E-01 C. Dissolved and Entrained Gases
- 1. Total release Note (1) Ci 1.65E-02 8.53E-02
- 2. Average diluted concentration during period Note (2) uCi/ml 1.09E-09 5.06E-09
- 3. Percent of applicable limit during period Note (2) % 5.47E-04 2.53E-03 l D. Gross Alpha Radioactivity l Total release Note (1) Ci 0.00E 00 0.00E-00 E. Volume of Waste Water Note (3) i 1. WMT liters 1.09E 06 1.05E 06 l 2. SGBD and Turbine Bldg Sumps liters 7.57E 07 6.59E 07 l 3. Liquid Radioactive Effluent TOTAL Note (4) liters 7.68E 07 6.69E 07 l
F. Volume of Dilution Water during Quarter liters 1.51E 10 1.69E 10 NOTE: (1) Steam Generator Blowdown and Turbine Building Sump release curie amounts and doses were measured and are included in these totals and in table 23-1C in accordance with TABLE 4.11-1, Footnote E of Joseph M. Farley Nuclear Plant Unit Number 1 Technical Specifications (Appendix A of License No. NPF-2). (2) During period of discharge (3) Prior to dilution (4) Steam Generator Blowdown and Turbine Building Sump release 9 are excluded from Total Liquid Radioactive Effluent in accordance with 10 CFR 20, Appendix B, Note 5. 27
TABLE 2A-2 LIQUID EFFLUENT--SUMMATION OF ALL RELEASES Farley Unit 2 - 2nd Half, 1985 UNIT Qtr 3 Qtr 4 A. Fission and Activation Products
- 1. Total release Note (1) Ci 4.07E-03 5.93E-03
- 2. Average diluted concentration during period Note (2) uCi/ml 3.10E-10 4.43E-10
- 3. Percent of applicable limit during period Note (2) % 1.43E-04 1.48E-04 B. Tritium
- 1. Total release Note (1) Ci 1.27E 02 1.93E 02
- 2. Average diluted concentration during Period Note (2) uCi/ml 9.72E-06 1.44E-05
- 3. Percent of applicable limit during period Note (2) % 3.24E-01 4.79E-01 C. Dissolved and Entrained Gases
- 1. Total release Note (1) Ci 1.53E-02 9.19E-02
- 2. Average diluted concentration during period Note (2) uCi/ml 1.17E-09 6.86E-09
- 3. Percent of applicable limit during period Note (2) % 5.84E-04 3.43E-03 D. Gross Alpha Radioactivity Total release Note (1) Ci 0.00E 00 0.00E 00 E. Volume of Waste Water Note (3)
- 1. WMT liters 8.51E 05 7.64E 05
- 2. SGBD and Turbine Bldg Sumps liters 2.69E 07 2.97E 07
- 3. Liquid Radioactive Effluent TOTAL Note (4) liters 2.77E 07 3.04E 07 F. Volume of Dilution Water during Quarter liters 1.31E 10 1.34E 10 NOTE:
(1) Steam Generator Blowdown and Turbine Building Sump release curie amounts and doses were measured and are included in these totals and in table 2B-2C in accordance with TABLE 4.11-1, Footnote E of Joseph M. Farley Nuclear Plant Unit Number 2 Technical Specifications (Appendix A of License No. NPF-8). (2) During periods of discharge '3) Prior to dilution (4) Steam Generator Blowdown and Turbine Building Sump releases are excluded from Total Liquid Radioactive Effluent in accordance with 10 CFR 20, Appendix B, Note 5. 28
TABLE 2'3-13 LIQUID EFFLUENTS--EATCH Farley Unit 1 - 2nd Half, 1995 Nuclides Released Unit Qtr 3 Qtr 4 Sr-89 Ci 0.00E 00 0.00E 00 Sr-90 Ci 0.00E 00 0.00E 00 Fe-55 C1 1.65E-03 3.07E-03 Co-57 Ci 0.00E 00 0.00E 00 Ce-144 Ci 1.04E-05 0.00E 00 Tc-99M Ci 0.00E 00 0.00E 00 Ce-141 Ci 0.00E 00 6.00E 00 Np-239 Ci 0.00E 00 0.00E 00 Cr-51 Ci 2.86E-05 0.00E 00 I-131 Ci 2.45E-07 3.36E-06 Ru-103 Ci 7.60E-06 0.00E 00 I-133 Ci 0.00E 00 0.00E 00 Ba-140 Ci 0.00E 00 0.00E 00 As-76 Ci 0.00E 00 0.00E 00 Cs-134 Ci 2.2SE-06 1.32E-06 Ru-106 Ci 2.34E-05 0.00E 00 Cs-137 Ci 3.45E-05 2.70E-05 Mo-99 Ci 0.00E 00 0.00E 00 Zr-95 Ci 1.30E-05 0.00E-00 Nb-95 Ci 7.54E-05 3.29E-05 I-132 Ci 0.00E 00 0.00E 00 Co-58 C1 1.03E-04 3.71E-05 Cs-136 Ci 0.00E 00 4.27E-06 Mn-54 Ci 5.81E-06 1.05E-05 Ag-110M Ci 1.77E-04 1.73E-04 Sr-91 Ci 0.00E 00 0.00E 00 Zn-65 Ci 0.00E 00 0.00E 00 I-135 Ci 0.00E 00 0.00E 00 Fe-59 Ci 1.91E-06 0.00E 00 Co-60 Ci 3.07E-04 3.34E-04 Na-24 Ci 0.00E 00 0.00E 00 La-140 Ci 0.00E 00 0.00E 00 Cu-64 Ci 0.00E 00 0.00E 00 Sb-124 Ci 1.34E-04 0.00E 00 Te-132 Ci 0.00E 00 0.00E 00 Sb-125 Ci 1.06E-03 0.00E 00 Zr-97 Ci 0.00E 00 0.00E 00 TOTALS Ci 3.63E-03 3.70E-03 Xe-133 C1 1.35E-02 1.74E-02 Xe-135 Ci 6.82E-06 0.00E 00 TOTALS Ci 1.35E-02 1.74E-02 H-3 Ci 1.05E 02 1.29E 02 29
TA3LE 23-23 LIQUID EFFLUENTS--3ATCH Farley Unit 2- 2nd Half, 1985 Nuclides Released Unit Qtr 3 Qtr 4 Sr-89 Ci 0.00E 00 0.00E 00 Sr-90 Ci 0.00E 00 0.00E 00 Fe-55 C1 1.74E-03 5.28E-03 Co-57 Ci 0.00E 00 0.00E 00 Ce-144 Ci 7.62E-06 7.89E-06 Tc-99M Ci 0.00E 00 0.00E 00 Ce-141 Ci 2.76E-07 0.00E 00 Np-239 Ci 0.00E 00 0.00E 00 Cr-51 Ci 9.07E-05 0.00E 00 I-131 Ci 0.00E 00 3.55E-07 Ru-103 Ci 1.17E-06 0.00E 00 I-133 Ci 0.00E 00 0.00E 00 Ba-140 Ci 0.00E 00 8.32E-06 As-76 Ci 0.00E 00 2.79E-06 Cs-134 Ci 0.00E 00 8.22E-07 Ru-106 Ci 0.00E 00 6.30E-06 Cs-137 Ci 4.63E-06 2.82E-06 Mo-99 Ci 0.00E 00 0.00E 00 2r-95 Ci 1.21E-05 0.00E 00 Nb-95 Ci 5.05E-05 4.23E-05 I-132 Ci 0.00E 00 0.00E 00 Co-58 Ci 2.55E-04 5.06E-05 Cs-136 Ci 2.14E-06 1.83E-06 Mn-54 Ci 2.99E-05 1.93E-05 Ag-110M Ci 1.22E-04 2.04E-04 Sr-91 Ci 3.58E-06 0.00E 00 I-135 Ci 0.00E 00 0.00E 00 Fe-59 Ci 0.00E 00 0.00E 00 Co-60 C1 2.82E-04 2.50E-04 Na-24 Ci 0.00E 00 0.00E 00 La-140 Ci 5.55E-06 1.03E-06 Sb-124 Ci 1.86E-04 0.00E 00 Sb-125 Ci 1.04E-03 0.00E 00 Te-132 Ci 0.00E 00 0.00E 00 TOTALS Ci 3.84E-03 5.88E-03 Xe-133 C1 1.50E-02 9.19E-02 Xe-135 C1 1.68E-06 4.26E-06 TOTALS C1 1.50E-02 9.19E-02 H-3 C1 1.27E 02 1.91E 02 30 , I l
r-TABLE 23-1C LIQUID EFFLUENTS--CONTINUOUS Farley Unit 1 - 2nd Half,_1985 Nuclidec Released Unit Qtr 3 Qtr 4 Sr-89 Ci 0.00E 00 0.00E 00 Sr-90 Ci 0.00E 00 0.00E 00 Ce-144 Ci 0.00E 00 0.00E 00 Ce-141 Ci 0.00E 00 0.00E 00 Np-239 Ci 0.00E 00 0.00E 00 Cs-134 Ci 0.00E 00 0.00E 00 Cs-137 Ci 0.00E 00 0.00E 00 Mo-99 Ci 0.00E 00 0.00E 00 Co-58 Ci 0.00E 00 0.00E 00 Mn-54 Ci 0.00E 00 0.00E 00 Ag-110M Ci 0.00E 00 0.00E 00 Fe-55 Ci 0.00E 00 0.00E 00 Zn-65 Ci 0.00E 00 0.00E 00 Fe-59 Ci 0.00E 00 0.00E 00 Co-60 Ci 0.00E 00 0.00E 00' Zr-95 Ci 0.00E 00 0.00E 00 TOTALS Ci 0.00E 00 0.00E 00 Xe-133 Ci 3.46E-03 0.00E 00 Xe-135 Ci 0.00E 00 0.00E 00 Kr-87 Ci 0.00E 00 0.00E.00 Kr-88 Ci 0.00E 00 0.00E 00 TOTALS Ci 3.46E-03 0.00E 00 H-3 Ci 0.00E 00 4.35E-01 NOTE: Although Steam Generator Blowdown and Turbine Building Sump releases were excluded from total liquid radioactive effluent volume in accordance with 10 CFR 20, Appendix B, Note 5, curie amounts and doses from these releases were measured and are reported here in accordance with Table 4.11-1, Footnote E of Joseph M. Farley Nuclear Plant Unit Number i Technical Specification (Appendix A of License No. NPF-2). 31
TA3LE 23-2C LIQUID EFFLUENTS--CONTINUOUS Farley Unit 2 - 2nd Half, 1985 Nuclides Released Unit Qtr 3 Qtr 4 Sr-89 Ci 0.00E 00 0.00E 00 Sr-90 Ci 0.00E 00 0.00E 00 Ce-144 Ci 0.00E 00 0.00E 00 Ce-141 Ci 0.00E 00 0.00E 00 Cs-134 Ci 0.00E 00 0.00E 00 Cs-137 Ci 0.00E 00 0.00E 00 Mo-99 Ci 0.00E 00 0.00E 00 Zr Ci 0.00E 00 0.00E 00 Nb-95 Ci 0.00E 00 0.00E 00-Co-58 Ci 0.00E 00 0.00E 00 Mn-54 Ci 0.00E 00 0.00E 00 Zn-65 Ci 0.00E 00 0.00E 00 I-135 Ci 0.00E 00 0.00E 00 Fe-59 Ci
- 0.00E 00 0.00E 00 Co-60 Ci 0.00E 00 0.00E 00 I-131 Ci 0.00E 00 0.00E 00 I-133 Ci 0.00E 00 0.00E 00 Co-57 Ci 0.00E 00 4.85E-05 Fe-55 Ci 2.30E-04 0.00E 00 Ag-110M Ci 0.00E 00 0.00E 00 TOTALS C1 2.30E-04 4.85E-05 Xe-133 Ci 3.32E-04 0.00E 00 Xe-135 Ci 0.00E 00 0.00E 00 Kr-87 Ci 0.00E 00 0.00E 00 Kr-88 Ci 0.00E 00 0.00E'00 TOTALS Ci 3.32E-04 0.00E 00 H-3 Ci 7.58E-01 2.10E 00 NOTE:
Although Steam Generator Blowdown and Turbine Building Sump releases were excluded from total liquid radioactive effluent volume in accordance with 10 CFR 20, Appendix B, Note 5, curie amounts and doses from these releases were measured and are reported here in accordance with Table 4.11-1, Footnote E of Joseph M. Farley Nuclear Plant Unit Number 2 Technical Specification (Appendix A of License No. NPF-8). 32
l l TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 2nd Half, 1985 SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)
- 1. Type of Waste UNITS PERIOD July 1-Dec.31 3
- a. Spent resins, filter sludges, m 3.539E 01 evaporator bottoms, etc. Ci 7.723E 02 3
- b. Dry compressible waste, m 1.298E 02 contaminated equipment, etc. Ci 5.50 E 00 3
- c. Irradiated components, m None control rods, etc. Ci None 3
- d. Other (described) Absorbed Oil m 1.720E 01 Ci 2.2 E-03
- 2. Estimate of major,nuc.lide composition ISOTOPES % ISOTOPES %
- a. Sb-124 1.17 c. N/A Cs-137 3.24 Co-58 28.99 Mn-54 5.77 Co-60 46.99 Ni-63 13.86
- b. H-3 67.98 d. H-3 86.14 Co-58 2.60 C-14 11.24 Mn-54 3.26 Co-60 1.50 Co-60 23.28 Ni-63 1.12 Zr-95 1.00 Nb-95 1.96 33
TABLE 3 (con't) SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 2nd Half, 1985
- 3. Solid Waste Disposition
- a. Number of Shipments 20
- b. Mode of Transportation Chem-Nuclear Transport (11)
Hittman Transport (9)
- c. Destination Chem-Nuclear Systems, Inc.
Barnwell, South Carolina (19) U.S Ecology,Inc. Hanford, Washington (1)
- 4. Type of Containers
- a. ( 1a ) Type "A" and "B" Packages
- b. ( lb ) " Strong and Tight" Steel Drums, Wooden Boxes, Steel Liners, & High Integrity Containers.
- c. ( id ) " Strong and Tight" Steel Drums
- 5. Solidification Agents
- a. ( 1a ) No solidifications during this period. All items (spent resin and charcoal) that are categorized for item la were shipped dewatered,
- b. ( ib ) N/A
- c. ( id ) N/A, utilized absorption methodology B. IRRADIATED FUEL SHIPMENTS-(Disposition)
- 1. Number of Sh ipmena t s None
- 2. Mode of Transportation N/A
- 3. Destination N/A 34
3e Walden Rav Date: Document Numbsr: Rav: ! WESTINGHOUSE STD-P-04-002 4 10/8/85 !
^
Title:
Process Control Program for Dewatering Ion-Exchange , N PORATED ' l l Resin & Activated Charcoal Filter Media to % Drainable Licuid esponsible Director % 11ty Prepared Reviewed Manager Engineering Assurance Rev, Rev Date by by 0 12- 3-81 g ,
, s p 8
- ECN-83-133 1 5-19-83 U Mb. '
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Page 2 of 7 PROCESS CONTROL PROGRAM FOR DEWATERING ION EXCHANGE RESIN AND ACTIVATED CHARCOAL FILTER MEDIA TO 1/2% DRAINABLE LIQUID 1.0 SCOPE This procedure is applicable to Hittman steel liners having rigid underdrains for dewatering besa ion exchange resins or activated carbon. 2.0 PURPOSE 2.1 The purpose of the Process Control Program (PCP) for de-watered resin and activated carbon is to provide a program which will assure that at the time of arrival at the burial site the disposable liner contains less than one-half of one per ent free liquid. 2.2 This document is complete in and of itself and can be used for demineralizer and carbon filter liners into which ex-haustad resins are transferred. Other Hittman procedures may also include procedures for connecting dewatering equip-ment to the liner prior to other operations. Should this be the case those procedures obviously need not be required.
3.0 REFERENCES
3.1 Report on Dewatering of Bead Ion Exchange Resin and Acti-vated Carbon, Hittman Report STD-R-03-001. 4.0 EQUIPMENT 4.1 Diaphragm pump,1\" or equivalent, with interconnecting hoses, quick disconnect fittings and clamps as required. 4.2 Hoses with fittings and clamps as required to connect from the service air system to the diaphragm pump. Minimum service air required is 40 SCFM at 100 psig. 4.3 Vacuum pump with minimum suction of 25 inches of mercury and 1/4-inch vacuum hoses and clamp. 4.4 Glass collection bottle per Figure 1, minimum size of two (2) gallons. 4.5 Tool for connection to side bottom dewatering connection similar to device shown in Figure 1 (Optional). 5.0 GENERAL REQUIREMENTS 5.1 As required by the South Carolina Department of Health and , 'cO. Environmental Controls License No. 097, Amendment No. 30 for L -. __ -_. _ _ __ .
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'.~* . STD-P-04-002 Pcg2 3 of 7 . t the Barnwell Waste Management Facility, the PCP shall be used to verify adequate dewatering of unsolidified wet () radioactive wastes. J 5.2 The PCP applies to shipments of resins transferred to Hitt-man liners and for Hittman liners used as portable demin- - eralizers or carbon filters. These shipments shall be de-watered to meet burial site free liquid criteria according to Hittman's Liner Dewatering Test Report, STD-R-03-001, which has been filed, on behalf of Hittman clients, with the operator of the Barnwell, South Carolina burial facility. 5.3 For liners that are to be shipped unshielded, or when adequate shielding can be supplied at the plant, this dewatering pro-cedure can be accomplished prior to loading the liner onto the truck. When adequate shielding is not available, or for resins transferred to a liner already in the shipping cask, this dewatering procedure must be accomplished after the liner is loaded into the shipping cask. 4 5.4 In all cases, the liner must be tipped approximately 7* to 9* with the final dewatering element at the low point. The location of the final dewatering element is marked on the. outside of the liner. - 5.5 For liners to be dewatered in the shipping cask, the method of tipping the cask either on or off the trailer must be ( cleared with the responsible Hittman transportation office
) prior to commencement of work.
6.0 DEWATERING PM CEDURE 6.1 Disposable Demineralizers and Carbon Filters 6.1.1 Upon completion of the waste processing, CONTINUE DEWATERING the liner until pump suction is lost. 6.1.2 MOVE the liner to the location for final dewatering and set in the tipped configuration. 6.1.3 CONNECT the dewatering hose used during normal ' waste processing to a Warren-Rupp double diaphragm air operated pump or equivalent. 6.1.4 CONNECT the pump discharge hose to the appropriate plant drain. 6.1.5 REMOVE the pipe plug from the final dewatering ! connection. , NOTE: For liners with a top dewatering connec-tion this is a 1/4" pipe plug. For liners with the side bottom dewatering j(]) connection this is a 1\" pipe plug. . i i i
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'e 6.1.6 For liners with the top dewatering connection REPLACE the pipe plug with a \" threaded pipe.
6.1.7 For liners with the side bottom dewatering connec-tion CONNECT the dewatering tool shown in Figure 1, or a similar device, to the quick disconnect fitting found under the 1\" pipe plug. 6.1.8 CONNECT the vacuum hose from the vacuum bottle to the final dewatering connection installed in Step 6.1.6 or Step 6.1.7. See Figure 2. 6.1.9 CONNECT a second vacuum hose from the vacuum bottle to the vaccum pump. 6.1.10 CLAMP off hose near vacuum bottle. 6.1.11 DEWATER the liner using the air operated pump for a minimum of four (4) hours at which time the pump is to be shut off, but not disconnected. 6.1.12 Allow the liner to SIT in this position for twenty (20) hours. 6.1.13 DEWATER using the pump for one (1) hour. 6.1.14 ESTABLISH vacuum pressure (15" - 18" mercury) in fO ce11ectien bettie. REn0vE Pinch c1 amp. nos1 TOR waste level in collection bottle. NOTE: Should the liquid level in the bottle get close enough to the top to risk waste being sucked into the vacuum pump, stop the pump and empty the collection bottle, using proper radiological pro-cedures. 6.1.15 DEWATER via this method for one (1) hour after continuous flow is lost. Continuous flow is considered lost when air bubbles begin coming through the vacuum hose from the container. 6.1.16 REPEAT Steps 6.1.14 and 6.1.15 at 24-hour inter-vals for three days. 6.1.17 Upon completion of the fourth vacuum draining, the liner is dewatered and ready for shipment. 6.2 Resin Transfer Liners 6.2.1 Upon completion of the resin transfer operation, CONTINUE operating the dewatering pump until pump h suction is lost. DISCONNECT the dewatering pump from the liner. 6.2.2
P. 'e STD-P-04-002
- Pcge 5 of 7 l 6.2.3 PMCE the liner in the tipped configuration.
r 6.2.4 COMPI.ETE steps 6.1.3 through 6.1.17. l 6.2.5 For liners containing greater than 140 cubic feet of resin, ADD one additional day of dewatering , 1 prior to shipment. l 7.0 DISCONNECTING DEWATERING EQUIPMENT j 7.1 DISCONNECT dewatering hose from the dewatering pump. The portion of this hose exiting the liner through the liner neck is to be pushed back into the liner prior to capping. . 7.2 DISCONNECT the final dewatering line from the liner top and replace the 1/4 inch plug, or remove the dewatering tool, or similar device, and replace the 1-1/2 inch plug. NOTE: For liners with the side bottom connection it is recoonnended that the pipe plug be tack welded in place to eliminate the possibility of it vibrating loose during transportation. 26A o
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HITIMAN NUCLEAR & STD-P-05-003 4 8-16-65 D EVELOPMENT CORPORATION Tale: Process Control Program for Incontainer l l Solidification cf 4 to 20 Weight Percent Boric Acid Supervisor Prepared Reviewed Director Manager Laboratory Rzv. Rev Date by by Engineering QA Services 0 1-5-82 [,b ' N.N Daa;e( -263 1 12-14-82 Director Proj ect QA Engr. Manager Manager ECN-2 12-8-83 l h ou
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This document supersedes STD-P. 05-007. l 4 h, [ 4 8-16-85 /g
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t- . STD-P-05-003 Page 2 of 32 O PROCESS CONTROL PROGRAM FOR INCONTAINER SOLIDIFICATION OF . 4 TO 20 WEIGHT PERCENT BORIC ACID 1.0 SCOPE This procedure is applicable to the solidification of 10 to 14 weight
. percent boric acid classified as Class A Unstable waste and 4 to 20 weight percent boric acid classified as either Class-A Unstable or Stable, Class B or Class C wastes. Class A Unstable waste meets the minimum requirements under the NRC Criteria of 10CFR61.56, Waste Characteristics. Class A Stable waste meets the stability require-ments of Class B and C wastes under the criteria of 10CFR61.56, Waste Characteristics as required by the state of South Carolina.
2.0 PURPOSE 2.1 The purpose of the Process Control Program (PCP) for the incon-tainer solidification of boric acid wastes is to provide a pro-gram which will assure a solidified product which meets the requirements of 10CFR61.56, Waste characteristics. The program consists of four major steps: 2.1.1 Procedures for collecting and analyzing samples; 2.1.2 Procedures for solidifying samples;
; 2.1.3 Criteria for process parameters for acceptance or rejec-tion as solidified waste.
2.1.4 Calculation of recommended quantities of cement and anhydrous sodium metasilicate to be used in full scale liner solidifications. 2.2 .This document shall be considered complete only when used in concert with the Westinghouse Hittman Nuclear Incorporated proce-dures for field solidification. This document describes the methodology for determining the acceptable ratios of waste, cement and additive that will result in an acceptable product for transportation and burial. The Solidification Data Sheet then converts these ratios into the recommended quantities of cement and additive that must be mixed with the waste. 3.0 COLLECTION AND ANALYSIS OF SAMPLES 3.1 General Requirements O
~- 3.1.1 As required by the Radiological Effluent Technical Specifications for PWR's and BWR's the PCP shall be i
> ** ". STD-P-05-003 Page 3 cf 32
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(d used to verify the solidification of at least one representative test specimen from every tenth batch of each type of wet radioactive waste. . 3.1.2 For the purpose of the PCP e batch is defined as the quantity of waste required to fill a disposable liner with the appropriate quantity of waste prior to solidi-fication. 3.1.3 If any test specimen fails to solidify, the batch under test shall be suspended until such time as additional test specimens can be obtained, alternate solidification parameters can be determined in accordance with the Process Control Program, and a subsequent test verifies solidification. Solidification of the batch may then be resumed using the alternate solidification parameters determined. 3.1.4 If the initial test specimen from a batch of waste fails to verify solidification, then representative test specimens shall be collected from each consecutive batch of the same type of waste until three consecu-tive initial test specimers demonstrate solidification. The Process Control Program shall be modified as re-(f') quired to assure solidification of subsequent batches of waste. 3.1.5 For high activity wastes where the handling of samples could result in personnel radiation exposures which are inconsistent with the ALARA principle, representative non-radioactive samples will be tested. These samples should be as close as possible to the actual wastes' chemical properties. 3.2 Collection of Samples 3.2.1 Radiological Protection 3.2.1.1 Comply with applicable Radiation Work Permits. 3.2.1.2 Test samples which use actual waste shall be disposed of by placing in the solidified liner. 3.2.1.3 A Test Solidification Data Sheet will be maintained for each test sample solidified. Each data sheet will contain pertinent infor-mation on the tast sample and the batch numoers of waste solidified based on each test sample. j{ }
'. STD-P-05-003 Page 4 of 32 3.2.2 Test Solidification Data Sheet The Test Solidification Data Sheet will contain perti- .
nent information on the characteristics of the test sample solidified so as to verify solidification of subsequent batches of similar wastes without retesting. 3.2.2.1 The. test sample data for boric acid waste will in-clude, but not necessarily be limited to, the type of waste solidified, percent solids, pH of waste, volume of sample, and the ' mnt of oil in sample. 3.2.2.2 The Test Solidification Data sheet will include the Solidification Number, Liner Number, Waste Volume, and Date Solidified, for each batch solidi-fled. 3.2.3 Collection of Samples 3.2.3.1 Evaporator bottoms shall be kept heated or re-heated to 100*F prior to testing. 3.2.3.2 One sample shall be taken for solidification! If the radioactivity levels are too high to permit f~N full size samples to be taken then smaller samples Dd shall be taken with the results corrected accord-ingly. Sample sizes shall be determined by the plant Health Physics Staff. 3.2.3.3 If possible, samples should be drawn at least two days prior to the planned waste solidification procedure to allow adequate time to complete the required testing and verification of solidifica-tion, and to allow for retesting if necessary. For Class A Unstable waste, approximately 6 hours - are required to perform and verify the test solidi-fication. Approximately 28 hours are necessary to verify solidification for Class A Stable, B and C wastes. 3.2.3.4 If the sample is drawn from the liner, it should be mixed for 10 minutes, or recirculated in the liner for at least three (3) volume changes prior to sampling to assure a representative sample. 4 3.2.3.5 If the contents of more than one tank are to be solidified in the same liner then representative samples of each tank should be drawn. The samples t should be of such size that when mixed together they fonn samples of standard size as prescribed 4 '(]) in Section 3.2.3.2. If the contents of a particu-lar tank represents x% of the total waste quantity f I
' ".. '.- STD-P-05-003 Page 5 of 32
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' to be solidified then the sample of that tank should be of such size to represent x% of the composite samples.
3.3 Analysis of Samples This document only defines the parameters to be analyzed and not the methodology. This is left to the plant staff. Parameter Acceptable pH 8* for 4 to 10 weight percent boric acid, Class A Unstable and Stable, Class B or C. 12* for >10 to 20 weight percent boric acid, Class A Unstable and Stable, Class B or C. NOTE: The pH shall be reduced to 7.4 to 9.2 for >10 to 14 weight percent boric acid Class A Unstable only, per the instructions in Step 4.1.1.1. Detergents No appreciable foaming Oil <1%
*After addition of sodium hydroxide.
4.0 TEST SOLIDIFICATION AND ACCEPTANCE CRITERIA 4.1 Class A Unstable - >10 to 14 Weight Percent Boric Acid 4.1.1 Waste Conditioning 4.1.1.1 Prior to the test sample solidification, the pH of the sample shall be adjusted to a range of 7.4 to 9.2. 4.1.1.2 It is recoraended that 50 weight percent sodium , hydroxide 'Je used to adjust the pH. The amount of ) l sodium hyuroxide necessary for the pH adjustment shall be recorded on the Class A Unstable Test Solidific ation Data Sheet for >10 to 14 Weight Percent Biric Acid. 4.1.1.3 If large (i.e., foam causing) quantities of deter-gents are present, the sample should be treated with an anti-foaming agent. The quantity of anti-foaming agent shall be recorded on the Class A Un-stable Test Solidification Data Sheet for >10 to 14 Weight Percent Boric Acid and shall not exceed one half of one percent by volume of the waste.
STD-P-05-003 Page 6 of 32 O 4.1.1.4 If oil is present in quantities greater than 1% by volume, . the oil shall be reduced to less than 1% by skimming. - NOTE: Waste with oil greater than 1% by volume may not be shipped to Barnwell, South Carolina, but must be shipped to Hanford, Washington. Emulsification agents need not be used until the volume of oil exceeds 3% of the waste volume. The quantity of any substance added to the sample for this purpose shall be recorded on the proper Test Solidifica-tion Data Sheet and shall not exceed one percent by volume of the waste. Oil in concentrations greater than 12% by volume may not be solidified under this procedure. 4.1.2 Test Solidification (Class A Unstable >10 to 14 Weight percent Boric Acid) 4.1.2.1 MEASURE 500 ml of untreated waste into a con-tainer. 4.1.2.2 RECORD the weight and volume on the Class A Un-stable Test Solidification Data Sheet for >10 to j{ J 14 Weight Percent Boric Acid. 4.1.2.3 ADD 50 weight percent sodium hydroxide until the pH is 7.4 to 9.2. 4.1.2.4 RECORD the weight of sodium hydroxide used on the Class A Unstable Test Solidification Data Sheet for >10 to 14 Weight Percent Boric Acid. 4.1.2.5 If large (i.e., foam causing) quantities of deter-gents are present, TREAT the sample with an anti-foaming agent. 4.1.2.6 RECORD the weight of anti-foaming agent used on the Class A Unstable Test Solidification Data Sheet for >10 to 14 Weight Percent Boric Acid. 4.1.2.7 If oil is present and the volume is between 3 and 12% of the volume of waste, TREAT with an emulsify-ing agent such as Maysol 776 (20% of the volume of oil). NOTE: If density of Maysol 776 is 1.0 g/ml; the volume in el is equal to the weight in grams. 4.1.2.8 RECORD the quantity of any emulsifying agent used on the Class A Unstable Test Solidification Data Sheet for >10 to 14 Weight Percent Boric Acid. J
. a.- '.- STD-P-05-003 Page 7 of 32 ; .~
4.1.2.9 For the test solidification of the borated waste, j measure into a mixing vessel 400 ml of waste pre-treated as in Sections 4.1.2.3 through 4.1.2.7. l-NOTE: Test Solidifications should be conducted
- using a 1,000 ml disposable beaker or I similar size container.
