ML20148P030

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Semiannual Radioactive Effluent Release Rept for Jan - June 1986
ML20148P030
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 06/30/1986
From: Mcdonald R
ALABAMA POWER CO.
To: Grace J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NT-86-0403, NT-86-403, NUDOCS 8801280645
Download: ML20148P030 (203)
v • d • e


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ALABAMA POWER COMPANY FARLEY NUCLEAR PLANT UNIT NO. ONE LICENSE NO. NPF-2 AND FARLEY NUCLEAR PLANT UNIT NO. TWO LICENSE NO. NPF-8 l

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JAN.1, 1986 THROUGH JUNE 30, 1986 i

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V 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. Iodines and Particulates
c. Liquid Effluents
2. Maximum Permissible Concentrations 3
a. Airborne
b. Liquid
3. Average Energy 3 i 4. Measurements and Approximations of Total 3 Activity l
a. Fission and Activation Gases
b. Iodines and Particulates
c. Liquid Effluents
5. Batch Releases 6
a. Liquid
b. Gaseous
6. Abnormal Releases 6 1
a. Liquid l

l b. Gaseous l

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i k , , _ . . . , . _ _ . _ , , . . _ . _ _ . _ _ _ . _ _ _ _ _ _ _ _ _____________;

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TABLE OF CONTENTS (con't) 1 SUBJECT PAGE

7. Estimate of Total Error 8 8.' -Solid Waste I 9
9. Radiological Impact on Man 9 l 10. Meteorological Data ,

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11. Minimum Detectable Concentration (MDC) 11
12. Process Control Program 98 ,

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(si LIST OF TABLES TABLE PAGE 1A-1Q1 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES, 12 Farley Unit 1 - 1st Quarter, 1986 1A-1Q2 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES, 13 Farley Unit 1 - 2nd Quarter, 1986 1A-2Q1' GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES, 14 Farley Unit 2- 1st Quarter, 1986 1A-2Q2 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES, 15 Farley Unit 2 - 2nd Quarter, 1986 1B-1Q1 GASEOUS EFFLUENTS--ELEVATED RELEASE, Farley 16 Unit 1 -

1st Quarter, 1986 1B-1Q2 GASEOUS EFFLUENTS--ELEVATED RELEASE, Farley 17 Unit 1 - 2nd Quarter, 1986 1B-2Q1 GASEOUS EFFLUENTS--ELEVATED RELEASE, Farley 18 Unit 2- 1st Quarter, 1986

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1B-2Q2 GASEOUS EFFLUENTS--ELEVATED RELEASE, Farley 19 Unit 2 - 2nd Quarter, 1986 1C-1Q1 GASEOUS EFFLUENTS--GROUND RELEASE, Farley 20 Unit 1 - 1st Quarter, 1986 l 1C-1Q2 GASEOUS EFFLUENTS--GROUND RELEASE, Farley 21 l Unit 1 - 2nd Quarter, 1986 1C-2Q1 GASEOUS EFFLUENTS--GROUND RELEASE,'Farley 22 Unit 2 - 1st Quarter, 1986 1C-2Q2 GASEOUS EFFLUENTS--GROUND RELEASE, Farley 23 Unit 2 - 2nd Quarter, 1986 2A-1 LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES, 24-Farley Unit 1 - 1st Half, 1986 l 2A-2 LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES, 25 Farley Unit 2 - 1st Half, 1986 l

2B-1B LIQUID EFFLUENTS--BATCH, Farley Unit 1 26 ist Half, 1986 l

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) 2B-2B LIQUID EFFLUENTS--BATCH, Farley Unit 2 1st Half, 1986 27 111

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LIST OF TABLES (cont.)

TABLE PAGE 2B-1C LIQUID EFFLUENTS--C^NTINUOUS, Farley. Unit 1 28 ist Half, 1986 2B-2C LIQUID EFFLUENTS--CONTINUOUS, Farley Unit 2 29 1st Half, 1986 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS, 30 ist Half, 1986 4A-CQ1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION, 32 Continuous Mode - 1st Quarter, 1986 4A-CQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION, 46 Continuous Mo,de - 2nd Quarter, 1986 5

4A-1BQ1 CUMULATIVE JOINT, FREQUENCY DISTRIBUTION, 60 Unit i Batch Mode - 1st Quarter, 1986 4A-1BQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION, 61 Unit i Batch Mode - 2nd Quarter, 1986 4A-2BQ1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION, 62 Unit 2 Batch Mode - 1st Quarter, 1986 4A-2BQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION, 76 Unit 2 Batch Mode - 2nd Quarter, 1986 4B CLASSIFICATION OF ATEOSPHERIC STABILITY 90 5 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS 91 PROGRAM, Units 1 &2 6 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS 94 PROGRAM, Units 1 &2 7 LIQUID DISCHARGES NOT MEETING SPECIFIED DETECTION 97 LIMITS, Units 1 &2- 1st Half, 1986 iv

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.C A. INTRODUCTION This semi-annual radioactive release report, for the period January 1 through June 30, 1986, is submitted in accordance with Appendix A of License Nos. NPF-2 and NPF-8. Appendix A will hereinafter be referred to as the' Standard Technical Specifications or STS.

A single submittal is made 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 a summary of hourly meteorological measurements taken during each quarter in the six month

-reporting period. This data appear as joint frequency distributions of wind direction and wind speed by atmospheric l (T stability class. Hourly meteorological data for batch releases E/ are presented for the periods of actual release. All assessments of radiation doses are performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

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B. SUPPLEMENTAL INFORMATIUN FOR EFFLUENT AND WASTE DISPOSAL

/~T 1. Regulatory Limits

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a. Fission and Activation Gases
1. The dose rate from the sito at any time due to noble gases,shall be less than or equal to 500 mrem /yr to the total body and 3000 meem/yrto 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 f~)

( any calendar quarter due to iodines, particulates and radionuclides with half-lives greater than 8 days shall be 1ers 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 op 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 orgap.
3. The dose or dose commitment due to liquid effluents O 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.

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2. Maximum Permissible Concentrations
a. Airborne - The maximum permissible con' centration 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 B, Table II, Column 2.*
  • NOTE: The MPC chosen is the most conservative value of either the soluble or insoluble MPC 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:

rs k_,) 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 l The following noble gases are considered in evaluating 1

gaseous airborne discharge:

Kr-87 Xe-133 Kr-88 Xe-135 Xe-133m Xe-138 O

b 3

Periodic grab samples from plant effluent streams are analyzed by a computerized pulse height analyzer system

(S g ,/ 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 radioactivity released is based on't'he 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 = isotopic calibration factor for isotope i.

i A = concentration of isotope in the grab sample, in i uC1/ml.

m = net monitor, reading associated with the effluent '

stream.

These calibration factors along with the hourly effluent monitor readings are inputs to the laboratory computer

(g where the release rates for individual nuclides are calculated and stored.

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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:

Hn-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. The r 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.

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Continuous Releases: Continuous sampling is performed on the continuous release points (i.e. the Plant Vent Stack, Containment Purge and the Turbine Building Vent).

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'~ 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 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 are considered when evaluating liquid effluents:

Mn-54 I-131 Fe-59 Cs-134 Co-58 Cs-137

("T Cc-141

\-) Co-60 Zn-65 Ce-144 Sr-89 Ho-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 l

chemical separations and counting the separated samples, j Strontium samples are counted on a 2 pi gas flow pro-

portional counter. Iron samples are counted on either
a 2 pi gas flow proportional counter or a liquid scin-tillation counter. Gross beta and gross alpha deter-minations are made using 2 pl gas flow proportional counters. Tritium concentrations are determined by by using liquid scintillation techniques. Dissolved gases I are determined employing grab sampling techniques and l

then counting on the pulse height analyzer.

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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 I composite basis per Table 6.

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l UNIT # 1 l 1986

5. Batch Release
a. Liquid Quarter i Quarter 2
1. Number of batch releasest 80 146
2. Total time period for releases: 6672 min. 11914 min.
3. Maximum time period for a release: 157 min. 117 min.
4. Average time period for a release: 83 min. 82 min.
5. Minimum time period for a release: 60 min. 31 min.
6. Average stream flow during periods of release-of effluent into a *8.54E3 efs *3.98E3 cfs flowing streams
b. Gaseous Quarter 1 Quarter 2
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.

S. 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 l

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  • Average River Flow Rate, taken at Walter F. George Lock and Dam, located 30.7 miles above Farley Nuclear Plant.

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i UNIT # 2 1986

5. Batch Release
a. Liquid Quarter i Quarter 2
1. Number of batch releases: 62 117
2. Total time period for releases: ,5306 min. 10207 min.
3. Maximum time period for a release: 107 min. 150 min.
4. Average time period for a release 86 min. 87 min.
5. Minimum time period for a release: 75 min. 65 min.
6. Average stream flow during periods of release of effluent into a *8.54E3 cfs *3.98E3 cfs flowing stream:
6. Gaseous Quarter i Quarter 2
1. Number of releases: 2 6
2. Toi.al time period for releases: 1080 min. 3049 min.
3. Maximum time period for a releases 660 min. 784 min.
4. Average time period for a release: 540 min. 508 min.
5. Minimum time period for a release: 420 min. 405 min.
6. Abnormal Releases
a. Liquid
1. Number of releases: None l
2. Total activity released: N/A l

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b. Gaseous
1. Number of releases: None
2. Total activity released: N/A Average River Flow Rate, taken at Walter F. George Lock 1

l and Dam, located 30,7 miles above Farley Nuclear Plant.

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3 7. Estimate of Total Error

'N- 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:

O 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%.

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s UNIT # 1

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8. Solid Waste See Table 3
9. Radiological 'mpact On Man
a. Water Related Exposure Pathways ist Quarter 2nd Quarter Total Body = 3.5E-03 mrem 1.2E-02 mrem Bone = 1.9E-03 mrem 7.7E-03 mrem Liver = 4.7E-03' mrem 1.9E-02 mrem .

Thyroid = 1.4E-03 mrem 3.2E-03 mrem Kidney - 2.3E-03 mrem 5.9E-03 mrem

, Lungs = 2.3E-03 mrem 1.1E-02 mrem GI Tract = 6.7E-03 mrem 1.6E-02 mrem

b. Gaseous F. elated Exposure Pathways ist Quarter . 2nd Quarter Total Body = 2.2E-02 mrem 1.7E-02 mrem Skin = 3.5E-02 mrem 3.8E-02 mrem
c. Particulate and Iodine 1st Quarter 2nd Quarter Organ Dose = 1.6E-02 mrem 4.2E-03 mrem 9

UNIT # 2 1986

8. Solid Waste See Table 3
9. Radiological Impact'On Man
a. Water Related Exposure Pathways ist Quarter 2nd Quarter Total Body = 3.2E-03 mrem 3.8E-03 mrem Bone = 4.2E-02 mrem 4.0E-03 mrem Liver = 4.3E-03 mrem 7.9E-03 mrem
  • Thyroid = 2.2E-03 mrem 2.9E-03 mrem Kidney = 2.6E-03 mrem 2.3E-03 mrem O Lungs = 3.5E-03 mrem 8.2E-03 mrem GI Tract = 6.3E-03 mrem 5.3E-03 mrem
b. Gaseous Related Exposure Pathways ist Quarter . 2nd Quarter Total Body = 9.4E-03 mrem 1.2E-02 mrem f Skin = 1.7E-02 mrem 3.3E-02 mrem
c. Particulate and Iodine l

l 1st Quarter 2nd Quarter

! Organ Dose = 5.7E-03 mrem 4.9E-03 mrem i

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10. Meteorological Data See Table 4A, "Cumulative Joint Frequency Distribution".

Continuous Release Mode:

1st Quarter, 1986  : 4A-CQ1 2nd Quarter, 1986  : 4A-CQ2 Batch Release Mode (Units 1&2):

1st Quarter, 1986  : 4A-1BQ1 & 4A-2BQ1 2nd Quarter, 1986  : 4A-1BQ2 & 4A-2BQ2

11. Minimum Detectable Concentration (MDC)

Detectable limits 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 HDC 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.

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'i TABLE 1A-1Q1 GASEOUS. EFFLUENTS--SUMMATION OF ALL RELEASES Farley Unit 1 - 1st Quarter, 1986 UNITS QTR 1 Est Error A. Fission & activation gases:

1. Total release Ci 1.51E 02 1.24E 01
2. Average release rate -

uCi/sec 1.95E 01 .

3. % of Technical Specification  % 8.54E-04*

% 1.52E-03**

B. Iodines

1. Total iodint-131 Ci 2.02E-05 5.55E-06
2. Average relsese rate uCi/sec 2.59E-06
3. % of Technical Specification  % 1.50E-05***

C. Particulates ,

1. Particulates with T1/2>8 days Ci 4.56E-06 1.79E-06
2. Average release rate uCi/sec 5.87E-07
3. % of Technical Specification  % 1.26E-06***
4. Gross alpha radioactivity Ci 0.00E 00 D. Tritium
1. Total release Ci 5.09E 01 3.12E-01
2. Average release rate uCi/sec 6.54E 00
3. % of Technical Specification  % 1.15E-03***
  • Whole body limit (<500 mrem /yr)

} **: Extrem. limit (<3000 mrem /yr) g,j ***: % of 1500 mrem /yr for all 19 isotopes 12

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TABLE 1A-1Q2 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES Farley Unit 1 - 2nd Quarter, 1986 UNITS QTR 2 Est Error A. Fission & activation gases:

1. Total release C1 2.40E 02 2.32E 01
2. Average release rate -

uCi/sec 3.05E 01 ,

3. % of Technical Specification  % 6.77E-04*

% 1.36E-03**

B. Iodines

1. Total iodine-131 C1 2.29E-05 5.71E-06
2. Average release rate uCi/sec 2.91E-06
3. % of Technical Specification  % 1.69E-05***

C. Particulates .

1. Particulates with T1/2>8 days Ci 5.18E-06 1.94E-06
2. Average release rate uCi/sec 6.59E-07
3. % of Technical Specification  % 6.91E-09***
4. Gross alpha radioactivity Ci 0.00E 00 I

D. Tritium

1. Total release Ci 1.55E 01 1.40E-01
2. Average release rate uCi/sec 1.97E 00
3. % of Technical Specificatioc,  % 3.47E-04***

t

  • Whole body limit (<500 mrem /yr)
    • Extrem. limit (<3000 mrem /yr)

( ***: % of 1500 mrem /yr for all 19 isotopes 13

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TABLE 1A-2Q1 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES Farley Unit 2- 1st Quarter, 1986 UNITS QTR 1 Est Error A. Fission & activation gases:

1. Total release C1 2.04E 02 1.17E 01
2. Average release rate '

cOi/sec 2.62E 01 .

3.  % of Technical Specification 4 9.13E-04*

% 1.62E-03**

[)

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B. Iodines

1. Total iodine-131 Ci 7.97E-06 6.94E-07
2. Average release rate uCi/sec 1.02E-06
3.  % of Technical Specification  % 5.93E-06***

C. Particulates .

1. Particulates with T1/2>8 days Ci 6.23E-08 1.88E-08
2. Average release rate uCi/sec 8.01E-09
3.  % of Technical Specification  % 4.64E-08***
4. Gross alpha radioactivity Ci 0.00E 00 D. Tritium
1. Total release Ci 2.05E 01 1.98E-01
2. Average release rate uCi/sec 2.64E 00
3. \ of Technical Specification  % 4.81E-04***
  • Whole body limit (<500 mrem /yr)

O' **: Extrem. limit (<3000 mrem /yr)

      • \ of 1500 mrem /yr r3r all 19 isotopes 14

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TABLE 1A-2Q2 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES Farley Unit 2 - 2nd Quarter, 1986 UNITS QTR 2 Est Error A. Fission & activation gases:

1. Total release .

Ci 1.13E 03 1.88E 01

2. Average release rate uCi/sec 1.44E 02 '
3. % of Technical Specification  % 1.85E-03*

% 4.32E-03**

B. Iodines

1. Total iodine-131 Ci 8.80E-04 2.19E-05
2. Average release rate uCi/sec 1.12E-04
3. % of Technical Specifica'.'.on  % 6.48E-04***

C. Particulates .

1. Particulates with T1/2>8 days Ci 4.12E-06 1.18E-06
2. Average release rate uC1/sec 5.24E-07
3. % of Technical Specification  % 2.56E-07***
4. Gross alpha radioactivity Ci 0.00E 00 D. Tritium
1. Total release Ci 2.05E 01 6.31E-01
2. Average release rate uCi/sec 2.61E 00
3. % of Technical Specification  % 4.59E-04***

f- *: Whole body limit (<500 mrem /yr)

( j **: Extrem. limit (<3000 mrem /yr)

      • % of 1500 mrem /yr for all 19 isotopes 1

15

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%J

) TABLE 1B-1Q1 GASEOUS EFFLUENTS--ELEVATED RELEASE Farley Unit 1 -

1st Quarter, 1986 CONTINUOUS BATCH Mode Mode Nuclides Released Unit QTR# 1 QTR# 1

1. Fission gases Ar-41 Ci 1.11E 01 0.00E 00 Xe-138 Ci 0.00E 00 0.00E 00 Kr-87 Ci 3.80E-01 0.00E 00 Kr-85M Ci 8.68E-02 0.00E 00 Xe-135 Ci 1.60E 01 0.00E 00 Xe-133M Ci 0.00E 00 0.00E 00 Kr-88 Ci 3.04E-01 0.00E 00 '

Xe-133 Ci 1.16E 02 0.00E 00 Total for period Ci 1.44E 02 0.00E 00

2. Iodines

()

C I-133 I-131 C1 Ci 1.53E-08 1.80E-05 0.00E 00 0.00E 00 Total for period Ci 1.80E-05 0.00E 00

3. Particulates 4

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 Ba-140 Ci 9.92E-07 0.00E 00

'

  • I-133 Ci 0.00E 00 0.00E 00 I-131 C1 1.43E-06 0.00E 00

. Ce-141 C1 1.83E-06 0.00E 00 Other 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 4.25E-06 0.00E 00

-~g

  • Isotope with half-life less than 8 days d

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A TABLE 1B-1Q2 GASEOUS EFFLUENTS--ELEVATED RELEASE Farley Unit 1 -

2nd Quarter,.1986 CONTINUOUS BATCH Mode Mode Nuclides Released Unit QTR# 2 QTR# 2

1. Fission gases Ar-41 C1 5.57E 00 0.00E 00 Kr-85 Ci 3.62E-01 0.00E 00 Xe-138 Ci 0.00E 00 0.00E 00 Kr-87 Ci 0.00E 00 0.00E 00 Xe-135 C1 1.42E 01 0.00E 00 Xe-133M Ci 0.00E 00 0.00E 00 Kr -

Ci 7.67E-03 0.00E 00 ,

Xe-133 Ci 2.13E 02 0.00E 00 Total for period Ci 2.33E 02 0.00E 00

2. Iodines I-133 Ci 6.70E-07 0.00E 00 I-131 C1 2.22E-05 0.00E 00 Total for period Ci 2.29E-05 0.00E 00
3. Particulates

0.00E 00 0.00E 00 Co-60 -

Ci O.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 Ce-144 Ci 5.05E-06 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 Other 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 5.05E-06 0.00E 00
  • Isotope with half-life less than 8 days 17

[D TABLE 1B-2Q1 V

GASEOUS EFFLUENTS--ELEVATED RELEASE Farley Unit 2- 1st Quarter, 1986 CONTINUOUS BATCH Mode -Mode Nuclides Released Unit QTR# 1 QTR# 1

1. Fission gases Ar-41 C1 1.35E 01 0.00E 00 Xe-137 Ci 0.00E 00 2.09E-02 Kr-85 Ci 0.00E 00 1.45E 00 Xe-138 Ci 0.00E 00 0.00E 00 Kr-87 Ci 0.00E 00 0.00E 00 Kr-85M Ci 0.00E 00 2.87E-02 Xe-135 Ci 5.69E 00 2.38E-01 Xe-133M -

Ci 1.06E-01 1.99E-01 .

Kr*88 Ci 0.00E 00 1.06E-02 Xe-131M Ci 4.94E-01 8.01E-01 Xe-133 Ci 1.47E 02 2.77E 01

_ Total for period C1 1.66E 02 3.05E 01 k_. 2. Iodines I-133 Ci 2.90E-07 0.00E 00 I-131 Ci 7.71E-06 0.00E 00 Total for period Ci 8.00E-06 0.00E 00

3. Particulates ,
  • Mo-99 Ci 0.00E 00 0.00E 00 Ci Co-60 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 6.11E-08 0.00E 00 Ce-141 Ci 0.00E 00 0.00E 00 Other Ci 0.00E 00 0.00E 00 Sr-89 Ci 0.00E 00 0.00E 00 ,

Ci Sr-90 0.00E 00 0.00E 00 Total for period Ci 6.11E-08 0.00E 00

)

  • Isotope with half-life less than 8 days 18

TABLE 1B-2Q2 GASEOUS EFFLUENTS--ELEVATED RELEASE (v) Farley Unit 2 -

2nd Quarter, 1986' i CONTINUOUS BATCM Mode --

Mode Nuclides Released Unit QTR# 2 QTR# 2

1. Fission gases Ar-41 Ci 3.21E 00 0.00E 00 Kr-85 Ci 0.00E 00 5.46E 00 Xe-138 Ci 0.00E 00 0.00E 00 Kr-87 Ci 0.00E 00 1.37E-03 Kr-85M C1 1.38E 00 0.00E 00 Xe-135 Ci 1.69E 01 1.44E-01 Xe-133M Ci 1.40E 01 2.93E 00 Kr-88 Ci 0.00E 00 0.00E 00 Xe-131M '

Ci 0.00E 00 3.14E 00 Xe-133 Ci 7.22E 02 3.41E 02 -

Total for period Ci 7.57E 02 3.53E 02

2. Iodines I-133 Ci 1.37E-05 2.31E-08 1

I-131 Ci 8.60E-04 2.75E-08 Total for period Ci 8.73E-04 5.06E-08

3. Particulates
  • Mo-99 Ci 6.86E-10 0.00E 00 Co-60 Ci . 1.89E-07 6.75E-09 Zn-65 Ci 2.35E-10 0.00E 00 Fe-59 Ci 1.48E-10 0.00E 00 Mn-54 Ci 8.86E-11 0.00E 00

{ Ce-144 Ci 4.99E-10 0.00E 00 Co-58 Ci 3.68E-06 0.00E 00 Zr-95 Ci 1.48E-10 0.00E 00 Cs-137 Ci 1.60E-07 0.00E 00 Cs-134 Ci 9.19E-11 0.00E 00 ba-140 C1 1.75E-10 0.00E 00 l

  • I-133 Ci 1.41E-10 2.31E-08 I-131 C1 1.10E-10 2.75E-08 Cr-51 Ci 7.77E-10 0.00E 00 Ce-141 C1 1.00E-10 0.00E 00 Other Ci 0.00E 00 0.00E 00 Sr-89 Ci 6.71E-12 0.00E 00 Sr-90 C1 4.92E-12 0.00E 00 Total for period Ci 4.03E-06 5.73E-08
  • Isotope with half-life less than 8 days i

19

TABLE 1C-1Q1 GASEOUS EFFLUENTS--GROUND RELEASE Farley Unit 1 - 1st Quarter, 1986 CONTINUOUS BATCH Mode -' Mode Nuclides Released Unit QTR# 1 QTR# 1

1. Fission gases Ar-41 Ci 5.55E-01 0.00E 00 Xe-138 Ci 0.00E 00 0.00E 00 Kr-87 Ci 2.15E-02 0.00E 00 Kr-85M Ci 5.68E-03 0.00E 00 Xe-135 Ci 8.08E-01 0.00E 00 Xe-133M Ci 0.00E 00 0.00E 00 Kr-88 Ci 1.34E-02 0.00E 00 Xe-133 Ci 6.00E 00 C.00E 00 Total for period Ci 7.40E 00 0.00E 00
2. Iodines I-133 C1 1.00E-09 0.00E 00 I-131 Ci 2.13E-06 0.00E 00 O Total-for period Ci 2.13E-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 Ba-140 Ci 5.89E-08 0.00E 00
  • I-133 Ci 0.00E 00 0.00E 00 l I-131 Ci 5.97E-08 0.00E 00
Ce-141 Ci 1.96E-07 0.00E 00 i

Other 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 3.15E-07 0.00E 00

  • Isotope with half-life less than 8 days i

O 20

TABLE 1C-1Q2

) GASEOUS EFFLUENTS--GROUND RELEASE Farley Unit 1 - 2nd Quarter, 1986-CONTINUOUS

BATCH Mode Mode Nuclides Released Unit QTR# 2 QTR# 2

1. Fission gases Ar-41 Ci 2.08E-01 0.00E 00 Kr-85 Ci 1.65E-02 0.00E 00 Xe-138 Ci 0.00E 00 0.00E 00 Kr-87 Ci 0.00E 00 0.00E 00 Xe-135 Ci 4.44E-01 0.00E 00 Xe-133M Ci 0.00E 00 0.00E 0Q Kr-88 Ci 3.50E-04 0.00E 00 Xe-133 Ci 6.18E 00 0.00E 00 Total for period .