4.1.2.10 RECORD the volume AND weight of the sample on the 4 Class A Unstable Test Solidification Data Sheet for >10 to 14 Weight Percent Boric Acid. 4.1.2.11 MEASURE out 505.0 gas of Portland Type I Cement and 84.2 gas of Anhydrous Sodium Metasilicate (ASMS) into separate vassels. ( l 4.1.2.12 RECORD the quantities of cement and ASMS on the
, Class A Unstable Test Solidification Data Sheet for >10 to 14 Weight Percent Boric Acid.
4.1.2.13 Slowly ADD the cement to the test sample while it is being mixed. NOTE: Mixing should be accomplished by stir-( ring with an electric mixing motor with j blade until a homogeneous mixture is
- obtained, approximately one minute.
1 } 4.1.2.14 After all the cement is added, slowly ADD the ASMS l to the test sample while it is being mixed.
, 4.1.2.15 After sufficient mixing (2 minutes after all the
! ASMS is added) so that a homogeneous mixture is j obtained, SEAL the sample and ALLOW it to cure for , i a minimum of 4 hours. t 4.2 Class A Unstable and Stable, Class B or C Waste (4 to 20 Weight Percent Boric Acid i 4.2.1 Waste Conditioning i 4.2.1.1 Prior to the test sample solidification, the pH of l the sample shall be adjusted to 8 for 4 to 10 l weight percent boric acid and to 12 for >10 to 20 weight percent boric acid. 4.2.1.2 It is recommended that 50 weight percent sodium j hydroxide be used to adjust the pH. The amount of sodium hydroxide necessary for the pH adjustment shall be recorded on the proper Test Solidifica-i - tion Data Sheet for Class A Unstable and Stable, i Class B or C Waste. b l ' _ - - , . , . . _ , _ . . _ . - - , _ _ . , _ - . - _ - . _ _ . - . - - , , _ . - - ~ _ . _ . . _ . . . _ . . . . . . _ _ _ _ _ . _ . _ , _ . - - _ . . . _ . , _ _ . _ _ - , , ~ _ . - . - . _ . -
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', STD-P-05-003 Page 8 of 32 4.2.1.3 If large (i.e., foam causing) quantities of deter-gents are present, the sample should be treated with an anti-foaming agent. The quantity of anti-foaming agent shall be recorded on the proper Test Solidification Data Sheet for Class A Unstable and Stable, Class B or C Wastes and shall not exceed one half of one percent by volume of the waste.
4.2.1.4 If oil is present in quantities greater than 1% by volume, the oil shall be reduced to less than 1% by skimming. NOTE: Waste with oil greater than 1% by volume may not be shipped to Barnwell, South Carolina, but must be shipped to Hanford, Washington. Emusification agents need not be used until the volume of oil exceeds 3% of the waste volume. The quantity of any substance added to the sample for this purpose shall be re-corded on the proper Test Solidification Data Sheet for Class A Unstable and Stable, Class B or C Wastes and shall not exceed one percent by volume of the .
' Oil in concentrations greater u
waste. than 12% by volume may not be solidified under this procedure. 4.2.2 Test Solidification of 4 to 10 Weight Percent Boric Acid Class A Unstable and Stable, Class B or C 4.2.2.1 MEASURE 500 gms of untreated waste into a con-tainer. 4.2.2.2 RECORD the weight and volume on the Test Solidifi-cation Data Sheet for 4 to 10 Weight Percent Boric Acid. 4.2.2.3 ADD 50 weight percent sodium hydroxide until the pH is 8. 4.2.2.4 RECORD the weight of sodium hydroxide used on the . Test Solidification Data Sheet for 4 to 10 Weight Percent Boric Acid, Class A Unstable and Stable, Class B or C. 4.2.2.5 If large (i.e., foam causing) quantities of deter-gents are present, TREAT the sample with an anti-foaming agent.
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STD-P-05-003 Page 9 of 32 4 O
\# 4.2.2.6 RECORD the weight of anti-foaming agent used on the Test Solidification Data Sheet for 4 to 10 Weight Percent Boric Acid. Class A Unstable and .
Stable, Class B or C. 4.2.2.7 If oil is present and the volume is between 3 and 12% of the volume of waste, TREAT with an emul-sifying agent such as Maysol 776 (20% of the volume of oil). NOTE: The density of Maysol 776 is 1.0 g/ml; the volume in al is equal to the weight in grams. 4.2.2.8 RECORD the quantity of any emulsifying agent used on the Test Solidification Data Sheet for 4 to 10 Weight Percent Boric Acid Class A Unstable and Stable, Class B or C. 4.2.2.9 For the test solidification of the borated waste, measure into two mixing vessels 400ml of waste each pretreated as in Sections 4.2.2.3 through 4.2.2.7. (/~' NOTE: Test solidifications should be conducted using a 1,000 ml disposable beaker or similar size container. 4.2.2.10 CALCULATE Items (9), (10), (11) and (12) on the Test Solidification Data Sheet for 4 to 10 Weight Percent Boric Acid Class A Unstable and Stable, Class B or C. 4.2.2.11 RECORD the volume AND weight of the sample to be solidified on the Test Solidification Data Sheet for 4 to 10 Weight Percent Boric Acid Class A Unstable and Stable, Class B or C. 4.2.2.12 CALCULATE Items (15), and (16) on the Test Solidifi-cation Data Sheet for 4 to 10 Weight Percent Boric Acid Class A Unstable and Stable, Class B or C. 4.2.2.13 DETERMINE the water / cement ratio using Figure 1 and the percent solids from the Test Solidifica-tion Data Sheet, Form STD-P-05-003-04. 4.2.2.14 RECORD the water / cement ratio on the Test Solidifi-cation Data Sheet for 4 to 10 Weight Percent Boric Acid Class A Unstable and Stable, Class B or C. , (~\ ! \~) 4.2.2.15 CALCULATE Items (18) and (19) on Form STD-P-05-003-04. l L
STD-P-05-003 Page 10 of 32 O 4.2.2.16 WEIGH out the required quantity of cement. 4.2.2.17 WEIGH out the required quantity of anhydrous - sodium metasilicate (ASMS) into a separate vessel. NOTE: The quantity of ASMS is 15% of the cement weight. 4.2.2.18 Slowly ADD the cement to the test sample while it is being mixed. NOTE: Mixing should be accomplished by stir-ring with an electric mixing motor with blade until a homogeneous mixture is obtained, approximately one minute or less if the mixture begins to set. 4.2.2.19 After all the cement is added, slowly ADD the ASMS to the test sample while it is being mixed. 4.2.2.20 Af ter sufficient mixing (2 minutes after all the ASMS is added) so that a homogeneous mixture is obtained, SEAL the sample and CURE at 120 5*F for 24 hours.
'h7 '
NOTE: If at any time during the 24 hour cure, , the sample meets the acceptance criteria, the liner solidification may proceed. However, no test solidification shall be disqualified without at least 24 hours of cure. ! 4.2.3 Test Solidification of >10 to 20 Weight Percent Boric Acid 4.2.3.1 MEASURE 500 gms of untreated waste into a container. i 4.2.3.2 RECORD the weight and volume on the Test Solidifi-cation Data Sheet for >10 to 20 Weight Percent Boric Acid, Class A Unstable and Stable, Class B or C. 4.2.3.3 ADD 50 weight percent sodium hydroxide until the pH is 12. 4.2.3.4 RECORD the weight of sodium hydroxide used on the Test Solidification Data Sheet for >10 to 20 Weight Percent Boric Acid, Class A Unstable and Stable, Class B or C. O '.2.3.5 If large (i.e., foam causing) quantities of deter-gents are present, TREAT the sample with an anti-foaming agent.
. STD-P-05-003 Page 11 of 32 g
# 4.2.3.6 RECORD ' the weight of anti-foaming agent used on the Test Solidification Data Sheet for >10 to 20 Weight Percent Boric Acid, Class A Unstable and Stable, Class B or C. ,
4.2.3.7 If oil is present and the- volume is between 3 and 12% of the volume of waste, TREAT with an emul-sifying agent such as Maysol 776 (20% of the volume of oil). NOTE: The density of Maysol 776 is 1.0 g/ml; the volume in ml is equal to the weight in grams. 4.2.3.8 RECORD the quantity of any emulsifying agent used on the Test Solidification Data Sheet for >10 to 20 Weight Percent Boric Acid, Class A Unstable and Stable, Class B or C. 4.2.3.9 For the test solidification of the borated waste, MEASURE into two mixing vessels 400 ml of waste pretreated as in Sections 4.2.3.3 through 4.2.3.8. NOTE: Test Solidifications should be conducted g^)
- using a 1,000 ml disposable beaker or U similar size container.
4.2.3.10 CALCULATE Items (9), (10), (11) and (12) on the Test Solidification Data Sheet for >10 to 20 Weight Percent Boric Acid, Class A Unstable and Stable, Class B or C. 4.2.3.11 RECORD the volume AND weight of the sample on the Test Solidification Data Sheet for >10 to 20 I Weight Percent Boric Acid, Class A Unstable and Stable, Class B or C. 4.2.3.12 CALCULATE Items (15 and (16) on the Test Solidifi-cation Data Sheet for >10 to 20 Weight Percent Boric Acid, Class A Unstable and Stable, Class B or C. 4.2.3.13 DETERMINE the water / cement ratio using Figure 1 and the percent solids from the Test Solidifica-tion Data Sheet, Form STD-P-05-003-06. 4.2.3.14 RECORD the water / cement ratio on the Test Solidifi-e cation Data Sheet for >10 to 20 Weight Percent Boric Acid, Class A Unstable and Stable, Class B or C. 4.2.4.15 CALCULATE Items (18) and (19) on Form STD-P-05-003-06.
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STD-P-05-003 Page 12 of 32 4.2.3.16 WEIGH out the required quantity of cement. 4.2.3.17 WEIGH out the required quantity of anhydrous sodium metasilicate (ASMS) into a separate vessel. NOTE: The quantity of ASMS is 15% of the cement weight. 4.2.3.18 Slowly ADD the cement to the test sample while it is being mixed. NOTE: Mixing should be accomplished by stir-ring with an electric mixing motor with blade until a homogeneous mixture is obtained, approximately one minute. 4.2.3.19 After all the cement is added, slowly ADD the ASMS to the test sample while it is being mixt ,. 4.2.3.20 Af ter sufficient mixing (2 minutes af ter all the ASMS is added) so that a homogeneous mixture.is obtained, SEAL the sample and CURE at 120 15 F for 24 hours. NOTE: If at any time during the 24 hour cure, ((']' the sample meets the acceptance critiera, the liner solidification may proceed. However, no test solidification shall be disqualified without at least 24 hours of cure. 4.3 Solidification Acceptability The following criteria define an acceptable solidification process and process parameters. 4.3.1 The sample solidifications are considered acceptable if there is no free standing water, and 4.3.2 If upon visual inspection, the waste appears that it would hold its shape if removed from the mixing vessel,
- and 4.3.3 It resists penetration.
NOTE: Even though the sample surface appears hard and dry, this may be just a thin surface crust. In order to avoid this situation, the solidification shall be considered acceptable if a flat surfaced metal probe approximately (\_/~3 1/8 inch in diameter cannot break the surface and penetrate to the sample core. Nominal denting of the surface is acceptable. 4
STD-P-05-003 Page 13 of 32 i O(_/ 4.4 Solidification Unacceptability 4.4.1 If the waste fails any of the criteria set forth in . Section 4.3, the solidification will be termed un-acceptable and a new set of solidification parameters will need to be established under the procedures in Section 4.5. 4.4.1 If the test solidification is unacceptable then the same test procedures must be followed on each sub-- sequent batch of the same type of waste until three (3) consecutive test samples are solidified. 4.5 Alternate Solidification Parameters 4.5.1 If a test sample fails to provide acceptable solidifi-cation of the waste, the following procedures should be followed. 4.5.1.1 Class A Unstable Wastes > (a) Mix 454.5 grams of cement and 45.5 grams of ASMS with 400 ml of water to ensure that the problem is not a bad batch of cement. A D (b) If the waste is only partially solidified, USE lower waste to cement and additive ratios. Using the recommended quantities of cement and additive, reduce the waste sample to 375 ml and CONTINUE reducing by the 25 ml increment until the acceptability criteria of Section 4.3 are met. (c) If an acceptable product is still not achieved, or if additional information is needed, CONTACT Hittman. 4.5.1.2 Class A Stable Class B and C vastes (a) Repeat Section 4.5.1.1 (a). (b) CONTACT Hittman for specific instructions. 5.0 PREMATURE LINER MIXING BLADE STALL 5.1 Class A Unstable Wastes 5.1.1 If a premature stall of the liner mixing blade occurs before the entire quantity of cement is added, CALCULATE the quantity of cement that was added, u
STD-P-05-003 Page 14 of 32 O 5.1.2 DETERMINE the pounds of cement per cubic feet of waste added. Refer to Items 8 through 10 on the Solidifi-cation Calculation Sheets. . 5.1.3 The minimum quantity of cement necessary to meet the minimum requirements for Class A Unstable Wastes is shown below. 5.1.3.1 >10-14 Weight Percent Boric Acid - 68.6 lbs/ft3 5.1.3.2 4 to 10 Weight Percent Boric Acid - 62 lbs/ft3 5.1.3.3 >10 to 20 Weight Percent Boric Acid - 60 lbs/ft3 42A/B O B O
STD-P-05-003 Page 15 of 32 ./ 'O TEST SOLIDIFICATION DATA SHEET FOR CLASS A UNSTABLE >10-14 WEIGHT PERCENT BORIC ACID . I. PRECONDITIONING Weight Percent of Boric Acid (in decimal form) (1) Weight of Untreated Sample, gms: (2) Volume of Untreated Sample, al: (3) Weight of 50% NaOH Added to Adjust pH, gms: (4) Final pH: (5) Weight of Anti-foam Added, gms: . (6) Weight of Emulsifier Added, gms l: (7) Final Volume of Treated Sample, ml: (8) II. TEST SOLIDIFICATION Volume of Pretreated Sample for Solidification, al: (9) Weight of Pretreated Sample for Solidification, gms: (10) () Weight of Portland Type I Cement 2, gms: (11) Weight of ASMS3 , gms: (12) Additional batches of solidified based on this sample solidification: Liner Waste Liner Waste Liner Waste No. Vol. Date No. Vol. Date No. Vol. Date III. SAMPLE INSPECTION Sample cured for 4 hours at room temperature: 0 Yes a No Verified by Date Sample contains "No Free Liquid": 0 Yes O No Verified by Date Sample is a " Free Stan ;*og Monolith": 0 Yes a No Verified by Date FORM STD-P-05-003-01 Sheet 1 of 2
~
- STD-P-05-003 Page 16 of 32
( D
'V TEST SOLIDIFICATION DATA SHEET FOR CLASS A UNSTABLE >10-14 WEIGHT PERCENT BORIC ACID -
(Continued) IV. PCP PERFORMED BY: Date: FOOTNOTES: ( 1 If emulsification is not accomplished call Hittman. 2 The cement ratio is defined as the pounds of cement required to solidify one cubic foot of waste. The ratio in the PCP for Class A Unstable
>10-14 Weight Percent Boric Acid is 78.8 lbs/ft3preteated waste.
3 The additive ratio is defined as the pounds of additive required to solidify one cubic foot of waste. The ratio in this PCP for Class A Unstable >10-14 Weight Percent Boric Acid is 13.1 lbs/ft3 of pretreated waste. FORM STD-P-05-003-01 Sheet 2 of 2
STD-P-05-003 Paga 17 of 32 3 l i SOLIDIFICATION CALCULATION SHEET FOR CLASS A UNSTABLE >10-14 WEIGHT PERCENT BORIC ACID 1 Volume of Untreated Waste to Add to Liner, ft : Item (3) + Item (8) X Max. Treated Waste Form STD-P-05-003-01 Form STD-P-05-003-01 Vol. from Solidifi-cation Data Tables Form STD-P-05-003-03 3
+ X = ft (3)
Volume of Additives to Add to Liner, Gallons: 50% NaOH: Item (4) (Item 3) Form STD-P-05-003-01 X 4.88 + Form STD-P-05-003-01 x (1): ! X 4.88 + X = gallons (2) n Anti-Foam: ((_/ (Item 3) 3 Item (6) Form STD-P-05-003-01 X 7.48 + Form STD-P-05-003-01 x (1): X 7.48 + _X
= gallons (3)
Emulsifier: 1
- Item (7) (Item 3)
Form STD-P-05-003-01 X 7.48 + Form STD-P-05-003-01 x (1): X 7.48 + X = gallons (4) i Volume of Pre-Treated Waste to be Solidified 1, ft 3: 4 (2) + (3) + (4), (3) ,
- 7.48
. ( )+( )+( ) = ft 3
(5) 7.48 l Cement Quantity for Full-Scale Solidification: 4 (5) x 78.8 = lbs cement (6) I ( FORM STD-P-05-003-02 i Sheet 1 of 2
STD-P-05-003 Page 18 of 32 i SOLIDIFICATION CALCULATION SHEET FOR CLASS A s UNSTABLE >10-14 WEIGHT PERCENT BORIC ACID (Continued) ASMS Quantity for Full-Scale Solidification:
-(5) x 13.1 = lbs ASMS (7)
Determination of the Quantity of Cement Added to Waste: Quantity of Cement Added to Hopper: lbs. (8) Quantity of Cement Left in Hopper: lbs. (9) Quantity of Cement Added per ft Waste: 3 (8) - (9) = lbs cement added per ft waste (10) ft" of Waste in Liner Minimum Quantity of Cement Allowable is 68.6 lbs/ft waste. Quantity of Cement Added Meets Minimum Requirements: 0 Yes a No Verified by Date FOOTNOTES: 1 The volume of TREATED waste to be solidified in a single liner cannot exceed the maximum waste volume listed on the Solidification Data Table for Class A Unstable >10 to 14 Weight Percent Boric Acid, Form STD-P-05-003-03. O FORMSheetSTD-P-05-003-02 2 of 2
^ '
STD-P-05-003 Paga 19 of 32
' V]
SOLIDIFICATION DATA TABLES FOR CLASS A UNSTABLE >10 TO 14 WEIGHT PERCENT BORIC ACID HN-100 HN-100 M LVM Series l' Series 21 Series 3 S Series 32 HN-100TVAM Usable Liner Vol., cu.ft. 141.1 141.1 141.1 141.1 157.5 123.9 Max. Treated Waste Vol., cu.ft. 81.3 78.2 95.8 95.8 106.9 84.1 Max. Solidified Waste Vol., cu.ft. 119.7 115.2 141.1 141.1 157.5 123.9 Cement Added at Max. Vaste Vol. Pounds 6406.4 6162.2 7549.0 7549.0 8423.7 6627.1 94 Pound Bags 68.1 65.6 S0.3 80.3 89.6 70.5 Anhydrous Sodium h Metasilicate Added at Max. Waste Vol. Pounds 1065.0 1024.4 1255.0 1255.0 1400.4 1101.7 , 100 Pound Bags 10.6 10.2 12.6 12.6 14.0 11.0 Max. Radiation Level R/hr Contact 12 12 12 3 12 10 1 For less than A2 quantities f LSA waste use data for Series 3 or S cask. 2 For less than A2 quantities of LSA waste. For greater than A,, quantities of i LSA waste the maximum treated waste volume is 98.5 cu.ft, due to weight limitations.
)
O FORM STD-P-05-003-03 Sheet 1 of 1
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STD-P-05-003 Paga 20 cf 32 r Liner No.: Sample No.: Date: - TEST SOLIDIFICATION DATA SHEET FOR 4 TO 10 WEIGHT PERCENT BORIC ACID (CLASS A UNSTABLE AND STABLE, CLASS B OR C) I. PRECONDITIONING Weight Percent of Boric Acid (in decimal form) (1) Weight of Untreated Sample, ges: (2) Volume of Untreated Sample, al: (3) Weight of 50% NaOH Added to Adjusted pH to 8, gms: (4) Final pH: (5) Weight of Anti-foam Added, gms: (6) Weight of Emulsifier Added, gms: (7) Volume of Treated Sample, al: (8) II. DETERMINATION OF PERCENT SOLIDS OF SAMPLE ' 'th Weight of Untreated Sample (2) x Percent Boric Acid (1) gas (9) Weight of 50% Na0H (4) x 0.5 gas (10) Weight of Solids in Treated Sample, ges: (6) + (7) + (9) + (10): ( )+( )+( )+( )= gas (11) Percent Solids in Treated Sample: i 100 x (11) + ((2) + (4) + (6) + (7)]: 100 x ( ) + [( )+( )+( )+( )] = % (12) III. DETERMINATION OF WATER IN SAMPLE FOR SOLIDIFICATION: Volume of Sample to be Solidified, al (13) ! l Weight of Sample to be Solidified, gas (14) O FORM STD-P-05-003-04 Sheet 1 of 3
L, , STD-P-05-003 Pega 21 of 32 r TEST SOLIDIFICATION DATA SHEET FOR 4 TO 10 WEIGHT PERCENT BORIC ACID (CLASS A UNSTABLE AND STABLE, CLASS B OR C) (Continued) Weight of Water in 50% NaOH Used to Adjust pH, gas: [ (2) (4) x (4) ] x 0.5: [( ) ( )x( ) ] x 0.5 = gas (15) Weight of Water in Sample to be Solidified, gas: [(14) - 2 x (15)] x [1 - (1)] + (15): [( )-2x( )] x [1 - ( )] + ( )= (16) IV. DETERMINATION OF QUANTITY OF PORTLAND T*lPE I CEMENT TO USE FOR SAMPLE SOLIDIFICATION, ges: Using Figure I, find the % solids in sample (12), and DETERMINE p v the Water / Cement Ratio: (17) Weight of Cement to Use, gas:
, , g,,(gg) fl6) g)
Weight of ASMS to Use, ges: Item 18 _ x .15 = gas (19) Additional batches solidified based on this sample solidification: Liner Waste Liner Waste Liner Waste No. Vol. Date No. Vol. Date No. Vol. Date V. SAMPLE INSPECTION Sample cured for 24 hours 1 @ 120* t 5'F: 0 Yes a No Verified by Date Sample contains "No Free Liquid" O Yes a No Verified by Date FORM STD-P-05-003-04 Sheet 2 of 3 .
1 I' STD-P-05-003
! Page 22 of 32 ! TEST SOLIDIFICATION DATA SHEET FOR 4 TO 10 WEIGHT j PERCENT BORIC ACID (CLASS A UNSTABLE AND STABLE, CLASS B OR C)
(Continued) i Sample is a " Free Standing Monolith": 0 Yes a No l i Verified by . Date , h l i i i I i r 4 !O I FOOTNOTES I 4 1It is not necessary to cure at 120* 1 5'F for Class A Unstable Waste, f If Class A Stable, Class B or C wastes are qualified in less than j 24 haurs, note the total hours cured. i i l i : 1 1 I 1 l r ( i FORM STD-P-05-003-04 } / Sheet 3 of 3 1 i l
STD-P-05-003 ; Paga 23 of 32 () . SOLIDIFICATION CALCULATION SHEET FOR CLASS A UNSTABLE AND STABLE, CLASS B OR C - 4 TO 10 WEIGHT PERCENT BORIC ACID Volume of Untreated Waste to Add to Liner, ft 3, 1 Item (3) + Item (8) X Max. Treated Vaste : Form STD-P-05-003-04 Form STD-P-05-003-04 Vol. from Solidifi-cation Data Tables Form STD-P-05-003-08
+ X = ft3 (1)
Volume of Additives to Add to Liner, Gallons: 50% NaOH: Item (4) (Item 3) Form STD-P-05-003-04 X 4.88 Form STD-P-05-003-04 x (1): X 4.88 + X = gallons (2) Anti-Foam: O Item (6) (Item 3) Form STD-P-05-003-04 X 7.48 + Form STD-P-05-003-04 x (1): X 7.48 + X = gallons (3) Emulsifier: Item (7) (Item 3) Form STD-P-05-003-04 X 7.48 + Form STD-P-05-003-34 x (1): X 7.48 + X = gallons (4) 3 Volume of Pre-Treated Waste to be Solidified 1 , ft gg) , (2) + (3) + (4) 7.48
, ( )+( )+( ) = ft 3
(5) 7.48 Cement Quantity for Full-Scale Solidification: Item (18) x 62.45 + Item (13) x (5): Form STD-P-05-003-04 Form STD-P-05-003-04 O x 62.45 + x = lbs cement (6) FORM STD-P-05-003-05 Sheet 1 of 2
STD-P-05-003 Page 24 of 32 O SOLIDIFICATION CALCULATION SHEET FOR CLASS A UNSTABLE AND STABLE, CLASS B OR C - 4 to 10 WEIGHT PERCENT BORIC ACID - (Continued) ASMS Quantity for Full-Scale Solidification: Item (6) x .15 = lbs. (7) DETERMINATION OF THE QUANTITY OF CEMENT ADDED TO WASTE Quantity of Cement Added to Hopper: lbs. (8) Quantity of Cement Left in Hopper: lbs. (9) Quantity of Cement Added per ft 3 y,,g, 3 (8) - (9) = lbs cement added per ft waste (10) ft3 of Waste in Liner _ _ Minimum Quantity of Cement Allowable for 4 t 10 3 Weight Percent Boric Acid CLASS A UNSTABLE Waste is 62 lbs/ft . Quantity of Cement Added Meets Minimum Requirements: 0 Yes a No Verified by Date FOOTNOTES: 1 The volume of TREATED waste to be solidified in a single liner cannot exceed the maximum waste volume listed on the Solidification Data Tables, Form STD-P-05-003-08. i O FORM STD-P-05-003-05 l Sheet 2 of 2
STD-P-05-003 Page 25 of 32 [ Liner No.: Sample No.: Date: - TEST SOLIDIFICATION DATA SHEET FOR >10 TO 20 WEIGHT PERCENT BORIC ACID (CLASS A UNSTABLE AND STABLE, CLASS B OR C) I. PRECONDITIONING Weight Percent of Boric Acid (in decimal form) (1) Weight of Untreated Sample, ges: (2) Volume of Untreated Sample, al: (3) Weight of 50% NaOH Added to Adjusted pH to 12, gms: (4) Final pH: (5) Weight of Anti-foam Added, gms: (6) Weight of Emulsifier Added, gas: (7) Volume of Treated Sample, al: (8) II. DETERMINATION OF PERCENT SOLIDS OF SAMPLE Weight of Untreated Sample (2) x Percent Boric Acid (1) gms (9) Weight of 50% NaOH (4) x 0.5 gas (10) Weight of Solids in Treated Sample, gas: (6) + (7) + (9) + (10): ( )+( )+( )+( )= gas (11) Percent Solids in Treated Sample: 100 x (11) + [(2) + (4) + (6) + (7)]: 100 x ( ) + (( )+( )+( )+( )] = % (12) III. DETERMINATION OF WATER IN SAMPLE FOR SOLIDIFICATION: Volume of Sample to be Solidified, al (13) Weight of Sample to be Solidified, gms (14) O FORM STD-P-05-003-06 Sheet 1 of 3
STD-P-05-003 Paga 26 of 32 TEST SOLIDIFICATION DATA SHEET FOR >10 TO 20 WEIGHT PERCENT BORIC ACID (CLASS A UNSTABLE AND STABLE, CLASS B OR C) (Continued) Weight of Water in 50% NaOH Used to Adjust pH, gas: ( (2) (4) x ( ) } x 0.5: ( [( ),( ) x( ) ) x 0.5 = gas. (15) Weight of Water in Sample to be Solidified, ges: [(14) - 2 x (15)] x (1 - (1)] + (15): [( )-2x( )] x (1 - ( )] + ( )= (16) IV. DETERMINATION OF QUANTITY OF PORTLAND TYPE I CEMENT TO USE FOR SAMPLE SOLIDIFICATION, gas: Using Figure I, find the % solids in sample (12), and DETERMINE
) the Water / Cement Ratio: (17)
Weight of Cement to Use, ges: (16) , ( ) = gas (18) (17) ( ) Weight of ASMS to Use, gas: Item 18 x .15 = gas (19) Additional batches solidified based on this sample solidification: Liner Waste Liner Waste Liner Waste , No. Vol. D_ay No. Vol. Date No. Vol. Date FORM STD-P-05-003-06 Sheet 2 of 3 0.
STD-P-05-003 Pege 27 of 32 ,O TEST SOLIDIFICATION DATA SKEET FOR >10 TO 20 WEIGHT PERCENT BORIC ACID (CLASS A UNSTABLE AND STABLE, CLASS B OR C) (Continued) V. SAMPLE INSPECTION Sample cured for 24 hours 1 @ 120' 1 5*F: 0 Yes a No Verified by Date Sample contains "No Free Liquid" O Yes O No Verified by Date Sample is a " Free Standing Monolith": 0 Yes 0 No Verified by Date O U FOOTNOTES IIt is not necessary to cure at 120* i 5'F for Cless A Unstable Waste. If Class A Stable, Clasr B or C wastes are qualified in less than 24 hours, note the total hours cured. FORM STD-P-05-003-06 Sheet 3 of 3 (])
* ** STD-P-05-003 Pcgn 28 of 32 n
V SOLIDIFICATION CALCULATION SHEET FOR CLASS A UNSTABLE AND STABLE, CLASS B OR C - >10 TO 20 WEIGHT PERCENT BORIC ACID Volume of Untreated Waste to Add to Liner, ft 1: Item (3) + Item (8) X Max. Treated Waste : Form STD-P-05-003-06 Form STD-P-05-003-06 Vol. from Solidifi-cation Data Tables Form STD-P-05-003-09
+ X = ft3 , (1)
Volume of Additives to Add to Liner, Gallons: 50% NaOH: Item (4) (Item 3) Form STD-P-05-003-06 X 4.88 + Form STD-P-05-003-06 x (1): X 4.88 + X = gallons (2) Anti-Foam: q Item (6) (Item 3) L/ Form STD-P-05-003-06 X 7.48 + Form STD-P-05-003-06 x (1): X 7.48 + X = gallons (3) Emulsifier: Item (7) (Item 3) Form STD-P-05-003-06 X 7.48 + Form STD-P-05-003-06 x (1): X 7.48 + X = gallons (4) 3 Volume of Pre-Treated Waste to be Solidified 1, ft , (3) , (2) + (3) + (4) , 7.48
, ( )+( )+( ) , gg 3 (5) 7.48 ;
Cement Quantity for Full-Scale Solidification: Item (18) (Item 13) x (5): Form STD-P-05-003-06 X 62.45 + Form STD-P-05-003-06 X 62.45 + X = gallons (6) FORM STD-P-05-003-07 Sheet 1 of 2
STD-P-05-003 Paga 29 of 32 SOLIDIFICATION CALCULATION SHEET FOR CLASS A UNSTABLE AND STABLE, CLASS B OR C - >10 TO 20 WEIGHT PERCENT BORIC ACID (Continued) . ASMS Quantity for Full-Scale Solidification: Item (6) x .15 = lbs. (7) Determination of the Quantity of Cement Added to Waste: Quantity of Cement Added to Hopper: lbs. (8) Quantity of Cement Left in Hopper: lbs. (9) 3 y,,g,; Quantity of Cement Added per ft 3 (8) - (9) = lbs cement added per ft was,te (10) ft" of Waste in Liner Minimum Quantity of Cement Allowable for CLASS A UNSTABLE Waste is 60 lbs/ft3 waste, g,m Quantity of Cement Added Meets Minimum Requirements: 0 Yes a No <q) Verified by Date FOOTNOTES: 1 The volume of TREATED waste to be solidified in a single liner cannot exceed the maximum waste volume listed on the Solidification Data Table, Form STD-P-05-003-09. FORM STD-P-05-003-07 Sheet 2 of 2
Pcg2 30 of 32
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~* STD-P-05-003 Pcg2 31 of 32 (3
k' SOLIDIFICATION DATA TABLES FOR CLASS A UNSTABLE AND STABLE, CLASS B OR C 4 TO 10 WEIGHT PERCENT BORIC ACID HN-100M HN-100 LVM Series 11 Series 21 Series 3 S Series 32 HN-100TVAM Usable Liner Vol. (cu.ft.) 141.1 141.1 141.1 141.1 157.5 123.9 Max. Treated Waste Vol. (cu.ft.) 93.1 89.5 104.4 104.4 116.6 91.7 Max. Solidified Waste Vol. (cu.ft.) 125.8 121.0 141.1 141.1 157.5 123.9 , Recommended Min. Treated Waste, Vol.3, (cu.ft.) 3 3 98.1 98.1 103.8 86.1 Min. Solidified Waste, Vol.3
\p) e
\s- (cu.ft.) 3 3 132.6 132.6 140.2 116.4 Max. Rad. Level R/hr Contact 12 12 12 3 12 10 1 For less than A2 quantities LSA waste, use data for Series 3 or S cask.
2 For less than A 2 quantities of LSA waste. For greater than A 2 9"*"titi'8 LSA waste, the maximum treated waste volume is 112.4 cu.ft. due to weight limitations. 3 These minimums are required when shipping to Barnwell, to comply with the 15% maximum void space criteria for liners containing solidified stable waste forms. Due to weight limitations, the Series 1 and 2 casks cannot be used. O FORM STD-P-05-003-08
, . ~t STD-P-05-003 Pegn 32 of 32 s
/^l SOLIDIFICATION DATA TABLES FOR ,
CLASS A UN3 TABLE AND STABLE, CLASS B OR C
>10 to 20 WEIGHT PERCENT BORIC ACID HN-100M HN-100 LVM Series 11 Series 21 Series 3 S Series 32 HN-100TVAM Usable Liner .
Vol. (cu.ft.) 141.1 141.1 141.1 141.1 157.5 123.9 Max. Treated Waste Vol. (cu.ft.) 87.4 84.0 101.3 101.3 113.1 89.0 Max. Solidified Waste Vol. (cu.ft.) 121.7 117.0 141.1 141.1 157.5 123.9 Reconumended Min. Treated Waste, Vol.3, (cu.ft.) 3 3 95.2 95.2 100.7 83.6 Min. Solidified Waste, Vol.3 3 3 116.4 (cu.ft.) 132.6 140.2 { 132.6 Max. Rad. Level R/hr Contact 12 12 12 3 12 10 1 For less than A2 quantities LSA waste, use data for Series 3 or S cask. 2 For less than A2 quantities of LSA waste. For greater than A,, quantities of LSA waste, the maximum treated waste volume is 106 cu.ft. due t5 weight limitations. 3 These minimums are required when shipping to Barnwell, to comply with the 15% maximum void space criteria for liners containing solidified stable waste forms. Due to weight limitations, the Series 1 and 2 casks cannot be used. FORM STD-P-05-003-09 ENG42A/B
FNP-0-M-30 APPENDIX A 7 (] GDIERIC INFORMATION FOR V DEVELOPING A PROCESS CONTROL PROGRAM o Standard Technical Specification 3.11.3 in NUREG-0472 and NUREG-0473 requires that the operator of each commercial nuclear power plant process low-level radioactive waste in accordance with a process control program (PCP). The PCP is also required to maintain surveillance requirements for the solidification of radioactive waste. o The purpose of the PCP is to describe the envelope within which processing and packaging of low-level radioactive waste will be accomplished to provide reasonable assurance of compliance with federal regulations and other requirements governing the transport and disposal of the low-level radioactive wastes, o The PCP is to be a manual containing a general description of the methods used for processing and packaging the radioactive waste and the specific process parameters pertaining to each method. The PCP also needs to address shipping manifest preparation and the quality assurance provided to verify compliance with applicable regulations and requirements, o All commercial nuclear power plant licensees must have an NRC-approved PCP for each of their respective plants, even if a contracted vendor
, processes and packages the waste. When the waste is processed by a vendor, a description of the plant-to-vendor equipment interface and l'~') \~/ the vendor's service requirements must also be addressed in the PCP.
The vendor is not required to have an approved PCP, but must maintain an NRC-approved topical report to process and package the waste. o Additional NRC guidance documents recommend that a training program be developed and implemented for personnel having responsibilities related to radioactive waste processing operations. This is to ensure that the waste processing is performed in accordance with the PCP. The training program is to be a repetitive training cycle with personnel requalified on a periodic basis. Individua1' training records ar to be maintained for audit and inspection. f /%
/
D
- Z r ._ ..c,c,. - Ec r ie Document Number: Rev: Rev Date:
o WESTINGHOUSE STD-P-05-034 1 8/14/85 HITTM AN NUCL E AR INCORPORATED
Title:
PCP for Incontainer Solidification of Class A Stable, Class B and C Bead Resia at Maximum Packaging Efficiency Director Project QA Rov, Rev Date Engineering Manager Manager r ENR-0 8-17-84 [ % p 84-235
/
c- ,ECN 8/14/85 g
~
.00 85-049 1 , ,
C OCUMENT CONTROL TONTRO _ LED CO P
.A > No. 00f 4 >
FORM 01(B) p.g. 1 or 13
4-STD-P-05-034 Page 2 of 13 (:) PROCESS CONTROL PROGRAM
- FOR INCONTAINER SOLIDIFICATION OF CLASS A STABLE, CLASS B AND C BEAD RESIN AT MAXIMUM .
PACKAGING EFFICIENCY 1.0 SCOPE 2 This procedure is applicable to the solidification of bead ion exchange resin of the mixed bed type classified as either Class A Stable, Class B or Class C wastes under the requirements of 10CFR61.55, Waste Classification. Class A Stable waste must meet the same stability requirements of Class B and C wastes under the criteria of 10CFR61.55, Waste Classification as required by the state of South Carolina. 2.0 PURPOSE 2.1 The purpose of the Process Control Program (PCP) for incon-tainer solidification of bead resin is to provide a program which will assure a solidified product which meets the requirements of 10CFR61.56, Waste Characteristics. 4
- The program consists of three major steps, which are:
(a) Procedures for collecting and analyzing samples; I (b) Procedures for solidifying samples; 1 (c) Criteria for process parameters for acceptance or re-l jection as solidified waste; , 2.2 This document shall be considered complete only when used in concert with the Westinghouse Hittman Nuclear Incorporated l procedures for field solidification. This document describes the methodology for determining the acceptable ratio of waste, additional water, cement and additive that will result in an acceptable product for transportation and burial. The Solidification Data Sheet then converts these ratico into the recommended quantity of cement and additive i that must be mixed with the waste.
! 3.0 COLLECTION AND ANALYSIS OF SAMPLES l ! 3.1 General Requirements l
3.1.1 As required by the Radiological Effluent Technical Specifications for PWR's and BWR's the PCP shall l be used to verify the solidification of at least one representative test specimen from every tenth
. i k- batch of each type of wet radioactive waste.
STD-P-05-034 Page 3 of 13 o O 3.1.2 For the purpose of the PCP a batch is defined as that quantity of waste required to fill a disposable liner with the appropriate quantity of waste prior to solidification. 3.1.3 If any test specimen fails to solidify, the batch under test shall be suspended until such time as additional test specimens can be obtained, alter-native solidification parameters can be determined in accordance with the Process Control Program, and a subsequent test verifies solidification. Solidification of the batch may then be resumed using the alternate solidification parameters determined. 3.1.4 If the initial test specimen from a batch of waste fails to verify solidification, then representative test specimens shall be collected from each con-secutive batch of the same type of waste until three (3) consecutive initial test specimens demonstrate solidification. The Process Control l Program shall be modified as required to assure solidification of subsequent batches of waste. 3.1.5 For high activity wastes, where handling of sam-(' ples could result in personnel radiation exposures which are inconsistent with the ALARA principle, representative non-radioactive samples will be tested. These samples should be as close to the actual wastes' chemical properties as possible. Typical expended mixed bed resin shall be used to simulate the spent bead resin. 3.2 Collection of Samples 3.2.1 Radiological protection. These procedures must be followed during sampling to minimize personnel exposure and to prevent the spread of contamination. 3.2.1.1 Comply with applicable Radiation Work Permits. 3.2.1.2 Test samples which use actual waste shall be disposed of by placing in the solidified liner. 3.2.1.3 A Test Solidification Data Sheet will be maintained for each test sample solidified. Each data sheet will contain pertinent infor-6 (} mation on the test sample and the batch numbers of waste solidified based on each test sample.
STD-P-05-034 Page 4 of 13 O 3.2.2 Test Solidification Data Sheet The Test Solidification Data Sheet will contain pertiment information on the characteristics of the test sample solidified so as to verify solid-ification of subsequent batches of similar waste without retesting. 3.2.2.1 The test sample data for spent resin will in-clude, but not necessarily be limited to, the type of waste solidified, volume of sample, sample number and the quantity of any addi-tive used to precondition the waste. 3.2.2.2 The appropriate Test Solidification Data Sheet will include the Solidification Number,
' Liner Number, Waste Volume, and Date Solid-ified, for each batch solidified.
3.2.3 Collection of Samples 3.2.3.1 Two samples shall be taken for analysis. If the radioactivity levels are too high to permit full size samples to be taken then g( ) smaller samples shall be taken with the results corrected accordingly. Sample sizes shall be determined by the plant Health Physics Staff. 3.2.3.2 If possible, samples should be drawn at least two days prior to the planned waste solidifi-cation procedure to allow adequate time to l complete the required testing and verifica-tion of solidification, and to allow for retesting if necessary. For Class A Stable, Class B and C wastes, approximately 28 hours are required for verification. ' 3.2.3.3 If the contents of more than one tank are to be solidified in the same liner then repre-sentative samples of each tank should be i drawn. The samples should be of such size that when mixed together they form samples of standard size as prescribed in Section 3 2.3.1. If the contents of a particular tank repre-l sent x% of the total waste quantity to be solidified then the sample of that tank should be of such size to represent.x% of the
~
l composite samples. [)
"# If the sample is drawn from the liner, it 3.2.3.4 should be mixed for 10 minutes or recircu-lated in the liner for at least three (3)
STD-P-05-034 Page 5 of 13
.on O volume changes prior to sampling to assure a representative sample.
3.3 Analysis of Samples This document only defines the parameters to be analyzed and not the methodology. This is left to the plant staff. Parameter Acceptable pH Initial pH for information only, pH adjusted as part of solidification process. Detergents No Appreciable Foaming , 4 Oil <1% 4.0 Test Solidification and Acceptance Criteria 4.1 Waste Conditioning 4.1.1 If large (i.e., foam causing) quantities of deter-gents are present, the sample should be treated with an anti-foaming agent. The quantity of anti-foaming agent required shall be recorded on the Test Solidification Data Sheet and shall not exceed one half of one percent by volume of the dewatered waste. 4.1.2 If oil is present in quantities greater than 1% by volume, the oil shall be reduced to less than 1% by skimming. NOTE: Wastes with oil greater than 1% by volume may not be shipped to Barnwell, South Carolina, but may be shipped to Hanford, Washingtou. Emulsification agents need not be used until the volume of oil exceeds 3% of the waste volume. The quantity of any emulsifier added to the sample for this purpose shall be recorded on the Test Solidification Data Sheet and shall not exceed one percent by volume of the dewatered waste. Oil in concentrations greater than 12% by volume may not be solidified under this procedure. ,
STD-P-05-034 Page 6 of 13 4.1.3 pH Conditioning 4.1.3.1 pH conditioning of Class A Stable, Class B and Class C wastes is accom-plished as part of the solidification process. 4.2 Test Solidification of Class A Stable, Class B and Class C Wastes 4.2.1 For the test solidification of bead resin, MEASURE into the mixing vessel 240 gm of dewatered resin. NOTE: Test solidification should be conducted using a 1,000 ml disposable beaker or similar size container. 4.2.2 DETERMINE the volume of the bead resin. NOTE: Tap the beaker gently on the bench to consolidate the resin prior to measuring the volume. 4.2.3 REC 0kD the volume of the consolidated bead resin on the Test Solidification Data Sheet for Class A Stable, Class B and C waste. g']) 4.2.4 WEIGH out 2.1 gms of EC-3 into a separate vessel. NOTE: EC-3 is a proprietary additive supplied solely by Hittman. 4.2.5 RECORD the weight of EC-3 on the Test Solidifica-tion Sheet for Class A Stable, Class B or C waste. 4.2.6 WEIGH out 84.3 gms of water and ADD to the vessel containing the EC-3. 4.2.7 RECORD the weight of water on the Test Solidifi-cation Data Sheet for Class A Stable, Class B or C waste. 4.2.8 MIX the EC-3 and the water thoroughly. 4.2.9 ADD the water-EC-3 solution to the bead resin and MIX thoroughly. l 1 ! 4.2.10 PRETREAT the sample to be solidified as specified in Section 4.1. . O
STD-P-05-034 Page 7 of 13
,)
4.2.11 MEASURE out 178.2 gm of Portland Type I cement and approximately 11.5 grams of Calcium Hydrcxide, Ca(OH)2, also known as hydrated lime into separate vessels. 4.2.12 RECORD the quantity of cement on the Class A Stable, Class B and C Test Solidification Data Sheet. 4.2.13 Slowly ADD the calcium hydroxide to the bead resin slurry, two (2) grams at a time. Mix for three (3) minutes between additions until the pH of the slurry is at least 11.5. ADD an additional three (3) grams of calcium hydroxide. This final addition may or may not alter the pH of the slurry. NOTE: Mixing should be accomplished by stirring with an electric mixing motor with blade. 4.2.14 RECORD the quantity of calcium hydroxide added to the slurry on the Class A Stable, Class B and C Test Solidification Data Sheet.
) 4.2.15 Slowly ADD the cement to the test sample while it
( is being mixed. 4.2.16 MIX for two (2) minutes after all the cement is added to obtain a homogeneous mix. I 4.2.17 SEAL the sample. l l i 4.2.18 Allow the sample to CURE for up to 24 hours at 120 1 5*F. NOTE: If at any time during the 24-hour cure time, the sample meets the acceptance criteria, the liner solidification may proceed. However, no test solidifica-tion shall be disqualified without at least 24 hours of cure. 4.3 Solidification Acceptablility The following criteria define an acceptable solidification process and process parameters. 4.3.1 The sample solidifications are considered accept-able if there is no free standing water, and O 4.3.2 If upon visual inspection the waste appears that it would hold its shape if removed from the mixing l I vessel, and
STD-P-05-034 Page 8 of 13 O k/ 4.3.3 It resists penetration. NOTE: Even though the sample surface appears hard and dry, this may be just a thin surface crust. In order to avoid this situation, the solidification shall be considered acceptable if a flat surfaced metal probe approximately 1/8 inch in diameter cannot break the surface and penetrate to the sample core. Nominal denting of the surface is acceptable. 4.4 Solidification Unacceptability 4.4.1 If the waste fails any of the criteria set forth in Section 4.3, the solidification will be termed unacceptable and a revised test procedure with revised solidification parameters will need to be established under the procedures in Section 4.5. 4.4.2 If the test solidification is unacceptable then the revised test procedures must be followed on each subsequent batch of the same type of waste until three (3) consecutive test samples are solidified. () 4.5 Alternate Solidification Parameters 4.5.1 If a test sample fails to provide acceptable solidification of the waste, contact Hittman for specific instructions. 5.0 PARAMETERS FOR FULL SCALE SOLIDIFICATION l 5.1 After successful completion of the test solidifications, calculate the amounts of additives and solidification agents l necessary per cubic foot of total waste using Section III of the Test Solidification Data Sheet. 5.2 Determine the amounts of additives and solidification agents to be added to the liner per instructions on the Class A Stable, Class B and C Waste Solidification Calculation Sheet, Form STD-P-05-034-02. 42A/G r
STD-P-05-034 Page 9 of 13
*/
C> Solidification No.: Batch No.: Sample No.: Date: CLASS A STABLE, CLASS B AND C TEST SOLIDIFICATION DATA SHEET for Bead Resin I. Sample Preparation Sample Volume, al: (1) Weight of EC-3 gms: (2) Weight of Water, gms: (3) Quantity of Oil l, %: (4) Weight of Emulsifier (20% by volume of oil) gas: (5) Weight of Anti-foam agent, gms: (6) O Initial pH: (7) 2 (8) Weight of Ca(OH)2 t raise pH to 2 11.5 , gas: Final pH: (9) Weight of Portland Type I Cement, ges: (10) Additional batches solidified based on this sample solidification: Liner Waste Liner Waste Liner Waste No. Vol. Date No. Vol. Date No. Vol. Date 5 t Form STD-P-05-034-01 Sheet 1 of 3 l
STD-P-05-034 Page 10 of 13 O II. SAMPLE INSPECTION Sample cured for 24 hours 3 @ 120' t 5* F: Verified by Date Sample contains 'No Free Liquid': Verified by Date Sample is a ' Free Standing Monolith': Verified by Date III. PARAMETERS FOR FULL SCALE SOLIDIFICATION Quantity of EC-3: 3 [ (2) x 6.3] + (1) = gallons EC-3 per ft of dewatered resin (11) O. Quantity of Water: [ (3) x 7 48] + (1) = gallons water per ft 3 of dewatered resin (12) Quantity of Emulsifier: [ (5) x 7.48] + (1) = gallons water per ft3 of dewatered resin (13) Quantity of Anti-fcam Agent: [ (6) x 7.48] + (1) = gallons anti-foam per ft3 of dewatered resin (14) Quantity of Calcium Hydroxide: [ (8) x 62.46] + (1) = lbs3 Ca(OH)2 Per ft of dewatered resin (15) Quantity of Portland Type I Cement: [ (10) x 62.46] + (1) = lbs Cement per ft 3 of dewatered resin (16) Form STD-P-05-034-01 Sheet 2 of 3
STD-P-05-034 Page 11 of 13 i o FOOTNOTES: 1 Must be $1% of waste volume for burial at Barnwell S.C. (See Section 4.1.2) 2Added in accordance with Section 4.2.13. 8 If the sample is qualified in less than 24 hours cure time, note the j total hours cured. co. 1 l. t l l Form STD-P-05-034-01
;O Sheet 3 of 3
STD-P-05-034 Page 12 of 13
~ ,..
O CLASS A STABLE, CLASS B AND C WASTE SOLIDIFICATION CALCULATION SHEET Volume Dewatered Resin to be Solidified 1 ft8 (1) Quantity of EC-3: . , (1) x = gallons. (2) Item 11 Form STD-P-05-034-01 Quantity of Water: (1) x = gallons. (3) Item 12 Form STD-P-05-034-01 Quantity of Emulsifier 2 (1) x = gallons. (4) Item 13 Form STD-P-05-034-01 Quantity of Anti-Foam Agent 2: (() (1) x = gallons. (5) Item 14 Form STD-P-05-034-01 Quantity of Calcium Hydroxide: (1) x = pounds. (6) Item 15 Form STD-P-05-034-01 Quantity of Portland Type I Cement: (1) x = pounds. (7) Item 16 Form STD-P-05-034-01 FOOTNOTES 1 The volume of dewatered bead resin to be solidified cannot exceed the maximum waste volume listed on Form STD-P-05-034-03, Class A Stable, Class B and C Test Solidification Data Sheet for Bead Resin. 2 Reduce the quantity of waste in the liner by 1 ft3 for every 10 gallons of emulsifier plus anti-foam agent added to the liner. . O l Form STD-P-05-034-02
O 8 O' ' l CLASS A STABLE, CLASS B AND C WASTE l SOLIDIFICATION DATA TABLE FOR BEAD RESIN HN-100 MUG HN-100 LVMUG HN-6001 Series 1 Series 2 Series 3 Series 3 HN-200 MU MUS MUG MUGS Usable Liner 141.1 141.1 141.1 148.0 59.4 64.1 59.3 64.1 57.3 l Volume (cu.ft.) Max. Dewatered 109.7 2 105.02 112.9 118.4 47.5 51.3 47.4 51.3 45.8 l Waste Vol. (cu.ft.) Max. Solidified 137.1 131.3 141.1 148.0 59.4 64.1 59.3 64.1 57.3 Waste Vol., (cu.ft.) Min. Recommended 104.7 104.7 104.7 106.1 45.6 - 46.9 - - l l Waste Vol.3 (cu.ft.) ! Min. Solidified 130.9 130.9 130.9 132.6 57.0 - 58.6 - - l Waste Vol.3 (cu.ft.) i 12 800 100 100 100 100 Max. Radiation Level 12 12 12 R/hr Contact 1 When solidifying stable waste forms in HN-600.MU, HUG, and MUGS liners for shipment to Barnwell, SC, grout or similar approved material must be added to the liners to increase the solidified product volume to meet the 15% maximum void space criteria. This criteria is based on 15% of the total nominal capacity found on the liner data sheets. y 5a 2 Volume destrictions apply only when >A9 quantities of LSA are solidified. If <A2 quantities of LSA are g7 to be solidified, use the maximum dewatered waste volume listed for HN-100 MUG Series 3. u3 3 These minimums are for stable waste forms being shipped to Barnwell to meet the 15% maximum void space u criteria. FORM STD-P-05-034-003 Sheet 1 of 1
F f FNP-0-M-030 APPENDIX "B" PROCESS CONTROL PROGRAM FOR ABSORPTION OF OIL O l l Gen. Rev. 4 O
'""- -"- 3 O
APPENDIX "B" PROCESS CONTROL PROGRAM FOR
, ABSORPTION OF OIL O
i Gen. Rev. 4 lO
FNP-0-M-030 PROCESS CONTROL PROGRAM Oi FOR ABSORPTION OF OIL 1.0 Purposes To provide a Process Control Program (PCP) which will assure an absorbed product that will comply with the State of Washington's Radioactive Materials License requirements for shallow land burial of contaminated oil. The PCP will determine the efficiency and proper proportions of aborbent for oil to be absorbed. 2.0 References 2.1 State of Washington's Radioactive Materials License, WNM-1019-2 2.2 Notice dated April 28, 1982, " Washington State Radioactive Waste Disposal Information" 3.0 Limitations 3.1 Only absorbents approved by State of Washington's Department of Social and Health Services shall be used. n 3.2 The PCP must determine the absorption ratio of the selected U absorbent. The container being filled must contain at least enough absorbent material to absorb twice the volume of liquid radioactive oil. 4.0 Procedure 4.1 Select an approved absorbent listed in Appendix F
" Absorbents", of the State of Washington's Radioactive Materials License, as found in FNP-0-RCP-830.
4.2 Add a suitable volume of absorbent, approximately 250 mls, to a i clear plastic zip lock bag. This will allow observation of the absorbent during the testing. Record absorbent volume on Data Sheet, Figure 1. 4.3 Slowly add increments of oil to the test specimen until approaching the saturation point as visually observed. 4.4 Record oil increments on Data Sheet. i l 4.5 Agitate the oil-absorbent mixture in the bag to ensure uniformity. 4.6 Transfer contents of bag to a glass container and let set for 24 hours. O 4.7 rnspect to verify no 1eexeee of the 011 from the aesorbent. 1 Gen Rev. 4 l l
9 FNP-0-M-030 4.8 If inspection fails, repeat entire procedure with smaller hr1 volume of oil that will eventually reduce the absorbent to oil ratio. 4.9 If inspection passes, invert container and repeat 4.7. 4.10 Record inspection results on data sheet. 4.11 Determine absorbent to oil ratio for test specimen: oil,mls = ratio absorbent,mls 4.12 Determine absorbent to oil ratio for actual packaging of absorbed oil: (oil, gallons)(2.0) = ratio (absorbent, gals)
- O a
2 Gen Rev. 4
- FNP-0-M-030 O
~
" ' ' ^ * * " " " = ' " = '
- 1. Abscrbent used: (reference Appendix F of License)
- 2. Volume of absorbent for test specimen: mis.
- 3. Volume of oil added to test specimen (added in increments):
#1 mls.
#2 mis.
#3 mis.
, #4 mis.
#5 mis.
Total mls.
- 4. Ratio of absorbent to oil, Specimen:
( )mls. of absorbent " ( )mls. of oil
- 5. Ratio of absorbent to oil, actual waste package:
( ) mis. absorbent (2.0) = Actual Packaging Ratio ( )mls. oil ' O Date Performed: Tested By: Reviewed By: NOTE: A copy of this completed Data Sheet will accompany the shipping i paperwork to Washington. FIGURE 1 RCP 7A/16 3 Gen Rev. 4 l l
~ 2 Document Number: Rev: Rev Dote: WESTINGHOUSE STD-P-05-021 1 11/14/85 HI TTM AN NUCL E AR INCORPORATED
Title:
Process Control Program ror Incontainer { } Solidification of Class A Unstable and Stable, Class B or C Decznted Diatomaceous Earth Prepared UPe M sor Diractor "*"#E*# QA Rev. Rev Dat*--- by *D #8' U Engineering Manager se rvi ce s services 0 7-5-83 {,h\$h;d [.d {Y 8 -394 11/14/85 UL ECN 1 V ' 85-157
. Rewritter C
- _- _i DOC'JMENT CONT ROL CONTROLLED COPY _
N o. co 3
/
l I FORM Ol(B) pog, 1 of 24
STD-P-05-021 Page 2 of 24 s- PROCESS CONTROL PROGRAM FOR INCONTAINER SOLIDIFICATION OF CLASS A UNSTABLE AND STABLE, CLASS B OR C DECANTED DIATOMACEOUS EARTH 1.0 SCOPE This procedure is applicable to the solidification of decanted diatomaceous earth classified as either Class A Unstable or Stable, Class B or Class C wastes under the requirements of 10CFR61.55, Waste Classification. Class A
- Stable waste must meet the same stability requirements of Class B and C wastes under the criteria of 10CFR61.56, Waste Characteristics as required 3 by the State of South Carolina.
2.0 PURPOSE 2.1 The purpose of the Process Control Program (PCP) for incontainer solidification of diatomaceous earth is to provide a program which will assure a solidified product which meets the requirements of 10CFR61.56, Waste Characteristics. The program consists of three major steps, which are: (a) Procedures for collecting and analyzing samples; (b) Procedures for solidifying samples; (c) Criteria for process parameters for acceptance or rejection as solidified waste; 2.2 This document shall be considered complete only when used in concert with the Westinghouse Hittman Nuclear Incorporated procedures for field solidification. This document describes the methodology for detennining the acceptable ratio of decanted waste, additional dilute waste, cement and additive that will result in an acceptable product for transportation and burial. The Solidification Data Sheet then converts these ratios into the recommended quantity of cement and additive that should be mixed with Class A Unstable waste and the recommended quantity of cement and additives that must be mixed with Class A Stable and Class B and C waste. 3.0 COLLECTION AND ANALYSIS OF SAMPLES 3.1 General Requirements 3.1.1 As required by the Radiological Effluent Technical Specifi-cations for PWR's and BWR's the PCP shall be used to verify the solidification of at least one representative test specimen from every tenth batch of each type of wet radio-active waste. O GEN. REV. 4
~
. STD-P-05-021 Pega 3 of 24
() 3.1.2 For the purpose of the PCP a batch is defined as that quan-tity of waste required to fill a disposable liner with the appropriate quantity of waste prior to solidification. 3.1.3 If any test specimen fails to solidify, the batch under test shall be suspended until such time as additional test speci-mens can be obtained, alternative solidification parameters can be determined in accordance with the Process Control
~
Program, and a subsequent test verifies solidification. Solidification of the batch may then be resumed using the alternate solidification parameters determined. 3.1.4 If the initial test specimen from a batch of waste fails to verify solidification, then representative test specimens shall be collected from each consecutive batch of the same type of waste until three (3) consecutive initial test specimens demonstrate solidification. The Process Control Program shall be modified as required to assure solidifica-tion of subsequent batches of waste. 3.1.5 For high activity wastes, where handling of samples could result in personnel radiation exposures which are incon-sistent with the ALARA principle, representative non-radioactive samples will be tested. These samples should be as close to the actual wastes' chemical properties as pos-- () sible. Crud contaminated diatomaceous earth shall be used' to simulate the actual waste. 3.2 Collection of Samples 3.2.1 Radiological protection. NOTE: These procedures should be followed during sampling to minimize personnel exposure and to prevent the spread of contamination. 3.2.1.1 Comply with applicable Radiation Work Permits. 3.2.1.2 Test samples which use actual waste may be disposed of by placing in the solidified liner. 3.2.1.3 A Test Solidification Data Sheet will be maintained for each test sample solidified. Each data sheet will contain pertinent information on the test sample and the batch numbers of waste solidified based on each test sample. 3.2.2 Test Solidification Data Sheet The Test Solidification Data Sheet will contain pertiment () information on the characteristics of the test sample solidi-fied so as to verify solidification of subsequent batches of similar waste without retesting. GEN. REV. 4
STD-P-05-021 Page 4 of 24
~() 3.2.2.1 The test sample data for diatomaceous earth will in-clude, but not necessarily be limited to, the type of waste solidified, volume of sample, sample number and the quantity of any additive used to precondition the waste.
3.2.2.2 The appropriate Test Solidification Data Sheet will include the Solidification Number, Liner Number, Waste Volume, and Date Solidified, for each batch solidified. 3.2.3 Collection of Samples 3.2.3.1 Two samples shall be taken for analysis. If the radio-activity levels are too high to permit full size samples to be taken then smaller samples shall be taken with the results corrected accordingly. Sample sizes shall be determined by the plant Health Physics Staff. 3.2.3.2 If possible, samples should be drawn at least two days prior to the planned waste solidification procedure to allow adequate time to complete the required testing and verification of solidification, and to allow for retesting if necessary. For Class A Unstable Waste, approximately 6 hours are required for verification. s For Class A Stable, Class B and C wastes, approximately 28 hours are required for verification. 3.2.3.3 If the contents of more than one tank are to be solidi-fied in the same liner then representative samples of each tank should be drawn. The samples should be of such size that when mixed together they form samples of standard size or of a size determined by the plant Health Physics staff as prescribed in Section 3.2.3.1. If the contents of a particular tank represent x% of the total waste quantity to be solidified then the sample of that tank should be of such size to represent x% of the composite samples. 3.2.3.4 If the sample is drawn from the liner, it should be mixed for 10 minutes or recirculated in the liner for at least three (3) volume changes prior to sampling to assure a representative sample. 3.3 Analysis of Samples I This document only defines the parameters to be analyzed and not the
- methodology. This is left to the plant staff.