Ci 6.85E 00 0.00E 00 ,

2. Iodines I-133 C1 4.87E-08 0.00E 00 I-131 Ci 6.49E-07 0.00E 00 O Total for period Ci 6.97E-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 Ce-144 Ci 1.29E-07 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 Other Ci 0.00E 00 0.00E 00 Sr-89 C 's 0.00E 00 0.00E 00 Sr-90 Ci 0.00E 00 0.00E 00 Total for period Ci 1.29E-07 0.00E 00
  • Isotope with half-life less than 8 days O

< 21

TABLE 1C-2'Q1 (3 j GASEOUS EFFLUENTS--GROUND RELEASE Farley Unit 2- 1st Quarter, 1986 CONTINUOUS BATCH Mode Mode Nuclides Released Unit QTR# 1 QTR# 1 1

1. Fission gases Ar-41 Ci 6.33E-01 0.00E 00 Xe-137 Ci 0.00E 00 8.29E-04 Kr-85 Ci 0.00E 00 5.53E-02 l Xe-138 Ci 0.00E 00 0.00E 00 Kr-87 . Ci 0.00E 00 0.00E 00 Kr-85M Ci 0.00E 00 1.14E-03 Xe-135 Ci 2.03E-01 9.47E-03 Xe-133M Ci 5.47E-04 7.88E-03 Kr-88 Ci 0.00E 00 4.22E-04 Xe-131M Ci 2.55E-03 3.14E-02
  • Xe-la3 Ci 5.18E 00 1.09E 00 Total for period Ci 6.02E 00 1.20E 00
2. Iodines 0 I-133 I-131 Ci Ci 1.21E-08 2.55E-07 0.00E 00 0.00E 00 Total for period C1 2.67E-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 l
  • I-133 Ci 0.00E 00 0.00E 00 I-131 Ci 1.24E-09 0.00E 00 Ce-141 Ci 0.00E 00 0.00E 00 Other 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 C1 1.24E-09 0.00E 00
  • Isotope with half-life less than 8 days 22

TABLE 1C-2Q2

('O

_ ,/ GASEOUS EFFLUENTS--GROUND RELEASE Farley Unit 2 -

2nd Quarter, 1986 CONTINUOUS BATCH Mode ' Mode Nuclides Released Unit QTR# 2 QTR# 2

1. Fission gases Ar-41 Ci 4.53E-02 0.00E 00 Kr-85 Ci 0.00E 00 5.56E-02 Xe-138 Ci 0.00E 00 0.00E 00 Kr-87 Ci 0.00E 00 5.50E-06 Kr-85M Ci 7.34E-02 0.00E 00 Xe-135 Ci 5.36E-01 5.27E-04 Xe-133M Ci 3.72E-01 1.64E-02 Kr-88 Ci 0.00E 00 0.00E 00 Xe-131M '

Ci 0.00E 00 1.24E-02 Xe-133 Ci 1.93E 01 1.88E 00 '

Total for period Ci 2.04E 01 1.96E 00

2. Iodines

("

(_) I-133 Ci 9.20E-08 1.26E-09 "

I-131 Ci 2.07E-05 1.35E-09 Total for period Ci 2.08E-05 2.62E-09

3. Particulates
  • Mo-99 Ci 1.62E-11 0.00E 00 Co-60 Ci - 3.75E-09 8.07E-11 Zn-65 Ci 5.54E-12 0.00E 00 Fe-59 Ci 3.50E-12 0.00E 00 Mn-54 Ci 2.09E-12 0.00E 00 Ce-144 C1 1.18E-11 0.00E 00 Co-58 Ci 4.31E-08 0.00E 00  ;

Zr-95 Ci 3.49E-12 0.00E 00 Cs-137 Ci 3.17E-09 0.00E 00 Cs-134 Ci 2.17E-12 0.00E 00 Ba-140 Ci 4.13E-12 0.00E 00

  • I-133 Ci 3.34E-12 1.31E-09 I-131 C1 2.60E-12 1.40E-09 Cr-51 Ci 1.84E-11 0.00E 00 Ce-141 Ci 2.36E-12 0.00E 00 Other Ci 0.00E 00 0.00E 00 Sr-89 C1 1.58E-13 0.00E 00 Sr-90 Ci 1.16E-13 0.00E 00 Total for period Ci 5.01E-08 2.79E-09 O
  • Isotope with half-life less than 8 days 23

TABLE 2A-1

/~T

(- ) _ LIQUID EFFLUENT--SUMMATION OF ALL RELEASES Farley Unit 1 -

1st Half, 1986 UNIT Qtr 1 Qtr 2-A. Fission and Activation Products ,,

1. Total release Note (1) Ci 2.75E-02 2.56E-02
2. Average diluted concentration during period Note (2) uCi/ml 1.45E-09 1.35E-09
3. Percent of applicable limit during Period Note (2)  % 7.19E-04 8.63E-03 B. Tritium
1. Total release Note (1) Ci 2.62E 02 1.44E 02
2. Average diluted concentration during period Note (2) uCi/ml 1.38E-05 7.59E-06

. 3. Percent of applicable limit during period Note (2)  % 4.60E-01 2.53E-01 C. Dissolved and Entrained Gases

1. Total release Note (1) Ci 5.46E-01 5.14E-O'2
2. Average diluted concentration during period Note (2) uCi/ml 2.88E-08 2.71E-09
3. Percent of applicable limit during period Note (2)  % 1.44E-02 1.35E-03 O* .

D. Gross Alpha Radioactivity Total release Note (1) Ci 4.72E-07 0.00E 00 E. Volume of Waste Water Note (3)

1. WMT liters 1.16E 06 2.17E 06
2. SGBD and Turbine Bldg Sumps liters 5.81E 07 6.51E 07
3. Liquid Radioactive Effluent' TOTAL Note (4) liters 5.92E 07 6.73E 07 F. Volume of Dilution Water during Quarter liters 1.47E 10 1.55E 10 NOTE:

(1) Steam Generator Blowdown and Turbine Building Sump release curie amounts and doses vare measured and are included in these totals and in table 2B-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 disenarge (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.

l %

24

TABLE 2A-2 (7-

\'

)

LIQUID EFFLUENT--SUMMATION OF ALL RELEASES Farley Unit >2 - 1st Half, 1986 UNIT Qtr i Qtr 2 A. Fission and Activation Products --

1. Total release Note (1) Ci 2.15E-02 2.15E-02
2. Average diluted concentration

.,during period Note (2) uCi/ml 6.16E-09 1.45E-09

3. Percent of applicable limit during period Note (2) \ 1.45E-03 1.16E-02 B. Tritium
1. Total release Note (1) Ci 2.19E 02 1.66E 02
2. Average diluted concentration during Period No;e (2) uCi/ml 6.27E-05 1.12E-05
3. Percent of applicable limit during period Note (2)  % 2.09E 00 3.75E-01 C. Dissolved and Entrained Gases 6
1. Total release Note (1) Ci 6.49E-01 1.05E-01
2. Average diluted concentration during period Note (2) uCi/ml 1.86E-07 7.08E-09
3. Percent of applicable limit

[s) during period D. Gross Alpha Radioactivity Note (2)  % 9.29E-02 3.54E-03 Total release Note (1) Ci 0.00E 00 0.00E 00 E. Volume of Waste Water Note (3)

1. WMT liters 9.20E 05 1.72E 06
2. SGBD and Turbine Bldg Sumps, liters ~

2.95E 07 7.65E 07

3. Liquid Radioactive Effluent TOTAL Note (4) liters 3.04E 07 7.83E 07 F. Volume of Dilution Water during Quarter liters 1.32E 10 1.53E 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.

O V

25

TABLE 2B-1B fh

\,) '

LIQUID EFFLUENTS--BATCH Farley Unit 1 -

1st Half, 1986 Nuclides

~~

Released Unit .

Qtr 1 Qtr 2 Sr-89 Ci 0.00E 00 -0.00E 00 Sr-90 Ci 0.00E 00 0.00E 00 Fe-55 Ci 2.32E-02 4.60E-03 Co Ci 0.00E 00 0.00E 00 Ce-144 Ci 0.00E 00 0.00E 00 Tc-99M - Ci 0.00E 00 0.00E 00 Ce-141 Ci 0.00E 00 2.10E-06 Np-239 Ci 0.00E 00 0.00E 00 Cr-51 Ci 3.07E-05 1.65E-03 I-131 Ci 1.59E-05 4.22E-04 r Ru-103 Ci 1.44E-06 6.80E-07 I-133 Ci 0.00E 00 2.76E-06 Ba-140 Ci 0.00E 00 5.78E-06 As-76 Ci 0.00E 00 0.00E 00 Cs-134 Ci 3.32E-05 2.29E-04 Ru-106 Ci 1.04E-04 5.61E-06 Cs-137 Ci 1.43E-04 4.45E-04

  • s Mo-99 Ci 1.93E-05 1.50E-06 g Zr-95 Ci 8.13E-06 1.06E-04 Nb-95 Ci 1.22E-04 2.57E-04 I-132 Ci 0.00E 00 2.68E-06 Co-58 Ci 7.00E-05 6.15E-03 Cs-136 Ci 3.75E-06 0.00E 00 Mn-54 Ci 4.78E-05 3.75E-04 Ag-110M Ci 4.13E-04 1.49E-04 Sr-91 Ci . 8.44E-06 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 3.84E-04 i

Co-60 Ci 1.34E-03 2.54E-03 Na-24 Ci 1.49E-06 0.00E 00 La-140 Ci 4.65E-06 9.61E-05 Cu-64 Ci 0.00E 00 0.00E 00 Sb-124 Ci 4.11E-07 7.36E-06 Te-132 Ci 0.00E 00 3.37E-06 Sb-125 C1 1.85E-03 4.76E-03 Zr-97 Ci 0.00E 00 0.00E 00 TOTALS Ci 2.75E-02 2.22E-02 Xe-133 Ci 5.40E-01 5.13E-02 Xe-135 Ci 5.91E-03 1.53E-04 TOTALS Ci 5.46E-01 5.15E-02

)

H-3 Ci 2.62E 02 1.44E 02 26

~

TABLE 2B-2B p

LIQUID EFFLUENTS--BATCH Farley Unit 2- 1st Half, 1986 ,

Nuclides

Released Unit Qtr 1 Qtr 2

---- ---------- ------a---

Sr-89 Ci 0.00E 00 0.00E 00 Sr-90 Ci 0 00E 00 0.00E 00 Fe-55 Ci 1.78E-02 8.71E-03 Co-57 Ci 0.00E 00 0.00E 00 Ce-144 Ci 0.00E 00 0.00E 00 Tc-99M 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 Cr-51 Ci 0.00E 00 3.65E-04 I-131 Ci 4.28E-06 4.89E-04 Ru-103 Ci 0.00E 00 4.08E-06 I-133 Ci 0.00E 00 0.00E 00 Ba-140 Ci '

0.00E 00 0.00E 00 As-76 Ci 2.92E-06 0.00E 00 '

Cs-134 Ci 0.00E 00 0.00E 00 Ru-106 Ci 6.78E-06 0.00E 00 Cs-137 Ci 0.00E 00 9.34E-06 ,

Mo-99 Ci 2.21E-05 0.00E 00

)

, Zr-95 Ci 0.00E 00 4.01E-07 Nb-95 Ci 7.87E-05 2.17E-05 I-132 Ci 0.00E 00 2.70E-05 Co-58 C1 1.74E-05 3.11E-03 Cs-136 Ci 9.22E-06 0.00E 00 Mn-54 Ci 6.48E-06 9.46E-06 Ag-110M Ci 3.52E-04 3.95E-05 Sr-91 Ci . 0.00E 00 0.00E 00 Zn-65 Ci 3.05E-06 3.00E-07 I-135 Ci 0.00E 00 0.00E 00 Fe-59 C1 1.46E-06 6.08E-04 Co-60 Ci 5.40E-04 4.95E-04 Cu-64 Ci 0.00E 00 2.78E-04 Na-24 Ci 0.00E 00 1.68E-06 La-140 Ci 0.00E 00 1.565-05 Sb-124 Ci 4.82E-06 1.65E-04 Sb-125 C1 2.64E-03 6.50E-03 Te-132 Ci 0.00E 00 8.55E-06 TOTALS C1 2.14E-02 2.09E-02 Xe-133 Ci 6.49E-01 1.04E-01 ye-135 C1 1.86E-04 2.42E-04 TOTALS Ci 6.49E-01 1.04E-01 H-3 Ci 2.18E 02 1.64E 02 27

4

. TABLE 2B-1C

.g j'} - LIQUID EFFLUENTS--CONTINUOUS Farley Unit.1 -

1st Half, 1986

~~

Nuclides Released ~ -

Unit Qtr 1- Qtr-2 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 3.44E-03 Zn-65 Ci O.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 3.44E-03 Xe-133 Ci 0.00E 00 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 0.00E 00 0.00E 00 H-3 C1 1.95E-02 0.00E 00 l 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, i 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).

O 28

TABLE 2B-2C

'/ 4 LIQUID EFFLUENTS--CONTINUOUS hs/ Farley Unit 2 - 1st Half,-1986 Nuclides --

Released Unit Qtr 1 Qtr 2 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 7.89E-05 3.34E-05 Mo-39 Ci 0.00E 00 0.00E 00 Zr-95 Ci 0.00E 00 0.00E 00 Nb-95 Ci 0.00E 00 'O.00E 00 Co-58 Ci 0.00E 00 4.30E-04 Mn-54 Ci 0.00E 00 2.89E-05 Zn-65 Ci , 0.00E GO 0.00E 00 I-135 Ci 0.00E 00 0.00E 00 i Fe-59 Ci 0.00E 00 0.00E 00 Co-60 Ci 0.00E 00 1.11E-04 I-131 Ci 0.00E 00 0.00E 00 I-133 Ci 0.00E 00 0.00E 00 0 Co-57 Fe-55 Ag-110M Ci Ci .

Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 TOTALS -

Ci 7.89E-05 6.03E-04 Xe-133 Ci ,

0.00E 00 0,00E 00 Xe-135 Ci 0.00E 00 0.00E 00 Kr-87 Ci 0.00E 00 0.00E 00 i Kr-88 Ci 0.00E 00 0.00E 00 TOTALS Ci 0.00E 00 0.00E 00 H-3 Ci 7.17E-01 2.25E 00 I

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).

)

29 .

L

(~)f v

TABLE 3 4

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS ist Half, 1986 SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 4

1. Type of Waste UNITS _ PERIOD Jan.1-June 30 3
a. Spent resins, filter sludges, m 1.609E 01 evaporator bottoms, etc. Ci 3.063E 02 3
b. Dry compressible waste, m 6.008E 01 contaminated. equipment,_etc. Ci 2.010E-01

'( ) c. Irradiated components, control rods, etc.

m Ci None None 3

d. Other m None Ci None
2. Estimate of major nuclide composition ISOTOPES  % ISOTOPES  %
a. H3 0.38 Fe-55 16.00 Co-60 34.73 Co-57 0.18 Co-58 3.73 Sb-125 0.17 Mn-54 7.30 Cs-134 9.80 Cs-137 12.74 l Ni-63 14.81 l
b. H-3 1.56 Sr-90 1.59 Co-60 51.93 Cs-134 5.59 Co-58 9.49 Nb-95 1.26 Mn-54 11.30 Cs-137 10.75 Ni-63

()

3.51 Ce-144 2.84 j Pu-241 0.17 l

l 30

TABLE 3 (con't)

)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS ist Half, 1986 --

Sol'id Waste Disposition 3.

a. Number of Shipments 7
b. Mode of Transportation Chem-Nuclear Transport (2)

Hittman Transport (5) -

c. Destination Chem-Nuclear Systems, Inc.

Barnwell, South Carolina

4. Type of Containers
a. ( 1a ) Type "A" and "B" Packages, Steel Liners, High Integrity t' Containers

)

b. ( lb ) "Strong and Tight" Wooden i Boxes, Metal Boxes, and Steel Drums
5. Solidification Agents
a. ( la ) No solidifications during this period. All items (spent resin and charcoal) that are categorized for item la were shipped dewatered,
b. ( lb ) N/A i

B. IRRADIATED FUEL SHIPMENTS (Disposition)

1. Number of Shipments None
2. Mode of Transportation N/A
3. Destination N/A 1 31 ,

Tcblo 4A-CQ1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION

.() Farley Nuclear Plant - 1st Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 86 ) 3-31-86 STABILITY CLASS: A 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 t

N O O 6 0 0 0 6 NNE O O 2 0 0 0 2 NE O O 1 0 0 0 1 ENE O 2 2 0 0 0 4 E O 1 1 0 0 0 2 ,

{} ESE O O O O O O O SE O O 2 0 0 0 2 SSE O O 1 1 0 0 2 S 0 0 0 1 0 0 1 SSW 0 0 0 0 0 0 0 SW 1 0 0 1 0 0 2 WSW 0 4 2 1 0 0 7 W 0 0 2 5 0 0 7 WNW 0 0 0 2 0 0 2 NW 0 2 2 4 2 2 12 NNW 0 1 4 9 0 0 14 VARIABLE O O O O O O O Total 1 10 25 24 2 2 64 ,

Periods of calm (hours): 0 Hours of missing data: 0 32 1

[ h Tablo 4A-CQ1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION

() Farley Nuclear Plant - 1st Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 86 ) 3-31-86 STABILITY CLASS: A ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 ~)24 TOTAL N O 1 4 0 0 0 5 NNE O 1 0 0 0 .0 1 NE O 1 0 0 0 0 1 ENE O 3 1 0 0 0 4 E O 1 0 0 0 0 1 ESE O O 2 0 0 0 2 SE O O 1 1 0 0 2 SSE O O O 1 0 0 1 S 0 0 0 0 0 0 0 SSW 2 0 0 0 0 0 2 SW i 0 2 1 0 0 4 WSW 1 2 5 0 0 0 8 W 0 1 2 0 0 0 3 WNW 0 0 1 0 0 0 1 NW 0 4 7 8 0 0 19 NNW 0 2 6 2 0 0 10 VARIABLE O O O O O O O Total 4 16 31 13 0 0 64 O Periods of calm (hours): 0 Hours of missing data: 0 33

Tablo 4A-CQ1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION (q_j Farley Nuclear Plant - 1st Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 86 ) 3-31-86 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 O 3 8 3 0 0 14 NNE O 1 6 1 0 0 8 NE O 2 5 1 0 0 8 ENE O 5 3 4 0 0 12 E O 3 4 0 0 0 7 0 0 0 7

(^3 ESE O 3  %

v SE O 4 2 0 0 0 6 SSE 1 0 3 5 0 0 9 S 0 1 0 2 0 0 3 SSW 0 0 1 0 0 0 1 SW 0 0 0 0 0 0 0 WSW 0 3 7 1 1 0 12 W 0 0 1 6 0 0 7 WNW 0 0 3 4 0 0 7 NW 0 2 6 8 0 1 17 NNW 0 1 5 3 0 0 9 VARIABLE O O O O O O O i

l Total 1 28 58 38 1 1 127 i ( Periods of calm (hours): 0 Hours of missing data: 0 34 1

l Tablo 4A-CQ1 l

l CUMULATIVE JOINT FREQUENCY DISTRIBUTION l

() Farley Nuclear Plant - 1st Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE CONTINUOUS PERIOD OF RECORD: 1 86 } 3-31-86 STABILITY CLASSt B ELEVATION: 10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O 5 2 0 0 0 7 NNE O 7 0 0 0 0 7 NE O 6 5 1 0 0 12 ENE O 5 1 1 0 0 7 E 1 6 3 0 0 0 10

(} ESE O 5 1 0 0 0 6 SE 1 2 2 0 0 0 5 SSE O O 3 5 0 0 8 S 0 2 0 0 0 0 2 SSW 0 0 , 0 0 0 0 0 SW 0 2 1 1 0 0 4 WSW 0 3 7 1 0 0 11 W 0 1 7 0 0 0 8 WNW 0 3 6 0 0 0 9 NW 0 1 13 2 0 0 16

! NNW 0 4 10 1 0 0 15 j VAR *.ABLE O O O O O O O 4 _____________________________________________.____________________

! Total 2 52 61 12 0 0 127 O Periods of calm (hours): 0 Hours of missing datat 0 35

5%*r

' 1. .

Tablo 4A-CQ1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION

~~

(< ) Farley Nuclear Plant - 1st Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 86 ) 3-31-86 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 O 14 3 0 0 0 17 NNE O 9 16 0 0 0 25 ,

NE 1 7 6 0 0 0 14 .

ENE O 8 2 2 0 0 12 E O 5 8 1 0 0 14 .

i

{} ESE O 3 0 0 0 0 3 SE O 4 3 0 0 0 7 SSE O 2 3 2 0 0 7 S 0 1 1 4 0 0 6 SSW 0 2 1 0 0 0 3 SW 0 1 3 0 0 0 4 WSW 1 3 9 2 1 0 16 ,

J W 1 3 8 2 0 0 14 WNW 0 3 7 1 0 0 11 o

NW 0 5 4 2 2 0 13 NNW 0 1 4 4 0 0 9 t

VARIABLE O O O O O O O Total 3 71 78 20 3 0 175  :

O Periods of calm (hours): 0 Hours of missing data 0 36

i I

Table 4A-CQ1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION ,

~

.( Farley Nuclear Plant - 1st Quarter, 1986 i HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 86 ) 3-31-86 STABILITY CLASS: C ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 31 1 0 0 0 32 NNE O 11 0 0 0 0 11 NE 1 12 2 0 0 0 15 ENE O 9 3 1 0 0 13 E O 5 4 0 0 0 9

(} ESE O 1 0 0 0 0 1 SE 1 5 3 1 0 0 10 SSE O 3 3 3 0 0 9 S O 2 0 0 0 0 2 SSW 1 1 1 0 0 0 3 l SW 0 10 3 1 0 0 14 WSW 0 6 4 1 0 0 11 l W 1 7 5 0 0 0 13 1

WNW 0 2 4 3 0 0 9 NW 0 6 6 1 0 0 13 NNW 0 7 3 0 0 0 10

(

VARIABLE O O O O O O O Total 4 118 42 11 0 0 175

("%

%)

Periods of calm (hours): 0 Hours of r.issing data: 0 37 l

l l

l Tabit 4A-CQ1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION i

l

("',T/- Farley Nuclear Plant - 1st Quarter, 1986 1

HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 86 ) 3-31-86 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 2 23 43 4 0 0 72 NNE 5 15 25 0 0 0 45 NE 2 11 23 5 0 0 41 ENE 3 13 18 10 0 0 44 E 2 15 4 0 0 0 21 ESE 3 10 0 0 0 15 p/

L g 2 SE 1 16 5 0 0 0 22 SSE 2 6 9 7 0 0 24 S 2 5 4 19 0 0 30 SSW 4 3 5 11 1 0 24 SW 2 3 17 6 13 1 42

( WSW 5 12 24 9 6 2 58 W 4 13 15 7 0 0 39 WNW 2 12 6 8 0 0 28 l NW 3 15 16 24 7 1 66 l

NNW 5 7 37 29 2 1 81 VARIABLE O 0 0 0 0 0 0 l Total 47 179 253 139 29 5 652 l

l (S) Feriods of calm (hours): 0 Hours of missing data: 0 38 l

4 Table 4A-CQ1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION

-n

\/ Farley Nuclear Plant - 1st Quarter., 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 86 ) 3-31-86 STABILITY CLASS: D ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 10 28 1 0 0 0 39 NNE 5 35 1 0 0 0 41 NE 5 25 12 0 0 0 42 ENE 6 14 14 0 0 0 34 E 7 19 0 0 0 0 26

() ESE 2 9 1 0 0 0 12 SE 2 17 5 0 0 0 24 SSE 4 4 13 13 0 0 34 S 3 3 5 3 0 0 14 SSW 1 2 8 6 0 0 17 SW 12 19 27 19 2 0 79 WSW 7 25 10 2 0 0 44 W 6 11 8 0 0 0 25 WNW 5 11 9 4 0 0 29 l

l NW 13 33 36 11 0 1 94 HNW 6 48 40 4 0 0 98 VARIABLE O O O O O O O Total 94 303 190 62 2 1 652 Periods of calm (hours): 0 Hours of missing data: 0 l

l 39 i

Table 4A-CQ1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION

'T T

\_/ Farley Nuclear Plant - 1st Quarter, 1986 HOURS AT EACH WIND SPEEE AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 86 ) 3-31-86

' 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 2 23 28 2 0 0 55 NNE 2 8 18 0 0 0 28 NE 4 6 7 0 0 0 17 ENE 1 10 7 0 0 0 18 E O 21 9 0 0 0 30

() ESE 1 18 10 0 0 0 29 SE 1 7 15 0 0 0 23 SSE O 6 22 6 0 0 34 S 2 2 18 16 0 0 38 SSW 4 3 13 8 0 0 28 SW 1 6 49 20 1 0 77 WSW 0 11 51 10 0 0 72 W 3 12 24 3 0 0 42 WNW 1 10 20 3 0 0 34 NW 0 5 28 9 0 0 42 NNW 1 4 40 10 0 0 55 VARIABLE O O O O O O O Total 23 152 359 87 1 0 622 O Periods of calm (hours): 0 Hours of missing data: 0 40

i

.73m Table 4A-CQ1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION

() Farley Nuclear Plant - 1st Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 86 ) 3-31-86 STABILITY CLASS: E ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 14 11 0 0 0 0 25 NNE 14 14 0 0 0 0 28 NE 20 8 0 0 0 0 28 ENE. 14 7 0 0 0 0 21 E 16 10 1 0 0 0 27

(~1 ESE 8 12 2 0 0 0 22 V

SE 4 15 17 0 0 0 36 SSE 3 5 20 1 0 0 29 S 1 4 15 0 0 0 20 SSW 2 6 4 1 0 1 14 SW 8 70 40 2 0 0 120 WSW 11 33 5 0 0 0 49 W 17 9 4 0 0 0 30 WNW 17 24 4 0 0 0 45 l

l NW 8 41 11 1 0 0 61 l NNW 12 45 9 1 0 0 67 VARIABLE O O O O O O O

! Total 169 314 132 6 0 1 622 l

l Periods of calm (hours): 0 l Hours of missing data: 0 41 l

1 1

\

.-. - m v

Table 4A-CQ1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley' Nuclear Plant - 1st Quarter, 1986 HOURS AT EACE WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 86 } 3-31-86 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 1 9 5 0 0 0 15 NNE O 6 7 0 0 0 13 NE 1 4 3 0 0 0 8 ENE 1 17 2 0 0 0 20 E 2 14 6 0 0 0 22 ESE 2 15 12 0 0 0 29 SE 1 3 5 0 0 0 9 SSE 2 3 6 0 0 0 11 S 0 1 3 3 0 0 7 SSW 2 0 2 1 0 0 5 SW 1 0 5 2 0 0 8 WSW 1 1 13 0 0 0 15 W 0 6 11 0 0 0 17 WNW 0 2 7 0 0 0 9 NW 1 3 9 4 0 0 17 NNW 0 5 11 1 0 0 17 VARIABLE O O O O O O O Total 15 89 107 11 0 0 222 O Periods of calm (hours): 0 Hours of missing data: 0 42