Parameter Acceptable () pH Unstable: >5 GEN. REV. 4
STD-P-05-021 Page 5 of 24 () Parameter Acceptable pH Stable: Initial pH for informa-tion only, pH adjusted as part of solidification process. Detergents No Appreciable Foaming Oil 11% by volume 4.0 DETERMINATION OF THE QUANTITY OF WASTE IN THE LINER TO BE SOLIDIFIED NOTE: The maximum quantities of decanted waste, dilute waste ($ 12 weight percent diatomaceous earth), and total waste are listed in the Solidification Data Tables, Forms STD-P-05-021-06 through 09. Tables 1 and 2 are for Class A Unstable Waste (<A2 and >A2 9"*"~ tities of.LSA waste, respectively). Tables 3 and 4 are for Class A Stable, Class B and C waste (<A 2and >A 2 quantities of LSA waste respectively). 4.1 DETERMINE the quantity of decanted diatomaceous earth in the liner. 4.2 RECORD the volume of decanted diatomaceous earth in the liner on the proper Test Solidification Data Sheet (Item 1 on Form STD-P-() 05-021-01 for Class A Unstable, or Form STD-P-05-021-03 for Class A Stable, Class B or C wastes). 4.3 CALCULATE the total waste volume per instructions on the proper , Test Solidification Data Sheet (Item 2). 4.4 CALCULATE the volume of dilute slurry to be added to the liner per instructions on the proper Test Solidification Data Sheet (Item 3). 4.5 Items 1, 2, and 3 can be entered as Items 1, 2, and 3 on the proper Solidificacion Calculation Sheet (Form STD-P-05-021-02 for Class A Unstable waste or Form STD-P-05-021-04 for Class A Stable, Class B and C wastes). NOTE: ENSURE that Section 4.0, Determination of the Quantity of Waste in the Liner to be Solidified is completed according to Steps 4.1 through 4.5 and verify this on Form STD-P-05-021-05. 5.0 Test solidification and Acceptance Criteria 5.1 Waste Conditioning 5.1.1 If large (i.e., foam causing) quantities of detergents are present, the sample should be treated with an anti-foaming (]) agent. The quantity of anti-foaming agent required shall be ' recorded on the Test Solidification Data Sheet and shall not GEN. REV. 4
STD-P-05-021 Page 6 of 24 (b
exceed one half of one percent by volume of the decanted waste.
5.1.2 If oil is present in quantities greater than 1% by volume, the oil shall be reduced to less than 1% by skimming. NOTE: Wastes with oil greater than 1% by volume may not be shipped to Barnwell, South Carolina, but may be shipped to Hanford, Washington. Emulsification agents need not be used until the volume of oil exceeds 3% of the waste volume. The quantity of any emulsifier added to the sample for this pur-pose shall be recorded on the Test Solidification Data Sheet and shall not exceed one percent by volume of the dewatered waste. Oil in concentra-tions greater than 12% by volume may not be solidified under this procedure. 5.1.3 pH Conditions 5.1.3.1 For Class A Unstable wastes, if the pH of the sample is less than 5, it shall be adjusted to at least 5 by the addition of 50% sodium hydroxide. 5.1.3.2 For Class A Stable or Class B or C wastes, the pH is O' adjusted as part of the solidification process. 5.2 Test Solidification of Class A Unstable Wastes 5.2.1 MEASURE out 420 gas of decanted diatomaceous earth into a one liter disposable beaker or similar size container. 5.2.2 RECORD the sample weight and volume on the Class A Unstable Test Solidification Data Sheet, Form STD-P-05-021-01 (Items 4 and 5). 5.2.3 MEASURE out 51.1 gas of dilute diatomaceous earth slurry (<12 weight percent diatomaceous earth) and ADD to the decanted waste slurry. 5.2.4 RECORD the weight and volume of the dilute slurry added to the decanted waste on the Unstable Test Solidification Data Sheet (Items 6 and 7). 5.2.5 MEASURE the total volume of waste (dilute plus decanted waste). 5.2.6 RECORD the volume of total waste on the Unstable Test Solidi-fication Data Sheet (Item 8). ! s/ 5.2.7 PRETREAT the sample as specified in Section 5.1. GEN. REV. 4
STD-P-05-021 Page 7 of 24 s (_) 5.2.8 RECORD the quantity of oil in the sample, the amounts of additives, the initial pH, and the final pH on the Unstable Test Solidification Data Sheet (Items 9 through 14). 5.2.9 MEASURE out 254.7 gas of Portland Type I cement and 25.5 gms of anhydrous sodium metasilicate (ASMS). 5.2.10 RECORD the quantity of cement and ASMS on the Unstable. Test Solidification Data Sheet (Items 15 and 16). 5.2.11 Slowly ADD the cement to the waste slurry while mixing. NOTE: Mixing should be accomplished by stirring with an electric mixing motor with blade. 5.2.12 MIX for one (1) minute after all the cement is added to ob-tain a homogeneous mix. 5.2.13 Slowly ADD the ASMS to the sample while mixing. 5.2.14 MIX for two (2) minutes after the ASMS is added to obtain a homogeneous mix. 5.2.15 RECORD the final solidified product volume on the Unstable Waste Solidification Data Sheet (Item 17). O 5.2.16 SEAL the sample and allow it to cure for 24 hours at room temperature. NOTE: If at any time during the 24 hour cure, the sample meets the acceptance criteria, the liner solidifi-cation may proceed. However, no test solidifica-tion shall be disqualified without at least 24 hours of cure. NOTE: ENSURE that Section 5.2, Test Solidification of Class A Unstable Wastes is completed according to Steps 5.2.1 through 5.2.16 and verify this on Form STD-P-05-021-05. 5.3 Test Solidification of Class A Stable, Class B or C Wastes 5.3.1 MEASURE out 316.2 gms of decanted diatomaceous earth into a one liter disposable beaker or similar size container. 5.3.2 RECORD the sample weight and volume on the Class A Stable, Class B or C Test Solidification Data Sheet, Form STD-P-05-021-03 (Items 4 and 5). 5.3.3 MEASURE out 34.8 gms of dilute diatomaceous earth slurry () (<12 weight percent diatomaceous earth) and ADD to the decanted waste slurry. GEN. REV. 4
STD-P-05-021 Page 8 of 24 () 5.3.4 RECORD the weight and volume of the dilute slurry added to the decanted waste on the Stable Test Solidification Data Sheet (Items 6 and 7). ,' 5.3.5 RECORD the total waste volume - dilute plus decanted - on the Stable Test Solidification Data Sheet (Item 8). 5.3.6 PRETREAT the sample as specified in Section 5.1. 5.3.7 RECORD the quantity of oil in the sample, the amounts of emulsifier and anti-foam agent and the initial pH, on the Stable Test Solidification Data Sheet (Items 9 through 12). 5.3.8 MEASURE out approximately 11 gas of calcium hydroxide, Ca(OH)2, also known as hydrated lime, into separate vessels. 5.3.9 Slowly ADD the calcium hydroxide to the diatomaceous earth slurry, two (2) grams at a time. Mix for three (3) minutes between additions until the pH of the slurry is at least 11.5. ADD an additional three (3) grams of calcium hydroxide. This final addition may or may not alter the pH of the slurry. NOTE: Mixing should be accomplished by stirring with an electric mixing motor with blade. 5.3.10 RECORD the quantity of calcium hydroxide added to the slurry and the final pH on the Stable Test Solidification Data Sheet (Items 13 and 14). 5.3.11 MEASURE out 258.4 gms Portland Type I cement. 5.3.12 RECORD the amount of cement on the Stable Test Solidifi-cation Data Sheet (Item 15). 5.3.13 Slowly ADD the cement to the test sample while it is being mixed. 5.3.14 MIX for two (2) minutes after all the cement is added to obtain a homogeneous mix. 5.3.15 RECORD the final solidified volume on the Stable Test Solidification Data Sheet (Item 16). 5.3.16 SEAL the sample. 5.3.17 Allow the sample to CURE for up to 24 hours at 120 5 F. NOTE: If at any time during the 24-hour cure time, the sample meets the acceptance criteria, the liner () solidification may proceed. However, no test GEN. REV. 4
STD-P-05-021 Page 9 of 24 solidification shall be disqualified without at least 24 hours of cure. NOTE: ENSURE that Section 5.3, Test Solidification of Class A Stable, Class B and C wastes, is completed according to Steps 5.3.1 through 5.3.17 and verify this on Form STD-P-05-021-05. 5.4 Solidification Acceptablility The following criteria define an acceptable solidification process and process parameters. 5.4.1 The sample solidifications are considered acceptable if there is no free standing water, and 5.4.2 If upon visual inspection the waste appears that it would hold its shape if removed from the mixing vessel, and 5.4.3 It resists penetration. NOTE: Even though the sample surface appears hard and dry, this may be just a thin surface crust. In order to avoid this situation, the solidification shall be considered acceptable if a flat surfaced metal probe O- approximately 1/8 inch in diameter cannot break the surface and penetrate to the sample core. Nominal denting of the surface is acceptable. 5.4.4 VERIFY the acceptance criteria by signing and dating each item in Section IV of the proper Test Solidification Data Sheet. NOTE: ENSURE that Section 5.4, Solidification Accept-ability is completed according to Steps 5.4.1 through 5.4.4 and Verify this on Form STD-P 021-05. 5.5 Solidification Unacceptability 5.5.1 If the waste fails any of the criteria set forth in Section 5.4, the solidification will be termed unacceptable and a revised test procedure with revised solidification param-eters will need to be established under the procedures in Section 5.6. 5.5.2 If the test solidification is unacceptable then the revised test procedures must be followed on each subsequent batch of the same type of waste until three (3) consecutive test samples are solidified. O GEN. REV. 4
STD-P-05-021 Pags 10 of 24 9 C 5.6 Alternate Solidification Parameters 5.6.1 If a test sample fails to provide acceptable solidification of the waste, the following procedures should be followed. 5.6.1.1 Class A Unstable Wastes (a) MIX 454.5 grams of cement and 45.5 grams of ASMS with 400 ml of water to ensure that the problem is not a bad batch of cement. (b) If the waste is only partially solidified, Use lower waste to cement and additive ratios. Using the recommended quantities of cement and additive, reduce the waste sample to 395 gms and continue reducing by this increment until the acceptability criteria of Section 5.4 are met. (c) If an acceptable product is still not achieved, or if additional information is needed, CONTACT Hittman. 5.6.1.2 Class A Stable, Class B or C Wastes (a) CONTACT Hittman. 6.0 PARAMETERS FOR FULL SCALE SOLIDIFICATION 6.1 Unstable Waste Solidification , 6.1.1 After successful completion of the test solidifications, CALCULATE the amounts of additives and solidification agents necessary, per cubic foot of total waste per instructions in Section V of the Unstable Test Solidification Data Sheet (Items 18 through 22). 6.1.2 DETERMINE the amounts of additives and solidification agents to be added to the liner per instructions on the Unstable Solidification Calculation Sheet, Form STD-P-05-021-02 (Items 4 through 8). NOTE: ENSURE that Section 6.1, Unstable Waste Solidifi-cation, is completed according to Steps 6.1.1 and 6.1.2 and verify,this on Form STD-P-05-021-05. 6.2 Stable Waste Solidification 6.2.1 After successful completion of the test solidifications, CALCULATE the amounts of additives and solidification agents necessary, per cubic foot of total waste per instructions in s,/ Section V of the Stable Test Solidification Data Sheet (Items 17 through 20). GEN. REV. 4
. j STD-P-05-021 Page 11 of 24
( 6.2.2 DETERMINE the amounts of additives and solidification agents I to be added to the liner per instructions on the Stable ! Solidification Calculation Sheet, Form STD-P-05-021-04 1 (Items 4 through 7). NOTE: ENSURE that Section 6.2, Stable Waste Solidifica . tion, is completed according to Steps 6.2.1 and 6.2.2 and verify this on Form STD-P-05-021-05. 4 7.0 SOLIDIFICATION USING LESS THAN RECOMMENDED QUANTITIES OF CEMENT 7.1 If, for any reason, the entire quantity of cement calculated as neces-sary for solidification is not added to the liner, contact Hittman. 36W 1 O 1 () GEN. REV. 4
- l. STD-P-05-021 1 Paga 12 of 24 V CLASS A UNSTABLE TEST SOLIDIFICATION DATA SHEET FOR DECANTED DIATOMACEOUS EARTH I. DETERMINATION OF QUANTITY OF WASTE. TRANSFERRED TO THE LINER Volume of Decanted Diatomaceous Earth Waste in the Liner 1, ft : (1)
Total Waste Volumel, ft : (1) + 0.88 = (2) Volume of Dilute Slurry to be Added to the Liner 1, ft :* (2) - (1) = (3) II. SAMPLE PREPARATION Weight of Decanted Diatomaceous Earth, gms: (4) Volume of Decanted Diatomaceous Earth, ml: (5) Weight of Diluted Diatomaceous Earth slurry, gms: (6) Volume of Diluted Diatomaceous Earth slurry, ml: (7) Total Volume of Waste (Dilute plus Decanted waste), al: (8) Quantity of Oil in sample 2, %: (9) Weight of Emulsifier added to sample ,3gms: (10) Quantity of Anti-Foam Agent added to sample, gms: (11) Initial pH: (12) Weight of 50% NaOH to raise pH >5, gms: (13) Final pH: (14) III. SOLIDIFICATION Quantity of Portland Type I Cement added to sample, gms: (15) Quantity of Anhydrous Sodium Metasilicate added to sample, gas: (16) Final Solidification Volume, al: (17) Form STD-P-05-021-01 Sheet 1 of 3 O GEN. REV. 4
~ .
STD-P-05-021 Page 13 of 24 IV. SAMPLE INSPECTION Sample cured for 24 hours 4: O yes O no Verified by Date Sample contains 'No Free Liquid': O yes a no Verified by Date Sample is a ' Free Standing Monolith': O yes O no Verified by Date Sample Resists Penetration: O yes O no Verified by Date Additional batches solidified based on this sample solidification: Liner Waste Liner Waste Liner Waste No. Vol. Date No. Vol. Date No. Vol. Date l V. PARAMETERS FOR FULL-SCALE SOLIDIFICATION Quantity of Emulsifier: (10) x 7.48 + (8) = gallogs of emulsifier (18) per ft of total waste l Quantity of Anti-Foam Agent:
- (11) x 7.48 + (8) = gallogsofanti-foam (19) per ft of total waste O Form STD-e-0s-021-01 Sheet 2 of 3 GEN. REV. 4
STD-P-05-021 Page 14 of 24
} Quantity of 50% Sodium Hydroxide:
(13) x 4.86 + (8) = ga}lonsofNa0Hper (20) ft of total waste Quantity of Portland Type I Cement: (15) x 62.43 + (8) = lbs cement per ft (21) of total waste Quantity of ASMS: (16) x 62.43 + (8) = lbs ASMS per ft (22) of total waste FOOTNOTES: 1The volumes of decanted diatomaceous earth, dilute slurry and total waste cannot exceed the maximum volumes listed on the Unstable Solidification Data Tables (Tables 1 for <A 2 and Table 2 for >A2 quantities of LSA waste). 2Must be < 1% of total waste volume for burial at Barnwell, S.C. 3 Quantity of emulsifier is 20% by volume of the oil.
\
4 If the sample is qualified in less than 24 hours, note the total hours cured. Form STD-P-05-021-01 l O Sheet 3 of 3 GEN. REV, 4
- STD-P-05-021 Pags 15 of 24 ' CLASS A UNSTABLE SOLIDIFICATION CALCULATION SHEET Volume of Decanted Diatomaceous Earth Wastel, ft 3 (3) 3 1
Total Waste Volume to be solidified , ft : (2) 3 Volume of Dilute Diatomaceous Earth Slurry added to liner 1 , ft : (3) Quantity of Emulsifier 2: (2) x = gallons (4) Item 18 Form STD-P-05-021-01 Quantity of Anti-Foam Agent 2: (2) x = gallons (5) Item 19 Form STD-P-05-021-01 Quantity of 50% Sodium Hydroxide2 : (2) x = gallons (6) Item 20 Form STD-P-05-021-01 Quantity of Portland Type I Cement: (2) x = pounds (7) Item 21 Form STD-P-05-021-01 Quantity of ASMS: i (2) x = pounds (8) Item 22 Form STD-P-05-021-01 FOOTNOTES: 1The volumes of decanted diatomaceous earth, dilute diatomaceous earth and the total waste volumes cannot exceed the maximum volumes listed on the attached Unstable Solidification Data Tables (Table 1 for < A quantities of LSA waste; 2 Table 2 for > A quantities of LSA waste). 2 2 Reduce the quantity of waste in the liner by 1 ft for every 10 gallons of emulsifier plus anti-foam agent plus 50% sodium hydroxide added to the liner. No adjustment is necessary for the first 10 gallons. i Form STD-P-05-021-02 Sheet 1 of 1 GEN. REV. 4
STD-P-05-021 Page 16 of 24 tq v CLASS A STABLE, CLASS B OR C TEST SOLIDIFICATION DATA SHEET FOR DECANTED DIATOMACEOUS EARTH I. DETERMINATION OF QUANTITY OF WASTE TRANSFERRED TO THE LINER Volume of DeSanted Diatomaceous Earth Waste in the Liner 1 , ft : (1) 3 Total Waste Volumel, ft : (1) + 0.898 = (2) Volume of Dilute Slurry to be Added to the Liner 1 , ft : (2) - (1) = (3) II. SAMPLE PREPARATION Weight of Decanted Diatomaceous Earth, gms: (4) Volume of Decanted Diatomaceous Earth, m1: _ (5) Weight of Diluted Diatomaceous Earth slurry, gms: (6) Volume of Diluted Diatomaceous Earth slurry, al: (7) Total Volume of Waste (Dilute plus Decanted waste Mixed), ml: (8) Quantity of Oil in sample 2, g: (9) Weight of Emulsifier added to sample 3, gms: (10) Quantity of Anti-Foam added to sample, gms: (11) Initial pH: (12) III. SOLIDIFICATION Quantity of Ca(OH)2 necessary to raise the pH > 11.5, gms: (13) Final pH: (14) Quantity of Portland Type I Cement, gms: (15) Final Solidification Volume, al: (16) Form STD-P-05-021-03 Sheet 1 of 3 O GEN. REV. 4
STD-P-05-021 Page 17 of 24 l (, IV. SAMPLE INSPECTION Sample cured for 24 hours 4 at 120*F: O yes O no Verified by Date Sample contains 'No Free Liquid': O yes O no 4 Verified by Date Sample is a ' Free Standing Monolith': O yes O no Verified by Date Sample Resists Penetration: O yes a no Verified by Date 3 Additional batches solidified based on this sample solidification: 1 Liner Waste Liner Waste Liner Waste No. Vol. Date No. Vol. Date No. Vol. Date I V. PARAMETERS FOR FULL-SCALE SOLIDIFICATIOH l l Quantity of Emulsifier: (10) x 7.48 + (8) = gallogsofemulsifier (17) per ft of total waste Quantity of Anti-Foam Agent: (11) x 7.48 + (8) = gallogs of anti-foam (18) per ft of total waste Form STD-P-05-021-03 Sheet 2 of 3 GEN. REV. 4
-U
,, STD-P-05-021 Page 18 of 24
*G
(_,/ Quantity of Ca(OH)2 (13) x 62.43 + (8) = lbg of Ca(OH)2 Per (19) ft of total waste Quantity of Portland Type I Cement: 3 (15) x 62.43 + (8) = lbs cement per ft (20) of total waste FOOTNOTES: 1 The volumes of decanted diatomaceous earth, total waste, and dilute slurry added to the liner cannot exceed the maximum volumes listed on the Stable Solidification Data Tables (Table 3 for <A2 and Table 4 for >A2 quantities of LSA waste). 2 Must be 5 1% of total waste volume for burial at Barnwell, S.C. 3 Quantity of emulsifier is 20% by volume of the oil. 4 If the sample is qualified in less than 24 hours, note the total hours cured. i i a ! Form STD-P-05-021-03 () Sheet 3 of 3 GEN. REV 4
STD-P-05-021 Page 19 of 24 CLASS A STABLE, CLASS B AND C SOLIDIFICATION CALCULATION SHEET Volume of Decanted Diatomaceous Earth Waste in the Liner 1 , ft : (1) 3 Total Waste Volume in the Liner to be solidified 1, ft : (2) Volume of Dilute Diatomaceous Earth Slurry.added to liner 1 , ft : (3) Quantity of Emulsifier 2 (2) x = gallons (4) Item 17 Form STD-P-05-021-03 Quantity of Anti-Foam Agent 2 (2) x = gallons (5) Item 18 Form STD-P-05-021-03 Quantity of Ca(OH)2* (2) x = pounds (6) Item 19 Form STD-P-05-021-03 Quantity of Portland Type I Cement: (2) x = pounds (7) Item 20 Form STD-P-05-021-03 FOOTNOTES: 1The volumes of decanted diatomaceous earth, dilute diatomaceous earth and the total waste volumes cannot exceed the maximum volumes listed on the attached Stable Solidification Data Tables, Table 3 (<A qua 2 tities of LSA waste) or Table 4 (>A 2 quantities of LSA waste), 2 Reduce the quantity of waste in the liner by 1 ft 3for every 10 gallons of emulsifier plus anti-foam agent plus 50% sodium hydroxide added to the liner. No adjustment is necessary for the first 10 gallons. Form STD-P-05-021-04 p J Sheet 1 of 1 GEN. REV. 4
STD-P-05-021 Page 20 of 24 DATE: LINER NO.: PROCEDURE VERIFICATION SHEET Verified By: Section 4.0, Determination of the Quantity of Waste in the Liner to be Solidified, Steps 4.1 through 4.5 completed. Section 5.2, For Class A Unstable Wastes or Section 5.3 for Class A Stable, Class B or C Wastes, Test Solidification, Steps 5.2.1 through 5.2.16 or 5.3.1 through 5.3.17 completed. Section 5.4, Solidification Acceptability, Steps 5.4.1 through 5.4.4 completed. Section 6.0, Parameters for Full Scale Solidification, Steps 6.1.1 through 6.1.2 for Class A Unstable or 6.2.1 through 6.2.2 for Class A Stable, Class B or O C wastes completed. Form STD-P-05-021-05 Sheet 1 of 1 GEN. REV. 4
( STD-P-05-021 Page 21 of 24
- TABLE 1 UNSTABLE SOLIDIFICATION DATA TABLE 4
<A 2 Quanitites of LSA Waste Liner 100 M 100 MG 100 LVM 100 LVMG
! I Usable Liner 141.1 141.1 157.5 155.6 Volume, ft3 Max. Decanted Waste 109.2 109.2 122.0 120.5 Volume, ft 3 Max. Dilute Slurry 14.9 14.9 16.6 16.4 Volume, ft3
! Max. Total Waste 124.1 124.1 138.6 136.9 i Volume, ft3 Max. Solidified 141.1 141.1 157.5 155.6 Volume, ft3 Max. Radiation Level 12 12 12 12 .
O, R/br Contact i I i
- l i
j I Form STD-P-05-021-06 L () Sheet 1 of 1 GEN. REV. 4
STD-P-05-021 Page 22 of 24 O TABLE 2 UNSTABLE SOLIDIFICATION DATA TABLE
>A 2 Quanitites of LSA Waste Liner 100 M 100 LVM 100 LVMG Cask Series 1 Series 2 Series 3 Series S Series 3 Series 3 Usable Liner 141.1 141.1 141.1 141.1 157.5 155.6 Vol., ft 3 Max. Decanted 103.7 99.6 109.2 109.2 122.0 120.5 Waste Vol., ft 3 Max. Dilute Slurry 14.1 13.6 14.9 14.9 16.6 16.4 Waste Vol., ft 3 Max. Total Waste 117.8 113.2 124.1 124.1 138.6 136.9 Volume, ft3 Max. Solidified 133.8 128.7 141.1 141.1 157.5 155.6 Volume, ft 3 O Max. Radiation 12 12 12 12 12 12 Level R/hr Contact Form STD-P-05-021-07 Sheet 1 of 1 O
GEN. REV. 4
STD-P-05-021 Page 23 of 24 (, TABLE 3 STABLE SOLIDIFICATION DATA TABLE
<A Quanitites f LSA Waste 2
Liner 100 M 100 MG 100 LVM 100 LVMG Usable Liner 141.1 141.1 157.5 155.6 Volume, ft3 Max. Decanted Waste 96.5 96.5 107.8 106.5 Volumel, ft3 Max. Dilute Slurry 11.0 11.0 12.2 12.1 Volumel, ft3 Max. Total Waste 107.5 107.5 120.0 118.6 Volume l
, ft3 Max. Solidified .141.1 141.1 157.5 155.6 Volume, ft3 Min. Decanted Waste 90.7 89.5 96.0 94.8 O Volumel, ft3 Min. Dilute Slurry 10.3 10.2 10.9 10.8 Volumel, ft3 Min. Total Waste 101.0 99.7 106.9 105.6 Volumel, ft3 Min. Solidified 132.6 130.9 140.2 138.6 Volume, fts Max. Radiation Level 12 12 12 12 R/hr Contact FOOTNOTE 1
Using the maximum or minimum waste volumes or waste volumes between these limits shown assure meeting the 15% maximum void space criteria for shipments to Barnwell, S.C. Form STD-P-05-021-08 (j Sheet 1 of 1 GEN. REV. 4
STD-P-05-021 Pagn 24 of 24 O v TABLE 4 STABII SOLIDIFICATION DATA TABLE
>A 2 Quanitites of LSA Waste Liner 100 M 100 LVM 100 LVMG Cask Series 1 Series 2 Series 3 Series S Series 3 Series 3 Usable Liner 141.1 141.1 141.1 141.1 157.5 155.6 Vol., ft 3 Max. Decanted 92.9 89.42 96.5 96.5 107.8 106.5 Waste Vol.1, ft3 Max. Dilute Slurry 10.6 10.12 11.0 11.0 12.2 12.1 Waste Vol.1, ft 3 Max. Total Waste 103.5 99.52 107.5 107.5 120.0 118.6 Volumel, ft3 Max. Solidified .135.8 130.62 141.1 141.1 157.5 155.6 Volume, fts
() Min. Decanted Waste Vol.1, ft3 90.7 2 90.7 90.7 96.0 94.8 2 10.3 10.3 10.9 10.8 Min. Dilute Slurry 10.3 Volumel, ft3 2 105.6 Min. Total Waste 101.0 101.0 101.0 106.9 Volume , ft 3 l 132.6 2 132.6 132.6 140.2 138.6 Min. Solidified Volume, ft3 Max. Radiation 12 12 12 12 12 12 Level R/hr Contact FOOTNOTE 1Using the maximum or minimum waste volumes or waste volumes between these limits shown assure meeting the 15% maximum void space criteria for shipments to Barnwell, S.C. 2 When shipping stable waste of >A quantities of LSA waste in KN-100 M liners, a Series 2 cask cannot be used. T$e15%maximumvoidspacecriteriawillnotbe met due to weight restrictions. O Form STD-P-05-021-09 Sheet 1 of 1 GEN. REV. 4
.z .
Document Number: Rev: Rev Date: STD-P-05-022 1 10-24-85 WES11NGHOUSE HITTM AN NUCL E AR 9 INCORPORATED
Title:
Calcium Hydroxide Addition Procedure Director Proj ect QA Rev. Rev Date Engr. Manager Manager 0 2-9-84 Qi 7 - 2 y 1* , ECN 10-24-85 65-147 f ~ %.0
/
Jor w w,an Fpretsy DOCUMdNT CONTROL CONTR OLLED COPY N o. e29 P (s n
- V FORM- 01(B) page 1 or 7
STD-P-05-022
. Page 2 of 7 CALCIUM HYDROXIDE ADDITION PROCEDURE 1.0 SCOPE This procedure is applicable to all solidification operations using Hittman electric or hydraulic drive systems, with cement feed, where calcium hydroxide, Ca(OH)2 is used as an additive.
2.0 PURPOSE The purpose of this procedure is to provide generic instructions pertaining to how and at what point in the solidification opera-tion the calcium hydroxide is to be added.
3.0 REFERENCES
3.1 STD-P-05-040; Assembly and Operating Procedure for Hydraulic Drive Solidification System. 3.2 TS-13000; Field Assembly and Operating for Flexicon Cement Feed System. 3.3 TS-19000; Field Assembly and Operating Procedure for Electric {} Mixer Head Drive Assembly. 4.0 EQUIPMENT 4.1 Hittman Electric or Hydraulic Drive System. 4.2 Hittman Cement Feed System. 4.3 Dust Collector. 4.4 Charging Adaptor Extension. NOTE: Not required if the Ca(OH)2 is being added as a liquid. 4.5 For addition as a liquid the following equipment is needed. 4.5.1 Drum or similar mixing vessel equipped with a valved bottom connection. 4.5.2 Drum sized mixer or other mixing device. 5.0 SET-UP 5.1 Pre-requisites The solidification system is set-up in accordance with the appropriate procedure for either the electric or hydraulic O- drive. l
STD-P-05-022 Page 3 of 7 5.2 Precautions u. f-~) None. 5.3 Assembly 5.3.1 Remove the cement hopper from the support scaffold. NOTE: If the hopper cannot be removed, then the alternate procedures in 6.4 or 6.5 may be used. 5.3.2 Mount the charging adaptor extension in place of the cement hopper. 6.0 Ca(OH)2 ADDITION 6.1 Pre-requisites 6.1.1 The equipment is set-up in accordance with Section
. 5.0, Set-Up.