Tcble 4A-CQ1 CUMULATIVE JOINT. FREQUENCY DISTRIBUTION

() Farley Nuclear Plant -

1st Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 86 ) 3-31-86

. STABILITY CLASS: F ELEVATION:10.0m Wind Speed (mph) at 10,0m level

. Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 33 4 0 0 0 0 37 NNE 17 3 0 0 0 .0 20 NE 13 0 0 0 0 0 13 ENE 14 1 0 0 0 0 15 E 4 4 0 0 0 0 8 ESE 6 4 0 0 0 0 10 SE 2 4 4 0 0 0 10 SSE 2 1 0 0 0 0 3 S 0 1 0 0 0 0 1 SSW 0 1 2 0 0 0 3 SW 4 7 1 0 0 0 12 WSW 5 0 0 0 0 0 13 W 10 7 0 0 0 0 17 WNW 7 1 0 0 0 0 8 l

NW 12 15 0 0 0 0 27 N N',7 21 4 0 0 0 0 25 l

VARIABLE O O O O O O O l Total 150 65 7 0 0 0 222 l

() Periods of calm (hours): 0 Hours of missing data: 0 43 l

Table 4A-CQ1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION

(/ Farley Nuclaar Plant - 1st Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 1 86 ) 3-31-8A 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 4 24 2 0 0 0 30 NNE 1 21 9 0 0 0 31 NE 2 12 15 0 0 0 29 ENE 4 11 9 0 0 0 24 E 2 13 13 0 0 0 28

(} ESE 4 4 12 0 0 0 20 SE 4 4 7 0 0 0 15 l

3SE 2 7 4 1 0 0 14 i

i S 0 3 3 2 0 0 8 l

l SSW 3 1 2 0 0 0 6 l

SW 2 2 0 2 0 0 6 WSW 3 9 3 0 0 0 15 W 6 10 4 0 0 0 20 WNW 2 14 4 0 0 0 20 NW 1 8 6 1 0 0 16 NNW 2 2 12 0 0 0 16 VARIABLE O O O O O O O Total 42 145 105 6 0 0 298 O Periods of calm (hoers): 0 Hours of missing data: 0 l

44 l

h Table 4A-CQ1 l CUMULATIVE JOINT FREQUENCY DISTRIBUTION

(_) 7arley Nuclear Plant - 1st Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE HODE: CONTINUOUS PERIOD OF RECORD: 1 86 ) '3-31-86 UTABILITY CLASS: G ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL

!1 89 3 0 0 0 0 92 NNE 41 1 0 0 0 0 42 NE 21 1 0 0 0 0 22 ENE 9 0 0 0 0 0 9 E 8 0 0 0 0 0 8 (T

%)

ESE 2 0 0 0 O O 2 SE 6 3 0 0 0 0 9 SSE 1 1 0 0 0 0 2 S 0 1 0 0 0 0 1 SSW 3 1 1 0 0 0 5 SW 0 0 0 0 0 0 WSW 3 1 0 0 0 0 4 W 10 2 0 0 0 0 12 WNW 7 1 0 0 0 0 8 i NW 11 1 0 0 0 0 12 l

NNW 64 6 0 0 0 0 70 VARIABLE O O O O O O 0 Total 275 22 1 0 0 0 298

\

l Periods of calm (hours): 0 l Hours of missing data: 0 45

Table 4A-CQ2 l I

CUMULATIVE JOINT FREQUENCY DISTRIBUTION

) Farley Nuclear Plant - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 4 86 ) 6-30-86 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 O 2 2 4 0 0 8 NNE O 6 3 0 0 0 9' NE O 2 5 2 0 0 9 ENE O 3 7 0 0 0 10 E 1 5 6 0 0' O 12 ESE O 8 9 0 0 0 17

SE O 9 15 0 0 0 24 SSE O 4 8 0 0 0 12 S 0 4 6 0 0 0 10 SSW 0 0 4 0 0 0 4 SW 0 10 17 0 0 0 27 WSW 0 4 9 3 0 0 16 l

W 0 0 9 1 0 0 10 WNW 0 0 8 0 0 0 8 NW 0 3 10 4 0 0 17 NNW 0 0 6 6 0 0 12 VARIABLE O O O O O O O Total 1 60 124 20 0 0 205 Periods of calm (hours): 0 Hours of missing data: 0 46 i

Table 4A-CQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION

.(_,,)

Farley Nuclear Plant - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 4 86 ) 6-30-86 STABILITY CLASS: A ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 3 4 1 0 0 0 8 NNE 1 4 0 0 0 0 5 NE O 11 0 0 0 0 11 ENE 2 7 1 0 0 0 10 E 3 8 3 0 0 0 14

/~s ESE 7 14 5 0 0 0 26

d. SE 10 6 1 0 0 0 17 SSE 1 9 1 0 0 0 11 S 5 1 0 0 0 0 6 SSW 5 7 0 0 0 0 12 SW 12 10 6 0 0 0 28 WSW 0 1 7 1 0 0 8 W 0 5 4 0 0 0 9 WNW 1 5 5 0 0 0 11 NW 1 9 6 1 0 0 17 NNW 1 3 5 3 0 0 12 VARIABLE O O O O O O 0 Total 52 104 45 4 0 0 205 Periods of calm (hours): 0 Hours of missing data: 0 47

Table 4A-CQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION I Farley Nuclear Plant - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 4 86 ) 6-30-86 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 0 7 4 0 0 0 11

~

NNE O 10 3 0 0 0 13 NE 1 6 0 1 0 0 8 ENE 2 8 1 0 0 0 11 E O 4 1 0 0 0 5

() ESE 2 6 2 0 0 0 10 SE O 12 1 0 0 0 13 SSE O 7 7 0 0 0 14 S 0 4 5 0 0 0 9 SSW 0 1 3 0 0 0 4 SW 0 7 8 1 0 0 16 WSW 0 9 6 3 0 0 18 W 1 11 5 5 0 0 22 WNW 0 2 5 0 0 0 7 NW 0 10 10 1 0 0 21 NNW i 3 8 3 0 0 15 VARIABLE O O O O O O O Total 7 107 69 14 0 0 197 O Periods of calm (hours): 0 Hours of missing data: 0 48

Table 4A-CQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION O

-t ) Farley Nuclear Plant - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 4 86 ) 6-30-86 STABILITY CLASS: 'B ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 4 6 0 0 0 0 10 NNE 4 7 0 0 0 0 11 NE 2 6 0 0 0 0 8 ENE 3 6 0 0 0 0 9 E 1 7 0 0 0 0 8 ESE 6 5 0 0 0 0 11 SE 11 8 1 0 0 0 20 SSE 4 8 0 0 0 0 12 S 2 0 1 0 0 0 3 SSW 2 4 1 0 0 0 7 SW 7 13 4 1 0 0 25 WSW 3 10 4 0 0 0 17 W 2 6 6 0 0 0 14 WNW 1 12 2 0 0 0 15 NW 1 11 6 1 0 0 19 NNW 4 2 2 0 0 0 8 VARIABLE O O 0 0 0 0 0 Total 57 111 27 2 0 0 197 oriods of calm (hours): 0 Hours of missing data: 0 49

- . .- .. ~ .-

Table 4A-CQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF-RECORD:- 4 86 ) 6-30-86 GTABILITY 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 0 11 1 1 0 0 13 NNE 1 15 2 0 0 0 18 NE 1 10 2 0 0 0 13 ENE 5 8 0 0 0 0 13 E 2 4 1 0 0 0 7 ESE 1 7 2 0 0 0 10 SE 1 8 0 0 0 0 9 SSE 1 5 12 0 0 0 18 S 0 1 4 0 0 0 5 SSW 1 1 2 0 0 0 4 SW 0 5 8 2 0 0 15 WSW 2 6 6 1 0 0 15 W 0 12 9 2 0 0 23 WNW 1 7 4 0 0 0 12 NW 1 9 12 1 0 0 23 NNW 0 16 2 3 0 0 21 VARIABLE O O O O O u 0 Total 17 125 67 10 0 0 219 O' Periods of calm (hours): 0 Hours of missing data: 0 50

Table 4A-CQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION

() Farley Nuclear Plant - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 4 86 ) 6-30-86 STABILITY CLASS: C ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 9 6 1 0 0 0 16 NNE 7 8 1 0 0 0 16 NE 4 5 1 0 0 0 10 ENE. 4 5 1 0 0 0 10 E 7 8 0 0 0 0 15 "T ESE 1 2 0 0 0 0 3 (J 0 0 0 16 SE 9 6 1 SSE 3 6 3 0 0 0 12 S 1 2 2 0 0 0 5 SSW 3 5 2 0 0 0 10 SW 5 2 5 0 0 0 12 WSW 7 6 4 0 0 0 17 W 2 11 8 0 0 1 22 l

WNW 3 9 2 0 0 0 14 NW 6 15 1 1 0 0 23 NNW 6 11 0 1 0 0 18 l

1 VARIABLE O O 0 0 0 0 0 i Total 77 107 32 2 0 1 219 O Periods of calmihours): 0 Hours of missing data: 0 51

Table 4A-CQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION

/"

\,)T Farley Nuclear Plant - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 4 86 ) 6-30-86 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 5 21 3 3 0 0 32 NNE 5 19 5 0 0 0 29 NE 3 11 1 0 0 0 15 ENE 4 11 1 0 0 0 16 E O 8 7 0 0 0 15

/N ESE 3, 9 4 0 0 0 16 U

SE 2 14 10 1 0 0 27 SSE 3 6 11 0 0 0 20 S 1 7 5 0 0 0 13 SSW 1 4 11 9 1 0 26 SW 4 10 33 5 0 0 52 USW 3 15 32 10 0 0 60 W 4 16 13 1 0 0 34 WNW 6 12 7 1 0 0 26 NW 6 20 7 0 0 0 33 NNW 5 13 14 6 0 0 38 VARIABLE O O O O O O O Total 55 196 164 36 1 0 452 O Periods of calm (hours): 0 Mours of missing data: 0 52

Tabic 4A-CQ2 l

l CUMULATIVE JOINT FREQUENCY DISTRIBUTION

() Farley Nuclear Plant - 2nd Quarter, 1986  !

HOURS AT EACH WIND SPEED AND DIRECTION 1

l RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 4 86 ) 6-30-86 STABILITY CLASS: D ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 22 5 1 0 0 0 28 NNE 15

  • 0 0 0 0 23 NE 7 6 0 0 0 0 13 ENE 8 12 0 0 0 0 20 E 8 10 0 0 0 0 18 ESE 8 8 1 0 0 0 17 f').

SE 20 12 1 0 0 0 33 SSE 4 4 1 0 0 0 9 S 5 7 3 2 0 0 17 SSW 10 10 5 4 0 0 29 SW 29 24 21 1 0 0 75 WSW 14 21 3 0 0 0 38 W 14 12 4 0 0 0 30 WNW 7 10 2 0 0 0 19 NW 20 17 5 0 0 0 42 NNW 18 16 7 0 0 0 41 VARIABLE O O O O O O O Total 209 182 54 7 0 0 452

}

Periods of calm (hours): 0 Hours of missing data: 0 53

Table 4A-CQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 2nd Quarter, 1986 (f

HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 4 86 ) 6-30-86 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 1 19 6 0 0 0 26 NNE 4 17 3 0 0 .0 24 NE 5 4 1 0 0 0 10 ENE O 12 4 0 0 0 16 E 4 12 6 1 0 0 23 ESE 3 15 7 0 0 0 25

)

SE 5 18 16 0 0 0 39 SSE 2 13 18 1 0 0 34 S 3 11 9 1 0 0 24 SSW 2 10 2 1 0 0 15 SW 3 24 33 2 0 0 62 WSW 4 44 62 3 0 0 113 W 0 45 43 1 0 0 89 WNW 4 23 16 0 0 0 43 NW 1 18 13 1 0 0 33 NNW 1 10 15 4 0 0 30 VARIABLE O O O O O O O Total 42 295 254 15 0 0 606 O Periods of calm (hours): 0 Hours of missing data: 0 54

g . _ - a l

Table 4A-CQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION

, - Farley Nuclear Plant - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION

' RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 4 86 ) 6-30-86 STABILITY CLASS: E ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 e-12 13-18 19-24 >24 TOTAL N 17 4 0 C 0 0 21 NNE 16 1 0 0 0 0 17 NE 22 5 0 0 0 0 27 ENE 17 4 0 0 0 0 21 E 15 7 1 0 0 2 25 ESE 28 5 0 0 0 0 33

(~ }

1 SE 15 13 3 0 0 0 31 SSE 10 8 2 0 0 0 20 S 13 2 1 0 0 0 16 SSW 16 3 1 0 0 0 20 SW 63 40 5 0 0 0 108 WSW 65 30 3 0 0 0 98 W 37 13 0 0 0 0 50 WNW 24 7 1 0 0 0 32 NW 32 11 1 0 0 0 44 NNW 30 8 5 0 0 0 43 VARIABLE O O O O O O O Total 420 161 23 0 0 2 606 O Periods of calm (hours): 0 Hours of missing data: 0 55

Tcble 4A-CQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Nuclear Plant - 2nd Quarter, 1986 (f

HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 4 86 } 6-30-86 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 15 11 0 0 0 28 NNE 2 4 16 0 0 0 22 NE 1 8 3 0 0 0 12 ENE 1 8 0 0 0 0 9 E 1 4 2 0 0 0 7 0 0 7

{} ESE SE O

1 4

7 13 3 0 0 0 0 21 SSE O 4 13 0 0 0 17 S 2 2 6 2 0 0 12 SSW 2 2 0 1 0 0 5 SW 2 10 7 1 0 0 20 i

WSW 2 18 10 1 0 0 31 W 0 13 21 0 0 0 34 WNW 3 23 17 0 0 0 43 NW 2 9 16 0 0 0 27 NNW 4 13 18 0 0 0 35 VARIABLE O O O O O O O Total 25 144 156 5 0 0 330 t

l l Periods of calm (hours): 0 I Hours of missing data: 0 56 l

l

Table 4A-CQ2 l

1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION l i( ) Farley Nuclear Plant - 2nd Quarter, 1986 HOURS AT EACH WIND SPECD AND DIRECTION RELEASE HODE: CONTINUOUS PERIOD OF RECORD: 4 86 ) 6-30-86 STABILITY CLASS: F ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 23 0 0 0 0 0 23 NNE 14 1 0 0 0 0 15 NE 14 0 0 0 0 0- 14 ENE 12 0 0 0 0 0 12 E 10 1 0 0 0 0- 11 ESE 18 2 0 0 0 0 20 (v~)

SE 7 10 0 0 0 0 17 SSE 7 2 0 0 0 0 9 S 2 1 0 0 0 0 3 SSW 2 2 0 0 0 0 4 SW 14 5 0 0 0 0 19 l WSW 28 5 0 0 0 0 33 W 32 7 0 0 0 0 39 WNW 16 5 0 0 0 0 21 NW 35 5 0 0 0 0 40 NNW 47 3 0 0 0 0 50 l VARIABLF 0 0 0 0 0 0 0 l

Total 281 49 0 0 0 0 330 0 Periods of calm (hours): 0 Hours of missing data: 0 57

Table 4A-CQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION 1( ) Farley Nuclear Plant - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 4 86 ) 6-30-86 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 0 0 0 0 12 NNE 2 9 5 1 0 0 17 NE 2 1 7 0 0 0 10 ENE 1 3 2 0 0 0 6 E 2 5 4 0 0 0 11

() ESE 1 4 4 0 0 0 9 SE 1 6 3 0 0 0 10 SSE 1 3 4 0 0 0 8 S 2 3 1 0 0 0 6 SSW 2 3 0 0 0 0 5 SW 1 7 2 0 0 0 10 WSW 1 6 3 0 0 0 10 W 1 7 1 0 0 0 9 WNW 0 8 2 0 0 0 10 i

NW 3 12 3 0 0 0 18 NNW 3 14 7 0 0 0 24 l VARIABLE O O O O O O O Total 25 101 48 1 0 0 175

O Periods of calm (hours): 0 Hours of missing data: 0 58

. Table SA-CQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION f[) Farley Nuclear Plant - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: CONTINUOUS PERIOD OF RECORD: 4 86 ) 6-30-86 STABILITY CLASS: G ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 47 0 0 0 0 0 47 NNE 22 0 0 0 0 .0 22 NE 7 0 0 0 0 0 7 ENE 6 0 0 0 0 0 6 E 4 0 0 0 0 0 4 ESE 6 0 0 0 0 0 6 SE 3 0 0 0 0 0 3 SSE 1 0 0 0 0 0 1 S 1 0 C 0 0 0 1 SSW 4 0 0 0 0 0 4 SW 5 0 0 0 0 0 5 WSW 5 0 0 0 0 0 5 W 7 0 0 0 0 0 7 WNW 6 1 0 0 0 0 7 NW 18 1 0 0 0 0 19 NNW 31 0 0 0 0 0 31 VARIABLE O O O O O O O Total 173 2 0 0 0 0 175 O

Periods of calm (hours): 0 Hours of missing data: 0 59

- - - ' m m - -

e- , - -,, - -

O e

' TABLE 4A-1BQ1

' CUMULATIVE ~ JOINT-FREQUENCY DISTRIBUTION p Farley Unit 1 - 1st Quarter, 1986 No batch releases were.made during ist Quarter 1986 therefore Cumulative Joint Frequency Distribution tables are.not applicable.

t-4 I

]

j.

n 9

i s

n

?

l l.

l f

i f

I i

@ l k

I l

60

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

. . _ _ . . . _ _ . _ _ . . . . . . . . _ _ . . _ _ _ . _ _ . . _ = - . _ _ _ . . _ - . . . . - . _ _ - . - . _ . - . . _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ .

b TABLE 4A-1BQ2 i

CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley' Unit.'1 - 2nd Quarter, 1986 e

No batch releases were made~during 2nd Quarter 1986 therefore.

Cumulative Joint' Frequency Distribution tables are.not applicable.

4

=

P l

f l

e-i h b i

l@

a i

l i

r L

i h

B l- 61 1

+ - - , - - , - - . _ - - - - - . . , - _ _ . . . , _ - . ,- --- .. ..<---,- =

TABLE 4A-2BQ1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION f- Farley Unit 2'- 1st Quarter, 1986

?%d HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: BATCH PERIOD OF RECORD: - 1 86 ) 3-31-86 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 0 0 0 0 0 0 0 NNE O O O O O O O NE O O O O O O O ENE O O O O O 'O O E O O O O O O O P

ESE 0 0 0 0 0 0 0 SE 'O O O' O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 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 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O Total 0 0 0 0 0 0 0 k

Periods of calm (hours): 0 Hours of missing data: 0 62

, TABLE 4A-2BQ1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION I Farley Unit 2 - 1st Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: BATCH PERIOD OF RECORD: 1 86 ) 3-31-86 STABILITY CLASS: A ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0 0 0 0 0 0 I .

NNE O O O O O -0 0 NE O O O O O O O ENE O O O O O O O E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE O 0 0 0 0 0 0 S 0 0 0 0 0 0 0 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 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O Total 0 0 0 0 0 0 0 Periods of calm (hours): 0 Hours of missing data: 0 63

~ - . . _ ._ .~_ -

TABLE 4A-2BQ1' 1

i CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Unit 2 -

1st Quarter, 1986 i HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: BATCH PERIOD OF RECORD: 1 86 ) 3-31-86 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 O O O O O O O NNE O O O O O O O NE O O O O O O O ENE O O O O O O O E O O O O O O O ESE O O O O O O O O' SE O O O O O O O SSE O O O O O O ,0 S 0 0 0 0 0 0 0 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 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O Total 0 0 0 0 0 0 0 O

Periods of calm (hours): 0 Hours of missing data: 0 64

, s:

  • TABLE '4 A--2 BQ1 .

CUMULATIVE _ JOINT FREQUENCY DISTRIBUTION yw Farley Unit 2- 1st Quarter, 1986

.I HOURS AT EACH WIND SPEED AND DIRECTION-t

~~

-RELEASE MODE: BATCH

' PERIOD OF RECORD:

1 86 i- 3-31-86 STABILITY CLASS: B ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O 0- 0 0 0 0 t.

NNE 0- 0 0 0 0 0 0

'NE O O O O O O O ENE O 0 0 0 0 0 0 E O O O O O O O

, .ESE O O O O O O O

\

SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 C 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O q- Total 0 0 0 0 0 0 0 Periods of calm (hours): C

, Hours of missing data: 0 65

TABLE 4A-2BQ1

.r

. CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Unit 2- 1st Quarter, 1986 >

.J HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: BATCH PERIOD OF RECORD: 1 86 ) 3-31-86 -

STABILITY CLASS: C ELEVATION:45.7m Wir.d Speed (mph) at 45.7m, level Wind Direction' 1-3 4-7 8-12 13-18 19-24 > 24 TOTAL N 0 0 0 0 0 0 0 NNE O O O O O O O NE O O O O O O O ENE 0 0 0 0 0 0 -0 E O O O O O O O A ESE O O O O O O O V SE O O O O O O O i

SSE O O O O O O O S O O O O O O O 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 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O Tctal 0 0 0 0 0 0 0 O

Periods of calm (hours): 0 Hours of missing data: 0 ES P

-r_.w--- , ,,- . - - , - -- . , . , , . . ---v

. TABLE 4A-2BQ1 CUMULATIVE JOIN,T FREQUENCY DISTRIBUTION y Farley Unit 2 - 1st Quarter, 1986

- 'Q. .

HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: BATCH PERIOD OF RECORD: 1 86 ) 3-31-86 STABILITY CLASS: C ELEVATION:10.0m Wind Speed (mph) at 10.0m, level Wind Direction- 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O O O O O O NNE O O O O O O O NE O O O O O O O ENE O O O O O O O E ,

0 0 'O O O O O ,

ESE O O O O O O O Ors SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 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 0 0 0 0 0 4

WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 o

VARIABLE O O O O O O O ,

Total 0 0 0 0 0 0 0 v l Periods of' calm (hours): 0 Hoars of missing data: 0 i

67

' TABLE'4A-2BQ1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Fa.rley Unit 2- 1st Quarter, 1986

.- \ ,

HOURS AT EACM WIND-SPEED AND DIRECTION RELEASE HODE: BATCH PERIOD OF RECORD: 1 86 ) 3-31-86 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 O O 4 0 0 0 4 NNE O O O 0 0 0 0 NE O O O O O O 0 ENE O O 1 0 0 0 0 E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S 0 1 0 0 0 0 1 SSW 0 0 1 0 0 0 1 SW C 0 1 0 0 0 1 i

WSN O O 3 0 0 0 3 i W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0

?!W 0 0 0 0 0 0 0  ;

NNW 0 0 4 4 0 0 8 VARIAb*.E J 0 0 0 0 0 0

,q Total 0 1 13 4 0 0 18 b

Periods of calmthours): 0 Hours of missing data: 0 -

68

TABLE 4A-2BQ1' CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Unit 2- 1st Quarter, 1986 G

HOURS AT EACH' WIND SPEED AND DIRECTION

~~

RELEASE. MODE: BATCH PERIOD OF RECORD: 1 86 ) 3-31-86 STABILITY CLASS: D FLEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction. 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0 0 0 0 0 0 NNE O O O O O O O NE O O O O O O O ENE O O O O O O O E O O O O O O O

- - ESE O O O O O O O S2 0 0 0 0 0 0 0 SSE O O O O O O O S 0 2 0 0 0 0 2 SSW 0 0 . 0 -

0 0 0 0 SW 0 2 1 0 0 0 3 WSW 0 1 0 0 0 0 1 i

W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 1 0 0 0 1 NNW 0 6 5 0 0 0 11 VARIABLE O O O O O O O Total 0 11 7 0 0 0 18 Petlods of calm (hours): 0 Hours of missing dat': 0 fo

m'- .

TABLE 4A-2BQ1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Unit 2- 1st Quarter, 1986 O

HOURS AT EACH WIND SPEED AND DIRECTION

~~

RELEASE MODE: BATCH PERIOD OF. RECORD: 1 86 }' 3-31-86 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 O O O O O O O NNE O O O O O O O NE O O O O 7 0 0 ENE O O O O O O O E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 O O O O SW 0 0 2 0 0 0 2 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O Total 0 0 2 0 0 0 2 O

Periods of calm (bours): 0 Hours of missing data: 0 70 1

~ '

TABLE 45-2BQ1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Unit 2.- 1st Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE-MODE: BATCH PERIOD OF RECORD: 1 86-} 3-31-86 STABILITY CLASS: E ,

ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction- 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0 0 0 0 0 0 NNE O O O O O O O NE O O O O O O O ENE O O O O O O O E O O O O O O O ESE O O O O O O O 1

\ SE O O O O O O O >

i SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 0 - 0 0 0 0 l

l SW 0 2 0 0 0 0 2 WSW 0 0 0 0 0 0 0 i

! . W 0 0 0 0 0 0 0 l

WNW 0 0 0 0 0 0 0

j. NW 0 0 0 0 0 0 0 l

l NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O Total 0 2 0 0 0 0 2 a

Periods of calm (hours): 0 t Hours of missing data: 0 ,

71

~

m,. - -

PN . TABLE 14A-2BQ1.

CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Unit 2 -

1st Qua, er,-1986 O.

x;.

HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: BATCH- --

PERIOD _OF RECORD: 1 86 } 3-31-86 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 O O O O O O O NNE O O O O O O O NE O O O O O O O I

ENE O O O O O O O

  • E 0' O O O O O O 4

ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 .