6.1. 2 ' The correct quantity of waste is in the liner. 6.1.3 The test solidification has been performed and {} found acceptable. 6.1.4 The required quantity of calcium hydroxide is available as determined by the test solidifica-tion. NOTE: Use one-half (1/2) extra bag to compen-sate for dead feed space in charging adaptor and carry over to dust collector. NJTE: The following sections, Section 6.1.5 through 6.1.9 apply only when a calcium hydroxide - water slurry is to be pre-pared per Section 6.5. 6.1.5 A 55-gallon drum or similar type mixing vessel is available. The mixing vessel should have an outlet connection at the bottom equipped with a valve and quick disconnect fitting. 6.1.6 A source of plant water is available near the mixing vessel. 6.1.7 A mixing motor such as an XJA-100 Lightnin Mixer powered either by air or electric or other mixing device is available. The mixing motor should have O' a 6 to 8 inch diameter blade fastened to a stirrer shaft long enough so that the mixing blade is near
. STD-P-05-022 Page 4 of 7
() the bottom of the mixing vessel (within one half blade diameter). 6.1.8 A transfer pump such as a Warren-Rupp pump is available. 6.1.9 Plant air is available, i.e., 60 CFM at 90 psig. 6.2 Precautions 6.2.1 Be prepared to adjust the dust collector to elimi-nate any dusting that may occur. 6.2.2 Have dust masks available for use if needed. 6.3 Addition Through the Charging Adapter l 6.3.1 SET dust collector opening at two (2) inches. NOTE: If subsequent operations prove that a wider or narrower opening is desirable, use that size opening. 6.3.2 START dust collector. {} 6.3.3 START the cement feed system. 6.3.4 START the mixer. 6.3.5 CUT a small opening in the corner of the bag. CAUTION: KEEP HANDS CLEAR OF SCREW CONVEYOR INSIDE CHARGING ADAPT 0R. 6.3.6 START pouring the calcium hydroxide slowly into i the charing adapter. NOTE: If dusting occurs, open the discharge opening on top of the dust collector to draw more air. 6.3.7 STOP the cement feed system when the required quantity of calcium hydroxide has been added. 6.3.8 MIX the calcium hydroxide and waste for a minimum of fifteen (15) minutes prior to adding any cement. NOTE: The following steps may be omitted if the solidification operation is to com-mence immediately following completion {} of this step. t 6.3.9 STOP the mixer. l
- .~ STD-P-05-022 Page 5 of 7 6.3.10 STOP the dust collector.
[) 6.4 Addition Through the Cement Hopper NOTE: Calcium hyroxide shall be added through the cement hopper only when large quantities are involved (more than 15 bags) or the cement hopper cannot be moved off the charging adaptor. 6.4.1 With the cement hopper top open, BLOCK OFF all but an 18" square opening. 6~.4.2 SET-UP the dust collector to take suction near the top of the cement hopper where the calcium hydroxide is to be added. 6.4.3 SET the dust collector opening at two (2) inches. NOTE: If subsequent operations prove that a wider or narrower opening is desirable, use that size opening. 6.4.4 START the dust collector. 6.4.5 CUT a small opening in the corner of the bag. () 6.4.6 POUR the calcium hydroxide slowly into the cement hopper. 6.4.7 ADJUST the dust collector top opening to prevent spread of dust. 6.4.8 After the hopper is loaded, CLOSE the hopper. 6.4.9 RECONNECT the dust collector to the mixer fill I head. 6.4.10 MOVE the hopper onto the support scaffold. NOTE: This step is not necessary if the hopper is already in position. 6.4.11 OPEN the cement hopper discharge slide gate. 6.4.12 START the dust collector. 6.4.13 START the mixer. 6.4.14 START the cement feed system.
- 6.4.15 START the cement hopper vibrator if more than 500 pounds of calcium hydroxide are in the hopper, i
, STD-P-05-022 Page 6 of 7 6.4.16 When the cement hopper is empty, STOP the cement
(_~)3 feed system. 6.4.17 STOP the cement hopper vibrator. 6.4.18 MIX the calcium hydroxide and waste for fifteen (15) minutes prior to adding any cement. NOTE: The following steps may be omitted if l
- the solidification operation is to com-mence immediately following completion of this step. j 6.4.19 STOP the mixer.
6.4.20 STOP the dust collector. 6.5 Preparation and Transfer of Calcium Hydroxide - Water Slurry i NOTE: Calcium Lydroxide shall be added as a slurry only when water is to be added to the waste as part of the solidification process. The quantity of water used for the preparation of the calcium hydroxide-water slurry shall be deducted from the total , 5 quantity of water needed for solidification. Sections 6.3 or 6.4 shall be used in lieu of this s, section when possible. 6.5.1 SET-UP the dust collector to take suction near the top of the mixing vessel where the calcium hydroxide is to be added. 6.5.2 SET the dust collector opening at two (2) inches. NOTE: If subsequent operations prove that a wider or narrower opening is desirable, 5 use that size opening. ! 6.5.3 PLACE the bottom valve on the mixing vessel in the closed position. 6.5.4 ADD 45 gallons of water to the mixing vessel. 6.5.5 START the mixing. 6.5.6 START the dust collector. 6.5.7 CUT a small opening in the corner of one bag of i calcium hydroxide. 6.5.8 Slowly ADD up to 50 pounds of calcium hydroxide to () the water.
E, STD-P-05-022 7l Page 7 of 7 NOTE: If subsequent operations prove that more () or less calcium hydroxide is desirable use that amount. However, be aware that no more water or calcium hydroxide than is necessary for solidification per the PCP can be used. 6.5.9 After the calcium hydroxide is thoroughly wetted and suspended, CONNECT the hose from the suction side of the transfer pump to the quick disconnect on the bottom of the mixing vessel. 6.5.10 STOP the dust collector. CAUTION: BE SURE THAT THE MIXING BLADES OF THE SOLIDIFICATION LINER ARE NOT TURNING. 6.5.11 PLACE the discharge line from the transfer pump into the liner containing the waste to be solidi-fied. 6.5.12 OPEN the ball valve on the bottom of the mixing vessel. 6.5.13 START the transfer pump. (} 6.5.14 STOP the mixer when the blades become uncovered. 6.5.15 When the mixing vessel is empty, STOP the transfer pump. 6.5.16 REPEAT Steps 6.5.3 through 6.5.15 until the re-quired quantity of calcium hydroxide has been added to the solidification liner. l 6.5.17 FLUSH the mixing vessel and lines with any re-maining water that is to be used for the solidifi-cation process into the solidification liner. NOTE: In no case use more water than is re-quired for the solidification. l l 6.5.18 STOP the transfer pump. 6.5.19 CLOSE the bottom ball valve on the mixing vessel. l l l 6.5.20 REMOVE the discharge line from the liner. l l 6.5.21 START the solidification liner mixer and mix for l 15 minutes before the cement addition is begun. f 22 C) 1 l l [
t
. Docum:nt Numbar: Rsv: 2 Rsv Date:
A WESTINGHOUSE STD-R-05-007 11/1/85 A N PORATED Title Topical Report Cement Solidified Waste To O seet Tae Seasitity aequirements of 10crR61 Director Proj ect QA Rev, Rev Date Engr. Manager Manager 0 5-22-84 EWR-h 84-115 1 6-20-84 / v- 105 c> ' ECN-2 11/1/85 , I {M, - BS-lu8 "gl lJ se waam rmewy 9 DOCUMENT CONTROL CONTR'OLLED CO PY No. oo 7 O - FORM 01(B) page 1 of 37
T, . I O-WESTINGHOUSE.HITTMAN NUCLEAR INCORPORATED TOPICAL REPORT CEMENT SOLIDIFIED WASTES TO MEET THE STABILITY REQUIREMENTS OF 10CFR61 Revision 2 GTD-R-05-007 O October 29, 1985 i l l i Prepared by: l i Westinghouse Hittman Nuclear Incorporated - 9151 Rumsey Road O Columbia, Maryland 21045 i l
4 TABLE OF CONTENTS G
.b Section Page I. INTRODUCTION. . . . . . . . . . . . . . . . . . . . . 4 II. BACKGROUND. . . . . . . . . . . . . . . . . . . . . . 5 III.
SUMMARY
AND CONCLUSION. . . . . . . . . . . . . . . . 6 IV. . WASTE QUALIFICATION PROGRAM DESCRIPTION . . . . . . . 12 V. SMPLE PRODUCTION . . . . . . . . . . . . . . . . . . 15 VI. TESTS AND TEST METHODS. . . . . . . . . . . . . . . . 16 VII. TEST RESULTS. . . . . . . . . . . . . . .~. . . . . . 18 VIII. SCALE UP TESTING. . . . . . . . . . . . . . . . . . . 32 : i t ATTACHMENT A - WASTE QUALIFICATION PROGRAM O O -
STD-R-05-007 Page 4 of 37 0 1- 1*Taoouction This Topical Report, prepared by Westinghouse Hittman Nuclear Incorporated, presents the results of testing performed on simulated low-level radioactive waste to demonstrate compliance with the stability requirements of 10CFR61.56 Waste Qualification, and the Branch Technical Position on Waste Forms. This report represents the culmination of several years of experimentation and test-ing of Portland Type I Cement for the solidification of LWR wastes. The program conducted by Hittman included seventeen wastes commonly found in U.S. light water reactors in addition to a " blank" and a " grout" for encap-sulation of filters and other scrap material. This compendium of wastes is the I most comprehensive program of its kind currently being pursued today. Hittman is currently under contract to supply mobile solidification ser-t vices to 23 power plants throughout the country. The first mobile cement solidification system went into service over seven years ago and since that time has always produced products acceptable by applicable criteria in existence at the time of solidification using Portland Type I or Type II cement. In 1983 alone, over 1,000 large liners were solidified and shipped for burial. The formulations used to produce the samples tested for the program were made using Portland Type I cement as the major component in the solidification process. The exact formulations of waste to cement and additives were provided as Proprietary Data with the original submittal of this Topical Report. , Section VII, Test Results provides specific data on the samples put through the various tests required to show product stability. 4 i 4 I i i } i I
STD-R-05-007 Page 5 of 37 O II. BACKGROUND On December 27, 1982, the U.S. Nuclear Regulatory Commission issued, in the Federal Register, a new paragraph 311, Transfer for disposal and manifests, to 10CFR20, Standards for Protection Against Radiation. Section (d)(1) of 20.311 requires that a licensee shall " prepare all wastes so that the waste is classi-fied according to paragraph 61.55 and meets the waste characteristics require-ments in paragraph 61.56 of this chapter." The referenced paragraphs, contained in 10CFR61, Licensing Requirements for Land Disposal of Radioactive Wastes, are, paragraph. 61.55, Waste Classification and paragraph 61.56, Waste Characterization. Under the definitions presented in paragraph 61.55 certain wastes, classi-fied as Class B and Class C wastes must meet certain " rigorous requirements on waste form to ensure stability after disposal." These rigorous requirements are defined in paragraph 61.56 with further guidance being provided by the NRC in the Branch Technical Position on Waste Forms issued in May 1983. In response to these regulations, Westinghouse Hittman Nuclear Incorporated instituted a program to qualify specific solidification formulations, to the requirements of a stable waste form per paragraph 61.56. The formulations are all based on Portland Type I cement with additives.
, Specific additives are a function of the waste stream and its chemistry. While ! many of these additives are commonly known to be used in the solidification of
(} specific wastes certain other additives are proprietary. In developing the qualification program certain alternate test methods were identified which differed slightly from the test methods specified in the Branch Technical Position on Waste Forms. These alternate test methods were discussed with the NRC staff prior to incorporation in this program. This program was submitted to the NRC for review. A subsequent letter from the NRC stated that the test program was " acceptable for demonstrating compliance with the waste stability requirements of 10CFR Part 61". ! The program undertaken involved the testing of nine separate waste types, a blank and a grout. Some of these waste types were then combined at various combinations of concentrations to yield an additional six waste types. Liquid I concentrates were also tested at two separate concentrations for a total of nineteen waste types. A complete listing of the waste types tested is shown at the beginning of Section IV. As can be seen, these waste types cover all of the I waste streams commonly found in most PWRs and BWRs and thus comprises the most extensive and comprehensive test program undertaken to date for the qualifica-tion of solidified wastes to these criteria. i L
STD-R-05-007 Page 6 of 37 I III.
SUMMARY
AND CONCLUSION Based on the analyses performed on the waste types listed in Tables 1 and 2, the formulations tested possess superb structural stability far exceeding the requirements specified in the BTP on Waste Forms. Table 1 gives the compressive strength of the sample (s) after each of the stability tests were completed. Table 2 gives the leachability index after the completion of the 90-day leach test. Two blank formulations, i.e., samples made using Portland Cement with different 'dditives a and no waste, refered to as " Blank and Grout," were tested as control samples for the biodegradation test, leach tests, thermal cycling test, and long-term immersion in water. These test results verify the stability of these formulations for use in encapsulating Class B or C cartridge filters and other scrap material. Results of these tests are also in Tables 1 and 2. The scale-up testing conclusively demonstrates that the product quality of wastes solidified in the Hittman mobile solidification system can be extra-polated from laboratory size samples. The tests performed on the core drilled samples has also shown that the product strength throughout the solidified liner is homogeneous. Visual inspections of the liners has shown that there are no voids or other areas where complete mixing does not occur. U 9
STD-R-Ob-007 Page 7 of 37 C
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O O O Table 1 - (Cont'd.) 5 J l i Compressive Strength After Testing, psi ! Waste Initial 93-Day 90-Day Thermal Biodegradation Type Strength Immersion Non-Immersion Cycling Bacteria Fungus Irradiation Crit - 280 500 210 360 8 3 340 I 51 Boric Acid - 30% Bead 1 Resin 140 490 140 130 8 340 16% Boric Acid - 30% Bead 1 Rqsin 170 280 120 2802 1 190 16% Boric Acid - i 62% Bead ! Resin 260 370 120 300 1 8 250 l' 5% Sodium Sulfate - 4 301 Mixed i Solids 850 I,040 1,490 1,720 a g,499 i i 20% Sodium Sulfate - o, a 1' 30% Mixed . yC Solids 1,120 460 1,340 1,850 1 1 890 x ' co e OC
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O O O , Table 1 - (Cont'd.) r-Compressive Strength After Testing, psi Waste Initial 90-Day 90-Day Thermal Biodegradation Type _ Strength Immersion Non-Immersion Cgg y Hacteria Fungus Irradiation 20% Sodium Sulfate - 62% Mixed Solids 660 1,210 1,600 1,070 1,610 1,310 1,070 Blank 300 480 590 240 530 730 250 Decon Solution 340 460 230 200 200 200 200 1 1,540 2,900 2,700 8 8 1840 Crout l Acceptance 3 >50 >50 >50 >50 Criteria >50 >50 , 1 Not tested 2 Inadvertently crushed 5 days early 3 Not required, no acceptance criteria l 33C m c00 m4 eo CD 8 23D Ee C O UT
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O O O Table 2 Leach Test Siumma ry , Average Leachability Index Sample 1 Sample 2 Waste Type Co-60 Cs-137 Sr-85 Ce-144 Co-60 _Cs-137 Sr-85 Ce-144 l Bead Resin, Low PE 12.9 7.5 8.9 >l1.6 13.0 7.5 8.9 >ll.6
- Bead Resin, liigh PE 12.8 7.6 8.9 >11.8 12.9 7.5 8.5 >l1.4 Powdered Resin, Low PE 12.4 7.0 8.9 >l1.4 12.3 7.0 '8 . 5 >11.5 Powdered Resin, liigh PE 9.1 6.2 7.5 >l1.6 9.1 6.25 7.5 >11.6 Diatomaceous Earth 13.2 46 . 5 8.4 >l2.7 13.1 6.5 8.4 >l2.7 Filter Sludge 11.8 6.5 7.8 >11.3 12.2 6.5 7.9 >11.3 8% Boric Acid 10.8 46 . 3 8.9 >l2.6 10.7 6.3 8.9 >l2.6 20% Boric Acid 11.1 ,6 . 6 9.3 >12.7 10.8 6.5 9.2 >l2.7 10% Sodium Sulfate 13.6 6.6 8.7 >l1.3 13.6 6.7 8.9 >11.3 20% Sodium Sulfate 13.2 6.6 8.7 >II.4 13.5 6.6 8.7 >l1.3 Oil 10.8 7.3 10.0 >12.7 10.5 6.7 9.2 >l2.5 8$
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- Grit 11.1 6.9 8.6 >12.6 11.3 6.8 , 8.6 >l2.5 m
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O O O Table 2 - (Cont'd.) - Leach Test Summary Average Leachability I'ndex
- Sample 1 Sample 2
! Waste Type Co-60 Cs-137 Sr-85 Ce-144 Co-60 Cs-137 Sr-85 Ce-144 k l 5% Boric Acid w/
30% Bead Resin 11.6 6.8 8.9 >l2.2 11.4 6.6 9.0 >12.1 , 16% Boric Acid w/ 1 30% Bead Hesin 12.1 7.5 9.7 >l2.8 12.1 6.9 , 9.6 >l2.7 1 16% Boric Acid w/ 62% Bead Hesin 12.5 7.1 9.8 >11.4 12.4 7.1 9.8 >l1.5 5% Sodium Sulfate w/ 30% Mixed Solids 12.9 6.8 8.8. >
'l1.2 13.2 6.8 8.8 >l1.3 20% Sodium Sulfate w/
30% Hixed Solids 13.6 6.7 9.0 >11.4 13.2 6.6 8. fi >l1.3 20% Sodium Sulfate w/ 62% Mixed Solids 11.3 6.5 8.2 >l1.5 11.4 6.3 8.1 >l1.3 Blank 10.9 6.4 8.3 >12.3 11.1 6.4 8.2 >l2.5 Acceptance Criteria 26.0 26.0 26.0 26.0 26.0 26.0 26.0 26.0 o sn W ~4 Note: Leachate was demineralized water for all samples except bead and powdered resin, for which systhetic 1 j C' sea water was used. ,, ga
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2 Revised formulation using Proprietary additive. gafi SOM m ,
F l STD-R-05-007 Page 12 of 37 IV. WASTE QUALIFICATION PROGRAM DESCRIPTION Scope The program undertaken b,y Hittman covered nine basic types of liquid and solid wastes typically found in a nuclear power plant. These are: o _ Mixed Bed Bead Ion-Exchange Resin o Mixed Powdered Ion-Exchange Resin o Diatomaceous Earth (DE) o Filter Sludge (a mixture of powdered resin, DE, iron oxide and dirt). o Oil o Boric Acid (8% and 20%) o Sodium Sulfate (10% and 20%) o Grit (from abrasive decontamination processes) o Decontamination Solution As indicated two concentrations of both boric acid and sodium sulfate were tested to demonstrate the ability to produce qualified products over a range of concentrations. Additionally, three cembinations of boric acid and bead resin and three combinc.;1cos of sodium sulfate and a mixture of bead resin, powdered resin and diatomaceous earth'were tested. Figures 1 and 2 give a graphical presentation of the relative concentrations tested. The shaded areas in both figures represents the combinations of liquid chemical wastes and wet solids that can be solidified to the stability require-ments of the BTP on Waste Forms as demonstrated by the test data in this report. l The last two samples tested contained no physical wastes but were cement l slurries each using one of the two major additives used with the basic waste j i forms. One of these is identified as the " Blank" and the other as " Grout". The latter can be used as a pumpable grout slurry for encapsulation of cartridge ' filters and other scrap material. Both formulations also provide a data point for the extrapolation of formulations for wastes at zero concentration. t l i
STD-R-05-007 Page 13 of 37 O 30 - 3
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DS PJi n .P2 . - t T: j 10 - 3 G.!P4 isd$ P1 C 40 50 60 70 10 26 3d P6 Wet Weight l' Rend Resin Figure 1 Bead Rc:in with Boric Acid o Points P1, P2 and P3 in Figure 1 are the mixed boric acid and bead resin where: o P1 is 30% bead resin and the liquid is a 5% boric acid solution; o P2 is also 30% bead resin but the liquid is a 16% boric acid solution; o P3 is 62% bead resin with again a 16% boric acid solution; o- Points P4 and P5 are the pure boric acid samples at 8% and 20% con-centrations respectively. o Point P6 is a plain bead resin sample at 57.6 wet weight percent , solids and no boric acid. O -
STD-R-05-007 Page 14 of 37 Figure 2 is similar to Figure I with slightly modified concentrations. o Points S1, S2 and S3 in Figure 2, are the mixed sodium sulfate and mixed solids (powdered resin, bead resin, and diatomaceous earth) where: o S1 is 30% mixed solids and 5% sodium sulfate; o S2 is 30% mixed solids and 20% sodium sulfate; o S3 is 62% mixed solids with, again, 20% sodium sulfate; o Points S4 and S5 are the pure sodium sulfate concentrations of 10% and 20% respectively; o Point S6 represents plain mixed solids at 66 wet weight percent solids. O b 30 - o E M 5 20 - .S5 _g7_ 33
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', STD-R-05-007 Page 15 of 37
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,/ V. SAMPLE PRODUCTION Individual samples for initial testing were prepared in 1,000 ml plastic beakers using a standard laboratory mixer with a three inch diameter mixing blade. These blades are made specifically for this purpose and are shaped in the same configuration as the full scale in-container mixing system. As specific mixes were identified for complete testing a large scale laboratory mix was prepared. Each of these large scale lab mixes was formulated to produce a sufficient batch of waste to fill sixteen three (3) inch diameter by six (6) inch high, molds. These mixes were prepared in a five gallon can using a mixer blade shaped to recreate the same basic mixing action as a full scale in-container mixing system. The motor used was a variable speed motor which per-mitted adjusting the speed to hold a tip speed on the mixing blade at the same tip speed experienced with the Hittman in-container mixing system.
As soon as the samples were molded they were placed in sealed plastic bags, one sample per bag, to prevent moisture loss due to evaporation. All of the samples were then placed in an oven at 120*F for twenty-four hours to simulate the elevated curing temperature experienced in full scale operations due to the exothermic reaction as cement cures. After the samples were removed from the oven they were marked and put into storage while they awaited additional testing. If samples were stored for prolonged periods prior to being used for one of the tests a companion sample from that batch was compressively teste:3 to provide an adjusted base line against which to judge the effects of the test. In those () cases where this additional test was performed it is so noted and the compres-sive strength of the additional sample is listed. Samples for leach testing were prepared by the Westinghouse R & D Center. These samples were cured for one week in the same manner as the other test samples described above. Leach testing for all the waste types was performed on two identical samples measuring one (1) inch in diameter by two (2) inches long. Samples were produced using water containing7Co-60, CS-137, Sr-85 and Ce-144 in concentrations of approximately 1pCi/gm each . Demineralized water was used as the leachate for all samples except bead resin and powdered resin which were leached in synthetic sea water.
-1/ Due to a packaging error by the isotope vendor, approximately half of the samples had Cs-137 concentrations approximately ten times higher than the other isotopes. This has no impact on the leach index as the calculation is based on the fraction leached and not the absolute quantity leached.
STD-R-05-007 Page 16 of 37 VI. TESTS'AND TEST METHODS The tests performed and the methods of testing are given in Attachment A, Waste Qualification Program. This program differs from the program outlined in the BTP for the thermal cycling and the biodegradation testing. These dif-ferences are described below. A. Thermal Cycling-The ASTM Standard _B-553 referenced in the BTP was not used for three l reasons. First, the rapid cycling time is not representative of the actual environmental conditions that wastes will be subjected to. Second, the tempera-ture ranges specified are not available in normal laboratocy equipment designed for the large number of samples required. Third, unpublished results of tests performed by a national lab indicate that the large temperature difference,
-40*C to 60*C, and the rapid cycling prevents the centerline of the samples from ever reaching the requisite temperature extremes. It should be noted however, that these latter tests used uncovered samples which may have an effect on the heating and cooling rates of the samples.
The method selected used more realistic temperature extremes of -18'C and 48'C (0*F and 120*F respectively). The test chamber was set to alternate between these two temperatures on a 24-hour cycle. During each cycle, the O'F and 120*F temperatures are maintained for 8 hours each with a 4-hour transition (') time. Each sample was tested for a total of 50 cycles, or 50 days. Following completion of the test, the samples were compressively tested to demonstrate a minimum of 50 psi compressive strength. B. Biodegradation: The ASTM Standards G21 and G22 referenced in the BTP were modified slightly as follows. Both tests are. designed to use samples approximately one quarter inch thick and to be incubated in a shallow petri dish. In order to be able to use samples that could be compressively tested upon completion of the test, samples three (3) inches in diameter by six (6) inches high were used. Each sample was placed in a beaker and covered with the non-nutrient salt and injected with the appropriate bacteria and fungus. Ins _ ting was performed by l Biospherics Incorporated of Rockville, Maryland. Testing for degradation due to fungus growth was modified by replacing penicillium funiculosum with penicillium jenseni. This substitution was made because of the strict sterilization requirements imposed on any item that comes in contact with penicillium funiculosum which is a plant pathogen. l Due to an adverse reaction between the bead resin sample and the agar. l this test was cond'cted u using the recommended salts dissolved in water without () the agar. The initial attempt to conduct this test resulted in a surface crumbling of the sample as the agar was poured around the sample. This occurred i f l L
STD-R-05-007 Page 17 of 37 before any of the cultures were added and the agar was still warm. The nature of the reaction is unknown but retesting with a new sample using the same non- , nutrient salts but without the agar did not result in any adverse reactions as can be seen in Table 3. Upon complet, ion of the test, the samples were inspected for growth of the fungus or bacteria and then compressively tested to demonstrate a minimum compressive strength of 50 psi. C. Irrediation Testing j 1 Irradiation testing was performed in accordance with the BTP on Waste Fo rms . Testing was performed by Isomedics, Inc. using a Co-60 source. The dose rate at the location where the samples are to be located is determined experi-mentally and the time required to achieve the desired integrated dose is then calculated. Upon completion of the irradiation cycle the samples were returned to Hittman for compressive strength testing. O
4 . STD-R-05-007 Page 18 of 37 i l i O VII. TEST RESULTS ! The results of the testing on individual waste types are as follows:
- 1. Bead Resin Samples of solidified bead resin were prepared using chemically de-pleted mixed bed ion exchange resia consisting of 50% anion and 50% cation resin by volume. The initial average compressive strength of the lab mixed samples was 1,090 psi while the drum mixed samples had an average strength of 1,500 psi.
After 90 days immersion the average strength of two samples tested was over 1,960 psi. None of the samples contained any free liquid following the 24 hour i cure period. l The formulation tested in the irradiation, thermal cycling and leach tests was slightly different from the final reference formulation. By com . parison, the original formulation had an average initial compressive strength of 740 psi compared to 1,090 psi for the reference formulation. The difference in these two formulations is in the water to cement ratio while maintaining iden-tical volumetric waste loading. Therefore, the test results for the original formulation are conservative in both strength and leach characteristics compared to the reference formulation and additional, or repeat testing,of the reference formulation was not required. O The thermal cycling tests on the original formulation resulted in an average compressive strength of 300 psi. The sample irradiated to the 108 Rad had a compressive strength of 670 psi. The average leachability index for each of the four radionuclides tested is given in Table 2 for both samples. The two samples used in the biodegradation tests showed no visible signs of bacteria or fungus growth. The compressive strengths were 1,570 psi and 1,860 psi after exposure to the bacteria and fungus respectively. Table 3A contains the data i for the individual bead resin samples tested at the low packaging efficiency recipe. Table 3A , Compressive Strength Summary i Low P.E. Bead Resin, psi - Initial 90-Day 90-Day Thermal Irradiation I Test Immersion Non-Imm. Biodegradation Cveling 108 Rad. I i l Sample 1 1,260 1,660 1,340 1,570 1 270 670 l l Sample 2 1,740. 2,260 -- 1,860 2 330 -- 1 Bacterial Attack. . 2 Fungus Attack.
} ,
. STD-R-05-007 Page 19 of 37 l
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k A high packaging efficiency formulation was also developed, the data for which is shown in Table 3B. Table 3B Compressive Strength Summary High P.E. Bead Resin, psi , i i _ Initial 90-Day 90-Day Thermal Irradiation ! Test Immersion Non-Imm. Biodegradation Cycling 108 Rad. 8 Sample 1 600 860 7101 NT NT 430 Sample 2 760 1,0300 -- NT NT 500 1 ' Actually. tested at 14 months.
- 2. Powdered Resin The initial strength of two powdered resin samples measured 630 psi and 770 psi with little change seen after 90 days immersion in water. The
- immersed samples had strengths of 630 psi and 700 psi. Over the same time period the non-immersed sample increased in strength to 1,040 psi. All samples contained 50% anion and 50% cation by volume. -
The sample irradiated to 10s Rad exhibited a compressive strength of 600 psi after irradiation. The samples tested for biodegradation had strengths of 1,010 psi after bacterial attach and 770 psi after fungus attach. There was no visual growth of bacteria or fungus on either sample. Thermal cycling tests on two samples resulted in compressive strengths of 860 psi and 900 psi. This data is summarized in Table 4A. None of the samples contained any free liquid following the 24 hour cure period. Leach test'ing of powdered resin was also conducted using synthetic sea water. The average leachability index for each of the four radionuclides tested is given in Table 2 for both samples. I Table 4A i Compressive Strength Summary Low P.E. Powdered Resin, psi Initial 90-Day 90-Day Thermal Irradiation Test Immersion Non-Imm. Blodegradation Cycling 10s Rad. i Sample 1 770 630 1,040 1,010 1 860 600 l Sample 2 630 700 -- 7702 900 -- () 1 Bacterial Attack 2 Fungus Attack l - 6
STD-R-05-007 Page 20 of 37 r' . k-- A high packaging efficiency formulation was also developed for powdered resin. The test results on samples made with this formulation are shown in Table 4B.
~
Table 4B Compressive Strength Summary High P.E. Powdered Resin, psi
~ Initial 90-Day 90-Day Thermal Irradiation Test Immersion Non-Imm. Biodegradation Cycling 108 Rad.
4 Sample 1 360 440 NT NT NT 430 Sample 2 -- 500 -- NT NT 260
- 3. Diatomaceous Earth The initial compressive strength of two samples of solidified diato-maceous earth are 1,300 psi and 970 psi. The 90-day immersion strengths were 1,140 psi for both samples with a non-immersed sample testing at 1,200 psi. The s two samples used in the thermal cycling tests had strengths of 1,640 psi and
- 1,150 psi. The irradiated sample was 1,400 psi. This data is summarized in Table 5. None of the samples contained any free liquid following the 24 hour '
cure period. Average leachability indices for the four radionuclides tested are given in Table 2 for both samples. The leachate for DE was demineralized water. Table 5 Compressive Strength Summary Diatomaceous Earth, psi Initial 90-Day 90-Day The rmal Irradiation Test Immersion Non-Imm. Biodegradation Cycling 10s Rad. Sample 1 9.70 1,140 1,200 NT1 1,640 1,400 Sample 2 1,030 1,140 -- NT 1,150 -- 1Not tested
- 4. Filter Sludge Filter sludge was simulated using equal parts of powdered resin and O,s diatomaceous earth with 1/2% iron oxide and dirt each. The initial compressive strengths of the filter sludge solidifed samples were 510 psi and 910 psi.
STD-R-05-007 Page 21 of 37 p 5 Af ter 90 days of immersion the strengths were 1,200 psi and 1,270 psi with a non-immersed sample having a compressive strength of 1,290 psi. After irradiation to 10s rad the compressive strength of a single sample was 670 psi. Thermal cycling a tests resulted in compressive strengths of 1,070 psi and 1,140 psi. Biodegrada-tion tests were not conducted on solidified filter sludge. This. information is summarized in Table 6. None of the samples contained any free liquid after the 24 hour cure period. Table 6 Compressive Strength Summary Filter Sludge, psi Initial 90-Day 90-Day Thermal Irradiation Test Immersion Non-Imm. Biodegradation Cycling 10s Rad. Sample 1 510 1,200 1,290 NT 1,070 670 Sample 2 910 1,270 -- NT 1,140 -- Leach testing of filter sludge were conducted in demineralized water. The average leachability indices for the four radionuclides tested are given in Table 2 for both samples. l rg 5. 8% Boric Acid U The initial compressive strengths of the 8% boric acid samples were 140 psi and 110 psi. Following irradiation to 10 8 rad, the samples exhibited strength ! of 140 psi, 210 psi and 140 psi, while the samples exposed to bacterial and fungus I attach had strength of 470 psi and 340 psi respectively. Neither sample showed any visible signs of bacteria or fungus growth. After 90 days immersion the compres-sive strengths of two samples were 370 psi and 430 psi. Thermal cycling tests re-sulted in compressive strengths of 270 psi for both samples. This data is sum-marized in Table 7. None of the samples contained any free liquid following the l t 24 hour cure period. Leach testing of 8% boric acid was conducted using demineralized water. The average leachability indices for the four radionuclides tested are given in Table 2 for both samples. ( Table 7 l Compressive Strength Summary 8% Boric Acid, psi Initial 90-Day 90-Day Thermal Irradiation f Test Immersion t Non-Imm. Biodegradation Cycling 108 Rad. j l Sample 1 140 430 130 4701 270 140 - Sample 2 110 370 3402 270 140, 210 3 l (1)\ 1 Bacterial Attack 2 Fungus Attack 3 Duplicate samples for retesting. L
. STD-R-05-007 Page 22 of 37 fm d
- 6. 20% Boric Acid After 90 days immersion, the compressive strength of two samples were 310 psi and 340 psi. Prior to immersion, the compressive strengths were 140 psi and 110 psi, while a non-immersed sample had a compressive strength of 230 psi after 90 days. After exposure to a gamma radiation source to a total centerline dose of los Rad, the compression strength of three samples were 140 psi, 230 psi and 240 psi. None of the, samples contained any free liquid after the 24 hour cure period.
Due to an earlier failure of one sample to pass the thermal cycling test, four additional samples were tested. These four samples had strengths following testing of 410 psi, 440 psi, 410 psi and 330 psi. The average of these four samples is shown for Sample 2. Table 8 Compressive Strength Summary - 20% Boric Acid, psi Initial 90-Day 90-Day . Thermal Irradiation Test Immersion Non-Imm. Biodegradation Cycling 10s Rad. Sample 1 110 310 230 NT 140 140 (~T 4001 230, 240 2 (_/ Sample 2 140 340 -- NT 1 The average of four samples. 2 Duplicate samples for retesting. ! Leach testing was conducted using demineralized water. The average leachability index is shown in Table 2 for each of the four radionuclides tested for both samples.
- 7. 10% Sodium Sulfate The initial compressive strengths of the 10% sodium sulfate samples were 570 psi and 490 psi. The samples used in the 90-day immersion test had compressive strengths of 690 psi and 390 psi. After exposure of 108 Rads, the strength of a single sample was 630 psi. Thermal cycling test resulted in sample strengths of 1,410 psi and 1,530 psi. Since sodium sulfate is a non-nutrient salt it was not considered necessary to test this waste form for biede- ,
gradation. These data are summarized in Table 9. None of the samples contained any free liquid following the 24 hour cure period. Leach testing of the 10% sodium sulfate samples was conducted using demineralized water. The average leach indices for the four radionuclides , tested are given in Table 2 for both samples. O
,m, , - - - - - -
l ^ STD-R-05-007 Page 23 of 37 O Table 9 Compressive Strength Summary 10% Sodium Sulfate, psi Initial 90-Day 90-Day Thermal Irradiation Test Immersion Non-Imm. Biodegradation Cycling 10s Rad. Sample 1- 490 690 1,170 . NT 1,410 630 Sample 2 570 390 -- NT 1,530 --
- 8. 20% Sodium Sulfate The initial compressive strength of both 20% sodium sulfate samples was 830 psi. The samples used in the 90-day immersion test had compressive strengths of 1,000 psi and 1,100 psi. The thermal cycling test resulted in sample strengths of 1,280 psi and 1,530 psi. Following irradiation to 10s rads, the. strength of a single sample was 1,540 psi. Biodegradation tests were not performed as stated under 10% sodium sulfate. See Table 10 for a summary of these data. None of the samples contained any. free liquid following the 24 hour cure period.
(~)
\_/
Leach testing was conducted in demineralized water. The average leach indices for the four radionuclides tested are given in Table 2 for both samples. Table 10 Compressive Strength Surmary 20% Sodium Sulfate, psi Initial 90-Day 90-Day Thermal Irradiation Test Immersion Non-Imm. Biodegradation Cycling los Rad. Sample 1 830 1,000 910 NT 1,280 1,540 Sample 2 830 1,100 -- NT 1,530 --
- 9. Oil Samples solidified contained used motor and turbine lube oil diluted in water and emalsified with a proprietary emulsifier.
The initial compressive strengths after 7 days of cure were 140 psi and 130 psi. Af ter 90 days immersion in water, both samples had compressive () strengths of 340 psi. A single non-immersed sample from the same batch ex-hibited a compressive strengh of 190 psi.
STD-R-05-007 Page 24 of 37 rs U After exposure to a gamma radiation source to a total centerline dose of 3 los rads, the compressive strengths of three samples were 410, 390, and 290 psi. A Both samples used in the thermal cycling tests hcd compressive strengths of 210 l psi. The samples tested for biodegradation had strengths of 230 psi after bac-V[y.-lg terial attack and 200 psi after fungus attack. There was no visual growth of bac-teria or fungus on either sample. Table 11 provides a summary of the testing dis-
. cussed above. None of the samples contained any free liquid following the 24 hour cure period. i I
.. Table ~2 contains the leach indices for solidified oil for the four radio-nuclides tested, for both samples. Demineralized water was used for the leachate.
Table 11 Compressive Strength Summary - Oil, psi
. Initial 90-Day 90-Day Thermal Irradiation Test Immersion Non-Imm. Biodegradation Cycling 10s Rad.
Sample 1 140 340 190 2301 210 290 Sample 2 130 340 -- 2002 210 390, 410 3 1 Bacterial Attack 2 Fungus Attack 3 Duplicate samples for retesting. ,
- 10. Grit The grit used in these samples is aluminum oxide; however, due to the inert nature of the material, the results of these tests are considered appli-cable to other similar materials such as magnetite and steel grits at comparable waste loadings.
Prior to immersion, the average compressive strength was 280 psi. Samples immersed for 90 days had an average compressive strengths of 390 psi and 610 psi while a non-immersed sample of the same age had a compressive strength of 210 psi. Due to the inert nature of the waste, biodegradation testing was not considered necessa ry. A single irradiated sample had a compressive strength of 340 psi after irradiation in a gamma field to a centerline dose of 10s Rads. The samples used l in the thermal cycling test had strengths of 400 psi and 320 psi. This data is summarized in Table 12. None of the samples contained any free liquid following the 24 hour cure period. , Table 12 Compressive Strength Summary - Grit, psi , Initial 90-Day 90-Day The rmal Irradiation Test Immersion Non-Imm. Biodegradation Cycling 10 8 Rad. Sample 1 280 390 210 NT 400 340 l Sample 2 270 610 -- NT 320 -- l
. - - - - - - , _ , , _ _ _ _ _ _ _ _ , , , _ . - , - , , - - , , - . , , _ - , ,. .,.-y.-- _ . . _ , _ _ , , , _ , _ , _ , , , - , , - - _ . _ - . . _ _ , _ ~ , , , _ - - _ . . _-
STD-R-05-007 Page 25 of 37 O Table 2 shows the leach indices for the solidified grit, for all four radionuclides for both saeples. The leachate for.this waste type was also demineralized water.
- 11. 5% Boric Acid and_30% Bead Resin This waste form consists of a slurry which, if separated by dewatering, would be 30% by weight dewate' red resin and,the liquid would be a 5% boric acid solution.
Prior to immersion, the compressive strength of both samples was 140 psi. Ninety-one days later, the compressive strength of a non-immersed sample was unchanged, at 140 psi. The compressive strength of the immersed samples at 90 days was 490 psi. Biodegradation testing was not performed since both bead resin and boric acid were tested separately. Following irradiation to 10s Rads, the compressive strengths of tnree samples were 390, 460, and 160 psi. Samples used in the thermal cycling tests had compressive strengths of 120 psi and 140 psi. Table 13 provides a summary of the testing discussed above. None of the samples contained free liquid , t following the 24 hour cure period. Table 13 fg Compressive Strength Summary - 30% Resin, 5% Boric Acid, psi
\_) '
Initial 90-Day 90-Day The rmal Irradiation Test Immersion Non-Imm. Biodegradation Cycling 10s Rad. Sample 1 140 490 140 NT 140 160 Sample 2 140 490 -- NT 120 390, 460 1 1 Duplicate samples for retesting. Leach testing was performed using demineralized water. The average leachability indices for each of the four radionuclides for both samples are shown in Table 2.
- 12. 16% Boric Acid with 30% Bead Resin The initial compressive strength of both samples was 170 psi. After 90 days immersion the two samples tested had compressive strengths of 230 psi and 330 psi. During the same period a non-immersed sample had a strength of 120 psi. Following irradiation to 10s rads, the compressive strength of three samples were 290, 170, and 110 psi. Biodegradation testing was not performed since both boric acid and bead resin were tested separately. Thermal cycling '
tests resulted in compressive strengths of 270 psi and 290 pri. This data is summarized in Table 14. None of the samples contained any free liquid following O the 24 hour cure period.
STD-R-05-007 Page 26 of 37
~s (d
Table 14 Compressive Strength Summary 16% Boric Acid with 30% 3ead Resin, psi Initial 90-Day 90-Day Thermal Irradiation, Test Immersion Non-Imm. Biodegradation Cycling 108 Rad.
~
Sample 1 170 230 120 NT 270 110
, Sample 2 170 330 --
NT 290 170 1 , 290 2 , I 2 Sample damaged in transport following irradiation. . 2 Duplicate samples for retesting. Leach testing of the 16% boric acid with 30% bead resin samples were ' conducted in demineralized water. The average leach indices for the four radio-nuclides tested are given' in Table 2 for both samples.
- 13. 16% Boric Acid with 62% Bead Resin The initial compressive strengths of both' samples tested was 260 psi.
After 90 days immersion the two samples tested had strengths of 430 psi and O* 310 psi. Af ter 90 days the non-immersed sample had a strength of 120 psi. After exposure to 108 rad the irradiated samples had strengths of 170, 360, and 210 psi. Biodegradation tests are not being performed since both boric acid.and bead resin were tested separately. Both of the thermal cycling samples had compressive strengths of 300 psi. These data are summarized in Table 15. None of the samples contained any free liquid following the 24 hour cure period. Table 15 Compressive Strength Summary 16% Boric Acid with 62% Bead Resin, psi Initial 90-Day 90-Day Thermal Irradiation Test Immersion Non-Imm. Biodegradation Cycling 1 10s Rad. Sample 1 260 430 120 NT 300 210 i Sample 2 260 310 -- NT 300 170, 360 2 l 1 Inadvertently crushed at 45 days. 2 Duplicate samples for retesting _ l Leach testing was conducted in demineralized water. The average leach indices for the four radionuclides being tested are given in Table 2 for both samples.
STD-R-05-007 Page 27 of 37 4 O , '14. s 5% Sodium Sulfate with 30% Mixed Solids
,e f The mixed solids used in this and the following two formulations I w p),' consists of equal parts by weight,
,t of spent mixed bed bead resins, spent mixed .
t bed powdered resin and DE. The initial compressive strengths for the two samples ! ' (V) tested were 700 psi and 1,000 psi. The 90-day inumersion test samples had com-pressive strengths of 660 psi and 1,430 psi. After the same period, a non-immersed sample had a compres'sive strength of 1,490 psi. The thermal cycling test samples had strengths of 1,730 psi and 1,720 psi. The single sample ex-posed to 108 Rad had a strength of 1,400 psi. Biodegradation tests were per-formed on the 20% sodium sulfate with 62% mixed solids samples. Table 16 4 provides a summary of these data. None of the samples contained any free liquid following th'e 24 hour cure period. Leach testing on the 5% sodium sulfate with 30% mixed solids was ' conducted in demineralized water. The average leach indices for the four radio-nuclides tested are given in Table 2 for both samples. Tabla 16 Compressive Strength Summary 5% Sodium Sulfate with 30% Mixed Solids, psi 90-Day 90-Day Thermal O Initial Test Immersion Non-Imm. Biodegradation Cycling Irradiation 10s Rad. Sample 1 700 660 1,490 NT 1,730 1,400 - Sample 2 1,000 1,430 -- NT 1,720 -- ! 15. 20% Sodium Sulfate with 30% Mixed Solids The initial compressive strengths for two samples of this waste type were 1,000 psi and 1,230 psi for lab samples and 830 psi and 1,230 psi for samples from the drum mix. The 90-day immersion test on the drum samples resulted in compressive strengths of 660 psi and 960 psi. After 90 days of curing a non-immersed sample had a compressive strength of 1,340 psi. Following irradiation to los Rads, a single sample had a strength of 890 psi. The thermal cycling test samples had compressive strengths of 1,820 psi and 1,880 psi. Biode-gradation tests were performed on the 20% sodium sulfate with 62% mixed solids samples. These data are susumarized in Table 17. .None of the samples cont'ained, > any free liquid following the 24 hour cure period. .l Leach testing was conducted using demineralized water. The average leach indices for the four radionuclides tested are given in Table 2 for both samples. O
STD-R-05-007 Page 28 of 37 Table 17 Compressive Strength Summary 20% Sodium Sulfate with 30% Mixed Solids, psi Initial 90-Da'y 90-Day Thermal Irradiation Test Immersion Non-Imm. Biodegradation Cycling 10s Rad. Sample 1 830 660 1,340 NT 1,820 890 Sample 2 1,230 960 -- NT 1,880 --
- 16. 20% Sodium Sulfate with 62% Mixed Solids i
The initial compressive strengths of these two samples were 660 psi and 670 psi. After 90 days immersion the strengths of two samples were 1,140 psi and 1,280 psi. A non-immersed sample after the same time interval had a strength. of 1,600 psi. After exposure to 10s rads, the strength of a single sample was 1,070 psi. The samples subjected to biodegradation testing had compressive strengths of 1,610 psi and 1,310 psi after bacterial attack and fungus attack respectively. There was no visible growth of bacteria or fungus on either
~N sample. The thermal cycling test samples had compressive strengths of 1,060 psi (d and 1,080 psi. These data are summarized in Table 18. None of the samples '
contained any free liquid following the 24 hour cure period. l Leach testing for the 20% sodium sulfate with 62% mixed solids samples was conducted using demineralized water. The average leach indices for the four radionuclides tested are given in Table 2 for both samples. Table 18 Compressive Strength Summary 20% Sodium Sulfate with 62% Mixed Solids, psi Initial 90-Day 90-Day i The rmal Irradiation Test Immersion Non-Imm. Biodegradation Cycling 10s Rad. Sample 1 660 1,140 1,600 1,610 1 1,060 1,070 Sample 2 670 1,280 -- 1,310 2 1,080 -- 1 Bacterial Attack 2 Fungus Attack '
STD-R-05-007 Page 29 of 37 () 17. Miscellaneous Chemical Wastes The' composition of the miscellaneous chemical waste was taken from
" Properties of Radioactive Wastes and Waste Containers" Progress Report No. 7, October - December 1977, by Brookhaven National Laboratory, BNL-NUREG-50837.
This document defines the decontamination waste of a forced recirculation evapo-rator as follows: Material Weight % in Bottoms
~
Water 80 Nutek NT-700 9.4 i I EDTA 5
. tt Citric Acid 5 i u) e,[,?>y Crud 0.2 j I g 'J V .
Hydraulic Oil No. 2 0.2
~
kf Lubricating Oil No. 20 0.2 The initial compression strength of the miscellaneous chemical waste samples was 340 psi for both samples. Following 90 days immersion in water, the samples had compressive strengths of 430 psi and 490 psi. A non-immersed sample had a strength of 230 psi after 90 days. The samples used in the thermal cycling test both had strengths of 200 psi, as did the samples used in the radiation test, the bacterial attack test and the fungus attack test. There was no visible growth of bacteria or fungus on either sample. Table 19 provides a summary of () this data. None of the samples contained any free liquid following the_24_ hour cure period.
~
Table 19 Compressive Strength Summary, psi Miscellaneous Chemical Waste Initial 90-Day 90-Day Thermal Irradiation Test Immersion Non-Imm. Biodegradation Cycling 10s Rad. f Sample 1 340 430 230 2001 200 200 Sample 2 340 490 -- 2002 200 -- 1 Bacterial Attack
- 2 Fungus Attack Leach tests using demineralized water as the leachate resulted in average leach in' dices after 90 days of greater than 6.0 for three of the four isotopes as shown in Table 2. The average leachability index for Cs-137 was 5.9 for both samples. Subsequent retesting of several independent additives.has identified two chemicals that resulted in a significant increase in the leach -
ability index for cesium. However, due to the high cost of both additives, on ()
+
the order of several thousands of dollars for a large liner, and the fact that the leach index is virtually 6.0 without them, we do not feel that this cost is
STD-R-05-007 Page 30 of 37 O justified. It should also be noted that the waste formulation tested contains
- chelating agents well in excess of the one percent limit allowed by the burial sites. Since chelating agents are generally known to promote, or assist, radio-nuclide migration, it is also felt that it contributed to the low leach index for cesium. Actual processing of wastes that contain no chelating agents or only small amounts (<1% by volume) would then exhibit a cesium leach index well in excess of 6.0. .
Therefore, the formulation for consideration is the original formula-tion without additional additives.
- 18. Blank and Grout Two blank cement formulations were tested for qualification as a
] Class B waste form for the encapsulation of cartridge filters or other non-dispersable wastes. The initial strengths were 310 psi and 290 psi for the formulation identified as " Blank". For the " Grout" formulation, the initial strengths were 2,070 psi and 1,000 psi. The blank formulation was used in the biodegradation tests, and the thermal cycling tests. Following thermal cycling tests, the blank samples had compressive strengths of 240 psi and 250 psi. After completion of the bacterial and fungus attack tests, the blank sample strengths were 530 psi and 730 psi, respectively. Following the 90-day immer-sion tests on the blank formulation, the two samples had compression strengths ., of 460 psi and 500 psi. After 90 days immersion the grout samples had compres- { () sive strengths of 2,970 psi and 2,860 psi. The non-immersed samples had strengths of 2,290 psi and 3,110 psi after 90 days of curing. Irradiation [ , testing was performed on two blank samples and two grout samples. The post- ' irradiation compressive strengths were 290 psi and 210 psi for the blank and 280
- psi and 830 psi for the grout. Table 20 and 21 provide a summary of this data.
] None of the samples contained any free liquid following the 24 hour cure period. , Leach testing of this waste form was' performed on the blank with the same four radionuclides dispersed throughout the sample as in all the other > waste types'. Table 2 lists the individual leachability indices for the four radionuclides tested. Table 20 ! Compressive Strength Summary
- Blank Waste, psi Initial 90-Day 90-Day Thermal Irradiation
- Test Immersion Non-Imm. Biodegradation Cycling 10s Rad.
I . k Sample 1 310 460 590 5301 240 290
- Sample 2 290 500 --
7302 250 210 . 1 Bacterial Attack O 2 Fungus Attack 4
---...--,-,-__m - _ _ , _ . . - . _ _ _ . - . , , _ . . . _ _ . -
STD-R-05-007 Page 31 of 37 3. O Table 21 l > Compressive Strength Summarv ' Grout, psi Initial 90-Day 90-Day Thermal Irradiation Test Immersion Non-Imm. Biodegradation Cycling los Rad. Sample 1 2070 2970 2290 NT NT 2860 Sample 2 1000 2860 i 3110 NT NT 830 i n 4 O 90 e O . 4 i
STD-R-05-007 Page 32 of 37 VIII. SCAII-UP TESTING A. Solidification Testing and Sample Compression Strength As recommended by the NRC Branch Technical Position on Waste Forms, additional testing was performed, culminating in a full scale liner solidifica-tion, to demonstrate the scal.e-up of product quality from the lab size samples used for testing to the full size product. Both the Hydraulic Drive and Elec-tric Drive In-Container Solidification systems are proven systems and have been in use for over seven years. In 1983, Hittman solidified over 1,000 large liners, never once failing to produce an acceptable product using Portland Type I or Portland Type II Cement. In developing the scale-up program, the real impetus was to scale down from the full scale system to lab and drum scale mixes. In performing these calculations, four parameters were analyzed. These were: o Mixing blade diameter to container diameter. This ratio was held constant, t 5%, and used to define the mixing blade diameter for the drum and lab scale mixes. o Horsepower per cubic foot. This ratio was used to define mixer motor horsepower for the drum and lab scale mixes. () o Total BTU input. With the mixer horsepower def'ined, this was used to determine the interval over which the solidification ingredients would be added and the total mix time. o Mixing blade ~tip speed. This was used to determine the appro-priate gear reducer for the drum scale mixing system, and the appropriate mixing speeds for the lab scale mixes. i The methodology used to select equipment for a specific test was as follows: I know that my total energy input from the electric drive system is i 107 Btu 3
/ft of final product. A drum system, using a similarly designed mixing blade should result in the same, or higher, input. Assuming, for test purposes, that the final product volume will be 5 ft says 3 that my total input must be 535 Btu (or 0.21 hp-hr) . Several motors at different six times will fullfil this criteria. One such set of parameters that satisfies this criteria is a total mix time of 21 minutes and a motor rating of 0.60 hp. However, since motors of this size run 1750 rpm the system also requires a gear reducer which typically (and as ultimately selected) have efficiencies of 80%. Thus the motor must be 0.60 hp/0.8 = 0.75 hp. And therefore the motor is sized.
The next step is to size the gear reducer. In a 24-inch diameter drum, with a 0.94 mixer to drum diameter ratio the mixer diameter should be , 22-3/4 inches. To obtain a tip speed of 8.3 ft/see the blade must rotate at 84 i rpm. The ratio of 1750 to 84 is 20.8 to 1. The closest available unit, for a j (} 3/4 hp motor was 20:1, and is the unit used. i l
. . _ _ _ _ _ _ _ _ ~ - _ _ _ _ _ __ ___. _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ , _ . - _ _ _ _ . . - _ _ _ _ _ , _ _ . . _ _
STD-R-05-007 Page 33 of 37
) The folls ing table shows the scaling parameters used to size each of the scaled down components used in this program. The large batch and lab scale mixing systems were sized using an identical analysis.
Drive Full Drum Large Lab Parameter Scale Sys. Tests Batch PCP i Mixer Blade Diameter 0.94 0.94 .903 .913
.to container Diameter:
Motor hp ~
~
51 0.75 0.2 .012 I i Mixer Blade rpm 282 87 110 630 Mixer Blade Tip Speed, 8.3 8.7 10.4 10.0 ft/sec. Btu per ft 3 107 107 107 107 Mix time, min. 90 21 5 3 Total Btu Input 15,300 535 39.6 1.5 1 For electric drive systems, hydraulic drive systems higher. 2 For electric drive systems, hydraulic drive systems faster. () 3 Clearances too tight to hold ratio of 0.94. As discussed in Section V, the sample production utilized both in - dividual lab mixed samples and large lab mixes. The individual lab samples were prepared in 1,000 ml containers, preparing sufficient product to fill a 3" diameter by 6" high mold. The large lab mixes were prepared to supply suf-ficient product to fill up to seventeen of the same molds. These samples were used in the immersion, biodegradation, thermal cycling and irradiation tests. Following completion of these tests, drum scale tests were performed on four of the mixes. The selected mixes were: o Bead Resin o 20% Boric Acid o 20% Sodium Sulfate o 30% Mixed Solids with 20% Sodium Sulfate Each mix was prepared in a 55 gallon drum using an in-drum mixing system specifically designed for these tests. This design was based on the scaling factors outlined above. At the completion of the mix cycle, some of the product was removed from the drum and used to fill several 3" diameter by 6" molds. These samples were then cured in a manner identical to the large lab () sample mixes. After the initial cure period, two samples were tested for initial
STD-R-05-007
. Page 34 of 37 s.
O compression strength. Additional samples were immersed in water for duplication of the 90-day immersion tests. After the samples had been taken from the drums, each drum was sealed with a standard drum lid and bolt-closure ring. Samples and drums were examined at 24 hours to check for final set and free liquid. At this check, all samples and drums were hard and contained no liquid, drainable or otherwise. To complete the scale-up testing, two lin'ers were solidified. The first was an KN-100 LVM (large volume mixer) containing 30 percent mixed solids and a 20 percent sodium sulfate solution. This liner is an upsized standard KN-100 designed to maximize the usable internal volume. The second liner solidification was a standard EN-100 UM (underdrain mixer) containing bead resin. Both solidifications were performed using a Hittman Hydraulic Drive In-Container Solidification System. The HN-100 LVM was solidifed at the normal mixing speed of a hydraulic drive system. The waste type solidified in this liner is representative of a BWR, and, therefore would be solidified in the field using this system. A reduced mixing speed, representative of the electric drive, was used for the bead resin solidification in the HN-100 UM. During both solidifications, the hydraulic pressure was monitored. At no time in either solidification did the system pressure exceed 20 percent of the stall pressure. By comparison to an electric drive system this would still be only a fraction of the motor capacity. In this instance, the higher mixing () speed of the hydraulic urive system does not appear to have resulted in a stronger product since the initial strength of the liner samples from the KN-100 LVM are very similar to the initial strength of*the lab and drum scale samples. It can then be concluded that both waste types tested could also have been solidified with an Electric Driv'e System with similar results. Comparisons of the initial sample strengths and the immersed sample strengths are provided in Table 22 for the four waste types tested in the scale- l up program. Dipped samples taken at the completicn of the mixing cycle were
~
cured in the liners for seven days prior to being removed for testing. A closer examination of the individual sample strengths in Table 22 l gives a clearer impression of the curing process:
- 1. Bead Resin. While the average initial strength of the three bead resin liner samples is lower than the average lab strength, one of the three liner samples falls between the two lab samples. Similarly, for the drum samples, one had a strength close to the stronger of the two lab samples, while the other was close to the two lower strength liner samples.
The range of strengths experienced here is not unexpected. Previous testing, as part of this and other programs has demonstrated a significant distribution of sample strengths for cement solidified wastes. In particular, tests conducted as part of this program showed an average initial compression ' strength for 16 identical samples, of 960 psi with a standard deviation of 210 psi for the 30% mixed solids with 20% sodium sulfate waste type. While the (}
STD-R-05-007 Page 35 of 37 O Table 22 l Individual Scale-Up Testing Sample Strengths Compressive Strength, psi
. Lab Sample Drum Sample Liner Sample Bead Resin Initial Strength 1260, 1740 830, 1660 770, 1430, 860 Immersion Strength 1660, 2260 740, 1030 1029, 829 4
30% Mixed Solids With 20% Sodium Sulfate Initial Strength 1230, 1000 830, 1230 1200, 700 Immersion Strength 460 660, 960 1290, 1010 20% Boric Acid Initial Strength 110, 140 200, 200 Not Tested
- Immersion Strength 310, 340 260, 400 Not Tested-() 20% Sodium Sulfate Initial Strength 830', 830 570, 460 Not Tested Immersion Strength 1000, 1100 570, 570 Not Tested seven initial bead resin strengths are higher than those in this test, they do follow the same general distribution.
Following the 90-day immersion test, the two bead resin lab samples had compression strength of 1,660 psi and 2,260 psi. For this drum scale test the compressive strengths af ter 90 days immersion were 740 psi and 1,030 psi. Samples from the drum cured for 90 days and not immersed had strengths of 1,090 psi and 1,790 psi. Samples taken from the liner solidification had 90 day immersion strengths of 1,029 psi and 829 psi. A single mold cured sample from the liner had a compressive strength of 2,057 psi after ninety (90) days.
- 2. 30% Mixed Solids With 20% Sodium Sulfate. Drum scale and full size liner tests were also performed on the 30% mixed solids with 20% sodium sulfate. The data for the samples of this waste type is also shown in Table 22. l A comparison of the initial sample strengths from the lab, drum and liner samples with the previously mentioned data on the distribution of sample compressive strength shows good correlation between the two sets of data. Although one of the lab samples was cracked at the end of the 90-day immersion test and was not ;
j tested, both drum samples had compression tests well in excess of the minimum 7-~ l
\ 50 psi. Two samples taken from the liner had compressive strengths of 1,290 psi and 1,010 psi after 90 days immersion in water. A single mold cured sample from the liner had a compressive strength of 1,930 psi after 90 days.
STD-R-05-007 Page 36 of 37 For consistency within the procens control program with other ccm-binations of mixed solids and sodium sulfate, the final formulation selected for this particular combination has been increased in cement by approximately 8.5%. To demonstrate that this formulation does not result in a weaker product than the formulation tested, a drum scale test solidification was performed. Dipped samples were taken for testing. The initial sample strengths were 860 psi and 1,430 psi compared to the original drum samples of 830 psi and 1,230 psi. After the 90 days immersion in water the samples had compressive strengths of 1,810 psi and 1,630 psi. The 90 day mold cured samples from this drum had compressive strengths ,of 1,210 ps,i and 2,110 psi.
- 3. 20% Boric Acid and 20% Sodium Sulfate. Two other waste types, 20% boric acid and 20% sodium sulfate were taken to the drum scale tests. The similarity in strengths for the 20% boric acid samples shows good scale-up from the lab mixes to the drum size mix. For the sodium sulfate samples the strengths of the drum samples, although lower than the lab mixes, are an order of magnitude higher than minimum recommended strength of 50 psi. And, as shown in Table 10, the sample strength can be expected to increase as additional curing occurs.
B. Homogeneity of Liner In addition to testing samples taken from the two full scale liners prior to setting of the cement product, both liners were core drilled to demon-strate the homogeneity of the product. Two cores were taken from each liner. () One core was on a horizontal plane from the outer wall to the center of the liner. The second core was vertical from the top down to the bottom of the liner. Core samples were removed in 9 to 20 inch sections and then cut into six inch segments for compression testing. While these are considered nominal three inch diameter core samples, the actual. diameter of the samples was 2.75 inches. Five samples were cut from the vertical cores and three from the horizontal cores. Each sample was capped and tested for compression strength. These results are shown in Table 23. Table 23 Compression Strengths of Core Drilled Samples Compression Strength, psi Bead Resin 30% Mixed Solids with Liner 20% Sodium Sulfate Horizontal Core Outer Edge 1780 1720 Middle 1630 740 Center 1430 1010 Vertical Core Top 2120 1480 () Middle Top Middle 2220 1950 840 1350 960 Middle Bottom 1110 Bottom 2120 1650
STD-R-05-007 Page 37 of 37 O As the data demonstrates, the vJriation in sample strengths is random, following the same pattern of distribution found previously. The mixed solids with sodium sulfate strengths are very similar to those reported in Table 22 for initial strengths. Tne bead resin strengths are, on the average, higher than the initial l liner strength. While this too may also be a function of the normal distribu-tion of strength, it may also be an indication that the solidified product continued to cure and strengthen beyond the initial seven-day period used for the initial strength testing. This theory is supported by the fact that after the seven-day curing, the internal temperature of the liner was still at 100*F having peaked at 180*F at 24 hours. The temperature of the waste prior to solidification was approximately 65'F. Visual examinations of the liners has also confirmed complete mixing within the liners. Two removable plates along the bottom of the KN-100 UM were removed subsequent to the core drilling. Examination of the corner formed by the liner wall and the underdrain found a complete homogeneous mix of waste and cement with no unmixed solids. These examinations and tests conclusively demonstrate that the product quality throughout the liners is completed homogeneous with no voids or other areas of unmixed wastes. - 50L O
i i ATTACHMENT A
, WASTE QUALIFICATION PROGRAM .