0 . 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 i W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O Total 0 0 0 0 0 0 0 Periods of calm (hours): 0 Hours of missing data: 0 72

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

,7- - - ,

TABLE 4A-2BQ1

.i CUMULATIVE JOINT' FREQUENCY DISTRIBUTION Farley Unit 2- 1st Quarter,.1986 O

HOURS AT EACH WIND SPEED AND DIRECTION ,

RELEASE MODE: BATCH PERIOD OF RECORD: 1 86-) 3-31-86 STABILITY CLASS: F '

ELEVATION:10.0m Wind Speed (mph) at 10.0m, level Direction 1-3 4-7 8-12 13 19-24 >24 TOTAL

, .N 0 0 0 0 0 0 0

.NNE O O O O O O 0

NE O O O O O O O t ENE O O O O O O O E -0 0 0 0 0 0 0 ESE -0 0 0 0 0 0 .0 O
SE O O O O O O O l

SSE O O O O O O O S 0 0 0 0 0 0 0 I 1

j SSW 0 0 0 Q 0 0 0 SW 0 0 0 0 0 0 0  ;

WSW 0 0 0 0 0 0 0  ;

W 0 0 0 0 0 0 0 l

l WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 L l

I VARIABLE O O O O O O O l

Total 0 0 0 0 0 0 0 Periods of calm (hours): 0

! Hours of missing data: 0 73 '

i

.-- _ _ , , - _ . _ . - _ m _ , , _ ,

TABLE 4A-2BQ1-CUMULATIVE JOINT FREQUENCY DISTRIBUTION Farley Unit 2 - 1st Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: BATCH PERIOD OF RECORD: 1 86 ) 3-31-86 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 'O O O O O O O NNE O O O O O 0. O NE O O O O O O O ENE O O 0- 0 0 0 0 E O O O O O O O ESE O O O O O O O V SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 0 O O O O SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 i

NNW 0 0 0 0 0 0 0 l

l VARIABLE O O O O O O O Total 0 0 0 0 0 0 0

, w L i Periods of calm (hours): 0 Hours of .nissing data: 0 74

,.,w--

,% - - - - - - - . - . . . - ---tr - - * . - - . ,

TABLE 4A-2BQ1 CUMULATIVE JOINT FREQUENCY DISTRIBUTION

/N Farley Unit 2- 1st Quarter, 1986 HOURS AT EACH WIND' SPEED AND DIRECTION RELEASE MODE:-BATCH PERIOD OF RECORD: 1 86 ) 3-31-86 STABILITY CLASS: G ELEVATION:10.0m Wind Speed (mph) at 10.0m, level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O O O O O O NNE O O O O O O O NE O O O O O O O ENE- 0 0 0 0 0 0 0 r

E O O O O O O O ESE O O O O O O O s

SE O O O O O O 0-SSE O O O O O 0 0, S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 L SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O Total 0 0 0 0 0 0 0 Periods of calm (hours): 0 Hours of missing cata: 0 75

TABLE 4A-2BQ2 CUMULATkVE JOINT FREQUENCY DISTRIBUTION Farley Unit 2 - 2nd Quarter, 1986

({}

HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: BATCH PERIOD OF RECORD: 4 86 ) 6-30-06 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 0 0 0 0 0 0 0 NNE O O O O O C 0 NE O O O O O O O ENE O O O O O O O E O O O O O O O ESE O O O

/^3 O O O O

'%./ '

SE O O O O O O O SSE O O 2 0 0 0 2 S 0 0 2 0 0 0 2 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 I

I WNW 0 0 3 0 0 0 3 NW 0 0 2 0 0 0 2 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O

! Total 0 0 10 0 0 0 10 l (

l l Periods of calm (hours): 0 l Hours of missing data: 0 i

l 76 l

TABLE 4A-2BQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION

/*

k_) Farley Unit 2 - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: BATCH PERIOD OF RECORD: 4 86 ) 6-30-86 STABILITY CLASS! A ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4 8-12 13-18 19-24 >24 TOTAL N O O O O O O O NNE O O O O O 0 0 NE O O O O O O O ENE O O O O O O O E O O O O O O O IT u) ESE O O O O O O O SE 1 0 0 0 0 0 1 SSE O 3 0 0 0 0 3 S 0 0 0 0 0 0 0 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 1 1 0 0 0 2 WNW 0 0 3 0 0 0 3 NW 0 1 0 0 0 0 1 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O Total 1 5 4 0 0 0 10 O

Periods of calm (hours): 0 Hours of missing data: 0 77

i i

TABLE 4A-2BQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION j

() Farley Unit 2 - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: BATCH PERIOD OF RECORD: 4 86 ) 6-30-86 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 O O O O O O O l l

NNE O O O O O O O l

l NE O O O O O O O ENE O O O O O O O E O O O O O O O

(} ESE O O O O O

O O

O O

O O

SE O O O SSE O O O O O O O S 0 0 0 0 0 0 0 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 1 0 0 0 0 1 WNW 0 0 0 0 0 0 0 NW 0 0 2 0 0 0 2 NNW 0 1 1 0 0 0 2 VARIABLE O O O O O O O Total 0 2 3 0 0 0 5 Periods of celm(hours): 0 Hours of missing data: 0 78

. .. - _ .. . . - - - = . .

1

'l TABLE 4A-2BQ2 CUMULATIVE' JOINT FREQUENCY DIt 'RIBUTION

() Farley Unit 2 - 2nd Quarter, 1986 l HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: BATCH PERIOD OF RECORD: . 4 86 ) 6-30-86 STABILITY CLASS: B ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O O O O O O NNE O O O O O O O NE O O O O O O O ENE O O O O O O O E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 l 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 1 0 0 0 0 1 WNW 0 1 0 0 0 0 1 NW 0 2 1 0 0 0 3 NNW 0 0 0 0 0 0 0  :

VARIABLE O O O O O O O Total 0 4 1 0 0 0 5 Periods of calm (bours): 0 i

Hours of missing data: 0 ,

79

TABLE 4A-2BQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION (3

( /. Farley Unit 2 - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: BATCH PERIOD OF RECORD: 4 86 } 6-30-86 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 O O O O O O O NNE O O O O O 0 0 NE 0 0 0 0 0 0 0 ENE O O O O O O O E O O O O O O O

() ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S 0 0 1 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 l W 0 1 1 0 0 0 2 l WNW 0 0 0 0 0 0 0 i

NW 0 1 0 0 0 0 1 NNW 0 1 0 0 0 0 i VARIABLE O O O O O O O Total 0 3 2 0 0 0 5 l <

l Periods of calm (hours): 0 Hours of missing data: 0 80 i

TABLE 4A-2BQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION

() Farley Unit 2 - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: BATCH PERIOD OF RECORD: 4 86 ) 6-30-86 STABILITY CLASS: C ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 O O O O O O NNE O O O O O O O NE O O O O O O O ENE O O O O O O O f

I E O O O O O O O

{} ESE O O O O O O O SE O O O O O O O SSE O O O O O O O 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 1 0 0 0 0 1 W 0 1 0 0 0 0 1 l

WNW 0 1 0 0 0 0 1 .

NW 0 0 0 0 0 0 0 NNW 0 1 0 0 0 0 1 VARIABLE O O O O O O O Total 0 5 0 0 3 0 5 Periods of calm (hours): 0 Hours of missing data: 0 81

TABLE 4A-2BQ2 CUHULATIVE JOINT FREQUENCY DISTRIBUTION

'O

-,_/ Fai' ley Unit 2 - 2nd Quarter, 1986 HOURS AT EACH WIND 3 PEED AND DIRECTION RELEASE MODE: BATCH PERIOD OF RECORD: 4 86 ) 6-30-86 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 O O O O O O O NNE O 2 0 0 0 .0 2 NE O 1 0 0 0 0 1 ENE 1 0 0 0 0 0 1 E O O O O O O O Il

%/

ESE 1 1 0 0 0 0 2 SE O 1 0 0 0 0 1 SSE O O 1 0 0 0 1 S 0 0 1 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 2 0 0 0 0 2 l

l WNW 0 1 0 0 0 0 1 i

NW 0 2 0 0 0 0 2 NNW 0 0 0 0 0 0 C VARIABLE O O O O O O O g- Total 2 10 2 0 0 0 14 V) l Periods of calm (hours): 0 Hours of missing data: 0 82

. :re TABLE 4A-2BQ2 CUMULATIVE JOINT FREQUENCY-DISTRIBUTION

() Farley Unit 2 - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: BATCH PERIOD OF RECORD: 4 86 ) 6-30-86 STABILITY CLASS: D ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 1 0 0 0 0 2 NNE 2 0 0 0 0 0 2 NE 1 0 0 0 0 0 1 ENE O O O O O O O E 1 0 0 0 0 0 1 ESE O 1 0 0 0 0 1 SE 1 0 0 0 0 0 1 SSE O O O O O O O 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 1 0 0 0 0 0 1 W 0 1 0 0 0 0 1 WNW 0 1 0 0 0 0 1 NW 0 2 0 0 0 0 2 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O Total 7 7 0 0 0 0 14

Periods of calm (hours)
0 Hours of missing data: 0 83

l l

TABLE 4A-2BQ2 l l

i l

CUMULATIVE JOINT FREQUENCY DISTRIBUTION

() Farley Unit 2 - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: BATCH PERIOD OF RECORD: 4 86 ) 6-30-86 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 O 1 0 0 0 0 1 NNE O O O O O O O NE O O O O O O O ENE 0 0 0 0 0 0 0 E 3 0 0 0 0 0 3 ESE O O O O O O O SE O O O O O O O f2S E O O 1 0 0 0 1 S 0 0 1 0 0 0 1 SSW 0 0 0 0 0 0 0 SW 0 3 0 0 0 0 3 WSW 0 1 0 0 0 0 1 W 0 2 1 0 0 0 3 WNW 0 2 2 0 0 0 4 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0  ;

J VARIABLE O O O O O O O Total 3 9 5 0 0 0 17 Periods of calm (hours): 0 Hours of missing data: 0 84

TABLE 4A-2BQ2 CVHULATIVE JOINT FREQUENCY DISTRIBUTION (f Farley Unit 2 - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: BATCH PERIOD OF RECORD: 4 86 ) 6-30-86 STABILITY CLASS: E ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4 8-12 13-18 19-24 >24 TOTAL N O 1 0 0 0 0 1 NNE 1 0 0 0 0 0 1 NE 1 0 0 0 0 0 1 ENE 1 0 0 0 0 0 1 E O O O O O O O

() ESE O O O O O O O SE 1 0 0 0 0 0 1 SSE O 1 0 0 0 0 1 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 3 0 0 0 0 0 3 WSW 1 0 0 0 0 0 1 W 2 2 0 0 0 0 4 WNW 2 1 0 0 0 0 3 NW 0 0 0 0 0 0 0 l

. NNW 0 0 0 0 0 0 0 l

VARIABLE O O O O O O O

Total 12 5 0 0 0 0 17 Periods of calm (hours)
0 Hours of missing data: 0 85

TABLE 4A-2BQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION

() Farley Unit 2 - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE Mr. JE: BATCH PERIOD OF RECORD: 4 86 ) 6-30-86 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 O 1 0 0 0 0 1 NNE O O O O O O O NE O O O O O O O ENE O O O O O O O E O O O O O O O

{) ESE O O O O O O O SE O O O O O O O SSE O O 1 0 0 0 1 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 0 0 0 0 0 WNW 1 0 0 0 0 0 1 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O Total 1 2 1 0 0 0 4 Periods of calm (hours): 0 Hours of missing data: 0 8f

TABLE 4A-2BQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION

() Farley Unit 2 --2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE HODE: BATCH PERIOD OF RECORD: 4 86 ) 6-30-86 STABILITY CLASS: F ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0 0 0 0 0 0 NNE O O O O O O O NE 1 0 0 0 0 0 1 ENE O O O O O O O E O O O O O O O ESE O O O O O O O p%/

SE 1 0 0 0 0 0 1 SSE O O O O O O O S 1 0 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 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 1 0 0 0 0 0 1 VARIABLE O O O O O O O

- Total 4 0 0 0 0 0 4 i

Periods of calm (hours): 0 Hours of missing data: 0 87

TABLE 4A-2BQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION

() Farley Unit 2 - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED AND DIRECTION RELEASE MODE: BA'tCH PERIOD OF RECORD: 4 86 ) 6-30-86 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 O O O O O O O NNE O O O O O O O NE O O O O O O O ENE O O O O O O O E 1 0 0 0 0 0 1

(} ESE O O O O 0

O 0

O 0

O SE O 1 0 1 SSE O O O O O O O S 0 0 0 0 0 0 0 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 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 VARIABLE O O O O O O O Total 1 1 0 0 0 0 2 Periods of calm (hours): 0 Hours of missing data: 0 88

)

TABLE 4A-2BQ2 CUMULATIVE JOINT FREQUENCY DISTRIBUTION

~()

( 'Farley Unit 2 - 2nd Quarter, 1986 HOURS AT EACH WIND SPEED 8.MD DIRECTION RELEASE MODE: BATCH PERIOD OF RECORD: 4 86 ) 6-30-86 STABILITY CLASS: G ELEVATION:10.0m Wind Speed (mph) at 10.0m level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0 0 0 0 0 0 NNE 1 0 0 0 0 0 1 NE O O O O O O O ENE 1 0 0 0 0 0 1 E O O 0 0 0 0 0 ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 C 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 l

VARIABLE O O O O O O O

, Total 2 0 0 0 0 0 2

\

(~J

Periods of calm (hours): 0
Hours of missing data
0 I 89 i

I

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

4 TABLE-4B CLASSIFICATION OF' ATMOSPHERIC STABILITY a

stability _ Pasquill e9 Temperature channel Classification Categories (degrees)= with height (0F/51m)

Extremely unstable A 25.0 <-1.74 Moderately unstable B 20.0 -1.74 to -l'.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 a period of-15 minutes to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The values shown are averages for each stability classification.

f%

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TABLE 5 RADIOACTIVE-GASEOUS WASTE CAMPLING AND ANALYSIS PROGRAM g FARLEY NUCLEAR PLANT - UNITS 1 & 2

/-~Y a,h Gaseous Release Sr.pling 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 9sj B. Col.tainment Each Purge Each Purge Principle 1E-04, Purge Grab b Grab b Gamma Emitters Sample P Sample P H-3 1E-06 Vsj

  • 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

( ) D. Plant Vent Stack Continuous Charcoal Charcoal Sample d I-131 1E-12 Containment W I-133 1E-10 Purge f g Continuous Particulate Principle Sample d Gamma Emitters 1E-11 .

W (I-131, Othersi  !

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

.nuous Noble Gas Noble Gases Gross 1E-06 Monitor Beta & Gamma r

E 91

+

7-TABLE 5 (Continued)

TABLE NOTATION (D

U 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 (-hat) 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 por 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 co'nstant 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 92

TABLE 5 (Continued)

TABLE NOTATION

,i-m t

\- 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 t e plant vent stack at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.
d. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding MDC may be increased by a factor of 10.

e. Tritium grab samples sha'll 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, The ratio of the sample flow rate to the sampled stream flow

()

f.

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, Cs-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 quant:ty of air sampled is proportional to the quantity of air discharged.

Either a specimen which is representative of the air discharged may be accumulate 6 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.

! 93

~. ,

s TABLE 6-RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM

.q FARLEY NUCLEAR PLANT - UNITS 1 & 2

.h a,g Minimum Type of Minimum Liquid Release Sampling Analysis Activity Detectable Type Frequency Frequency Analys-is Concentration (MDC)(uCi/ml) c P P e A. Batch Waste Each Each Principle

' Release Batch Batch Gamma SE 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 l

D b Grab Q Sr-89, Sr-90 SE-08 Sample Composite Fe-55 1E-06 4

P b e b

V

2. Turbine Building Grab Sample W

Composite Principle Gamma SE-07 Sump Emitters H-3 1E-05 94

TABLE 6 (Continued)-

TABLE NOTATION.

I

\' -

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 (-hat) 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),

A 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 l b i detection system shall be based on the actual observed variance of the background counting rate or of the counting j rate of the blank samples (as appropriate) rather than on an i unverified theoretically predicted variance. Typical values of E, V, Y, and at shall be used in the calculation.

O 95

r TABLE 6 (Continued)

TABLE NOTATION

-m

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 identifi'able, 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 HDC requirements of Table 4.11-1 shall be reported per Specification 6.9.1.8 in lieu of any other report.

96

c-TABLE-7 LIQUID DISCHARGES NOT MEETING SPECIFIED DETECTION LIMITS.

O Farley Units 1 & 2- 1st half, 1986

-~

Batch # .N/A*

Date N/A Count Time in Seconds N/A Volume Discharged in Gallons N/A Dilution Water in Gallons N/A To.tal 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 i

e i

i l

O 97

12. Process Control Program i Changes to the Process Control Program (PdP) during the first ,

semi-annual period of 1986 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.

T l

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98

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STD-P-03-004 Page 2 of 4 h

b CLOSURE OF HITTMAN RADLOK HIGH INTEGRITY CONTAINER FILL POINT CLOSURE ASSEMBLY 1.0 PURPOSE The purpose of this procedure is to describe the proper method of sealing the fill port opening on Mittman RADLOK High Integrity Con-tainers.

2.0 APPLICABLE DOCUMENTS The following drawings and documents are listed as applicable to this procedure:

STD-D-03-009, Users Manual for Hittman RADLOK-200, RADLOK-500, and RADLOK-100 Containers STD-D-03-008, Users Manual for Hittman RADLOK-55 3.0 PRE-SEALING INSTRUCTIONS These steps are to be taken prior to filling the container.

3.1 Compression Plug

(

i 3.1.1 Examine the 0-ring seal (Item 1, Figure 1) and small vertical seal (Item 2 Figure 1) for signs of signifi-cant gouges, splits, cracks or brittleness. Damaged seals should be replaced.

3.1.2 Clean the 0-ring and vertical seal seats on the com-pression plug (Item 3, Figure 1) and remove all foreign matter.

3.1.3 Spray the 0-ring and vertical seal seats with silicone rubber adhesive. Place the 0-ring seal in the seat area. Place the vertical seal in its respective seat area. A liquid adhesive such as 3M Scotch-Weld CA-4 Cyanoacrylate Adhesive may also be used.

3.1.4 Apply a liberal coating of lubricant grease on the exposed seal surfaces.

NOTE: Caution must be exercised to ensure that the i

, lubricant used does not contain any of the  ;

chemicals listed in Appendix A of the User's '

Manual. Acceptable lubricants include Vasoline r and other petroleum jelly products.

3.1.5 Apply a liberal coating of lubricant grease to the threads on the fill port lid (Item 4 Figure 1).

ument Nuden R;v: R;v Dsta:

kTSTINGHOUSE HITTMAN

' NUCLEAR INCORPORATED STD-P-03-004 7 12/19/85

Title:

I CLOSURE'0F HITIMAN RADLOK " HIGH INTEGRII':

O

'%) CONTAINER FILL PORT CLOSURE ASSEMBLY Prepar.ed operationa Director QA Rev, Rev Date by Engineering Manager h

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1 4-16-82 ok -

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5 9-30-83 h [ [/ 3-247 ECN-6 6/6/85 s -g, , j[t 85-035 Director Product Q.A.

Engr. Manager ,

Manager 7 12/19/85 ,

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STD-P-03-003

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PROCEDURE REQUEST FORM FNP-0-AP-1 fs 1. Procedure Number FNP-0-M-030 Revision Number 4

( ,, Procedure Title Process Control Program (PCP)

( \

Q)

XIX Safety Related C Non-Safety Related C New Procedure Request .

XXX Procedure Revision, New Revision Number 5 C Temporary Procedure Change, Effective until next permanent change, TCN ,

C Temporary Procedure Change, Req'd. by Plant Conditions, TCN _

C Te=porary Procedure Change, One Time Use, TCN O Delete procedure C Delete TCN

  1. The procedure has been revised per Section 9 of FNP-0-AP-1,
2. Change Summary 2.1 Procedure Page Numbers Affected by Change See attached list of ef f ective pages that show FNP revision 5 2.2 Description of Changes See attached list.

2.3 Reason for Change All changes are due to unerade of PCP prngenm by vendor.

(,., i f ) 1

3. Prepared B-(ijnature '

T' MM7M/M e

S-Wgg Daf.e

4. Reviewed By DC Y Yldbli nArubtN P,)/, l{o ?le iF ature 3 Title" ~ l Date S. Cross-D iplin ry/PORC Review Group Sienature Title Datef j

'P04c' e %s _ ,Pv4c o/L , r/sc/M

6. Temporary Change Approval (Signature /Date)

C Memb(r Group Staff /

O Shift Foreman /

C Senior Reactor Operator /

C General Manager-Nuclear Plant /

7. Final Approval (Signature /Date, required within 60 days of temporary approval)

C Group Supervisor .

a, / ,

% Manager f 0 IA > NVI

\ C MSAER

!h-}-Sl]

/ I C Senior Vice President C

/

)

/

O General Manager - Nuclear Plant /

FNP-0-AP-1 FARLEY NTCLEAR PL.GT NTCLEAR SAFETY EVALUATION CHECK LIST g.

[]

V (1) UNIT SHARED (2) CHECK LIST APPLICA3LE TO: FNP-0-M-030 Revision 5 TCN n/a (3) SAFETY EVALUATION - PART A: Does the procedure or procedure change to which this evaluation'is applicable represent: ,

_(3.1) Yes No x A change to the plant as described in the FSAR?

(3.2) Yes No y A change to procedures as described in the FSAR?

(3.3) Yes No y A test or experiment not described in'the TSAR?

(3.4) Yes No y A change to the Technical Specifications or Operating License?

(3.5) Yes No X A change to the Fire Protection System as described in the FPPR or a conflict with the requirements of 10CFR50, Appendix R?

If the answer to question 3.1, 3.2, or 3.3 or 3.4 is "Yes," complete Item-(4) and attach a 10 CFR 50.59 evaluation. If the answer to question 3.4 is "Yes," also complete a 10 CFR 50.92 check list. If the answer to question 3.5 is "Yes", provide an evaluation of the impact of the procedure or procedure change on the Fire Protection System and 10CFR50, Appendix R requirements.

If the answer to Items 3.1,3.2,3.3 and 3.4 is "No", omit Item (4) and Item (9).

(4) SAFETY EVALUATION - PART B (4.1) Yes No Will the probability of an accident previously evaluated in the FSAR be increased?

g (4.2) Yes No Will the consequences of an accident previously

(\ evaluated in the FSAR be increased?

(4.3) Yes No May the possibi,lity of an accident which is different than any already evaluated in the FSAR be created?

(4.4) Ye's No Will the probability of a malfunction of equipment important to safety previously evaluated en the FSAR be increased?

., (4.5) Yes No Will the consequences of a malfunction of equipment important to safety different than any already evaluated in the FSAR be increased?

(4.6) Yes No May the possibility of a malfunction of equipment important to safety different than any already evaluated in the FSAR be created?

(4.7) Yes No Will the margin of safety as defined in the basis to any Technical Soecification be reduced?

If the answer to any of the above questis:ts is "Yes," an unreviewed safety question may be involved.

(5) REMARKS: (Attach additional pages if necessary) These changes will not reduce the overall conformance of the Solidified Waste Program to existing criteria for solid wastes (6) PREPARED BY: M u M . h.) u Ja.--- f DATE 4 /,,'1 / d:, '

~

(7) REVIE%T.D BY: c

/ 2 I/ . _ , ~

DATE - -[d, (S) PORC REVIEW: N 9M DATE # I (d~( y '

~

(9) NORS REVIE'4: / DATE Figure 3 Rev. 19

x ENP-0-M-030 Revision 5 h.istofEffectivePage WHNI Number of FNP Section A Dewatering Revision Pages Revision RADLOCK"" Manway Lid Closure and 8 4 5 S1D-P-03-003 Sealing Procedure G1D-P-03-004 Closure of'HITINAN RADLOK" High Integrity 7 4 5 Container Fill Port Closure Assembly 4 5 0 STD-P-03-005 Dewatering Bead Ip"n Exchange Resin in HITINAN RADIDK Containers with Flexable Underdrains to Less 1han 1% Drainable Liquid Inspection of completed HIOC Liners 1 9 1 STD-P-03-006 S'ID-D-03-008 A Users Manual for the HITINAN BADIDCK"-55 7 15 5 STD-P-03-008 Transfer & Dewp"tering Powdered Resin in Hittman BADIDK -100, 200 or 500 containers with a Flexible Underdrain Assembly to Less than 1% Drainable Liquid 5 7 5 STD-D-03-009 9 18 5 A Userp, Manual for the HITINAN RADIDK -200, RADLOK 500, and RADIDK 100 O SID-P-03-010 Transfer & Dewatering Bead Resin in 6 12 5 Hittman RADLOK"-100, 200 or 500 containers with Single Layer Underdrain Assembly to Less 1han 1% Drainable Liquid STD-P-03-020 Radlok Inspection Procedure 5 5 5 STD-P-04-002 P.C.P. for Dewatering Ion Exchange 6 11 5 Resin & Activated Charcoal Filter Media to .5% Drainable Liquid Section B Solidification STD-P-05-002 P.C.P. for Incontainer Solidification 4 18 5 of oily Waste STD-P-05-003 P.C.P. for Incontainer Solidification 4 32 3 of 4 to 20 Weight Percent Boric Acid STD-P-05-004 P.C.P. for Incontainer Solidification 5 16 2 of Bead Resin RCP-7A/21

WHNI Number of FNP Revision Pages Revision 3 h P-05-011 Process Control Program for Incontainer Solidification of Granular Activated Carbon (12-40 MESH) 2 12 2 S h P-05-021 P.C.P. for Incontainer Solidification of Class A Unstable and Stable, Class B or C Decanted Diatomaceous Earth 1 24 4 SID-P-05-022 Calcium Hydroxide Addition Procedure 1 7 4 S h P-05-023 Incontainer Solidification System (ICSS)

Operational Inspection Procedure Sections A and B) 0 22 1 SID-P-05-027 Full Scale Test Solidification Procedure for Class B or C Bead Resin 0 11 1 STD-P-05-034 PCP for Incontainer Solidification of Class A Stable, Class B and C Bead Resin at Maximum Packaging Efficiency 1 13 3 F434-P-005 P.C.P. for Incontainer Solidification of Dilute Filter Sludge 1 10 0 Section C Equipment Information p ID-D-01-001 S Operation & Maintenance Manual tg Standard Dewatering Pump Skid 1 18 0

STD-P-04-001 Final Dewatering Pump Skid operating Instructions 1 8 0 SID-D-05-001 Standard Dewatering Pump Skid '

system Description 0 2 0 Section D Reports '

STD-R-03-001 Report on Dewatering of Bead Ion Exchange Resin and Activated Carbon 0 17 1 STD-R-03-002 Report on Dewatering of Bead Ion Exchange Resin and Activated Carbon in HITINAN RADLOK"" High Integrity Containers 1 17 1 STD-R-03-005 Summary Rep' ort of Powdered Resin Dewatering In a RAD w K " Container 0 24 1 S h R-03-006 Powdered Resin Dewatering in a Flat Bottom Container Using the Hittman Layered Underdrain System 0 6 1 STD-R-05-007 Topical Repott Cement Solidified Waste A To Meet Ihe Stability Requirements of C 10CFR61 2 37 2 RCP-7A/21

WHNI Number of FNP Revision Pages Revision Section E General Specifications O HNDC-TS-13000 rield Assembly & Operating Procedure for Flexcon Cement reed System 1 6 0 HNDC-TS-14000 Liner Loading Procedure 2 3 0 HNDC-TS-17000 Mixer Head Drive Mounting Procedure (Hydraulic / Electric) 1 2 0 HNDC-TS-19000 Field Assembly & Operating Procedure for Electric Mixer Drive Assembly 2 6 0 HNDC-TS-20000 Boric Acid Solidification Procedure 2 5 0 HNDC-TS-25000 Dewatering Pump Skid (Standard)

Operating Procedure 0 2 0 Appendix A Generic Information for Developing a Process Control Program NA 1 3 Appendix B Process Control Program For Absorption of Oil NA 2 4 O

O RCP-7A/21

'* STD-P-03-003

,, Page 2 of 4 d RADLOZ D MANWAY ASSEMBLY CLOSURE AND SFALING PROCEDURE 1.0 PURPOSE The purpose of this procedure is to set forth the proper method of sealing the aanway assembly on Hittaan RADLOK-200, RADLOX-500, and RADLOK-100 high integrity containers.