~
Bittman Nuclear & Development Corporation l Solidified Low-Level Westes j Using Portland Cement i INTRODUCTION
.The program described herein has been implemented by Hittman Nuclear & Development Corporation (HNDC) to demonstrate the required compliance with paragraphs 61.55, Waste Classification and 61.56, Waste Characteristics, of 10CFR61, Licensing Requirements for Land Disposal of Radioactive Wastes. This rule, asd an implementing rule for NRC licensed waste generators, were published simultaneously in the Federal Register on December 27, 1982. The implementing rule,
, 10CFR20.311, Transfer and Disposal Manifests, has an implementation date of December 28, 1983.
O In May of 1983, the NRC published additional guidance for estab-lishing conformance to paragraphs 61.55 and 61.56. This guidance, in the form of two Branch Technical Positions, is applicable as follows: o 10CFR61.55, Waste Classification - Low-Level Waste Licensing Branch Technical Position on Radioactive Weste Classification, Rev. O, May 1983. o 10CFR61.56, Waste Characteristics - Technical Position on Waste Form, Rev. O, May 1983. l APPLICABILITY l l l The program described herein is cpplicable to HNDC In-Cogtriner Solidification Systems using either electric drive or hydraulic drive ll systems. [ l
WASTE FORMS QUALIFIED { This program has been developed based on seventeen (17) weste , forms commonly found in light water cooled nuclear power plan,ts. Some of the waste forms are mixed reflecting various components of installed plant equipment which allows mixing of waste streams for processing. The basic waste forms tested are: o Bead Ion-Exchange Resin o Powdered Ion-Exchange Resin o Diatomaceous Earth o Oil o Boric Acid at 8 and 20 weight percent ( o Sodium Sulfate at 10 and 20 weight percent o Miscellaneous Chemical Waste with Decontamination Solutions o Filter Sludge - a mixture of powdered resin, diatomaceous earth, iron oxide, and dirt o Aluminum grit In addition, tests are also being conducted on mixed wastes. Three (3) discrete combinations are being tested to demonstrate the ability to meet the established criteria over a diverse range of waste combinations. Figure I shows this in a graphical representation for boric acid mixed with bead resia. P . b . 2- .
. 40
( 30. - 3 5 20, 5 _ P2 P3
'9l if e4 Q
E
!!. .!Ei !:N y isP1 2d 3'O 46 5'O 60 70 P6 l'0 Wet Weight % Bead Resin FIGURI. 1
( Boric Acid with Bead Resin O Points P1, P2 and P3 represent the three (3) discrete combined waste types being tested. The specific formulations are: P1 - 30 wet weight. % bead resin and 5% boric acid P2 - 30 wet weight % bead resin and 16% boric acid P3 - 62 wet weight % bead resin and 16% boric acid Points P4 and P5 are the concentration of plain boric acid being tested while Point P6 is the plain bead resin test point. Based ou the maximum boric acid concentration of 20% covered in these tests, any combination of wastes inside the shaded area are fully described s
" by the six (6) wastes tested. Combinatior.t outside this ares would .
require demonstration of similar physical properties. The nature and . extent of the testing would have to be determined on a case-by-case basis.
- 3*
A sicilor presantetion for combinatiens of sedium sulfate with mixed solid wastes is given in Figure 2. () Points S1, S2 and S3 represent the three (3) discrete combined
~
i 1 waste types being tested. The specific formulations being tekted: 1 l S1. 30 wet weight % mixed soli-3s and 5% sodium sulfate S2. 30 wet weight % mixed solids and 20% sodium sulfate S3. 62 wet weight % mixed solids and 20% sodium sulfate
. The mixed solids component of S1, S2 and S3 consists of equal
, parts of bead resin, powdered resin and diatomaceous earth.
Points S4 and S5 are the concentrations of plain sodium sulfate being tested while Point S6 is the filter sludge waste. Based on a maximum sodium sulfate concentration of 20% covered in these tests, any combination of wastes inside the shaded area are fully described by the six (6) wastes tested. Combinations outside this area would ( require demonstration of similar physical prope'rties. The nature and extent of the testing would have to be addressed on a case by case {} basis. P O _4
. - . . - . . . . ---..= ' :.n~-.~ -
i 40- . o W 30
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E s 52 s3 Go 20 .-..r.. . m , H t Tc a g 10 ds4 jg gg M g W 51$ O 6'O S6 70 ld 2'O 3b 4'O Sb Wet Weight % FExed Solids FIGURE 2 Sodium Sulfate with Mixed Solid Waste OUALIFICATION TESTING Samples for tests which do not require the use of radioactive tracers will be made from single batch mixes. Samples with tracers will be made on an individual basis at the testing facility.
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. . 2 * *, .~. : .
- __.~,__.____.__'*._-._._'.__.__..._.__....._.,..___
- Comprzesiva Strength - Duplicate scmples, 3-inch diceeter x 6-inch high will be compressively tested to demonstrate a minimum compressive strength of 50 psi when tested in accordance with-(]) ASTM C39. i Irradiation - Single samples, 3-inch diameter x 6-inch high will be exposed to a Co-60 source and irradiated to a calculated dose at the centerline of the sample of los rads. Upon completion of the irradiation the samples will be compressive tested to demonstrate a minimum 50 psi compressive strength when tested in accordance with ASTM C39.
Biodegradation - Testing for biodegradation of the waste samples will be performed using the technique described below. The bacteria-and fungus used will be as specified in ASTM G22 and ASTM G21, respec-tively. In the case of ASTM G21, the fungus penicillium funiculosum will not be used in the test program due to its classification as a plant pathogen. This classification requires that anything coming ( into contact with this fungus be sterilized in an autoclave for 30 minutes at 120*C and 15 psig. Subjecting samples to this environment (]) would present an additional variable that could not be reconciled with the results of other tests. As previously agreed upon, the penicillium funiculosus will be replaced by another common soil fungus, penicillium jenseni, which is not a plant pathogen. Testing will be performed on a limited number of waste types due to the well documented fact that cement solidified wastes are not susceptible to either fungus or bacterial growth.( The wastes to be tested are bead resin, powdered resin, boric' acid, oil, 20% sodium sulfate with 62% mixed solids, miscellaneous chemical waste, and a I blank.
~
?
l - l II) Piciulo, et al., " Biodegradation Testing of Solidified Low-Level I { Weste Streams," BNL-NUREG-32577, February, 1983. g e eg a . eew .
-- --. , - . - , _ _ _ _ - . . - - . _ - - -, , _ , - . . , . , , _ _ .. , _ , , , , . , , _ - _ , , , . - , , , , _ . . . , _ _ _ , , _ , , , , , , , , - - . , , __.,,c., , ,_ . . . _ - - , _ , .
- Samples 3-inch diameter by 6-inch high will ba incubated in the specified non-nutrient salt. Separate samples are to be used for each (GV At the end of the required incubation period the ASTM specification.
I samples are examined per the applicable ASTM specification and com-pressively tested in accordance with ASTM C39. The minimum compressive strength shall be 50 psi. Leach Testing - Leach testing will be performed on samples measuring 1-inch in diameter by 2 to 3 inches in length. Duplicate samples shall be leached for a total period of ninety (90) days in accordance with'ANS 16.1 leach test procedure. Each sample will contain radio-active tracers at the equivalent concentration of approximately 1pCi/ gram each. The radioactive tracers to be used are 'Co-60, Sr-85, The leachate to be used shall be demineralized ( Cs-137 and Ce-144. water with the exception of synthesized sea water for bead resin and powdered resin. The combined leachability index for the four radio-active elements tested should be greater than 6.0. 90-Day Water Immersion - Duplicate samples, 3-inch diameter by 6-inch high will be imersed in tap water for a period of ninety (90) days. Each sample will then be compressively tested in accordance ? with ASTM C39 to demonstrate a minimum compression strength of 50 psi. 1 Thermal Degradation - Duplicate samples, 3-inch disseter by 6-inch high, will be subjected to a 50-day freeze / thaw cycle between 0*F and 120*F. During each 24-hour period the samples will be main-tained at 0*F for eight (8) hours and eight (8) hours at 120'F. Four 1 (
- O -
. . x .2_ . . .
, - _ . _ . . . - - . . _ _ _ _ _ _ _ _ - . - _ _ . _ _ _ _ _ -- , . ~ _ - - - . - _ _ . _ - _ _ - - - _ _ _ - _ _ _ _ _ - _ _ _ _
l (4) hours are required at the end of each period for heat up from O'T l l to 120*F or cool down from 120*F to 0*F. O ; Upon completion of the 50-day test period, each sample will be compressively tested in accordance with ASTM C39 to demonstrate a minimum compressive strength of 50 psi, Free Liquid - The BTP on Waste Forms permits a maximum free i liquid content of 0.5 percent by volume of the waste specimen. The 1 waste solidification formulations used for testing shall have zero collectible liquid at 24 hours after solidification. i FINAL REPORT At the completion of testing a repo'rt will be filed with each plant using the HI1TMAN incontainer solidification system. This report will contain the results of the testing described in this program 'shich demonstrates that the guidelines set forth in the branen technical report have been set. Correlations between the size samples used in the testing program and full scale operations vill be made. . 16H
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- 8. ,
GWB 8W G 8
- e . Os e
Taole 4A-CQ3 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 3rd Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 7 85 ) 9-30-85 STABILITY CLASS: A ELEVATION:45.7m Wind Speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 2 1 0 0 0 4 N 1 0 0 0 0 3 NNE 2 1 0 4 3 0 0 8 NE 1 3 8 9 0 0 21 ENE 1 O 9 1'9 7 0 0 35 E 2 7 7 0 0 0 16 ESE 3 8 0 0 0 12 SE ~1 2 0 0 0 4 SSE 1 1 0 2 0 0 0 2 S 0 0 0 1 0 0 0 1 SSW 2 2 0 0 4 SW 0 0 3 0 0 0 6 WSW 0 3 , 9 4 1 0 0 15 W 1 0 10 8 0 0 0 18 WNW 11 4 0 0 0 15 NW 0 0 0 0 0 5 NNW 1 4 O O O O VARIABLE O O O
--------_-----_----------_----_--_-_-----_---__--_--_----_-_----_ 169 11 63 73 22 0 C Total Periods of calm (hours): 0 Hours of missing data: 0
-. _ 35 -- .--. . . _ . - _ _ _ _ , _ _ _ _ ._
Table 4A-CQ3 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 3rd Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 7 85 ) 9-30-85 STABILITY CLASS: A ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O O O O O O NNE 4 1 1 0 0 0 6 NE 1 2 '6 0 0 0 9 ENE 1 5 18 0 0 0 24 E O 18 12 0 0 0 30 ESE 2 9 3 0 0 0 14 SE 2 7 5 0 0 0 14 SSE 1 1 3 0 0 0 5 S 0 1 0 0 0 0 1 0 0 0 0 0 0 0 SSW 0 2 3 0 0 0 5 SW WSW 3 5 0 0 0 0 8 W 0 13 1 0 0 0 14 WNW 3 16 1 0 0 0 20 NW 0 12 0 0 0 0 12 6 0 0 0 0 7 NNW 1 O O O VARIABLE O O O O Total 18 98 53 0 0 0 169 Periods of calm (hours): 0 Hours of missing data: 0 36
"' a b l e 4A-CQ3 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Firley Nuclear Plant - 3rd Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 7 85 ) 9-30-85 STABILITY CLASS: B ELEVATION:45.7m Wind Speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 3 3 0 0 0 0 6 NNE 2 5 0 0 0 0 7 NE 3 9 3 1 0 0 16 ENE 1 2 9 6 0 0 18 E 3 7 14 2 0 1 27 ESE 3 3 5 0 0 0 11 SE 2 6 7 0 0 0 15 SSE O 2 3 3 0 0 8 S 0 1 1 0 0 0 2 SSW 0 2 1 0 0 0 3 SW 1 0 2 2 0 1 6 WSW 1 3 2 0 0 0 6 W 0 2 2 0 0 0 4 WNW 0 2 3 0 0 0 5 NW 3 7 3 0 0 0 13 NNW 2 3 5 0 0 0 10 O O VARIABLE O O O O O Total 24 57 60 14 0 2 157 Periods of calm (hours): 0 Hours of missing data: 0
- . _ _ _ - . __ ,- _37 .__ , __ _
)
Taolo 4A-CQ3 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 3rd Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONT 14UOUS PERIOD OF RECORD: T 85 ) 9-30-85 STABILITY CLASS: E ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 5 3 0 0 0 0 8 NNE 2 5 0 0 0 0 7
~
NE 5 7 3 0 0 0 15 ENE 2 9 10 1 0 0 22 E 4 14 4 0 0 1 23 ESE 3 11 0 0 0 0 14 SE 3 13 3 1 0 0 20 SSE O 1 1 0 0 0 2 S 0 3 0 0 0 0 3 SSW 0 2 0 0 0 0 2 SW 1 1 2 1 0 0 5 WSW 1 4 1 0 0 0 6 W 0 4 1 0 0 0 5 WNW 1 3 0 0 0 0 4 NW 3 8 5 0 0 0 16 NNW 4 1 0 0 0 0 5 VARIABLE O O O O O O O Total 34 89 30 3 0 1 157 Periods of calm (hours): 0 , Hours of missing datas 0 _ , _ . _38 - _ ,
Tacle 4A-CQ3 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant'- 3rd Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 7 85 ) 9-30-85 STABILITY CLASS: C ELEVATION:45.7m Wind Speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 3 5 0 0 0 0 8 N 2 3 0 0 0 0 5 NNE NE 3 2 3 2 0 0 10 ENE 2 8 5 3 2 0 20 E 1 11 8 2 0 0 22 ESE 1 4 9 0 0 0 14 SE 2 2 4 1 2 0 11 0 3 0 0 0 4 SSE 1 0 0 2 1 0 0 3 5 3 1 0 0 0 4 ! SSW 0 i 1 5 1 0 0 8 SW 1 9 0 0 0 0 14 WSW 5 r i 9 3 0 0 1 14 W 1 1 1 0 0 9 WNW 2 5 4 3 4 0 0 0 11 NW 2 1 0 0 0 5 NNW 2 O O O O O l VARIABLE O O
- ---------------_------_____---_-_--_-----_-------_---------_--- 162 30 67 49 11 4 1 Total i
Periods of calm (hours): 0 Hours of missing data: 0
- - . - _ . . _ _ 39-- -- . - - _ - -._ _ _ . _ _ _ . _ _ __
Table 4A-CQ3 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 3rd Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 7 85 ) 9-30-85 STABILITY CLASS: C ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 5 3 0 0 0 0 8 NNE 3 0 0 0 0 0 3
~
NE 2 4 3 0 0 0 9 ENE 3 13 7 3 0 0 26 E 2 15 3 0 0 0 20 ESE 4 11 0 0 0 0 15 SE 1 4 2 3 0 0 10 2 0 0 0 2 SSE O O S 0 1 1 0 0 0 2 i SSW 1 2 0 0 0 0 3 SW 3 6 3 0 0 0 12 WSW 4 6 1 0 0 0 11 l W 4 9 0 0 1 0 14 4 2 0 0 0 7 l WNW 1 NW 8 5 2 0 0 0 15 4 0 0 0 0 5 NNW 1 i O O O O l VARIABLE O O O i Total 42 87 26 6 1 0 162 l l Periods of calm (hours): 0 I Hours of missing data: 0 40
Taole 4A-CQ3 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 3rd Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 7 85 ) 9-30-85 STABILITY CLASS: D ELEVATION:45.7m Wind speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 12 9 0 0 0 0 21 7 12 2 0 0 0 21 NNE
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NE 12 21 19 12 2 0 66 ENE 10 28 31 18 6 1 94 E 7 23 22 4 0 4 60 10 17 4 4 3 1 39 ESE 6 10 11 1 0 0 28 SE 7 12 5 0 0 32 SSE 8 10 6 4 1 0 0 21 S 6 7 3 3 0 0 19 SSW 7 10 22 4 0 0 43 SW 17 22 10 0 0 0 49 WSW W 11 25 10 1 0 0 47 9 2 0 0 0 17 WNW 6 8 12 6 0 0 0 26 NW 8 7 2 0 0 0 17 NNW O O O O VARIABLE O O O 145 225 160 53 11 6 600 Total Periods of calm (hours): 0 Hours of missing data: 0 41
Tacle 4A-CQ3 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 3rd Quarter, 1985 HOUES AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 7 85 ) 9-30-85 STABILITY CLASS: D ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL l N 18 2 0 0 0 0 20 NNE 23 17 0 0 0 0 40 NE 26 24 23 4 4 0 81 ENE 14 , 49 19 4 3 0 89 E 13 27 8 2 0 1 51 ESE 12 14 8 0 0 0 34 SE 12 15 9 1 0 0 37 SSE 10 5 6 0 0 0 21 S 7 6 0 0 0 0 13 SSW 5 3 4 0 0 0 12 SW 19 19 8 1 0 0 47 i WSW 23 23 2 0 0 0 48 W 23 18 3 0 0 0 44 WNW 9 12 0 0 0 0 21 NW 17 7 1 0 0 0 25 NNW 12 5 0 0 0 0 17 O O O VARIABLE O O O O Total 243 246 91 12 7 1 600 Periods of calm (hours): 0
- Hours of missing data
- 0
_ _ _ , _ _ _ _ _ . . , __4 2__ __.__ _ . _ _ _ . , , _ _ _ _ _ , _ _ _ __ __ _
! Table 4A-CQ3 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 3rd Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS l PERIOD OF RECORD: 7 85 ) 9-30-85 STABILITY CLASS: E ELEVATION:45.7m Wind Speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 1 N 10 16 3 0 0 0 29 NNE 2 11 13 0 0 0 26
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NE 11 22 42 1 0 0 76 ENE 8 45 43 0 0 0 96 E 7 32 28 0 1 2 70 ESE 5 15 10 0 1 0 31 SE 7 25 18 1 0 0 51 SSE 13 16 17 0* 0 0 46 S 12 9 6 0 0 0 27 SSW 7 13 10 2 0 0 32 SW 7 22 39 5 0 0 73 WSW 2 28 19 0 0 0 49 W 11 16 4 0 0 0 31 WNW 6 15 5 0 0 0 26 11 17 0 0 0 31 NW 3 i 10 4 1 1 0 0 16 NNW O O O O VARIABLE O O O 121 300 275 10 2 2 710 l Total Periods of calm (hours): 0 Hours of missing data: 0 43 ,_ _ _ .
Table 4A-CQ3 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 3rd Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 7 85 ) 9-30-85 STABILITY CLASS: E ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 38 2 0 0 0 0 40 NNE 60 9 13 0 0 0 82 NE 53 39 3 0 0 0 95 ENE 28 24 0 1 0 0 53 E 28 12 0 2 0 1 43 ESE 35 22 0 0 0 0 57 SE 23 19 2 0 0 0 44 SSE 10 5 1 0 0 0 16 S 12 6 0 0 0 0 18 SSW 9 7 2 1 0 0 19 SW 24 35 7 0 0 0 66 WSW 41 14 0 0 0 0 55 W 18 3 0 0 0 0 21 WNW 15 6 0 0 0 0 21 NW 23 14 1 0 0 0 38 NNW 41 1 0 0 0 0 42 VARIABLE O O O O O O O Total 458 218 29 4 0 1 710 Periods of calm (hours): 0 Hours of missing data: 0
._ ._ _ -- --44 -- ___ _ _ . _ _ __ _ _ _ . _ _ _ ,
Tacle 4A-CQ3 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 3rd Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 7 85 } 9-30-85 STABILITY CLASS: F ELEVATION:45.7m Wind Speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 3 11 2 0 0 0 16 NNE 6 10 5 0 0 0 21 NE 4 7 18 0 0 0 29 ENE 5 5 17 0 0 0 27 E 4 14 11 0 0 0 29 ESE 4 8 2 0 0 0 14 SE 6 9 14 1 0 0 30 SSE 3 6 6 2 0 0 17 S 7 1 0 0 0 0 8 SSW 1 1 2 1 0 0 5 SW 3 9 20 0 0 0 32 WSW 6 5 3 0 0 0 14 W 3 12 5 0 0 0 20 WNW 7 7 0 0 0 0 14 NW 3 3 6 0 0 0 12 NNW 4 15 1 0 0 0 20 O O O VARIABLE O O O O Total 69 123 112 4 0 0 308 Periods of calm (hours): 0 Hours of missing data: 0 GA
Table 4A-CQ3 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 3rd Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 7 85 ) 9-30-85 STABILITY CLASS: F ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 47 1 0 0 0 0 48 NNE 33 4 0 0 0 0 37 NE 26 7 O O O O 33 ENE 7 5 0 0 0 0 12 E 11 2 0 0 0 0 13 ESE 12 3 0 0 0 0 15 SE 8 8 1 0 0 0 17 SSE 1 0 0 0 0 0 1 S 2 0 0 0 0 0 2 SSW 6 0 0 0 0 0 6 SW 6 10 0 0 0 0 16 WSW 11 4 0 0 0 0 15 W 18 1 0 0 0 0 19 WNW 17 3 0 0 0 0 20 NW 12 3 0 0 0 0 15 NNW 38 1 0 0 0 0 39 VARIABLE O O O O O O O Total 255 52 1 0 0 0 308 Periods of calm (hours): 0 Hours of missing data: 0 46
Table 4A-CQ3 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 3rd Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 7 85 ) 9-30-85 STABILITY CLASS: G ELEVATION:45.7m Wind Speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 6 4 0 0 0 11 2 4 0 0 0 7 NNE 1 1 4 0 0 0 6 NE 1 6 0 2 0 0 0 8 ENE 7 1 0 0 0 8 E O 3 0 0 0 0 4 ESE 1 2 3 1 0 0 0 6 SE 1 2 0 0 0 3 SSE O 0 0 0 0 0 0 0 S 0 0 0 0 0 1 SSW 1 i SW 0 0 1 0 0 0 1 3 0 0 0 0 5 WSW 2 3 1 0 0 0 4 W 0 WNW 6 4 3 0 0 0 13 NW 1 3 8 0 0 0 12 NNW 3 10 0 0 0 0 13 O O O VARIABLE O O O O Total 25 46 31 0 0 0 102 Periods of calm (hours): 0 Hours of missing data: 0 ' A9
Table 4A-CQ3 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 3rd Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 7 85 ) 9-30-85 STABILITY CLASS: G ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind . Direction 1-3 4-7 8',12 13-18 19-24 >24 TOTAL N 18 0 0 0 0 0 18 NNE 10 0 0 0 0 0 10 NE 8 0 0 0 0 0 8 ENE O O O O O O O E O 1 1 0 0 0 2 ESE 1 1 0 0 0 0 2 SE O 1 1 0 0 0 2 SSE 1 0 0 0 0 0 1 S 0 0 0 0 0 0 0 SSW 2 0 0 0 0 0 2 SW 1 0 0 0 0 0 1 WSW 2 0 0 0 0 0 2 W 3 1 0 0 0 0 4 WNW 9 3 1 0 0 0 13 NW 17 1 0 0 0 0 18 NNW 19 0 0 0 0 0 19 VARIABLE O O O O O O O Total 91 8 3 0 0 0 102 Periods of calm (hours): 0 Hours of missing data: 0 48
Taole 4A-CQ4 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 4th Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 10 85 ) 12-31-85 STABILITY CLASS: A ELEVATION:45.7m Wind Speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 0 3 0 0 0 5 NNE O 1 0 0 0 0 1
~
NE O 3 3 0 0 0 6 ENE O O 2 0 0 0 2 E O 4 3 0 0 0 7 ESE 1 0 1 0 0 0 2 SE 1 3 0 0 0 0 4 SSE O 0 0 0 0 0 0 S 0 1 0 0 0 0 1 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 1 0 0 0 1 WNW 0 2 0 4 0 0 6 NW 0 0 0 6 0 0 6 0 0 0 4 3 0 7 NNW VARIABLE O O O O O O O Total 4 14 13 14 3 0 48 Periods of calm (hours): 0 Hours of missing data: 0 69
Table 4A-CQ4 CUMULATIVE JOINT FREQUENCY DISTRIBUTION i FLrley Nuclear Plant - 4th Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 10 85 } 12-31-85 STABILITY CLASS: A ELEVATION:15.0m j _________________________________________________________________ Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 3 0 0 0 0 5 NNE O 1 0 0 0 0 1
~
7 1 0 0 0 8 NE O l O O ENE O O O O O 4 2 0 0 0 7 E 1 2 1 0 0 0 3 3 ESE O 3 0 0 0 0 3 SE O O O O O O SSE O O 0 0 0 0 0 0 0 S 0 0 0 0 0 1 SSW 1 0 0 0 0 0 0 0 SW 0 1 0 0 0 1 WSW 0 0 2 0 0 0 0 2 W 0 6 0 0 0 6 WNW 0 NW 0 0 5 4 0 0 9 0 2 0 0 0 2 NNW 0 O O O 0 VARIABLE O O O 4 22 18 4 0 0 48 Total Periods of calm (hours): 0 Hours of missing datas 0 , _..._____,_____50____._.____ _ _ _ _ __
Table 4A-CQ4 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 4th Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 10 85 ) 12-31-85 STABILITY CLASS: B ELEVATION:45.7m Wind Speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL O 5 4 0 0 0 9 N 6 0 0 0 0 6 NNE O 2 3 0 0 0 5 NE O 1 3 0 0 0 5 ENE 1 O 4 5 0 0 0 9 E ESE 2 6 2 0 0 0 10 SE 4 5 1 2 0 0 12 0 0 0 0 2 SSE 1 1 2 0 0 0 0 3 S 1 0 0 0 0 0 1 SSW 1 1 3 2 0 0 0 6 SW 1 l 4 0 3 0 0 0 WSW 1 0 5 0 0 0 6 W 1 1 0 0 0 2 WNW 0 1 0 0 2 6 1 0 9 NW 0 0 0 2 0 0 10 I NNW O O O O l VARIABLE O O O Total 11 38 39 10 1 0 99 Periods of calm (hours): 0 Hours of missing' data: 0 l I
- - -- . _ . - _ _ . . _ _ _ _ _.. __ _ _._ _ 5 1 _ _ _ _ _ _ _ _ , _ _ _ , , _ __ __
Table 4A-CQ4 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 4th Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 10 85 ) 12-31-85 STABILITY CLASS: B ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 5 0 0 0 0 8 N 3 4 0 0 0 0 5 NNE 1 3 0 0 0 0 3 NE O 6 0 1 0 0 7 ENE O 4 3 0 0 0 7 E O 9 2 0 0 0 16 ESE 5 5 1 0 0 0 7 SE 1 2 0 0 0 0 2 SSE O 0 0 0 0 0 3 S 3 0 0 0 0 0 0 SSW 0 0 6 2 0 0 0 8 SW 0 3 0 0 0 3 WSW 0 i 3 0 0 0 7 W 0 4 0 0 0 1 0 0 1 2 WNW 0 0 9 1 0 0 10 NW 0 2 9 1 0 0 12 NNW 4 O O O O O VARIABLE O O 50 32 4 0 0 99
- Total 13 Periods of calm (hours)
- 0 Hours of missing datas 0 I e
Table 4A-CQ4 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 4th Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 10 85 } 12-31-85 STABILITY CLASS: C ELEVATION 45.7m I Wind Speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 3 11 3 0 0 0 17 NNE 1 4 2 0 0 0 7
~
NE 1 9 3 0 0 0 13 ENE 1 13 6 0 0 0 20 E 2 3 4 0 0 0 9 ESE 5 9 1 0 0 0 15 SE O 6 3 0 0 0 9 SSE O 3 3 0 0 0 6 5 0 1 0 0 0 0 1 SSW 1 1 0 1 0 0 3 SW 1 2 2 0 0 0 5 WSW 0 2 6 1 0 0 9 W 1 0 3 1 0 0 5 WNW 3 5 3 0 0 0 11 NW 0 4 3 2 0 0 9 NNW 1 2 7 2 0 2 14 O 0 0 VARIABLE O O O O Total 20 75 49 7 0 2 153 i Periods of calm (hours): 0 Hours of missing datas 0
- - - ~ ' - ' -- , - . _ . _ , , , . _ _ - , _ . _ , . _ , _ _ , , _ _
Table 4A-CQ4 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 4th Quarter, 1985 HOURS AT FACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 10 85 ) 12-31-85 STABILITY CLASS: C ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 4 4 0 1 0 0 9 NNE 1 4 0 0 0 0 5 NE O 13 2 0 0 0 15 ENE 1 14 2 0 0 0 17 E 3 8 1 0 0 0 12 ESE 2 8 1 0 0 0 11 SE O 13 0 0 0 0 13 SSE 1 0 2 0 0 0 3 S 0 2 0 0 0 0 2 SSW 1 0 1 0 0 0 2 SW 0 4 5 0 0 0 9 0 4 0 0 0 0 4 WSW W 3 5 3 0 0 0 11 WNW 2 6 2 0 0 0 10 NW 0 2 6 0 0 0 8 NNW 3 12 5 0 0 2 22 O O O VARIABLE O O O O Total 21 99 30 1 0 2 153 Periods of calm (hours): 0 Hours of missing data 0 93 4
Table 4A-CQ4 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 4th Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RFLEASE MODE: CONTINUOUS PERIOD OF RECORD: 10 85 ) 12-31-85 STABILITY CLASS: D ELEVATION:45.7m Wind Speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 10 22 15 0 0 1 48 NNE 9 21 6 0 0 2 38
~
NE 17 26 29 1 1 0 74 EllE 12 63 34 7 1 0 117 E 17 38 33 5 0 0 93 ESE 8 9 5 0 0 0 22 SE 10 14 1 3 0 0 28 SSE 7 13 4 1 0 0 25 S 3 1 7 1 0 0 12 SSW 2 4 1 3 0 0 10 SW 5 3 17 7 0 0 32 WSW 1 9 14 3 0 0 27 W 1 8 11 1 0 0 21 WNW 8 12 10 8 1 0 39 NW 7 21 17 18 1 1 65 NNW 9 10 26 22 5 0 72 O O O O VARIABLE O O O Total 126 274 230 80 9 4 723 Periods of calm (hours): 0 Hours of missing data: 0 M
Tacle 4A-CQ4 ( CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 4th Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE M6DE: CONTINUOUS PERIOD OF RECORD: 10 85 } 12-31-85 STABILITY CLASS: D ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 19 7 0 0 0 1 27 NNE 24 15 0 0 0 1 40 NE 22 55 14 1 0 0 92 ENE 14 50 65 9 0 0 138 E 16 18 20 3 0 0 57 ESE 9 12 1 0 0 0 22 SE 15 12 5 0 0 0 32 SSE 4 6 3 0 0 0 13 S 5 3 2 1 0 0 11 2 2 2 1 0 0 7 SSW SW 1 12 17 4 0 0 34 WSW 6 20 3 0 0 0 29 W 5 15 2 0 0 0 22 WNW 8 25 15 2 0 0 50 NW 11 24 28 6 0 0 69 lINW 16 40 21 2 0 1 80 O O O VARIABLE O O O O Total 177 316 198 29 0 3 723 i Periods of calm (hours): 0 Hours of missing data: 0 56
Taole 4A-CQ4 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 4th Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 10 85 ) 12-31-85 STABILITY CLASS: E ELEVATION:45.7m Wind Speed (mph) at 45.'7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 5 22 19 0 0 0 46 NNE 7 21 6 0 0 0 34 NE 7 30 14 0 0 2 53 ENE 12 42 33 8 3 0 98 45 E 14 25 6 O O O ESE 10 20 16 5 0 0 51 SE 8 13 18 4 0 0 43 SSE 8 2 14 7 0 0 31 S 1 5 12 8 0 0 26 SSW 3 6 7 6 0 0 22 SW 5 5 39 15 1 0 65 WSW 1 6 11 1 0 0 19 W 2 11 8 0 0 0 21 WNW 1 9 13 2 0 0 25 NW 1 4 14 10 1 0 30 NNW 4 14 36 7 0 0 61 O O O O VARIABLE O O O Total 89 235 266 73 5 2 670 Periods of calm (hours): 0 Hours of missing data: 0
. @ 7. . _ _ . _ _ _ _ _ _
Table 4A-CQ4 < CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 4th Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION 4 RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 10 85 } 12-31-85 STABILITY CLASS: E ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 49 1 0 0 0 0 50 NNE 34 6 0 1 0 1 42
~
NE 38 38 1 0 1 0 78 ENE 28 14 9 2 1 0 54 E 20 15 5 0 0 0 40 ESE 25 24 3 0 0 0 52 SE 6 10 17 0 0 0 33 SSE 5 10 10 0 0 0 25 S 8 3 0 0 0 0 11 SSW 1 10 3 0 0 0 14 t SW 10 29 24 1 0 0 64 WSW 7 12 0 0 0 0 19 W 11 5 4 0 0 0 20 WNW 7 15 3 0 0 0 25 NW 20 27 18 1 0 0 66 l i 34 40 3 0 0 0 77 NNW O O O O VARIABLE O O O 303 259 100 5 2 1 670 Total Periods of calm (hours): 0 Hours of missing data: 0 R@
Table 4A-CQ4 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 4th Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 10 85 } 12-31-85 STABILITY CLASS: F ELEVATION:45.7m Wind Speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 11 7 0 0 0 20 NNE 6 6 8 0 0 0 20 NE 5 8 15 0 0 0 28 3 11 23 0 0 0 37 ENE E 4 17 12 0 0 0 33 2 5 4 0 0 0 11 ESE 3 7 6 0 0 0 16 SE 1 3 1 0 0 6 , SSE 1 1 0 0 0 0 0 1 S 1 1 0 0 0 4 SSW 2 2 7 5 0 0 15 SW 1 4 2 5 1 0 0 12 WSW 3 0 0 0 5 W 1 1 7 5 1 0 0 14 WNW 1 2 5 26 2 0 0 35 NW 10 27 0 0 0 38 NNW 1 O O O O O VARIABLE O O ___--___------------_--_________-_--_--_----_---_-___----_--_--__ 295 94 152 10 0 0 Total 39 Periods of calm (hours): 0 Hours of missing data: 0 M)
Table 4A-CQ4 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 4th Quarter, 1985 HOURS AT EACH WIND SPEED AND DIK"CTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 10 85 } 12-31-85 STABILITY CLASS: F ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 51 0 0 0 0 0 51 NNE 23 4 0 0 0 0 27 NE 14 5 0 0 0 0 19 ENE 12 3 0 0 0 0 15 E 12 0 0 0 0 0 12 ESE 7 1 0 0 0 0 8 SE 4 4 0 0 0 0 8 O O O O SSE O O O S 2 0 0 0 0 0 2 3 0 0 0 0 4 SSW 1 SW 2 4 3 0 0 0 9 2 5 0 0 0 0 7 WSW W 7 4 0 0 0 0 11 WNW 13 8 0 0 0 0 21 NW 21 27 0 0 0 0 48 NNW 44 9 0 0 0 0 53 O O O O O VARIABLE O O Total 215 77 3 0 0 0 295 Periods of calm (hours): 0 Hours of missing data: 0
- - . - _ _ ___ ._60 __ _ _
Table 4A-C04 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 4th Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 10 85 } 12-31-85 STABILITY CLASS: G ELEVATION:45.7m Wind Speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 10 8 0 0 0 20 NNE 2 1 7 0 0 0 10 NE 5 5 4 0 0 0 14 ENE 3 11 11 0 0 0 25 E 5 9 18 1 0 0 33 ESE 5 7 18 0 0 0 30 SE 6 7 10 0 0 0 23 SSE 6 2 10 0 0 0 18 S 4 1 0 0 0 0 5 SSW 1 0 0 0 0 0 1 SW 1 1 2 0 0 0 4 WSW 1 2 1 1 0 0 5 W 1 2 1 0 0 0 4 WNW 0 1 0 0 0 0 1 NW 4 2 1 0 0 0 7 NNW 0 6 14 0 0 0 20 VARIABLE O O O O O O O Total 46 67 105 2 0 0 220 Periods of calm (hours): 0 Hours of missing data: 0 61 ___
Table 4A-CQ4 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 4th Quarter, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 10 85 } 12-31-85 STABILITY CLASS: G ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 62 1 0 0 0 0 63 NNE 36 2 0 0 0 0 38 NE 22 0 O O O O 22 ENE 19 0 0 0 0 0 19 E 8 0 0 0 0 0 8 ESE 2 0 0 0 0 0 2 0 0 0 0 0 1 SE 1 O O O O SSE O O O 0 0 0 0 0 0 0 S SSW 1 0 0 0 0 0 1 0 2 0 0 0 0 2 SW 0 2 0 0 0 0 2 WSW 0 0 0 0 2 W 1 1 WNW 1 0 0 0 0 0 1 NW 10 0 0 0 0 0 10 NNW 47 2 0 0 0 0 49 O O O O VARIABLE O O O 210 10 0 0 0 0 220 Total Periods of calm (hours): 0 Hours of missing data: 0 __. 6 2 _ _ _ .. .