2.0 APPLICABLE DOCUMENTS The following document is applicable to this procedure:

STD-D-03-003, Users Manual for the Hittman RADLOK-200, RADLOK-500, and RADLOK-100 High Integrity Containers 3.0 MANWAY SEAL INSTALLATION 3.1 Examine both seals (Items 1 and 2, Figure 1) for signs of significant souges, splits, cracks or brittleness. Damaged seals should be replaced.

. 3.2 Clean the flat seal seat area on the container body and the vertical seal seat area on the aanway seal (Item 3, Figure 1) before installing seals or filling the container.

3.3 Spray the flat seal (Ites 1, Figure 1) on one side with silicon rubber adhesive, and place the seal on the container body seat surface, adhesive s..de down. A liquid adhesive such as 3M Scotch 4 Weld CA-4

Cyanoacrylate Adhesive may also be used. Make sure the seal is seated l at all points and in complete contact with the seat.

3.4 Using a small portion of a lubricant grease where necessary, slide the large vertical seal (Item 2, Figure 1) over the aanway seal. NOTE:

Caution must be exercised to ensure that the lubricant used does not contain any of the chemicals listed in Appendix A of the Users Manual. l

' Acceptable lubricants include Vasoline and other petroleus jelly products.

3.5 Apply a liberal coating of lubricant grease to the outer edge of the manway seal and large vertical seal.

3.6 Check the seal seating surfaces in the container to again ensure that they are clean, then CAREFULLY place the aanway seal inside the aanway opening,(small diameter face first) making sure not to disturb the flat seal.

4.0 MANVAY LID INSTALLAfION 4.1 Apply a liberal coating of lubricant grease to the aanway threads on the container or the threads of the aanway lid.  ;

Document Nun 6:r: Rev: . Rev Dato

'. WESTINGHOUSE - - STD-P-03-003 .

8 12/19/85 POR TED

Title:

RADLOKD Manway Assembly Closure and Sealing Procedure O Prepared Director QA operations Rev. Rev Date by Engineering Manager D 4~7-02 h f 1 4-16-82

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85 034 Director Product Q.A.

Engr. Manager Manager 8 12/19/85 In Ill g 8 212 O

FORN01(B) Poge 1 of

STD-P-03-003 i Psgs 3 of 4 i 4.2 Carefully ~ place the aanway lid (Ites 4, Figure 1) over the opening, making sure that the aanway seal is not disturbed in the precess.

4.3 Screw downt 'he manway lid by hand until a high degree of resistance is encountered.

4.4 Using an 8 ft length of 3/4" pipe or bar proceed to screw the lid down until less than 3/4" of space remains between the lid and container surface.

4.5 When the aanway lid is properly screwed down, the aanway lid may be secured with a ecurity wire between the lid and the container lift lugs.

NOTE: Securing the lid need not be performed on containers to be shipped in Type A or Type B casks, or on containers to be shipped as strong tight packages.

52X O ,e j '

4 O

4 STD-P-03-004  !

Page 3 of 4 l O

4.0 CONTAINER SEALING These steps are to be taken after the container is filled.

4.1 Clean the seal contact areas in the fill neck of the containc.r and remove all foreign material.

4.2 Place the fill port closure assembly (Item 5, Figure 1) into the fill port opening.

NOTE: Oo large RADLOKs with fill plates, orient the compression plus such that the vent filter does not interfere with any of the fill plate attachments.

4.3 Screw the lid into the container to a minimum of 150 foot-pounds of torque (this could be accomplished by a Hittman fill port torquing tool and a torque wrench).

4.4 Secure the fill port lid with a security wire between one ear of the fill port lid and the top perimeter lip of the container.

NOTE: Securing the fill port lid need not be performed on containers to be shipped in Type A or Type B casks, or on containers to be shipped as strong tight packages.

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STD-D-03-008 7 1-31-86 WESTINGHOUSE HITTMAN NUCLEAR

Title:

A Users Manual for the HITTMAN RADLOK*-5 5 l

[x INCORPORATED

(,7 espons m o OA Proj ect Depart:nent Director Rev, Engineer Manager Engineering Manager Manager Rev Date _

0 4-16-82

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STil-D-03-008 Pal;s 2 of 15 0

A USERS MANUAL TOR THE HITTMAN RADLOX -55 O Pu rpo s e The high integrity container is designed to provide waste isolation from the surrounding environment for a period of 300 year::. Various unsolidified wastes may be disposed of at Barnwell; howevier, if the total specific activities of isotopes with half lives greater than five years is lpCi/ml or greater, high integrity containers approved by the South Carolina Department of Health and Environmental Control must be used.

This document is intended to provide the user of the Hittman

  • RADLOK drum with basic information required for the safe and proper use of the container. Included is a general description of the con-tainer, a listing of the approved contents, a listing of prohibited chemicals, and the handling / storage requirements of a RADLOK contair.er.

Inspection requirements prior to usage, lift requirements, and closure methods are also provided. The user must also refer to the requirements of the respective container certificate of compliance from the burial s i t'e .

Description of the RADLOK-55 The Hittman RADLOK-55 drum has been designed to closely approximate g

the size of present 55 gallon steel drums. The RADLOK drum has envelope dimensions of 35 inches high by 23 inches in diameter. The drum con-tains an 8 inch diameter fill port centered in the top. The container is fabricated from high density cross-linked polyethylene, molded to provide a one-piece body to the container. An approved vent is provided ,

in the closure components of each container. An approved vent is required on containers buried after March 1, 1986.

Approved Contents The Hittman RADLOK container has been designed to safely contain nuclear wastes including bead and powdered ion exchange resin, filter sludges, mechanical filters, stabilized incinerator ash, activated carbon, contaminated soil, and sandblasting grit. Procedures for load-ing metal filters, scrap metal and other non-compactible trash into the RADLOK container to ensure that protrusions and sharp edges do not damage the container must be submitted and approved by Hittman. The container may not contain free stinding water greater than 1 percent of the waste volume.

Criteria for Packaging of Filter Elements and Serap The following criteria for the packaging of filter elements and scrap in Mittman RADLOK-55 containers shall be used in developing the

~

required procedures.

I I

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O O -O Packaging Criteria Waste Category Rigid Metal Filter Cartridge Elements with Exposed Metal Scrap, Non-Compactible filters Ends, Noncompactible Compactible Trash Parameter Trash Elements Trash with No Sharp Edges with Sharp Edges i

H;ximum Length of of Individual Piece Placed Horizontal none 20 20 20 Placed Vertical none 24 24 18 Packing Materia 1 8 none none cement, vermiculite, sand, gravel, etc.

Min. Depth of Packing 2 N/A N/A 1" 2" Material on Botton Padding 3 none none none pipe ends and sharp edges Min. dist. waste to none none none 2" wall

~

Packing between none none fill voids 2" layers

  • as loaded Maximum Depth to underside of fill neck 2" below underside of fill neck of Waste Final Filling
  • none none cover contents cover contents plus 2" o in 50 8The packing material is used to protect the interior of the container and to prevent *A excessive cettling of the waste during t.ransit. Only required of waste that could "E potentially damage the container.

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2 To be placed in container prior to waste.

3 To protect container walls if necessary. Among other items, rubber sheet or styrofoam blocks may be used. Only required on sharp edges or ends of rough cut pipe.

4 0nly necessary when packing material is used as defined in footnote number 8

STD-D-03-008

  • Pass 4 of 15 Prohibited Contents (A)

Included in this guide, as Attachment A, is a copy of a MARLEX R6 sins 1echnical Service Memorandum from Phillips Chemical Company, No.

1.M-293, Chemical Resistance of Marlex CL-100 and CL-50 Rotational Molding Cross linkable High Density Polyethylenes, dated December 1982.

This document lists those chemicals that are incompatible with the material used in RADLOK high integrity containers. (Note: This docu-ment is oriented towards those applications where tanks manufactured using CL-100 (or CL-50) are used to store these chemicals in their pure form and not as contaminants in other materials.) When using a Hittman RADLOK, those chemicals listed in Table IV of the Appendix to Attachment A are considered prohibited,and may not be disposed of in RADLOK high integrity containers. Chemicals listed elsewhere in'the Appendix are not prohibited when disposed of as incidental contaminants to radio-active wastes.

Thermal Limitations The Hittman RADLOK containers are licensed with a temperature limitation of 170*F for handling, lif ting, and disposal operations. At no time is the container to be subjected to a temperature in excess of 200*F due to any process or its contents. These thermal limitations apply to the containment of all anticipated waste forms including, where present, incidental chemical contaminants (as contaminants, the chemicals i

i listed in Table 1 of Attachment A are acceptable at the above temperature limits).

Storage Conditions The Hittman RADLOK drum may be stored under proper conditions for periods up to two years before use. Storage of unused Hittman RADLOK containers for periods longer than two years will require specific Hittman approval following review of the conditions under which the containers are stored. As a photosensitive material, the containers shall be kept out of direct sunlight, and away from any other sources of ultraviolet radiation. Containers stored out of doors in direct sun-light must be used within one year of fabrication. Containers shall be stored in such a way that the bottom is flat and that no weight is located over the fill port area. This is to ensure that no potential deformation of the fill port area of the container or seal material occurs. Each container shall be stored with its designated closure i assembly to prevent mismatching.

Following filling and closure of the container, it may be stored on-site prior to shipment for burial for up to five (5) years. The

! design of the facility must preclude the possibility of a wet or damp environment and any prolonged exposure of the container to any source of ultraviolet light. Short exposures to ultraviolet. light, such as during placement or inspection are permitted. Storage of RADLOX containers for i

periods longer than five (5) years after filling will require specific i Hittman approval following a review of the user's storage facility design.

i 1 STD-D-03-008 Pass 5 of 15 Inspection Prior to Use O

! Prior to the use of a container to receive waste material the following items must be checked. The fill port closure assembly, con-sisting of the seals and the fill port lid bolted to the compression plug, is accounted for and in good condition. Seals are not hard or brittle and are free of defects. Thread areas and seal aream are free of foreign matter that could impair the seal or thread engagement. The exterior surfaces shall be inspected for damage that may have occured during transport or storage that could lessen container integrity. See the RADLOX Inspection Procedure, STD-P-03-020, for a detailed inspection procedure.

Lift Requirements The RADLOK-55 comes equipped with a lift band, and may be lifted by either fork lif t tines under the edges of the liftband or by the use of a standard drun grappler. Under maximum load conditions, the entire assembly would have a final weight of 950 pounds. The lift assembly is designed to accomodate this weight during a 33 abrupt lift. Note: Due to the nature of the container material, some bowing and deformation may be evident during the lift. This is an anticipated condition.

Fill Port Use and Closure The standard fill port on the Hittman RADLOK-55 drum is an eight inch opening. The fill port is concentric with the top of the container

(-'j g

g and is sealed with the fill port closure assembly. Two seals are attached to the compression plug of the fill port closure assembly. The assembly is then lowered into the opening and screwed into position to a prescribed torque. For details of the closure procedure see Hittman procedure STD-P-03-004.

If the container is to be used as a Type A container, the lid shall be secured for transportation to prevent illicit opening. Details con-cerning methods of securing the ! d are also provided in STD-P-03-004.

6F O

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Page 6 of 15 j

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O l ATTACHMENT A TO STD-D-03-008 CHEMICAL RESISTANCE OF MARLEX CL-100 AND CL-50 ROTATIONAL MOLDING CROSSLINKABLE HIGH DENSITY POLYETHYLENES O .

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a PHILLIPS CHEMICAL COMPANY MAR W nessm a sussioian, os e. owns ottaotavu coMPah" TECHNaCAL SEAveCE ~

.se,e s PLASTICS TECHNICAL CENTER MEMenANGUM "

m aner.mmen ene maram saattesvi6tt onLaaoua ?*ooa STD-D-03-008 l Page 7 of 15 l

l l TSM-293 DECEMBE R , 1962 l

l CHEMICAL RESISTANCE OF MARLEX CL-100 AND CL-50 ROTATIONAL MOLDINC CROSSLINKABLE HICH DEN 5iTY POLYETHYLENES l

1 INTRODUCTION One of the most rapidly growing plastics applications is relatitely large rotational molded storage tanks. This applit itioti and its growth has been keyed to the develop-ment and marketing of crosslinkable high density polyethylenes by Phillips Chemical Company. These polyethylenes are marketed under the designation of Marlex CL-100 and CL-50 rotational molding crosslinkable high density polyethylene.

Rotational molding is ideally suited for the manuf acture of large tenks. In addition '

the unique toughness, chemical and stress crack resistance of the Marlex CL-100 and CL-50 resins are needed for the demanding requirements in industry and agriculture for O chemical storage tanks and are the key to this expanding market. Today tanks are molded as large as 15,000 gallons (57,000 liters) and are used in such diverse storage applications as acids, insecticides, and chemical plant waste by-products.

The scope of this Technical Service Memorandum is to address the question of c om pa t i-bility of chemicals with Marlex CL-100 and CL-50 resins in relation to storage tanks.

Engineering principles used in determining the suitability of a given application are discussed. Lists of chemicals both suitable and not suitable are included in the appendix along with any limitations which may apply.

. 1

,_ _ en- - tombe.~~.ge-rwchTJ .ds:cra cannot be gt.arwtood h == the conomons of use are tepnd our controd iniormenon proneMed %wn a ynn w8thoiJ roterorce to em patent @aoborn wench may be eW m ele use tNrsof Such r= me-o shoi.Ad be w*astosted ty those unang tM anfctmanen PNace Chemenf Cor ipeny ensames no etey %r

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STD-D-03-008 Page 8 of 15  !

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t D iv I CHEMICAL RESISTANCE "Chemical resistance" and "compatibility" are synonymous terms used in relation to the ability of a plastic to function in different environments. In regard to polyethylene I chemical storage tanks, chemical resistance encompasses the total effect a product I would have on a tank. The factors that make up the overall compatibility of a chemical l

to a rotomolded tank are chemical attack, solubility, absorption or permeation, and stress crack resistance. Each of these are discussed briefly.

Chemical Attack - By definition, chemical attack involves an actual chemical reaction with the plastic. This can be a breaking of molecular chains and/or addition of chemi-cal groups to the molecule. For example, in the case of an oxidation reaction with polyethylene both occur with the addition of carbonyl groups. This causes an eventual loss of properties to the point that a tank would not be serviceable, i Polyethylene in general is one of the most inert plastics available. Very few chemi-cats react with polyethylene, and even with those that do the rate is relatively slow. l The ultra high molecular weight characteristics of Marlex CL-100 and CL-50 resins after

, crosslinking makes these particular polyethylenes even more resistant than other grades. Therefore, chemical attack is not a factor in very many applications.

Permeation - This involves the physical absorption of the chemical into the polyethy- l lene. If this is a volatile chemical, then an actual loss of the product can occur as l the chemical vaporizes from the outer wall of the tank. The amount of absorption is Also, the loss of p generally limited to 3-7 percent by weight of the polyethylene.

volatile products is relatively small. For example, a 25-gallon tank with a 50-mil wall will only lose between 5 and 6 grams of gasoline a day due to permeation. The thicker the wall, the lower the rate of loss. -

The absorption of a product into the wall of a tank will cause some property changes. 4 The tensile strength is reduced approximately 10%, stiffner' approximately 25%, and a Norma 11, this does not affect the linear and radial swell of from 1 to 5% will occur.It does, utility of the tank nor prohibit the application. however, limit the tempera-ture at stich the tank can be used because the loss of these properties becomes a detemining factor as the temperature is increased. Also, if a cl.emical has too low a boiling point, the vapor pressure may be so high as to cause prohibitive distortion of the tank. This is why such chemicals as ether, pentane, etc. , would not be suitable for storage in a sealed tank.

Solubility and Stress Resistance - Although these factors are to be considered with other plastics it is of no sir. tificance with Marlex CL-100 or CL-50. There are no Also, when properly molded and known solvents at ambient conditions for these resins.

used, the phenomena of stress cracking just doesn't occur.

APPLICATION ENCIMEERING The appendix contains tables of chemicals indicating their compatibility with tanks solded using Marlex CL-100 and CL-50 resins. Table 1 lists chemicals that are suitable up to 1500F (660C) without further qualification. Table II and III lists chemicals q that permes.e or are absorbed by the polyethylene. In these cases the use conditions l

l

\

a. . so.

Page 9 of 15 should be more thoroughly considered. For example, most of these chemicals are flam- !

It should be determined if this would present a safety or code problem. Other i

considerations would be: 1) are the tanks vented, 2) are they in a confined or open O'mable.

space, and 3) personnel exposure, i In Table IV chemicals are listed that either attack polyethylene or have high Thisvapor does I pressure and are not normally recommended for long service life of the tank. . It may be not automatically preclude tanks from being used with these chemicals.

economical to periodically replace the tank after a relatively short service life. '

Factors such as life of the currently used tanks, cost of tanks made using exotic materials, and the consequences if a failure occurs should all be considered.

SUl#tARY Marlex CL-100 and C1.-50 rotational molding crosslinkable HDPE is one of the most chemi-cal resistant plastics manufactured today. It is not without limits, however, and the attached tables should be used only as a guide in determining those applications which are suitable.

O CHEM:126 .

ais .. ...

Page 10 of 15 l

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1 AFFENDII It has been well documented over tha years the types of chemicals that are compatible with polyethylene, either through tests or experience.

It would be impossible to list all the chemicals that may be involved in use with polyethylene storage tanks. Therefore, the included tables are only representative of typical chemicals.

Also, their rankings are specific to the application of chemical storage tanks and the superior properties of Marlex' CL-100 and CL-50.

The following tables are to be used only as a guide for establishing those uses that would give satisfactory service. They are not a substitute for a - angineering. .

l l

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!O .-. .

aas a .. v. .s TAB 12 I

() The following chemicals do not attack nor perme a t e Marlex

  • CL-100 or CL-50 resins up to 1500F (66oC). For temperatures over 1500F (650C) each application should be considered individually. All concentrations apply except where noted.

Gallic Acid Photographie Solutions Acetic Acid Propyl Alcohol Aluminum Salts Cluconic Acid Glycol Ethers Propylene Glycol Alum Ammonium Hydroxide Glycolic Acid Sea Water Ammonium Salts Hexanol Selenic Acid Hydrazine <35% Sewage Amyl Alcohol Antimony Salts Hydrotine Hydrochloride Silicic Acid Arsenic Acid Hydriodie Acid Silver Sales Barium Hydroxide Hydrobromic Acid Soap Solutions Hydrocyanic Acid Sodium Acrylates Barium Salts Sodium Ferricyanide Benzene Sulfonic Acid Hydrochloric Acid Hydrofluoric Acid Sodium Ferrocyanide Bismuth Salts Sodium Hydroxide Boric Acid Hydrofluotsilicic Acid Hydrogen Peroxide <30% Sodium Hypochlorite <16%

Bromic Acid Butanediol Hydrogen Phosphide Sodium Salts Butyl Alcohol Hydroquinone Sodium Sulfonates Calcium Hydroxide Hypochorous Acid Stanic Salts Calcium Sales Iodine Solutions Stannous Salts Chromic Acid < 50% Lactic Acid Starch Solutions Citric Acid Latex Stearic Acid

() Copper Salts Detergents Diazo Salts Lead Acetate Magnesium Salts Mercuric Salts f e -

Sulfuric Acid <98%*

Sulfurov- Acid Jugar Solutions i

1 Diethyl Carbonate Mercurous Salts - E ~ . 4 Glucose Mercury ~ Lactose Diethanol Amine -

Sucrose, etc.

Diethylene Glycol Methyl Alcohol Diglycolic Acid Methylsulfurie Acid Tannic Acid Hickle Salts Tanning Extracts Dimethylamine Dimethyl Formamide Nicotinic Acid Tartarie Acid Ethyl Alcohol Nitric Acid < 30% Titinium Sales Ethylene Glycol Oxalic Acid Toluene Sulfonic Acid Perchloric Acid Triethanolamine Ferrie Salts Urea Ferrous Salts Phenol < 10%

Potassium Hydroxide Vinegar Fluoboric Acid Wetting Agents Flousilicic Acid Potassium Salts Formic Acid Phosphorse Acid Zine Salts

  • Under some conditions acid will discolor. .

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' Siu-u-va vuo Page 12 of 15 TABLJL II O'

The following oils and organic chemicals do not attack Marlex' CL-100 or CL-50 resins. They will be absorbed into the well of the tank but there should be no loss of product. Because of this absorption, if tanks would be used for other service, contamination may result as the absorbed oil is les'ched out. Service at elevated temperatures up to 1500F (660C) can be recomended provided the effects of the absorption on the properties of the tank are not prohibitive.

Fatty Acids Butyric Lauric Linoleic Oleic Palmitic Stearic Mineral Oila Lube Transformer O Hydraulic Vegetable Oils Corn Coconut Cottenseed Olive Peanut Animal Fata Lard l Fish oil Musk oil Whale oil l

l 1

I l

  • TAB 12 III O The following organic chemicals do not attack Marlex' CL-100 or CL-50 resins.

They will be absorbed into the wall of the tank and a permeation loss will occur. Because of this premestion and the effect it has on the physical properties of the tank it is generally not reconnended they be used above 1000F (380C). However, their use largely depends on such factors as size of the tank, its location, toxicity of the chemical, and applicable codes such as NFPA, OSHA, etc. This is not to discourage these chemical storage applications in which considerable experience with many has been documented on various polyethylene containers. For example, polyethylene gasoline tanks are used on lawn movers, tractors, trucks, ATVs, snowmobiles, and as portable containers-even approved safety cans.

Aniline Benzene Carbon Tetrachloride Chlorabenzene Cychohexanol Cyclohexanone Dibuty1phthalate Diesel Fuel Dimethylamine Ethyl Butyrate Ethylene Chlorohydrin O. Fuel Oil

  • Furfural Aliphatic hydrocarbons (hexane, octane, hexene, octene, etc.)

Jet fuel Gasoline Nitrobenzene Octyl Cresol Propylene dichloride Toluene Xylene O

. aiu s v.2 vv.

l

  • Page 14 of 15

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l TAB 12 TV l U,n The following chemicals are not rec onenended for general storage in tanks molded using Marlex' CL-100 or CL-50 resins. Their effect is not immediate

- nor catastrophic in nature. Therefore, under certain cirevastances, tanks )

could be used either for the short ters or in a limited life situation, f Temperature is especially important!

1 Chenical Attack i

Aqua Regia Bromine Chromic / Sulfuric acid Fuming Sulfuric acid Nitric Acid >50%

Organic peroxides Phenol-concentrated Eigh Vapor Pressure Acetone Butane p Carben Disulphide g

Chloroform 5 -; Ethyl Ether

- Ethylene Dichloride Methylene Chloride Methyl Ethyl Ketone Propane Pentane

- - - ~

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  • gAntg y Page 15 of 15 AFPLICATIOUIS OF CROSSLINKID EDFE CEDGCAL TANKS AGEICULTURAL en

\ Type of Type of

- Tank Use H* V* S* P*

Size of Tank Years in Chemical Handled Service (gallons)*

X X 7 Cattle Supplements 5600 X X X 10 Insecticides 50 to 1500 X X X X 10 Herbicides 50 to 1500 X (Bicep. Dual, Setan. Lasso)

X X X 8 Liquid Fertilizer 100 to 5600 X X X 8 Nitrogen Solution 5600 X X 8 Phosphoric Acid 1500 to 5600 X X 8 Sulphur Solution 5600 X X 6 Treflan 200 INDUSTRIAL gb r Hydrochloric Acid 5600 X X 8 (37: and lower)

X X 6 Hydrofluoric Acid 55 to 2500 X X X 8 Sulfuric Acid 400 to 12,000 (98% and lower)

X X 8 Propionic Acid 5600 X X 8 Sodium Hypochlorite 4250 to 12,000 1500 to 12,000 X X 8 Sodium Hydroxide X X X 5 Hydrrgen Peroxide (52%) 55 to 1600 X X X 8 Alum 5600 X X 5 Cactus Juice 1500 to 6000 X X X 8 Detergents 100 to 6000 X X X 8 Floor Finishes & Cleaners 5600 X X 8 Latex 6400 I X 8 Oil Well Additives 200 to 1500 J .7 X 4 3000 X Plating Solutions X X 8 Waste Water 12,000 O H - Horizontal

  • Constant to convert gallons to liters -

gallons x 3.7854 = liters V - Vertical S - Stationary

)

P - Portable 1

.g.

f Document Number: Rev: L% Deter WESTINGHOUSE STD-P-03-008 5 p 6/_13485 N

Title:

Transfer & Devacering Powdered Resin in Hittman PORATED RADLOKE100,-200, or -500 containers with a Flexible Underdrain Assembly to less Than 1% Drainable Licuid. .

Supervisor Director QA

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y AND DEWATERING POWDERED RESIN IN HITmAN RADLOK -100, -200, OR -500 CONTAINERS WITH A FLEXIBLE UNDERDRAIN ASSIMBLY 70 LESS THAN 11, DRAINABLE LIQUID 1.0 SCOPE This procedure is applicable to RADLOK-100, -200, and -500 High Integrity Containers with multi-layered flexible dewatering under-drains for dewatering unsolidified powdered ion exchange resins.

2.0 PURPOSE To provide general instructions for the transfer and dewatering of powdered resin in RADLOK containers with flexible dewatering underdrains to meet burial site criteria of less than one percent drainable liquid upon receipt at the site. This procedure also l assures that there is no drainable liquid at the time of shipment i from the plant.