TABLE 4A-13Q3 CUMULATIVE JOINT FREQUENCY DISTRIBUTICN Farley Unit 1 - 3rd Quarter, 1985 l . No batch releases were made during 3rd Quarter 1985 therefore Cumulative Joint Frequency Distribution tables are-not applicable. i 1 4 4 4 3 4 l i i 1 1 i i i i i i j I l I 63 N +w- .e- -- - - - - e ~m y v>g -9 wem y W- g m g
- qe .m y m y --n gweWw -
-e---y--,m -=m--'p
TABLE 4A-13Q4 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Unit 1 - 4th Quarter, 1985 No batch releases were made during 4th Quarter 1985 therefore cumulative Joint Frequency Distribution tables are not applicable. 4 h I i l l l l l ! 64
~ _ . __ . _ _ . _ . _ _.- . . _ . _ _ _ _. _ - _ _. _ _ _ _ . _ . . _ _ _ - _ . _ . _
- n. .- v~ - -
TABLE 4A-23Q3 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Unit 2 - 3rd Quarter, 1985 No batch releases were made during 3rd Quarter 1985 therefore Cumulative Joint Frequency Distribution tables are not applicable. 1 1 65, . _ _ _ _ _ _ _ , _ _ .__,,_, . . . _ . _ _ _ _ . , . . __
TABLE 4A-2BQ4 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Unit 2 - 4th Quarter, 1985 No batch releases were made during 4th Quarter 1985 therefore Cumulative Joint Frequency Distribution tables are not applicable. i i 4 4 66
TABLE 4B CLASSIFICATION OF ATMOSPHERIC STABILITY a Stability Pasquill oG Temperature channel Classification Categories (degrees) with height (0F/51m) Extremely unstable A 25.0 <-1.74 Moderately unstable B 20.0 -1.74 to -1.56 Slightly unstable C 15.0 -1.56 to -1.38 Neutral D 10.0 -1.38 to -0.46 Slightly stable E 5.0 -0.46 to 1.38 Moderately stable F 2.5 1.38 to 3.6 Extremely stable G 1.7 >3.6 a Standard deviations of horizontal wind direction fluctuation over The values shown are averages . a period of 15 minutes to i hour. for each stability classification. l l t l l 67
TA3LE 5 RADICACT!?E GASECUS WASTE SAMPLING AND ANALYSIS PROGRAM
?ARLEY NUCLEAR PLANT - UNITS 1 & 2 a,h Gaseous Release Sampling Minimum Type of Minimum Type Frequency Analysis Activity Detectable Frequency Analysis Concentration (MDC)(uCi/ml) g,h A. Waste Gas Each Tank Each Tank Principle 1E-04 Storage Tank Grab b Gamma Sample P P Emitters 9s)
B. Containment Each Purge Each Purge Principle 1E-04 Purge Grab b Grab b Gamma Emitters Sample P Sample P H-3 1E-06 9sj C. Condenser M-b,c,e b Principle Steam Jet Air Grab 'M Gamma Emitters 1E-04 , Ejector Plant Sample Vent Stack H-3 1E-06 i D. Plant Vent Continuous Charcoal I-131 1E-12 Stack Charcoal Sample d Containment W I-133 1E-10 Purge f g Continuous Particulate Principle Sample d Gamma Emitters 1E-11 W (I-131, Others) f Continuous W i Composite Gross Alpha 1E-11 Particulate Sample f Continuous Q i Composite Particulate Sr-89, Sr-90 1E-11 Sample f Continuous Noble Gas Noble Gases Gross 1E-06 Monitor Beta & Gamma 68
TABLE 5 (Concinued) TABLE NCTATION
- a. The MDC is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5%
probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation): 6 MDC = 4.66 s / E*V* 2.22X10
- Y
- exp (-AAt) b where:
MDC is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume), s is the standard deviation of the background counting rate b or of the counting rate' of a blank sample as appropriate (as counts per minute), E is the counting efficiency as counts per transformation), V is the sample size (in units mass or volume), 6 2.22x10 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable), X is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples). The value of s used in the calculation of the MDC for a b detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E, V, Y, and at shall be used in the calculation. l 69
TABLE 5 (Continued) TABLZ NOTATION
- b. Analyses shall also be performed following shutdown from ) or =
15% RATED THERMAL POWER, startup to > or = 15% RATED THERMAL POWER or a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a one hour period.
- c. Tritium grab samples shall be taken from the plant vent stack at least once per 24 hours when the refueling canal is flooded.
- d. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours for at least 2 days following each shutdown from ) or = 15% RATED THERMAL POWER, startup to > or =
15% RATED THERMAL POWER or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in one hour and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding MDC may be increased by a factor of 10.
- e. Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
- f. The ratio of the sample flow rate to the sampled stream flow rate shall be.known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.
- g. The principle gamma emitters for which the MDC specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cc-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other which are measurable and identifiable, together with the above nuclides, shall also be identified and reported,
- h. Deviations from MDC requirements of Table 4.11-2 shall be reported per Specification 6.9.1.8 in lieu of any other report.
- i. A composite particulate sample is one in which the quantity of air sampled is proportional to the quantity of air discharged.
Either a specimen which is representative of the air discharged may be accumulated and analyzed or the. individual samples may be analyzed and weighted in proportion to their respective volume discharged.
- j. The principle gamma emitters for which the MDC specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions. This does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable together with the above nuclides, shall also be identified and reported.
70
TABLE 6 RADICACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM FARLEY NUCLEAR PLANT - UNITS 1 & 2 a9 s Minimum Type of Minimum Liquid Release Sampling Analysis Activity Detectable Type Frequency Frequency Analysis Concentration (MDC)(uCi/ml) c P P e A. Batch Waste Each Each Principle Release Batch Batch Gamma SE-07 Tanks Emitters I-131 1E-06 One Batch /M M Dissolved & Entrained Gases 1E-05 (Gamma Emitters) P Each b Batch M H-3 1E-05 Composite Gross Alpha 1E-07 P Each b Batch Q Sr-89, Sr-90 SE-08 Composite Fe-55 1E-06 d,f D b e B. Continuous Grab W Principle Releases Sample Composite Gamma SE-07 Emitters I-131 1E-06 M
- 1. Steam Grab M Dissolved &
Generator Sample Entrained Gases 1E-05 Blowdown (Gamma Emitters) D b Grab M H-3 1E-05 Sample Composite Gross Alpha 1E-07 D b Grab Q Sr-89, Sr-90 SE-08 Sample Composite Fe-55 1E-06 P b e
- 2. Turbine Grab W Principle SE-07 Building Sample Composite Gamma Sump Emitters H-3 1E-05 l
71 l i t
TABLE 5 (Continued) TABLE NOTATION
- a. The MDC is the smallest concentration of radioactive material in a sample that will be detected with 954 probability with 5%
probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation): 6 MDC = 4.66 s / E
- V
- 2.22X10
- Y
- exp (-Aat) b where:
MDC is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume), s is the standard deviation of the background counting rate
~
b or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per transformation), V is the sample size (in units mass or volume), 6 2.22x10 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable), h is the radioactive decay constant for the particular radionuclide, and I at is the elapsed time between midpoint df sample collection and time of counting (for plant effluents, not environmental samples). The value of s used in the calculation of the MDC for a b detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E, V, Y, and At shall be used in the calculation. 72
TABLE 6 (Continued) TABLE NOTATION
- b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
- c. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a. method described in the ODCM, to assure representative sampling.
- d. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the effluent release.
- e. The principle gamma emitters for which the MDC specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified'and reported.
- f. Sampling will be performed only if the effluent will be discharged to the environment.
- g. Deviation from the MDC requirements.of Table 4.11-1 shall be reported per Specification 6.9.1.8 in lieu of any other report.
1 c 73
TABLE 7 LIQUID DISCHARGES NOT MEETING SPECIFIED DETECTION LIMITS Farley Units 1 & 2 - 2nd half, 1985 Batch # N/A* Date N/A Count Time in Seconds N/A Volume Discharged in Gallons N/A Dilution Water in Gallons N/A Total Isotopic Activity (uCi/ml) N/A Isotope of Interest N/A MDC Measured N/A
% of. Total Isotopic Activity N/A
% of Total Dose N/A
- No liquid discharges made that did not meet specified detection limits.
I 74
Table 8-CA CUMLATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - Annual, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 85 } 12-31-85 STABILITY CLASS: A ELEVATION:45.7m Wind Speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL , N 5 15 26 6 0 0 52 NNE 3 19 20 11 0 0 53
~
NE 6 9 13 4 0 0 32 ENE 9 7 19 11 0 0 46 E 2 28 30 13 0 0 73 ESE 5 24 22 3 0 0 54 SE 7 22 23 4 0 0 56 SSE 2 21 22 2 0 'O 47 S 1 4 9 1 0 0 15 SSW i 1 4 12 3 0 21 SW -1 8 24 22 0 0 55 WSW 1 18 21 6 0 0 46 W 6 26 31 3 0 1 67 WNW 1 19 21 11 2 2 56 NW 1 20 30 20 2 0 73 NNW 5 13 16 6 3 1 44 O 0 0 0 VARIABLE O O O 56 254 331 135 10 4 790 Total Periods of calm (hours): 0 Hours of missing data: 0
._ 75. . __ _ _ _ _ _ _ . _
Table 9-CA CUMLATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - Annual, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 85 ) 12-31-85 STABILITY CLASS: A ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 9 30 19 0 0 0 58 NNE 8 15 4 0 0 0 27 NE 7 18 9 0 0 0 34 ENE 12 15 32 1 0 0 60 E 5 40 23 0 0 0 68 ESE 5 33 15 1 0 0 54 SE 13 31 19 0 0 0 63 SSE 2 15 16 0 1 0 34 S 2 2 2 3 0 0 9 SSW 3 6 9 18 2 0 38 SW 2 13 38 5 2 0 60 WSW 6 30 13 2 1 1 53 c i W 2 33 14 1 1 1 52 WNW 5 25 21 4 2 2 59 NW 1 25 31 11 0 1 69 NNW 7 26 18 0 0 1 52 I O O O O VARIABLE O O O Total 89 357 283 46 9 6 790 i Periods of calm (hours): 0 l Hours of missing data: 0
~
7@ - -
Table 3-CA CUMLATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - Annual, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 85 } 12-31-85 STABILITY CLASS: B ELEVATION:45.7m Wind Speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 7 22 10 2 0 0 41 NNE 9 24 8 0 0 0 41 NE 9 22 10 1 0 0 42 ENE 5 12 19 6 0 0 42 E 13 21 25 3 0 1 63 ESE 8 22 9 0 0 0 39 SE 11 19 18 2 0 0 50 SSE 4 14 12 5 0 0 35 S 2 10 4 4 0 0 20 SSW 2 3 3 8 1 0 17 SW 2 5 14 2 3 1 27 WSW 1 20 11 0 0 0 32 W 0 14 22 1 0 1 38 WNW 0 10 16 4 0 0 30 NW 7 23 28 12 1 1 72 11 20 3 0 0 38 NNW 4 O O O VARIABLE O O O O Total 84 252 229 53 5 4 627 Periods of calm (hours): 0 Hours of missing data: 0 77 - _ _ _ - _ - _ - . . _ . _ . _ , .. _ _ _ _ _ _ , ._,
Table 9-CA CUMLATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - Annual, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 85 } 12-31-85 STABILITY CLASS: B ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 19 30 0 0 0 0 49 NNE 9 21 2 0 0 0 32 NE 12 21 5 0 0 0 38 ENE 8 26 16 2 0 0 52 E 10 30 9 0 0 1 50 ESE 13 40 2 0 0 0 55 SE 10 34 8 1 0 0 53 SSE 3 7 11 0 0 0 21 S 6 4 3 4 0 0 17 SSW 0 5 4 3 1 0 13 SW 1 19 14 3 1 0 38 WSW 3 17 12 0 0 0 32 W 2 23 13 0 0 1 39 WNW 1 17 14 2 0 0 34 NW 8 28 27 2 0 1 66 NNW 7 15 15 1 0 0 38 VARIABLE O O O O O O O Total 112 337 155 18 2 3 627 Periods of calm (hours): 0 Hours of missing data: 0 - - _ . . _ . . _ . . . . . _ _7 8 . _ __ _ _ _ __ _ _ _ _
Table 8-CA CUMLATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - Annual, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 85 ) 12-31-85 STABILITY CLASS: C ELEVATION:45.7m Wind Speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 7 35 15 6 0 0 63 NNE 4 17 9 1 0 0 31 NE 10 16 7 2 0 0 35 ENE 4 33 16 3 2 1 59 E 11 35 13 3 0 0 62 9 21 15 1 0 0 46 ESE SE 2 17 10 1 2 0 32 l 2 7 14 2 0 1 26 SSE 4 3 4 7 0 0 18 S 4 5 4 8 1 0 22 SSW 3 8 15 18 3 1 48 SW 7 17 14 3 0 0 41 WSW 14 16 1 0 1 38 W 6 ! 52 WNW 5 20 13 12 1 1 l 6 29 19 5 1 0 60 NW 7 13 25 5 0 2 52 NNW O O O O O VARIABLE O O __-_-__----__---__----__--_-_-__--______--__---_-_--_----__-_-_-- 685 Total 91 290 209 78 10 7 Periods of calm (hours): 0 Hours of missing data: 0 l l 79
Table S-CA CUMLATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - Annual, 1985-HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 85 } 12-31-85 STABILITY CLASS: C ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 14 24 1 2 0 0 41 f NNE 8 6 1 0 0 0 15
~
NE 9 27 6 0 0 0 42 ENE 11 44 11 3 0 1 70 E 17 33 7 0 0 O 57 ESE 7 29 2 0 0 0 38 SE 5 28 9 3 0 1 46 SSE 2 6 11 3 0 0 22 S 2 8 8 1 1 0 20 l, SSW 7 4 7 11 0 0 29 l SW 5 20 24 1 2 0 52 l l WSW 7 21 12 0 0 0 40 l W 8 21 13 0 1 0 43 6 30 13 2 2 0 53 WNW 14 23 18 0 0 0 55 NW 8 39 12 1 0 2 62 NNW O O O O VARIABLE O O O Total 130 363 155 27 6 4 685 j i Periods of calm (hours): 0 Hours of missing data: 0
- - - -- __ _ 80_ _ _ _ _ __ _
Table 8-CA CUMLATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - Annual, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 85 } 12-31-85 STABILITY CLASS: D ELEVATION:45.7m Wind Speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 30 70 58 16 0 1 175 NNE 20 69 36 2 0 2 129 NE 38 69 '62 13 3 0 185 ENE 30 125 84 26 7 1 273 E 27 87 81 11 0 5 211 ESE 20 42 34 7 4 1 108 SE 22 42 42 8 0 1 115 SSE 17 34 53 20 1 0 125 S 20 15 29 7 0 0 71 15 19 14 32 7 0 87 SSW SW 19 30 100 55 12 2 218 WSW 21 81 98 15 1 1 217 W 18 60 44 7 0 0 129 WNW 21 40 41 24 12 0 138 NW 17 49 62 42 4 2 176 l NNW 21 56 88 37 6 2 210 O O O O VARIABLE O O O ! Total 356 888 926 322 57 18 2567 i i Periods of calm (hours): 0 l Hours of missing data: 0 mR
Table 8-CA CUMLATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - Annual, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 85 ) 12-31-85 STABILITY CLASS: D ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 64 37 0 0 0 1 102 NNE 65 58 0 1 0 1 125 NE 71 118 '37 5 4 0 235 ENE 39 140 91 13 3 0 286 E 42 78 39 6 0 1 166 ESE 27 63 16 1 0 1 108 SE 35 69 38 2 0 0 144 SSE 19 28 30 3 0 0 80 S 18 17 8 3 0 0 46 SSW 15 18 46 22 4 1 106 SW 40 125 88 17 2 3 275 WSW 46 87 21 2 0 0 156 W 47 59 15 0 0 0 121 WNW 34 74 43 15 3 0 169 NW 40 88 61 10 0 1 200 NNW 58 122 62 5 0 1 248 VARIABLE O O O O O O O Total 660 1181 595 105 16 10 2567 Periods of calm (hours): 0 Hours of missing data: 0 82 . - . - , _ _ . . _ . _ _
Table 8-CA CUMLATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - Annual, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORT.: 1 85 } 12-31-85 STABILITY CLASS: E ELEVATION:45.7m Wind Speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 18 56 41 0 0 0 115 NNE 19 50 26 0 0 0 95
~
NE 20 60 63 1 0 3 147 ENE 25 98 85 8 3 0 219 E 21 86 57 0 1 2 167 ESE 19 64 53 5 1 1 143 SE 17 52 63 7 0 0 139 SSE 24 26 64 15 1 0 130 S 18 26 44 16 0 0 104 SSW 13 24 26 21 0 0 84 SW 21 38 145 42 1 0 247 WSW 6 68 94 6 0 0 174 W 18 74 27 3 0 0 132 WNW 14 40 46 7 0 0 107 NW 10 42 84 15 1 0 152 NNW 18 42 81 11 0 0 152 O O O VARIABLE O O O O Total 281 846 1009 157 8 6 2307 Periods of calm (hours): 0 Hours of missing data: 0 83
Table 3-CA CUMLATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - Annual, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 85 ) 12-31-85 STABILITY CLASS: E ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 119 6 1 2 0 0 128 NNE 115 23 13 1 0 1 153 NE 102 84 4 0 1 0 191 ENE 90 59 10 3 1 0 163 E 67 46 10 3 0 1 127 ESE 87 77 4 0 0 0 168 SE 40 65 30 0 0 0 135 SSE 18 37 27 0 1 0 83 S 25 12 3- 2 0 0 42 SSW 21 35 20 2 0 0 78 SW 68 149 63 1 0 0 281 WSW 82 63 7 0 0 0 152 W 62 25 5 0 0 0 92 WNW 48 71 11 0 0 0 130 NW 78 97 22 1 0 0 198 NNW 109 70 5 1 1 0 196 O O O VARIABLE O O O O Total 1131 919 235 16 4 2 2307 Periods of calm (hours): 0 Hours of missing data: 0 ma
Table 8-CA CUMLATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - Annual, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 85 } 12-31-85 STABILITY CLASS: F ELEVATION:45.7m Wind Speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 6 35 28 0 0 0 69 NNE 14 26 24 0 0 0 64 NE 14 23 44 0 0 0 81 ENE 11 23 51 0 0 0 85 E 15 39 35 0 0 0 89 ESE 9 30 19 0 0 0 58 SE 14 28 37 1 0 0 80 SSE 6 16 25 4 0 0 51 S 12 6 3 1 0 0 22 SSW 5 6 3 1 0 0 15 SW 6 19 45 8 0 0 78 WSW 11 22 16 1 0 0 50 W 6 24 16 0 0 0 46 WNW 11 28 27 3 0 0 69 NW 9 23 69 4 0 0 105 NNW 8 40 57 2 0 0 107 O O O VARIABLE O O O O Total 157 388 499 25 0 0 1069 Periods of calm (hours): 0 Hours of missing data: 0 85
Table 8-CA CUMLATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - Annual, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 85 ) 12-31-85 STABILITY CLASS: F ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 133 1 1 0 0 0 135 NNE 80 9 0 0 0 0 89 NE 59 14 0 0 0 0 73 ENE 37 12 4 0 0 0 53 E 40 7 0 0 0 0 47 ESE 44 9 0 0 0 0 53 SE 22 25 4 0 0 0 51 SSE 9 1 0 0 0 0 10 S 6 0 1 0 0 0 7 SSW 11 8 0 0 0 0 19 SW 22 28 4 0 0 0 54 WSW 25 16 0 0 0 0 41 W 51 14 1 0 0 0 66 WNW 53 44 0 0 0 0 97 NW 63 58 1 0 0 0 122 NNW 126 24 2 0 0 0 152 O O O VARIABLE O O O O Total 781 270 18 0 0 0 1069 Periods of calm (hours): 0 Hours of missing data: 0 86 _ - ~ , - v.
Table S-CA CUMLATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - Annual, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 85 ) 12-31-85 STABILITY CLASS: G ELEVATION:45.7m Wind Speed (mph) at 45.7m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 9 38 19 0 0 0 66 NNE 10 22 26 1 0 0 59
~
NE 16 22 24 0 0 1 63 ENE 18 28 23 0 0 0 69 E 10 36 38 1 0 0 85 ESE 12 28 27 0 0 0 67 SE 14 31 17 0 0 0 62 SSE 12 9 21 0 0 0 42 S 5 8 2 0 0 0 15 SSW 5 5 2 0 0 0 12 SW 4 7 5 0 0 0 16 WSW 3 10 4 1 0 0 18 W 4 5 4 0 0 0 13 10 11 6 0 0 0 27 WNW 10 11 22 0 0 0 43 NW 7 22 29 0 0 0 58 NNW O O O O VARIABLE O O O 149 293 269 3 0 1 715 Total Periods of calm (hours): 0 Hours of missing data: 0 EG
Tacle 3-CA CUMLATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - Annual, 1985 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 85 } 12-31-85 STABILITY CLASS: G ELEVATION:15.0m Wind Speed (mph) at 15.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 188 2 0 0 0 0 190 NNE 80 4 1 0 0 0 85 NE 47 0 0 0 0 0 47 ENE 32 0 1 0 0 0 33 E 11 1 1 0 0 0 13 ESE 10 2 0 0 0 0 12 SE 12 2 1 0 0 0 15 0 0 0 0 0 9 SSE 9 3 0 0 0 0 0 3 S 0 0 0 0 8 SSW 7 1 5 2 0 0 0 0 7 SW WSW 6 4 0 0 0 0 10 W 7 5 0 0 0 0 12 WNW 24 7 1 0 0 0 32 NW 62 5 0 0 0 0 67 NNW 169 3 0 0 0 0 172 O O O O VARIABLE O O O Total 672 38 5 0 0 0 715 Periods of calm (hours): 0 Hours of missing data: O mm
~~
- 15. Process Control Program Changes to the Process Control Program (PCP) during the second semi-annual period of 1985 are submitted per STS section 6.13.2.
Documentation that the changes were reviewed and found acceptable by the Plant Operations Review Committee is also submitted in the following section of this report. 89 l
C- C M;lling Address Alabama Power company 5 o 600 North 18th Street S ' " ~ ~- . - Post office Box 2641 Birmingham, Alabama 35291 . Telephone 205 783-6090 , j - R. P. Mcdonald Senior Vice President ,"*, 3 ,$j" *. 7 l c g *. 3 Flintndge Building ' ' '
- Mabama POnW ry3 y ne.e e, .
February 24, 1986 Docket Nos. 50-348.0 50-364 Dr. J. Nelson Grace Regional Administrator U. S. Nuclear Regulatory Commission Suite 2900 101 Marietta Street, N. W. Atlanta, Georgia 30323 . RE: Joseph _M. Farley Nuclear Plant l Radioactive Effluent-Release' Report /
/
Dear Dr. Grace:
'Ihe Joseph M. Farley Nuclear Plant Semi-Annual Radioactive Effluent Release Report for the period of July 1, 1985 through December 31, 1985 is herewith submitted in accordance with the Unit 1 and Unit 2 Technical Specifications, Section 6.9.1.8. Included with this submittal as required by Technical Specification 6.13.2 is documentation of changes made to the Farley Nuclear Plant Process Control Program.
If you have any questions, please advise. Yours very tru , _
.g, R. P. McDonal m RPM / MAT:emb Enclosures (2) xc: Director Office of Nuclear Reactor Regulation '
Director Office of Inspection and Enforcement t ! Mr. L. B. Long hp 3
~
Mr. G. F. Trowbridge ) l Mr. W. H. Bradford i Mr. E. A. Reeves utticia\ C09Y f wm
r- - Dr. J. Nelson Grace February 24, 1986 U. S. Nuclear Regulatory Conunission Page 2 bc: Mr. W. G. Hairston, III Mr. N. M. Horsley Mr. J. D. Woodard (w/ Attachment) (G9.31 & A4.05) Mr. W. R. Bayne (w/ Attachment) Mr. A. V. Godwin (w/ Attachment) Mr. James Hardeman (w/ Attachment) Mr. J. R. Duck (w/ Attachment) Mr. K. W. McCracken ANI Library (w/ Attachment) Ms. B. C. English File A-2.8 (w/ Attachment) hi}}