3.0 REFERENCES

3.1 Hittaan RADLOK High Integrity Container Rad Services Manual, RSM-014.

3.2 Hittaan drawing, STD-03-051, Sheet 4, RADLOK-100 and -500 Three Layer Underdrain Assembly. ,

3.3 Hittman drawing, STD-03-075, Equipment Arrangement for RADLOK-100 and -500 containers with Three Layer Underdrain.

3.4 Hittaan drawing, STD-03-084, Sheet 4, RADLOK-200 Two Layer Underdrain Assembly.

3.5 Hittaan drawing, STD-03-091, Equipment Arrangement for RADLOK-200 Container with Two Layer Underdrain.

3.6 P,ittaan report, STD-R-03-0057MSummary Report of Powdered Resin Dewatering in a RADLOK Container.

3.7 Hittaan report, STD-R-03-006, Powdered Resin Dewatering in a l

Flat Botton Container Using the Hittaan Layered Underdrain l System.

3.8 Ifitta9n procedure, STD-P-03-003, RADLOK Manway Assembly Closure and Sealing Procedure.

l 1

l 3.9 Hittaan procedure, STD-P-03-004, Closure of Hittman RADLOX l

High Integrity Container Fill Port Closure Assembly.

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1 ._ _ - _ _ _ _ _ _ _ _ _ _

. STD-P-03-008

  • Paga 3 of 7 f3 3.10 Rittman procedure, STD-P-03-020, RADLOK Inspection Procedure.

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4.0 EQUIPMENT 4.1 Diaphragm pump 1-1/2" or equivalent with interconnecting hoses, quick disconnect fittings and clamps as required.

4.2 Hoses with fittings and clamps as required to connect f os service air sy,..ee to the diaphram pump. Minimum service air required is 40 SCFM at 100 psig.

4.3 Vacuum pump with minimum suction of 25 inches of mercury (29.9 inches Hg vacuum equals absolute vacuum) and 1/4 inch vacuum hoses.

4.4 Receiver tank with connecting hoaes to the RADLOK container.

4.5 Overflow drum with connecting hoses to the RADLOK container (optional).

4.6 Liner level indicator panel.

4.7 Receiver tank level indicator panel.

4.8 Standpipes.

5.0 EQUIPMENT SET-UP .

5.1 Prerequisites 5.1.1 The container has been satisfactorily inspected per STD-P-03-020.

5.2 Precautions None.

- 5.3 Assembly 5 '. 3.1 SET-UP equipment in accordance with Drawings STD-03-051, Sheet 4, and STD-03-075 for the RADLOK-100 or -500 or Drawings STD-03-084, Sheet 4 and STD-03-091 for the RADLOK-200.

6.0 TRANSFER AND DEWATERING l

6.1 Prerequisites 6.1.1 The equipment is set up in accordance with Section l

i 5.3.1 of this procedure.

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STD-P-03-008 Pago 4 cf 7 F

6.1.2 An RWP is issued and Health Physics is notified prior to the waste transfer.

6.1.3 All valves on receiver tank except between tank and vacuus pump are closed.

6.2 Precautions 6.2.1 Be aware of changing radiological conditions as waste is transferred to the container and the con-tainer is dewatered.

6.2.2 If the RADLOK container is to be lifted after waste transfer has begun and before all processing is complete, a bottom support plate shall be utilized to prevent damage to the container internals.

Consult Hittman home office for additional informa-tion.

6.3 Operating Steps NOTE: Following establishment of initial vacuum in Step 6.3.1, the air inlet valve on the receiver tank shall be used to maintain vacuum between 15 and 20 inches of Hg during the entire de-O wateri'ng process.

6.3.1 START the vacuus pump on' the receiver tank ind establish a vacuum of approximately 15 inches Hg.

NOTE: The diaphragm pump may be used to assist vacuum pump to establish desired vacuum.

6.3.2 START the transfer of waste in accordance with the appropriate system operating procedure.

6.3.3, TRANSFER until 50-100 gallons of waste are in the contair.ar and the bottom dewatering layer is covered.

6.'3.4 OPEN the bottom devatering layer isolation valve

- to the receiver tank while continuing the transfer.

NOTE: This valve will ressin open throughout the entire operation.

, g I

6.3.5 START the diaphragm pump when the receiver tank level indicator panel indicates "OP/HI".

I NOTE: Maintain diaphragm pump vacuum at least 5 inches of Hg greater than receiver tank vacuum.

.' 6.3.6 Immediately STOP the waste transfer when the liner

! level indicator panel sounds an "0P/HI" alam.

)

STD-P-03-008 Page 5 of 7 O NOTE: The receiver tank vacuum shall be modulated to maintain water level in the receiver tank between the "0P/ LOW" and "0P/RI" levels.

CAUTION: IF THE "HI/HI" LEVEL ON THE RECEIVER TANK ALARMS, TAKE IMMEDIATE ACTION TO REDUCE OR TERMINATE INFLUENT TO TE RECEIVER TANK UNTIL TE "0P/HI" LEVEL CLEARS. THIS CAN BE ACCOM-PLISHED BY SHVITING THE ISOLATION VALVES OR BY DECREASING THE VACUUM IN THE RECEIVER TANK.

6.3.7 CONTINUE dewatering from the bottoe lateral while allowing the solids to settle in the container for 30 minutes.

6.3.8 OPEN the devatering layer isolation valves to all remaining devatering layers.

6.3.9 When vacuum is lost, CLOSE top dewatering layer isolation valve. For RADLOK-200 containers, pro-ceed to Step 6.3.12 at this time.

6.3.10 CONTINUE dewatering until vacuum is lost again.

() 6.3.11 CLOSE middle dewatering layer isolation valve.

. r F h 6.3.12 RESTART waste transfer to container until "0P/HI'; [g A_ J f alarms. Repeat Steps 6.3.6 through 6.3.10 until "0P/ LOW" does not silence upon reaching loss o2 -

vacuum on the top laterals.

6.3.13 STOP the transfer operation.

NOTE: The waste transfer operation is now complete.

6.3.14 FLUSH the transfer line in accordance with the appropriate system operating procedure.

6.3.15 As the liquid level falls below the devatering

elements and vacuum in the receiver tank reduces by approximately ten (10) inches of mercury, CLOSE the devatering element isolation valves sequen-tially starting at the top. Allow time between l

i each isolation for the vacuum to recover and the container to dewater to the next lower layer.

6.3.16 CONTINUE the dewatering process through the lowest dewatering element for four hours after vacuum is lost. This completes the dewatering process.

O NOTE: If a container is expected to remain on-site for more than six (6) days after completion i

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STD-P-03-008 l Paga 6 of 7 l

.. J of final dewatering (Step 6.3.16), then Steps l 6.3.17 through 6.3.21 should be followed. This I will ensure compliance with Section 10.4.1 of l ANSI /ANS-55.1-1979 which states that "processed l solid weste, when ready for shipment, will not I 1

contain free liquid...".

6.3.17 CONNECT the suction hose from the diaphrsga pump directly to the bottom layer dewatering pipe exten-sion.

l 6.3.18 START the diaphragm pump. l 6.3.19 REGULATE the pump suction vacuum at approximately j 15 inches of vacuum. '

(

1 6.3.20 APPLY vacuum for a minimum of four (4) hours.

6.3.21 DISCONNECT the diaphragm pump suction hose from i the bottom layer dewatering pipe extension. l 1

I 7.0 DISCONNECTION AND CLOSURE OF CONTAINER 1

7.1 Prerequisites

~

The waste transfer and devatering operations are complete and ]

subsequent transfers of waste to the container are not placned.

l 7.2 Precautions As hoses are disconnected, be careful not to spill any residual water.

7.3 operating Steps 7.3.1 DISCONNECT the waste transfer line from the fill

, pipe extension. -

7.3.2 REMOVE the fill pipe extension from the container.

l 7.3.3 DISCONNECT the dewatering hoses from the devatering j pipe extensions on the container. ,

7,. 3 . 4, REMOVE the dewatering pipe extensions from the l container.

l 7.3.5 DISCONNECT the vent / overflow hose from the vent / )

overflow pipe extension.

7.3.6 REMOVE the vent / overflow pipe extension from the j container.

i

STD-P-03-008 Pass 7 of 7

'y .

O 7.3.7 DISCONNECT the electrical cables from container.

This can be accomplished by cutting the wire close to the fill plate or by unplugging.

NOTE: At this time the container may be secured.

7.3.8 DRAIN the receiver tank.

30H O .

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Document Number: Rav: Rsv Date:

STD-D-03-009 9 l-31-86 HITTMAN NUCLEAR &

D R TO

Title:

<A Userfs Manual for the.Hittman n

RADLok 500, and RADLOK 100 RADLOL -200, Responsible Department Director QA Pr oj ect Engineer Manager Engineering Manager Manager Rev. Rev Date 0* 4-16-82 y( . p 8 12 9 h 8. A0WE i W 8 -122 1* 6-9-82 4 .? '*

/ 9 4

2* 10-25-82 -227 3 1-4-83  ! 297 4 10-3-83 g) i l '

/ , *[3)158 5 2-9-84 -

8 bo9 6 6-6-84 '

b91 l <

7 6/6/85 '

b32

i. ECN-8 12/20/85 ,

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9 1-31-86 M [ 231 v

-cm mn) ee~ t a 18

. STD-D-03-009 Page 2 of 18 A

RADLOK, USERS

-200, RADLOX MANUAL,

-500, andTOR THE-HITTMAN , 100 RADLOK Purpose The high integrity container is designed to provide waste isolation

-from the surrounding environment for a period of-300 years. Various un-solidified wastes may be disposed of at Barnwell, however, if the total specific activities of isotopes with half lives greater than five years is lp Ci/ml or greater, high integrity containers approved by the South Caro-lina Department of Health and Environmental Control must be used.

This document is intended to provide the user of Hittman RADLOK con-tainers with basic information required for the safe and proper use of the container. Included is a general description of the containers, a listing of the approved contents, a listing of prohibited ehemicals, and the handling / storage requirements of a RADLOK container. Inspection require-ments prior to usage, lift requirements, and closure methods are also provided. The user must also refer to the requirements of the respective container certificate of compliance from the burial site.

Description of the Hittman RADLOK-200, RADLOK-500, AND RADLOK-100 The Hittman RADLOK containers have the following approximate envelope dimensions (listed from smallest to largest container):

Approx. Height Approx. Diameter Gross Weight (loadedl h

RADLOK-200 61" 53" 5,500 lb.

RADLOK-500 66" 72" 9,500 lbs.

RADLOK-100 72" 72" 10,500 lbs.

All containers have a domed top that contains a concentric 16 inch diameter manway opening for possible underdrain installation and an 8 inch diameter' fill port. Containers are fabricated frem high density cross-linked polyethylene, molded to provide a one-piece body to the container. An underdrain system can be provided for either dewatering slurries trans-ferred to the container or for disposable demineralizer applications. An approved vent is provided in the closure components of each container. An approved vent is required on containers buried after March 1, 1986. 1 i

Approved Contents Hittman RADLOK containers have been designed to safely contain nuclear wastes including bead and powdered ion exchange resin, filter sludges, mechanical filters, stabilized incinerator ash, activated carbon, contami-nated soil, and sandblasting grit. It should be noted that dewatering ion-exchange resin that has been in contact with nitrates or other strong oxidizing agents can be hazardous and should be avoided. Procedures for O loading metal filters, scrap and other non-compactible trash into a RADLOK container to ensure that protrusions and sharp edges do not damage the container must be submitted and approved by Hittman. The container may not contain free standing water greater than 1 percent of the waste volume.

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l Packaging Criteria for RADLOK-200

! Waste Category, Rigid Metal Filter Cartrid Re Elements with Exposed Metal Scrap, Non-Compactible filters Ends Noncompactible Compactible Trash Trash Eleme nt s Trash with No Sharp Edges with Sharp Edges Parameter Maximum Length of l Individual Piece 48" 40" 40" Placed Horizontal none l

none 40" 40" 30" Placed Vertical Pecking Material l none none cement, vermiculite, sand, gravel, etc.

1" 3" Min. Depth of Packing2 N/A N/A Material on Bottom none none pipe end and Padding 3 none sharp edges none none none 3" Min. dist. waste to vall none fill voids 2" Packing between none layers 4 as loaded Maximum Depth to underside of fill neck 3" below underside of fill neck of Waste none cover contents cover contents plus 3" Final Filling 4 none 3The packing material is used to protect the interior of the container and to prevent excessive o us cettling of the waste during transit. Only required of waste that. could potentially damage the C, e, container.

w? o 2To be placed in container prior to waste. ow Among other items, rubber sheet or styrofoam blocks 8 3To protect container walls if necessary.

may be used. Only required on sharp edges or ends of rough cut pipe.

j 4 0nly necessary when packing material is used as defined in footnote number 8

} O V

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Packaging Criteria for RADLOK-500 Waste Category Rigid Metal Filter Cartridge Elements with Exposed Metal Scrap, Non-Compact.ible filters Ends Noncompactible Compactible Trash Trash Elements Trash with No Sharp Edges with Sharp Edges Parameter Maximum Length of Individual Piece 62" 54", 54" Placed Horizontal none 36" Placed Vertical none 4ff' 48" l

l Packing Material l none All voids shall be filled with either cement. vermiculite, sand, gravel, etc.

2 N/A 1" 3" l Min.DepthofPacking N/A l

, Material on Bottom I

f Padding 3 none none none pipe end and sharp edges t

i none none none 3" Min. dist. waste to wall fill voids 2" Pecking between none fill voids as loaded layers 4 as loaded Maximum Depth to underside of fill neck 3" below underside of fill neck of Waste fill voids & cover Final Filling

  • none fill voids fill voids & cover contents contents plus 3"
The packing material is used to protect the interior of the container and to prevent excessive settling of the waste during transit. 7$

$?

eT o

2To be placed in container prior to waste.

-a

S 3To protect container walls if necessary. Among other items, rubber sheet or styrofoam blocks cay be used. Only required on sharp edges or ends of rough cut pipe.

4 0nly necessary when packing material is used as defined in footnote number 8

~~

p O'

Packaging Criterin for RADLOK-100 Waste Categoy Rigid Metal Filter Cartridge Elements with Exposed Metal Scrap, Non-Compactible filters Ends Noncompactible Compactible Trash Elements Trash with No Sharp Edges with Sharp Edges Parameter Trash Maximum Length of Individual Piece 68" 60" 60" Placed Horizontal none 48" 48" 36" Placed Vertical none Packing Materia 1 8 none none cement, vermiculite, sand, gravel, etc.

1" 3" Min. Depth of Packing 2 N/A N/A Material on Bottom none none pipe end and Padding 8 none sharp edges none none 3" Min. dist. waste to none vall none fill voids 2" Pecking between none as loaded layers i ,

Maximum Depth to underside of fill neck 3" below underside of fill neck of Waste cover contents cover contents plus 3" Final Filling4 none none 8 The packing material is used to protect the interior of the container and to prevent excessive ym settling of the waste during transit. Only required of waste that could potentially damage the gh container. v.%'

, ,o 2 To be placed in container prior to waste. *'

c>

go 3 To protect container walls if necessary. Among other items, rubber sheet or styrofoam blocks may be used. Only required on sharp edges or ends of rough cut pipe.

8 4 0nly necessary when packing material is used as defined in footnote number

- )

STD-D-03-009 Pege 6 of 18 Hittman standard dewatering procedures, provided in the Hittman Rad Ser-

/ vices Manual for RADLOK Containers, may be used by reference to the appro-V) priate document number.

Criteria for Packaging of Filter Elements and Scrap The tables provide the criteria for the packaging of filter elements and scrap in Hittman RADLOK containers that shall be used in developing the required procedures.

Prohibited Contents Included in this guide, as Attachment A, is a copy of a MARLEX Resins Technical Service Memorandum from Phillips Chemical Company, No. TSM-293, Chemical Resistance of Marlex CL-100 and CL-50 Rotational Molding Cross-linkable High Density Polyethylenes, dated December 1982. This document lists those chemicals that are incompatible with the material used in RADLOK high integrity containers. (Note: This document is oriented towards those applications where tanks manufactured using CL-100 (or CL-50) are used to store these chemicals in their pure form and not as contami-nants in other materials.) When using a Hittman RADLOK, those chemicals listed in Table IV of the Appendix to Attachment A are considered prohi-bited and may not be disposed of in RADLOK high integrity containers.

Chemicals listed elsewhere in the Appendix are not prohibited when disposed of as incidental contaminants to radioactive wastes.

Thermal Limitations

's.) The Hittman RADLOK containers are licensed with a temperature limita-tion of 170*F for handling, lifting, and disposal operations. At no time is the container to be subjected to a temperature in excess of 200*F due to any process or its contents. When the containers include underdrain systems for processing waste, the maximum permitted temperature is reduced to 140*F because of the materials used in the underdrain assembly.

These thermal limitations apply to the containment of all anticipated waste forms including, where present, incidental chemical contaminants (as contaminants, the chemicals listed in Table 1 of Attachment A are accept-able at the above temperature limits).

Storage Conditions Hittman RADLOK containers may be stored under proper conditions for periods up to two years before use. Storage of unused Hittman RADLOK con-tainers for periods longer than two years will require specific Hittman approval following review of the conditions under which the containers are stored. As a photosensitive material, the containers shall be kept out of direct sunlight, and away from any other sources of ultraviolet radiation.

Containers stored out of doors in direct sunlight must be used within one year of fabrication. To minimize any chance of damage to a container with an underdrain system, the container should be kept out of sub-freezing

<'" weather conditions. Containers shall be stored in such a way that the k ,g) bottom is flat and that no weight is located over the manway/ fill port area. This is to ensure that no potential deformation of the manway/ fill port area of the container or seal material occurs. Each container shall

STD-D-03-009 Page 7 of 18 be stored with its designated closure assemblies to prevent mismatching.

.7_s The RADLOK containers are shipped palletized for protection and handling

/

\ convenience. The container should remain palletized until just before use to extend this protection.

Following filling and closure of the container, it may be stored ,

on-site prior to shipment for burial for up to five (5) years. The design of the facility must preclude the possibility of a wet or damp environment and any prolonged exposure of the container to any source of ultraviolet light. Short exposures to ultraviolet light such as during placement or inspection are permitted. Storage of RADLOK containers for periods longer than five (5) years after filling will require spe.ific Hittman approval following a review of the user's storage facility oesign.

Inspection Prior to Use Prior to the use of a container to either receive waste material or to be put in service as a portable demineralizer, the following items must be checked. The fill port closure assembly, consisting of the seals and the fill port lid bolted to the compression plug, is accounted for and in good condition. The manway assembly parts are installed on the container (usually shipped this way) and in good condition. Seals are not hard or brittle and are free of defects. Thread areas and seal areas are free of foreign matter that could impair the seal or thread engagement. The exterior surfaces shall be inspected for damage that may have occured during trans-port or storage that could lessen container integrity. See the RADLOK Inspection Procedure, STD-P-03-020, for a detailed inspection procedure.

The manway lid shall be inspected for sufficient closure. There should be less than a 3/4-inch space between the bottom of the manway lid and the container body when properly closed. If this is not the case, refer to Hittman procedure STD-P-03-003 in the Rad Services Manual for proper closure methods.

Handling and Lift Requirements The Hittman RADLOK-200, RADLOK-500, and RADLOK-100 containers come equipped with a lift band, lift lugs, and two slings for lifting. Under maximum load conditions, the entire assembly would have a gross weight as listed earlier. The lift assembly for each container is designed to accomo-date the respective weight when both slings are used and a 3g abrupt lift is applied. It is recommended that both slings be used when lifting the container in an empty condition. The container shall not be lifted by one sling if it is partially or totally full. If an underdrained RADLOK con-toiner is to be lifted after waste transfer has regun and before all process-ing is complete, a bottom support plate shall be utilized to prevent damage to the container internals. Consult the Hittman home office for additional info rma tion. Note: Due to the nature of the container material, some bowing and deformation may be evident during lif ting. This is an antici-pated condition.

/

Underdrained RADLOKs must be handled with reasonable care to prevent (m- damage to the underdrain. A thorough inspection of the underdrain should

STD-D-03-009 Page 8 of 18 1

- be accomplished following rough handling (e.g., container dropped or banged

[ .,' against another object).

s The polyethylene container has extraordinary resilience but can be damaged (scraped or gouged) by sharp objects with sufficient application force (e.g., fork lift tines, setting the container down on sharp objects or abrasive surfaces). Reasonable care during handling (and using the pallet provided) will prevent this type of damage.

Remote grapples are available for remote handling of RADLOK containers.

Use of these grapples allows for remote pickup and set down in non-accessible  ;

areas such as interim and long-term storage facilities. Reusable grapples (removed when the containers are loaded for shipment) and disposable grapples are available for the RADLOK containers.

Manway Use and Closure The Hittman RADLOK containers are equipped with two concentric open-ings, a 16 inch diameter manway and an 8 inch diameter fill port. The manway opening is used in the installation of any internals and will be sealed prior to arrival at the user's site. If, for various reasons, it is desirable to use the manway as a large diameter "fill" port, advise Hittman and the appropriate measures will be taken.

Fill Port Use and Closure The standard fill port on the Hittman RADLOK container is an eight

('~/}

x_ inch opening. The fill port it, concentric with the manway opening, and is sealed with the fill port closure assembly. Two seals are attached to the compression plug of the fill port closure assembly. The assembly is then lowered into the opening and screwed into position to a prescribed torque.

For details of the closure procedure see Hittman procedure STD-P-03-004.

If the container is to be used as a Type A container the lid shall be secured for transportation to prevent illicit opening. Details concerning methods of securing the lid are also provided in procedure STD-P-03-004.

12M

Page 9 of 18 4

O ATTACHMENT A TO STD-D-03-009 CHEMICAL RESISTANCE OF MALLEX CL-100 AND CL-50 ROTATIONAL MOLDING CROSSLINKABLE HIGH DENSITY POLYETHYLENES O .

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~ IIAR * - nasims m an cam ussaS sem anuma PHILLIPS CHEMICAL COMPANY a sussician, ce paimes ettmosavu coupa v PLASTCS TECHNICAL CENTER samT6tsmst ouaaoua 14oon TECHNsCAL SEnveCE' MEMenANeuw STD-D-03-009 Page 10 of 18 TSH-293 DECEM3E R , 1982 CHEMICAL RESISTANCE OF MARLEX CL-100 AND CL-50 ROTATIONAL MOLDING CROSSLINKABLE HICH DENSITY POLYETHYLENES INTRODUCTIOM One of the most rapidly growing plastics applications is relatively large rotational molded storage tanks. This application and its growth has been keyed to the develop- '

ment and marketing of crosslinkable high density polyethylenes by Phillips Chemical  ;

Company. These polyethylenes are marketed under the designation of Marlex CL-100 and CL-50 rotational molding crosslinkable high density polyethylene.

In addition Rotational molding is ideally suited for the manufacture of large tanks. '

the unique toughness, chemical and stress crack resistance of the Marlex CL-100 and CL-resins are needed for the demanding requirements in industry andToday agriculture for O

t 50 tanks are chemical storage tanks and are the key to this expanding market. storage  ;

molded as large as 15,000 gallons (57,000_, liters) and are used in such diverse applications as acids, insecticides, and chemilal flantivaste by-products.

l I

The scope of this Technical Service Memorandum is to address the question of compati-

) bility of chemicals with Marlex CL-100 and CL-50 resins in relation to storage tanks. are ,

Engineering principles used in determining the suitability of a given application discussed. Lists of chemicals both suitable and not suitable are included in the appendix along with any limitations which may apply.

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m o__ _.e _ _ _f une are tercre w conen:s tr*:msnon roi c.mm camcs en gterenteed w- ew cermors o preeriod Perse a gun w#trenA rudersrce to ar'y patent chesucre wh:A may to eraveered e be m W

%:n viabore arcued be rws**;s**1 tv ?cee e tNo h PNece Chemcal Cm emeuma rc

.  % v, , , a - 9 , - m m . y ,3 % M m d W *y e v as'sao w w

> 1 D - D - v a - v u s Page 11 of 18 (S CBDOCAL RESISTANCE U "Chemical resistance" and "compatibility" are synonymous terms used in relation to the In regard to polyethylene l chility of a plastic to function in dif ferent environments.

chemical storage tanks, chemical resistance encompasses the total effect a product would have on a tank. The factors that make up the overall compatibility of a chemical to a rotomolded tank are chemical attack, solubility, absorption or pe rme a t ion , and stress crack resistance. Each of these are discussed briefly.

Chemical Attack - By definition, chemical attack involves an actual chemical reaction with the plastic. This can be a breaking of molecular chains and/or addition of chemi-cal groups to the molecule. For example, in the case of an oxidation reaction with j polyethylene both occur with the addition of carbonyl groups. This causes an eventual l loss of properties to the point that a tank would not be serviceable.

Very few chemi-Polyethylene in general is one of the most inert plastics available.

cals react with polyethylene, and even with those that do the rate is relatively slow.

The ultra high molecular weight characteristics of Marlex CL-100 and CL-50 resins after ,

crosslinking makes these particular polyethylenes even more resistant than other grades. Therefore, chemical attack is not a factor in very many applications.

1

)

Permeation - This involves the physical absorption of the chemical into the polyethy-can occur as If this is a volatile chemical, then an actual loss of the product l the chemical vaporizes from the outer wall of the tank. The amount of absorption is lent. ,

Also, the loss of )

generally limited to 3-7 percent by weight of the polyethylene. tank with a 50-=il volatile products is relatively small. For example, aa 25-gallen day due to permeation. The g wallthicker will only lose between 5 and 6 grams of the wall, the lower the rate of loss. gasoline )

l The absorption of a product into the vall of a tank will cause some property changes.

The tensile strength is reduced approximately 10%, stiffness approximately 25%, and a  ;

Normally this does not affect the l linear and radial swell of from 1 to 5% wil'. occur.It does, however, limit the tempera-utility of the tank nor prohibit the application.

ture at which the tank can be used because the loss of these properties becomes a detemining f actor as the temperature is increased. Also, if a chemical has too lov a boiling point, the vapor pressure may be so high as to cause prohibitive distortion of i the tank. This is why such chemicals as ether, pentane, etc., would not be suitable for storage in a sealed tank.

j Solubility and Stress Resistance - Although these factors are to be considered with There are no  ;

other plastics it is of no significance with Marlex CL-100 or CL-50.

Also, when properly molded and known solvents at ambient conditions for these resins. ,

used, the phenomena of stress cracking just doesn't occur. l i

APPLICATION ENGINEERIMC 1 The appendix contains tables of chemicals indicating their tempatibility with tanks molded using Marlex CL-100 and CL-50 resins. Table I lists chemicals that are suitable up to 1500F (660C) without further qualification. Table .II and III lists chemicals In these cases the use conditions that permeate or are absorbed by the polyethylene.

l

Page 12 of le should be more thoroughly considered. For example, most of these chemicals are flam-mable. It should be determined if this would pr"at a safety or code problem. Other i

2) are they in a confined or open considerations would be: 1) are the tanks van ,

space, and 3) personnel exposure.

In Table IV chemicals are listed that either attack polyethylene or have high vapor life of the tank. This does pressure and are not normally recommended for long service It may be not automatically preclude tanks from being used with these chemicals.

economical to periodically replace the tank after a relatively short service life. ,

Factors such as life of the currently ased tanks, cost of tanks made using exotic materials, and the consequences if a failure occurs should all be considered. ,

i SIDetutY Marlex CL-100 and CL-50 rotational molding crosslinkable HDPE is one of the most chemi-cal resistant plastics manufactured today. It is not without limits, however, and the at tached tables should be used only as a guide in determining those applications which are suitable.

O CHEM: 126 l

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STD-D-03-009 Page 13 of 18 AFFENDIX It has been well documented over the years the types of chemicals that are compatible with polyethylene , either through tests or experience.

It would be impossible to list all the chemicals that may be involved in use with polyethylene storage tanks. Therefore, the included tables are only representative of typical chemicals.

Also, their rankings are specific to the application of chemical storage tanks and the superior properties of Marlex' CL-100 and CL-50.

The following tables are to be used only as a guide for establishing those uses that viuld give satisfactory service. They are not a

,' I substitute for sound engineering. .

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SID-D-03-009 Page 14 of 18 TAtt.X 1

\ The following chemicals do not attack nor pe rme a t e Ma rlex' CL-100 or CL-50 resins up to 1500F (660C). For temperatures over 1500F (650C) each application should be considered individually. All concentrations apply except where noted.

Acetic Acid Callie Acid Photographic Solutions Aluminum Salts Cluconic Acid Propyl Alcohol Alum Glycol Ethers Propylene Glycol Ammonium Hydroxide Glycolic Acid Sea Water Ammonium Salts Hexanol Selenic Acid Amyl Alcohol Hydrazine <35% Sewage Antimony Salts Hydrozine Hydrochloride Silicic Acid Arsenic Acid Hydriodic Acid Silver Salts Barium Hydroxide Hydrobromic Acid Soap Solutions Barium Salts Hydrocyanic Acid Sodium Acrylates Benzene Sulfonic Acid Hydrochloric Acid Sodium Ferricyanide Bismuth Salts Hydrofluoric Acid Sodium Ferrocyanide Boric Acid Hydrofluorsilicic Acid Sodium Hydroxide Bromic Acid Hydrogen Peroxide <30% Sodium Hypochlorite <16%

Butanediol Hydrogen Phosphide Sodium Salts Butyl Alcohol Hydroquinone Sodium Sulfonates k leium Hydroxide Hypochorous Acid Stanic Salts Calcium Sales Iodine Solutions Stannous Salts Chromic Acid <50% Lactic Acid Starch Solutions Citric Acid Latex Stearic Acid s_,/ Copper Sales Lead Acetate Sulfuric Acid <98%*

Detergents Magnesium Salts . Sulfurous Acid Diazo Salts Mercuric Sales Sugar Solutions Diethyl Carbonate Mercurous Sales Glucose Diethanol Amine Mercury Lactose Diethylene Glycol Methyl Alcohol Sucrose, etc.

Diglycolic Acid Methylsulfuric Acid Tannic Acid Dimethylamine Nickle Salts Tanning Extracts l

Dimethyl Formamide Nicotinic Acid Tartaric Acid Ethyl Alcohol Nitric Acid <30% Titinium Sales Ethylene Glycol Oxalic Acid Toluene Sulfonic Acid Ferrie Salts Per:bloric Acid Triethanolamine Phenol < 10% Urea Ferrous Salts ~

Vinegar Fluoboric Acid Potassium Hydroxide Flousilicie Acid Potassium Salts Wetting Agents Formic Acid Phosphoric Acid Zine Salts

  • Under some conditions acid will discolor. .

e 0 -

Page 15 of 18 8

  • TAB 12 II O The following oils and organic chemicals do not attack Martex* CL-100 or CL-50 resins. They will be absorbed into the wall of the tant but there should be no loss of product. Because of this absorption, if tanks would be .used for other service, contamination may result as the absorbed oil is lesched out. Service at elevated temperatures up to 1500F (660C) can be recommended provided the effects of the absorption on the properties of the tank are not prohibitive.

Fatty Acide Butyric Lauric Linoleic Oleic Palmitic Stearic Mineral Oils Lube Transformer Hydraulic O .

Vegetable Oils Corn Coconut Cottenseed Olive Peanut Animal Fate f

Lard i

' Fish oil Musk oil Whale oil 1

Page 16 of 18 TA312 III The following organic chemicals do not attack Marlex' CL-100 or CL-50 resins. i They will be absorbed into the wall of the tank and a permeation loss will occur. Because of this preseation and the effect it has on the physical properties of the tank it is generally not recounsended they be used above 1000F (380C). However, their use largely depends on such factors as size of l the tank, its location, toxicity of the chemical, and applicable codes such as NFPA, OSHA, etc. This is not to discourage these chemical storage applications in which considerable experience with many has been documented on various polyethylene containers. For example, polyethylene gasoline tanks are used on lawn movers, tractors, trucks, ATVs, snowmobiles, and as portable containers-even approved safety cans.

Aniline Benzene Carbon Tetrachloride Chlorabenzene Cychehexanol Cyclohexanone Dibuty1phthalate Diesel Fuel Dimethylamine Ethyl Butyrate s Ethylene Chlorohydrin Fuel Oil .

Furfural Aliphatic hydrocarbons (hexane, octane, hexene, octene, etc.)

Jet fuel Casoline Nitrobenzene Octyl Cresol Propylene dichloride Toluene Xylene l

l t

, Page 1/ of 18 \

TAB 12 IV O The following chemicals are not recommended for general storage in tanks molded using Marlex' CL-100 or CL-50 resins. Their effect is not immediate nor catastrophic in nature. Therefore, under certain circumstances, . tanks could be used either for the short ters or in ' a limited life situation.

Temperature is especially important!

Chemical Attack Aqua Regia Bromine Chromic / Sulfuric acid Fuming Sulfuric acid Nitric Acid >50%

Organic peroxides Phenol-concentrated Eigh Vapor Pressure Acetone Butane Carben Disulphide Chloroform Ethyl Ether .

Ethylene Dichloride Methylene Chloride Methyl Ethyl Ketone Propane Pentane l

l O

. Page 18 of 18

. TAB 12 Y AFFLICATIONS OF CROSSLINKED EDPR CEDQCAL TANES 4 i AGRIQTLTURAL O ,

'V Type of Type of J Tank Use H* V* $*  ?*

Size of Tank Years in Chemical Handled Service (gallons)*

X X 7 Cattle Supplements 5600 X X 10 Insecticides 50 to 1500 X X X X X 10 Herbicides 50'co 1500 X (Bicep. Dual. Sutan. Lasso)

X X X 8 Liquid Fertilizer 100 to 5600 X X X 8 Nitrogen Solution 5600 X X 8 Phosphoric Acid 1500 to 5600 X X 8 Sulphur Solution 5600 X X 6 Treflan 200 INDUSTRIAL b

\ Hydrochloric Acid So00 X X 8 (37: and lower)

X X X 6 Hydrofluorie Acid 55 to 2500 X X 8 400 to 12,000 Sulfuric Acid (98% and lower)

X X 8 Propionic Acid 5600 X X 8 Sodium Hypochlorite 4250 to 12,000 X X 8 Sodium Hydroxide 1500 to 12,000 X X X 5 Hydrogen Peroxide (52%) 55 to 1600 X X X 8 Alum 5600 X X 5 Cactus Juice 1500 to 6000 ,

X X X 8 100 to 6000 X Detergents X X 8 Floor Finishes & Cleaners 5600 X X 8 Latex 6400 X X 8 200 to 1500 X X Oil Well Additives 4 X X Plating Solutions 3000 X 8 12,000 X Waste Water O H - Horizontal

  • Constant to convert gallons to liters -

V - Vertical gallons x 3.7854 = liters S - Stationary P - Portable

, ~\

t

, iDocument Number: Rev: 'Rev Date:

WESTINGHOUSE

  • STD-P-03-010 0 12/20/85 '

HITTMAN NUCLE AR - r O INCORPORATED Title ' iransfer & Dewatering Bead Resin in Ritt: nan RAD $OKE -100, -200, or -500 Containers with a Single' 1.a'yer

' Underdrain Asp edit to'Iesa than 11 Drainable 1.1ould l

Prepared Director Manager .'

A

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by Engineering Field ,

Services 0 11-10-82 f.D' [ ' 8 624 1 11-30-82 [. k -

f2265

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2 9-30-83( y I [ -248 3 3-19-84 [ ,

04 0 4 5-10-84 .

s84-082 5 6-6-84 . 093 t /

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FCNM Oln) yn i g 12

s STD-P-03-010 Pasa 2 cf 12

/\

V TRANS g W DEWATERING BEAD RESIN IN HITTMAN RADLOK -100, 200, or -500 CONTAINERS WITH A SINGLE LAYER UNDERDRAIN ASSEMBLY TO LESS THAN 1% DRAINABLE LIQUID 1.0 SCOPE This procedure is applicable to RADLOK-100, -200, and -500 High Integrity ll Containers with single layer underdrains for dewatering bead ion exchange resins and other granular media.

2.0 PURPOSE To provide general instructions for the transfer and dewatering of bead ion [

exchange resins (or other granular media) to meet the burial site criteria of less than one (1) percent drainable liquid upon receipt at the site.

This procedure also assures that there is no drainable liquid at the time of shipment from the plant.

3.0 REFERENCES

3.1 Hittaan RADLOK High Integrity Container Rad Services Manual, RSM-014.

A 3.2 ANSI /ANS-55.1-1979, Solid Radioactive Waste Processing System for Q Light Water Cooled Reactor Plants. )

3.3 Hittman report, STD-R-03-002, Report ou Dewatering of Bead Ion Ex-change Resin and Activated Carbon in Hittman RADLOK High Integrity 1 Containers, i 3.4 Hittma:s procedure, STD-P-03-003, RADLOK Manway Assembly Closure and l, Sealing Procedure.

3.5 Hittman procedure, STD-P-03-004, Closure of Hittman RADLOK High In-tegrity Container Fill Port Closure Assembly.

l 3.6 Hittman procedure, STD-P-03-020, RADLOK Inspection Procedure.

3.7 Hittman drawing, STD-03-010, Sheet 4, RADLOK -100 and -500 Single Layer Underdrain Assembly. l 3.8 Hittman drawing, STD-03-083, Sheet, 4, RADLOK-200 Single Layer Under-drain Assembly.

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.

l

STD-P-03-010 Pasa 3 of 12 A)

(_, 4.3 Overflow drum with connecting hose to the container (optional).

4.4 Standpipes,as required (pipe extensions for fill plate connections).

4.5 Liner level indicator panel.

4.6 Vacuum pump with minimum suction of 25 inches of mercury (29.9 inches Hg vacuum equals absolute vacuum) and k-inch vacuum hos s and clamp.

4.7 Glass collection bottle per Figure 1, minimum size of two (2) gallons, rated for full vacuum.

l 5.0 EQUIPMENT SETUP 5.1 Prerequisites 5.1.1 The container has been satisfactorily inspected in accord-ance with STD-P-03-020.

5.2 Precautions None.

5.3 Assembly for Transfer and Dewatering

()

5.3.1 CONNECT the standpipes to the threaded connections on the fill plate. See STD-03-010 or STD-03-083.

5.3.2 CONNECT the electrode plug to the level indicator panel.

5.3.3 CONNECT the dewatering pump suction hose to the standpipe on the fill plate suction connection.

5.3.4 CONNECT the dewatering pump to the service air system using service air hoses.

5.3.5 CONNECT the devatering pump discharge hose to the appropriate plant connection.

5.3.6 CONNECT the final dewatering connection hose from the con-

. tainer to the respective tube in the collection bottle. See l Figure 1.

5.3.7 ,

CLAMP off the final dewatering connection hose near the col-lection bottle.

l 5.3.8 CONNECT a hose from the standpipe on the fill plate vent connection, if provided, to an overflow drum, plant return line or plant drain as appropriate.

1 .

I l 5.3.9 CONNECT the standpipe on the fill plate fill connection to the plant's waste supply line, l.

l'

. STD-P-03-010 Page 4 of 12 O

V 5.4 Assembly for Dewaterina Only 5.4.1 CONNECT one of the standpipes to the suction connection on the fill plate. See STD-03-010 or STD-03-083.

5.4.2 CONNECT the dewatering pump suction hose to the standpipe on the fill plate suction connection.

5.4.3 CONNECT the dewatering pump to the service air system using service air hoses.

S.4.4 CONNECT the final dewatering connection hose from the con-tainer to the respective tube in the collection bottle. See Figure 1.

5.4.5 CLAMP off the final dewatering connection hose near the collection bottle.

5.4.6 CONNECT the dewatering pump discharge hose to the appropriate plant connection.

6.0 TRANSFER AND DEWATERING 6.1 Prerequisites

, 6.1.1 The equipment is set up in accordance with Section 5.3 or

jI. J 5.4 of this procedure, as appl'icable.

-- n.

6.1.2 An RWP is issued and Health Physics is notified prior to waste transfer.

6.2 Precautions Be aware of changing radiological conditions as waste is transferred to the container and the container is dewatered.

6.3 operating Steps, Transfer and Dewaterins 6.3.1 BEGIN the waste transfer.

6.3.2 CONTINUE the waste transfer until the "0P/ LOW" indicator alarm sounds. Once this alarm sounds terminate the waste transfer and allow the waste to settle for fifteen (15) minutes.

NOTE: If the "0P/HI" indicator alarm sounds, the waste is about to overflow the RADLOK container. If this alarm sounds, the operator should take action to isolate flow to the container. If the waste flow is not stopped it will overflow the container. Before restarting the

STD-P-03-010

. . Page 5 of 12 I

transfer operation, any overflow waste must be pumped out of the overflow drum and the "0P/HI" and "0P/ LOW"

. indicator signals aust be cleared.

6.3.3 START the diaphragm pump and begin the dewatering operation.

Tha waste level in the container will recede anc' the "0P/ LOW" light will go out.

6.3.4 MAINTAIN a no-fill mode for three (3) ainutes or until the dewatering pump loses suction. Loss of suction may be defined as less than ten (10) inches mercury vacuum.

6.3.5 RESUM2 waste transfer.

6.3.6 REPEAT steps 6.3.2 through 6.3.5 until the "0P/ LOW" indica-tor light fails to go out. At this point the container is full and the transfer is completed. Any flushing of transfer lines should be done at this time.

NOTE: If during the flush operation, the "0P/HI" alarm sounds, insnediately stop flush and do not resume it until the dewatering pump loses suction.

6.3.7 Continue to OPERATE the dewatering pump for four hours after loss of suction.

6.3.8 Twenty (20) hours after completion of Step 6.3.7, DEWATER with the dewatering pump for one (1) hour.

6.3.9 CONNECT the vacuum pump to the collection bottle.

6.3.10 CHECK all connections for fit and secure with hose clataps where necessary.

6.3.11 ESTABLISH 15"-18" mercury vacuum in the collection bottle.

REMOVE the pinch clamp. MONITOR the water level in the collection bottle.

l NOTE: Should the liquid level in the bottle get close enough to the top to risk water being sucked into the vacuun pump, stop the pump and empty the collection bottle, using proper radiological procedures.

6.3.12 '

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 hose from the container. l l 6.3.13 Upon termination of the dewatering process as defined in Step 6.3.12, STOP the vacuum pump.

6.3.14 If the container is expected to remain on-site for more than four (4) days after completion of Step 6.3.13, REPEAT steps l

l t

l i, STD-P-03-010 l Page 6 of 12 '

l

['~h 4-- ) 6.3.11 through 6.3.13 within the twenty-four (24) hour period prior to shipment.

NOTE: The purpose of this final step is to ensure compliance with ANSI /ANS standard 55.1-1979 that there be no drainable liquid in the container at the time of ship-ment and need only be performed if it is plant policy to conform to this standard.

6.4 Operatina Steps, Dewaterina only 6.4.1 START the dewa'tering pump and begin the dewatering opera-tion.

NOTE: Depending on the quantity of water in the container, continuous pump flow may not be attained. If this is the case, begin timing the next step whenever convenient.

6.4.2 Continue to OPERATE the dewatering pump for four (4) hours after loss of suction. Loss of suction may be defined as less than ten (10) inches of mercury vacuum.

6.4.3 Twenty (20) hours after completion of step 6.4.2, DEWATER with the dewatering pump for one (1) hour.

6.4.4 CONNECT the vacuum pump to the collection bottle.

6.4.5 CEECK all connections for fit and secure with hose clamps where necessary.

6.4.6 ESTABLISH 15"-18" mercury vacuum in the collection bottle.

REMOVE the pinch clamp. MONITOR the water level in the col-lection bottle.

NOTE: Should the liquid level in the bottle get close enough to the top to risk water being sucked into the vacuum pump, stop the pump and empty the collection bottle, using proper radiological precautions.

6.4.7 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 hose from the container.

l 6.4.8 . Upon termination of the dewatering process as defined in step 6.4.7, STOP the vacuum pump.

6.4.9 If the container is expected to remain on-site for more than four (4) days after completion of step 6.4.8, REPEAT steps 6.4.6 througn 6.4.8 within the twenty-four (24) hour period prior to shipment.

.Oe

., STD-P-03-010 Pcg2 7 of 12

() NOTE: The purpose of this final step is to ensure compliance with ANSI /ANS Standard 55.1-1979 that there be no drainable liquid in the container at the time of ship-ment and need only be performed if it is plant policy to conform to this standard.

7.0 DISCONNECTION AND CLOSURE OF CONTAIhTR 7.1 Prerequisites No additional transfers of waste into the container are planned and dewatering is complete.

7.2 Precautions As hoses are disconnected, be careful not to spill any residual water.

7.3 Operating Steps 7.3.1 DISCONNECT the final dewatering connection hose from the collection bottle.

7.3.2 EMPTY the collection bottle.

7.3.3 DISCONNECT the waste transfer hose from the standpipe on the O fill plate fill connection.

7.3.4 DISCONNECT the hose from the standpipe on the fill plate vent connection, if provided.

7.3.5 DISCONNECT the hose from the standpipe on the fill plate suction connection.

7.3.6 CUT the final dewatering connection hose close to the pack-ing gland on the fill plate.

7.3.7 UNSCREW the standpipes from the fill plate.

NOTE: The container is now ready to be closed and sealed for shipment to the 'uurial site.

7.3.8 CLOSE the container in accordance with Hittman procedure STD-P-03-004, 49E O

STD-P-03-010 Pag 2 8 of 12 INSPECTION AND OPERATION CHECXLIST FOR RADLOK-100,

-200, or -500 EQUIPPED WITH A SINGLE LAYER UNDERDRAIN SYSTEM FOR BEAD RESINS TRANSFER AND DEWATERING Date:

Shipment No.:

Container Serial Number:

TIME DATE INITIALS Container Inspected (In accordance with STD-P-03-020)

Manway Assembly Installed (In accordance with STD-P-03-003)

Transfer and Dewater The following steps should be performed:

(In accordance with STD-P-03-010)

1. Completed System Assembly O (In accordance with 5.3)
2. Completed Resin Transfer (In accordance with 6.3.1 through 6.3.6)
3. Started Initial Devatering (In accordance with 6.3.7)
4. Completed Initial Dewatering (In accordance with 6.3.7)
5. Started Final Dewatering (In accordance with 6.3.8 through 6.3.12)
6. Completed Final Dewatering (In accordance with 6.3.13)
7. Disconnected Container from all Connections (In accordance with 6.3.14 and 7.0)

Install and Torque Fill Port Closure Assembly

() (In accordance with STD-P-03-004)

Form STD-P-03-010-01 Sheet 1 of 2

' STD-P-03-010 Page 9 of 12 O TIME DATE INITIALS Label the Container -

(In accordance with burial site criteria)

Signature:

Title:

Date:

p O .

O Fons STD-P-03-010-01 Sheet 2 of 2

STD-P-03 010 Paga 10 of 12 INSPECTION AND OPERATION CHECKLIST FOR RADLOK-100,

-200, -500 EQUIPPED WITH A SINGLE LAYER UNDERDRAIN SYSTEM FOR BEAD RESINS DEWATERING ONLY Date:

Shipment No.:

Container Serial Number:

TIME DATE INITIALS Container Inspected .

(In accordance with STD-P-03-020)

Manway Assembly Installed (In accordance with STD-P-03-003) i Dewaterina Only The following steps should be performed:

(In accordance with STD-P-03-010)

1. Completed System Assembly (In accordance with 5.4)
2. Started Initial Dewatering -

(In accordance with 6.4.1)

3. Completed Initial Dewatering ,

(In accordance with 6.4.2)

I

5. Started Final Dewatering i (In accordance with 6.4.3 through 6.4.7)
6. Completed Final Dewatering (In accordance with 6.4.8)
7. Disconnected Container from all Connections (In accordance with 6.4.9 and 7.0)

Install and Torque Fill Port Closure Assembly (In accordance with STD-P-03-004) ,

O

l STD-P-03-010 Pag 3 11 of 12 1

INSPECTION AND OPERATION CHECKLIST FOR RADLOK-100,

-200, -500 EQUIPPED WITH A SINGLE LAYER UNDERDRAIN SYSTEM FOR BEAD RESINS

, (Continued)

DEWATERING ONLY TIME DATE INITIALS Label the Container .

[

(In accordance with burial site '

criteria)

Signature:

Title:

Date:

O .

.c I

.i Fom STD-P-03-010-02 1 l Sheet 2 of 2 1

' 1 I

STD-P-03-010 Page 12 sf 12 i

O l

Final Dewatering Connection Hose l

g: -

To Vacuum Pump From RADLOK Container

hlHtopper j

\ Short Tube '

Long, Clear Tube O C.ue.uo. tu.

Figure 1

't JO 8

1, f

I l 1

?

'. Document Number: Rev: Rev Date:

STD-P-03-020 5 1-30-86 WESTINGHOUSE ~

l /~N HITTMAN NUCL E AR INCORPORATED

Title:

g

'd RADLOK Inspection Procedure f Director Proj ect QA

~

Rev, Rev Date Engin, Manager Manager 10-3-83 8 b62 0

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~

049

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2 5-17-84 /-[ -A -

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O FORM 01(B) peg, 1 or 5

STD-P-03-020 Pag 2 2 of 5 RADLOX Inspection Procedure O 1.0 PURPOSE To provide instructions for inspection of RADLOK High Integrity Containers.

2.0 SCOPE This precedure is applicable to all RADLOK containers. Sections pertaining to the aanway assembly are not applicable to the RADLOK-55 or to large containers where the aanway assembly is presealed.

In these cases, the respective sections on the checklist should be marked N/A.

3.0 REFERENCES

3.1 STD-D-03-008, A Users Manual for the Hittman RADLOK-55.

3.2 STD-D-03-009, A Users Manual for the Hittman RADLOK-200, RADLOK-500, and RADLOK-100.

3.3 Drawing STD-03-006, RADLOK-55 User Drawing.

3.4 Drawing STD-03-104, RADLOK-200 User Drawing.

O 3.5 Drawing STD-03-110, RADLOK-500 User Drawing.

V 3.6 Drawing STD-03-007, RADLOK-100 User Drawing.

3.7 STD-P-03-003, RADLOK Manway Assembly Closure and Sealing Procedure.

4.0 INSPECTION 4.1 Prerequisites None.

4.2 Precautions Each container is matched with specific closure components and seals at time of manufacture. All components are identified using a common serial number. Should components become mismatched, contact your Hittman Regional Operations Manager prior to RADLOK use.

4.3 Pre-Use Inspection for All RADLOK Containers.

NOTE: Complete applicable portions of Attachment A as inspection steps are completed.

4.3.1 ENSURE that all of the sealing components including the fill s

port closure assembly, the aanway seal (if applicable), and the aanway lid (if applicable) are accounted for and are in good condition.

STD-P-03-020

.. Pagt 3 of 5

~

4.3.2 ENSURE that all of the seals are accounted for. The seals shall be free of defects, not hard or brittle, and the glued

(~'T t_

/ joints shall be intact.

4.3.3 CHECK the seal sizes to ensure proper fit.

4.3.4 ENSURE that the thread and seal seat areas are free of foreign material.

4.3.5 ENSURE that a vent filter is installed in the fill port closure assembly.

4.3.6 ENSURE a proper fit of the manway lid (if applicable) and the fill port closure assembly.

4.3.7 ENSURE that the exterior surfaces are free of damage.

NOTE: The following surface acceptance criteria has been compiled in keeping with the State of South Carolina's RADLOK Certificates of Compliance and provides guidance for inspection, o Container "pock" marks are acceptable, o Voids in the bottom (starting) thread of the container closures are acceptable.

bN,,/ o Surface abrasions and scrapes are acceptable when depth of removed material is less than 1/32" on the RADLOK-55, 1/16" on the RADLOK-200,

-500, and -100.

o Surface cuts (sharp, clearly defined separa-tion of the container skin) and punctures shall be evaluated on a case-by-case basis.

Report the size and location of same to the Hittman office so that an evaluation may be made.

4.3.8 INSPECT the manway lid for proper closure (does not apply to RADLOK-55). (criterion 1E 3/4 inch space between lid and container body).

4.3.9 ENSURE that the RADLOK certificate number and serial number are imprinted on the container.

4.3.10 NOTIFY Hittman if any components are missing or damaged for repair or replacement as necessary.

i 4.4 Additional Pre-Use Inspection for RADLOK Containers With Dewatering Systems.

NOTE: Complete applicable portions of Attachment A marked by (*)

as inspection steps are completed.

STD-P-03-020 Pass 4 of 5 4.4.1 REMOVE the fill port closure assembly.

l}

(_,/ 4.4.2 REMOVE the manway lid. (See STD-P-03-003).

NOTE: For single layer dewatering systems inspect the dewatering system per Sections 4.4.3 through 4.4.6, 4.4.9 through 4.4.11. For multi-layered dewatering systems inspect per Sections 4.4.7 through 4.4.11.

4.4.3 Carefully LIFT the manway seal to allow visual inspection of the internals.

4.4.4 VERIFY that the dewatering hose and the vacuum tube are secured to the proper fittings.

4.4.5 INSPECT the dewatering tubes for breakage.

4.4.6 INSPECT the hoses for kinks, crushing or tears.

4.4.7 Carefully LIFT the manway seal to allow visual inspection of internals while heeding the following cautions.

CAUTION: TO LIFT THE MANWAY SEAL AND UNDERDRAIN, SCREW A PIPE EXTENSION INTO THE CENTER DEWATERING CON-NECTION AND USE A STEADY, VERTICAL FORCE TO LIFT THE SEAL. AT NO TIME SHOULD THE MANVAY SEAL BE O\ PRIED OR TURNED, OR THE PIPE EXTENSION LEVERED DURING THE REMOVAL PROCESS (IF TIGHT, KNOCKING ON THE CONTAINER NECK-TO-MANWAY SEAL JOINT AREA SHOULD FREE THE SEAL). DO NOT LIFT THE MAW.AY SEAL ENOUGH TO PERMIT THE TOP LAYER OF DEWATERING TUBES TO IMPINGE ON THE UPPER SECTION OF RADLOK BODY.

4.4.8 VERIFY that the dewatering tubes and pipe risers are intact by visual inspection.

4.4.9 REPLACE the manway seal and manway lid per STD-P-03-003.

4.4.10 VERIFY that all strain relief connector bushings securely seal the electrical cords and tubing that penetrate the fill plate.

EDIL: Connectors shall only be band-tightened around tubing so that it is not constricted.

4.4.11 NOTIFY Hittman if any components are missing or damaged for repairs or replacements.

21J O

{

STD-P-03-020

.. Pass 5 of 5

  • ATTACHMENT A Q -

k/

s Pre-Use Inspection Checklist for RADLOK Container On-Site Inspector:

Location: Date:

Container Type / Options:

Container Serial No.:

(* - Applicable to RADLOK Containers with Dewatering Systems Only.)

Inspection Item Initials /Date Serial number matches on all components (4.2) __

All sealing components accounted for (4.3.1)

All seals accounted for and in good condition (4.3.2)

All seals fit properly (4.3.3)

Thread and seal seat areas free of foreign material (4.3.4)

Sealing components fit properly (4.3.6)

Manway Assembly (if applicable)

Fill Port Closure Assembly Exterior surface free of damage (4.3.7)

Manway lid properly sealed (if pre-sealed) (4.3.8)

Certificate number imprinted on container (4.3.9)

Containers with Single Layer Dewatering Systems.

]

  • Dewatering hose and vacuum tube secure (4.4.4)

I

  • Dewatering tubes intact (4.4.5)
  • Hoses not kinked, crushed or torn (4.4.6)

Containers with Multi-Layered Dewatering Systems.

  • Dewatering tubes and pipe risers intact (4.4.8)

'

  • Strain relief connectors intact and tightened (4.4.10) 21J P

1

. Docvment Numb:r: R:v: R v Dcte;:

c WESTINGHOUSE SE-P-04-002 .6 , 3-24-86 i PORATED

Title:

Process Control Program for Devatering Ion-Exchange

{

Resin & Activated Charcoal Filter Media to 1 % 5 Drainable 1.icuid Prepared. Respons ole Mrector M ty Reviewed gy, g,y pot

  • by by Manager Engineering Assurance 0 12- 3-81 ,

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f 85-156 5 2-07-86  %

6 3-24-86 [ k N-071 1 u: An n FM LEY DOCU! ' ENT CON TROL CONT  ?.O L L E D C DPY

. No C?d H NDC-Ol(A) Pege 1 of ' 11

STD-P-04-002 Pass 2 of 11 PROCESS CONTROL PROGRAM b.

V FOR DEWATERING ION EXCHANGE RESIN AND ACTIVATED CHARCOAL FILTER MEDIA TO 1/2% DRA1NABLE LIQUID 1.0 SCOPE This procedure is applicable to Hittman steel liners having rigid underdrains for dewatering bead 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 percent 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-hausted 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 Vecuum pump with minimum suction of 25 inches of mercury and ,

1/4-inch vacuum hoses and clamp. '

4.4 Tool for connection to side bottom dewatering connection similar to device shown in Figure 1 (Optional).  ;

4.5 Glass collection bottle per Figure 2, minimum size of two

(2) gallons. 1 i

i 5.0 GENERAL REQUIREMENTS ,

O i

5.1 As required by the South Carolina Department of Health and Environmental Controls License No. 097, Amendment No. 30 for ,

STD-P-04-002 Paga 3 of 11  !

the Barnwell Waste Management Facility, the PCP shall be used to verify adequate dewatering of unsolidified wet

,O' radioactive wastes.

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 cato 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.

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 b cleared with the responsible Hittman transportation office prior to commencement of work. -

6.0 DEWATERING PROCEDURE 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. I RECORD on the Dewatering Verification Data Sheet,

< Form STD-P-04-002, Item (1) that Step 6.1.1 is j complete.

6.1.2 MOVE the liner to the location for final dewater-ing and set in the tipped configuration. RECORD on the Dewatering Verification Sheet, Form STD-P-04-002-01, Item (2) that Step 6.1.2 is complete.

6. L. 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 or to a large collection vessel.

t

STD-P-04-002 Pago 4 of 11 6.1.5 REMOVE the pipe plug from the final dewatering connectiona p)

\'.

NOTE: For liners with a top dewatering connec-tion this is a 1/4" pipe plug. For liners with the side bottom dewatering connection this is a 1\" pipe plug.

6.1.6 For liners with the top dewatering connection REPLACE the pipe plug with a k" threaded pipe.

6.1.7 For liners with the side bottom dewatering connee-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 vacuum pump.

6.1.10 CLAMP off hose connected in Step 6.1.8 near vacuum bottle, 6.1.11 DEWATER the liner using the air operated pump for (n') a minimum of four (4) hours at which time the pump is to be shut offor but,not;-dis eonnected. If the discharge hose is-routed- to -a Earger collection vessel, RECORD on the Dewatering Verification Data Sheet, Form STD-P-04-002-01, Item (3) the volume of liquid collected. RECORD that Steps 6.1.3 through 6.1.11 are complete.

6.1.12 Allow the liner to SIT in this position for twenty '

(20) hours. RECORD on the Devatering Verification Sheet, Form STD-P-04-002-01, Item (4) Step 6.1.12

), is complete.

6.1.13 DEWATER using the air operated pump for one (1) hour.

If the discharge hose is routed to a collection vessel, RECORD on the Dewatering Verification Sheet, Form STD-P-04-002-01, Item (5) the volume of liquid collected. RECORD that Step 6.1.13 is complete.

6.1.14 START the vacuum pump and establish a vacuum l (15" - 18" mercury) in collection bottle. REMOVE pinch clamp. MONITOR water level in the collec-l tion bottle.

NOTE: Should the liquid level in the bottle O, get close enough to the top to risk water being sucked into the vacuum pump, j

I

STD-P-04-002 Paga 5 of 11 stop the pump and empty the collection

('~} bottle, using proper radiological pro-(j 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.

RECORD on the Dewatering Verification Sheet, Form STD-P-04-002-01, Item (6) the quantity of water collected and that Steps 6.1.14 and 6.1.15 are complete.

6.1.16 REPEAT Steps 6.1.14 and 6.1.15 at 24-hour inter-vals for three days. RECORD on the Dewatering Verification Sreet, Form STD-P-04-002-01, Items (7) through (9) the quantity of water collected and that Steps 6.1.14 and 6.1.15 are complete.

6.1.17 Upon completion of the fourth vacuum draining, the liner is dewatered and ready for shipment.

NOTE: Do not complete Item (10) on the Dewater-ing Verification Sheet, Form STD-P-04-002-01 unless the resin volume in the liner exceeds 140 cubic feet. In that case, g'"N REFER to Step 6.2.5.

6.2 Resin Transfer Liner,s -

6.2.1 Upcn completion of the resin transfer operation, CONTINUE operating the dewatering pump until pump suction is lost. RECORD on the Dewatering Verifi-cation Data Sheet, Form STD-P-04-002-01, Item (1),

Step 6.2.1 is complete.

6.2.2 DISCONNECT the dewatering pump from the liner.

6.2.3 PLACE the liner in the tipped configuration.

RECORD on the Dewatering Verification Sheet, Form STD-P-04-002-01, Item (2), Step 6.2.3 is complete.

6.2.4 COMPLETE cteps 6.1.3 through 6.1.16. COMPLETE Items (3) through (9) on the Verification Sheet, Form STD-F-04-002-01 as Steps 6.1.3 through 6.1.16

, are completed.

6.2.5 For liners containing greater than 140 cubic feet of resin, ADD one additional day of dewatering prior to shipment and COMPL;rE Item (10) on the Dewatering Verification Sheet, Form STD-P-04-002-01.

O

STD-P-04-002 Page 6 of 11 7.0 DISCONNECTING DEWATERING EQUIPMENT 7.1 DISCONNECT dewatering hose from the dewatering pump. The l portion of this hose exiting the liner through the liner neck is .to be pushed back into the liner prio* to capping.

RECORD on the Dewatering Verification Sheet, Form STD-P 002-01, Item (11) that Step 7.1 is complete.

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. RECORD on the Dewatering Verification Sheet, Form STD-P-04-002-01, Item (12) that Step 7.2 is complete. COMPLETE Items (13) through (18) on Form STD-P-04-002-01.

NOTE: For liners with the side bottom connection it is recommended that the pipe plug be tack welded in place to eliminate the possibility of it vibrating loose during transportation.

26A 03/18/86 0 .

l l

l

STD-P-04-002 Page 7 of 11 Ii Date: 1 Liner:

DEWATERING VERIFICATION SHEET SECTION I - DEWATERING Initials Hittman Plant Radwaste Item (1) Step 6.1.1 or 6.2.1, Waste Processing or Resin Transfer is complete and resin dewatered until loss of suction.

Item (2) Step 6.1.2 or 6.2.2 and 6.2.3, i I

Liner is Set in Tipped Configuration (7 to 9 degrees)

Item (3) Steps 6.1.3 through 6.1.11, set-up for dewatering are complete and liner has been dewatered for four (4) hours using the air operated pump ,

Time Start:

Time Completed: >

f Volume Collected:

[~- Item (4) Step 6.1.12, Liner allowed to sit for 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> Time Start: Date:  ;

Tire Completed: Date:

Ite:n (5) Step 6.1.13, Dewatered one (1) l bour using air operat.ed purap

' Time Start:

Time Completed: ,

Volume Collected: e Item (6) Steps 6.1.14 and 6.1.15, Vacuum (15" - 18" mercury) established in collection bottle and liner has been l detatered one (1)

  • hour after continuous l flow is lost. l l Date: l Vacuum:

Time Start (After Continuous flow is lost:

l O Time Completed:

Volume Collected:

Form STD-P-04-002-01 Sheet 1 of 3 1

STD-P-04-002 Pags 8 of 11

,- SECTION I - DEWATERING 4 8

(Continued) I

\s- Initials Hittman Plant Radwaste Item (7) Steps 6.1.16, Steps 6.1.14 and 6.1.15 repeated after first 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, Vacuum (15 - 18" mercury) established in collection bottle and liner has been dewatered one (1) hour after continuous flow is lost.

Date: __

Vacuum:

Time Start (after continuous flow is lost:

Time Completed:

Volume Collected:

Item (8) Step 6.1.16, Steps 6.1.14 and 6.1.15 repeated after second 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, Vacuum (15"-18" mercury) established in collection bottle and liner has been dewatered one (1)

() hour after continuous flow is lost.

Date:

Vacuum:

Time Start (after continuous flow is lost) j i

Time Completed:

Volume Collected:

Item (9) Step 6.1.16, Steps 6.1.14 and 6.1.15 repeated after third 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, Vacuum (15"-18" mercury) established in collection ,

bottle and liner has been dewatered one (1) hour after continuous flow is lost.

Date:

  • Vacuum:

l Time Start (after continuous flow is lost) {

Time Completed:

(

Volume Collected:

Form STD-P-04-002-01 Sheet 2 of 3

STD-P-04-002 Paga 9 of 11 SECTION II - DISCONNECTION OF DEWATERING EQUIPMENT

( m, Item (10) Step 6.2.5 completed if liner contains greater than 140 cubic feet of resin.

Date:

Vacuum:

Time Start (after continuous flow is lost)

Time Completed:

Volume Collected:

Item (11) Step 7.1, Disconnect and Storing of Dewatering Hose is complete.

Item (12) Step 7.2., Disconnect of Final Dewatering Line is complete.

SECTION III - LINFR INFORMATION N Item (13) Liner Number:

d Item (14) Liner Typ-: -

Item (15) Dose Rate: ___

Item (16) Shipping Date: __

Item (17) Site Technician: _

Date Item (18) Plant Radwaste Personnel: _

Date Form STD-P-04-002-01 Sheet 3 of 3 l0 l

' STD-P-04-002 Page 10 of 11 0 gg

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Final Dewatering Tube Prod CNER To Vacuum Pump 3

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Documr,nt Numbar: Rav: Rsv Date:

HITTMAN NUCLEAR & STD-P-05-002 4 4-9-86 D EVELOPMENT

{m) CORPORATION

Title:

Process control Program for Incontainer Solidification of Oily Waste SUP'fVIS I Manager Prepared Labora tory Di Mw Field QA Rey, Rev Date by Eng inee r ing Services Services 0

11-17'01 1 6-9-82 # 8 24

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STD-P-05-002

. Page 2 of 18 1 1

l in PROCESS CONTROL PROGRAM FOR INCONTAINER SOLIDIFICATION OF OIL 1.0 SCOPE This procedure is applicable to the solidification of oils classified as either Class A Unstable or Stable, Class B or Class C waste under the requirements of 10CFR61.55, Waste Classification. Class A Unstable waste meets the requirements under the NRC criteria of 10CFR61.55, Waste Clas-sification. Class A Stable waste must meet the same stability requirements of Class B and Class 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 incontainer solidification of oil is to provide a program which will assure a solidified product which meets the requirements of 10CFR61.56, Waste Characteristics.

The program consists of the following major steps:

3 (a) Procedures for collecting and analyzing samples; (b)

,p . y _ ;+ .s Procedures for solidifying samples;. ~

. -s; ~

(c) Criteria for process parameters for acceptance or rejection as solidified waste.

(d) Calculational methodology for determining quantities of solidifi-cation agents and additives for full scale operations.

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 determining the acceptable ratios of waste, additional water, cement and additive that will result in an acceptable product for trans-portation and burial.

3.0 COLLECTION AND ANALYSIS OF SAMPLES 3.1 General Requirements 3.1.1 As required by the Radiological Effluent Technical Specifi-cations for PWRs and BWRs, the PCP shall be used to verify

! the solidification of at least one representative test specimen from every tenth batch of each type of radioactive i

waste.

3.1.2 For the purposes of the PCP a batch is defined as the quan-tity of waste required to fill a disposable liner with the appropriate quantity of waste prior to solidification.

/

STD-P-05-002 1 Page 3 of 18 ,

\7->) 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. I Solidification of the batch may then be resumed using the alternate solidification parameters determined.

l 3.1.4 If the initial test specimen from a batch of waste fails to i verify solidification, then representative test specimens  !

shall be collected from each consecutive batch cf the same type of waste until three (3) consecutive initial test specimens demonstrate solidification. The Process Control j Program shall be modified as required to assure solidifi-cation 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-radio-active samples will be tested. These samples should be as close to the actual wastes' chemical properties as possible.

3.1.6 Since it is unlikely that more than one batch of oil will have the same properties, it is recommended that a test solidification be performed for each liner unless large O. quantities of relatively pure oil are to be solidified.

3.2 Collection of Samples 3.2.1 Radiological Protection NOTE: These procedures should be followed during sam-pling to minimize personnel exposure and to pre-vent 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 pertinent information on the characteristics of the test sample

> solidified so as to verify solidification of subsequent batches of similar waste without retesting.

I STD-P-05-002 Pegn 4 of 18 i l

('~)/

\s- 3.2.2.1 The test sample data for oil will include, but not ,

necessarily be limited to, the type of waste solidi-  !

fied, pH, volume of sample, sample number, amount of oil in sample, the volume ratio of oil to water, and the quantity of any additive used to precondition the l waste.

3.2.2.2 The 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. Approximately 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> are (7, required for verification.

U 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 si.ne 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.

3.3 Analysis of Samples This document only defines the parametera to be analyzed and not the methodology. This is left to the plant staff.

Parameter Acceptable pH >5 Detergents No Appreciable Foaming Oil (percent by volume) 40%

4.0 DETERMINATION OF THE QUANTITY OF WASTE IN THE LINER TO BE SOLIDIFIED NOTE: For the solidification of oil, water must be added to the oil.

O The total waste volume listed in the Solidification Data Tables,

STD-P-05-002 Pcgn 5 of 18

\, ,) Form STD-P-05-002-04, includes the water necessary for solidifi-cation. The quantity of oil that may be transferred to the liner is 40% of the listed volumes.

4.1 DETERMINE the volume of total waste that is to be added to the liner.

4.2 RECORD the volume of total waste on the Test Solidification Data Sheet (Item 1 on Form STD-P-05-002-01).

4.3 CALCULATE and RECORD the quantity of oil that is to be transferred to the liner per the instructions on the Test Solidification Data Sheet (Item 2 on Form STD-P-05-002-01).

4.4 CALCULATE and RECORD the quantity of water to be added to the oil in the liner per instructions on the Test Solidification Data Sheet (Item 3 on Form STD-P-05-002-01) .

4.5 CALCULATE and RECORD the quantity of Maysol 776 to be added to the liner per the instructions on the Test Solidification Data Sheet (Item '

l 4 on Form STD-P-05-002-01).

4.6 Items 1, 2, 3, and 4 should also be entered as Items 1, 2, 3, and 4 on the Solidification Calculation Sheet (Form STD-P-05-002-02).

NOTE: ENSURE that Section 4.0, Determination of the Quantity of

3) Waste in the Liner to be Solidified is completed accoraing

, .. e (p Steps 4.1 through 4.6 and verify this on Form STD-P 1 - ( .7] J QQ2.03.

5.0 TEST SOLIDIFICATION AND ACCEPTANCE CRITERIA 5.1 General NOTE: The sample for solidification may be fabricated using the same waste type that was added to the liner or the solidifi-cation sample.may be taken directly from the liner after the ,

l water and emulsifier have been added and are thoroughly mixed to emulsify the waste. )

5.1.1 If large foam causing quantities of detergents are present, the sample should be treated with an anti-foam agent. The quantity of anti-foam agent required shall not exceed one I half of one percent by volume of the oil plus water.

5.1.2 If the pH of the sample ia less than 5, it shall be adjusted to at least 5 by the addition of 50% sodium hydroxide.

NOTE: pH paper may be used to measure the pH level.

5.1.3 The test sample may be either fabricated or taken directly O from the liner after emulsification is complete.

l

STD-P-05-002 Pega 6 of 18 p)

(, ,

NOTE: If the test sample is to be taken directly from the liner after emulsification, OMIT sections 5.2 and 5.3.1. CONTINUE on to Section 5.3.2.

5.2 Fabrication of Test Sample 5.2.1 MEASURE into a one liter calibrated disposable beaker 140 ml of the oil to be solidified.

5.2.2 RECORD the volume of oil on the Test Solidification Data Sheet (Item 5 on Form STD-P-05-002-01).

5.2.3 ADD 210 ml of water to the oil to be solidified.

5.2.4 RECORD the quantity of water added on the Test Solidifi-cation Data Sheet (Item 6 on Form STD-P-05-002-01).

5.2.5 MEASURE the volume of oil plus water.

5.2.6 RECORD the volume on the Test Solidification Data Sheet (Item 7 on Form STD-P-05-002-01).

5.2.7 CALCULATE and RECORD the quantity of emulsifier to add to the Test Sample per instructions on the Test Solidification e

gg Data Sheet (Item 8 on Form STD-P-05-002-01).

O 5.2.8 MEASURE out the required quanti,ty of emulsifier and ADD it to the Test Sample.

NOTE: Maysol 776 is used as the emulsification agent at a ratio of 20% by volume of the oil. The density of the emulsifier is 1 gm/ml, i.e., 1 gram = 1 ml.

The quantity of emulsifer may be weighed directly into the test sample.

5.2.9 HIX the sample at least five (5) minutes so that a homogeneous mixture is obtained.

NOTE: Mixing should be accomplished by stirring with an electric mixer with blade. Any signs of pure oil may be an indication that the emulsion is breaking down. Should this occur do not proceed. Contact HITTMAN for further instructions.

5.2.10 If large foam causing quantities of detergents are present, TREAT the sample with an anti-foam agent. The quantity of anti-foam agent required sha'.1 be recorded on the Test Solidification Data Sheet.

5.2.11 If the pH of the sample is less than 5, ADD 50% sodium (m) ,

hydroxide solution until the pH is at least 5. The quantity of 50% sodium hydroxide used for this purpose shall be recorded on the Test Solidification Data Sheet.

( h STD-P-05-002 Page 7 of 18

(,,/ 5.2.12 RECORD the initial pH and the quantities of anti-foam agent and 50% sodium hydroxide used on the Test Solidification Data Sheet ('tems 9,10, and 11 on Form STD-P-05-002-01) .

5.3 Test Solidification of Class A Unstable and Stable, Class B or C Waste 5.3.1 Test Solidification of Fabricated Sample 5.3.1.1 WEIGH out 447.3 gms of Portland Type I cement and 51.8 gms of anhydrous sodium metasilicate (ASMS) into separate vessels.

5.3.1.2 RECORD the quantities of cement and ASMS on the Test Solidification Data Sheet (Items 12 and 13 on Form STD-P-05-002-01).

5.3.1.3 Slowly ADD the cement to the Test Sample while it is being mixed.

NOTE: Mixing should be accomplished by stirring with an electric mixer with blade until a homogeneous mixture is obtained but in no case less than two (2) minutes.

', 5.3.1.4 After all the cement is adde.d, slowly ADD the ASMS to the test sample while it is being mixed.

5.3.1.5 MIX for two (2) minuten after all the ASMS is added and a homogeneous mixture is obtained.

5.3.1.6 SEAL the sample and CURE at 120 15'F for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

NOTE: If at any time during the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cure time, the sample meets the acceptance criteria, the liner solidification may proceed. However, no test solidification shall be disqualified without at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of cure. It is not mandatory to cure Class A Unstable wastes at 120 15*F for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Class A Unstable wastes may be cured at room temperature for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

NOTE: Ensure that Section 5.3.1, Test Solidifica-tion of Fabricated Sample is completed accord-ing to Step 5.3.1.1 through 5.3.1.6 and verify this on Form STD-P-05-002-03.

5.3.2 Test Solidification of Pre-Emulsified Sample from Liner 5.3.2.1 For the solidification of pre-emulsified samples, y j MEASURE into the mixing vessel, 400 ml of emulsified waste taken from the liner.

r STD-P-05-002 Pega 8 of 18 m

() 5.3.2.2 RECORD the volume of waste on the Test Solidification Data Sheet (Item 14 on Form STD-P-05-002-01).

5.3.2.3 CALCULATE and RECORD the volume of oil plus water in the sample per the instructions on the Test Solidifica-tion Data Sheet (Item 15 on Fo rm STD-P-05-002-01) .

5.3.2.4 If large foam causing quantities of detergents are pre-sent, TREAT the sample with an anti-foam agent. The quantity of anti-foam agent required shall be recorded on the Test Solidification Data Sheet.

5.3.2.5 If the pH of the sample is less than 5, ADD 50% sodium hydroxide solution until the pH is at least 5. The quantity of 50% sodium hydroxide used for this purpose shall be recorded on the Test Solidification Data Sheet.

5.3.2.6 RECORD the initial pH and the quantities of anti-foam agent and 50% sodium hydroxide used on the Test Solidi-fication Data Sheet (Items 16, 17 and 18 on Form STD-P-0 5-002-01).

3.3.2.7 WEIGH out 473.3 gms of Portland Type I cement and 54.8 gg gms of anhydrous sodium metasilicate (ASMS) into separate t ) vessels.

5.3.2.8 RECORD the quantities of cement and ASMS on the Test Solidification Data Sheet (Items 19 and 20 on Form STD-P-05-002-01).

'5.3.2.9 REPEAT Steps 5.3.1.3 through 5.3.1.6.

NOTE: ENSURE that Section 5.3.2, Test Solidifica-tion of Pre-Emulsified Samples is completed according to Steps 5.3.2.1 through 5.3.2.9 and VERIFY this on Form STD-P-05-002-03.

5.4 Solidification Acceptability 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 or oil, 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.

O' NOTE: Even though the sample surface appears hard and dry, this may be just a thin surface crust. In

STD-P-05-002 Psga 9 of 18

/~'s

( ,) 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.

5.4.4 VERIFY the acceptance criteria by signing and dating each item in Section IV of the 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 002-03.

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 parameters will need to be established under the procedures in Section 5.6.

5.5.2 If the test solidification is unacceptable then the revised

(~'s test procedures must be followed on each subsequent batch of

\ the same type of waste until three (3) consecutive test samples are solidified. .

5.6 Alternate Solidification Parameters 5.6.1 If a test sample fails to provide acceptable solidificat. ion of the waste, the following procedures should be followed.

5.6.1.1 Class A Unstable Wastes (a) MIX 454.5 gms of cement and 45.5 gms 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 modified waste to cement and anhydrous sodium metasilicate ratios. Using the recommended quan-tities of cement and anhydrous sodium metasili-cate, reduce the waste sample volume by 25 ml.

Continue reducing the waste volume by this incre-ment 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.

f I STD-P-05-002  ;

Page 10 of 18 l r

i Class A Stable, Class B or C Wastes 5.6.1.2 (a) CONTACT Hittman.

6.0 PARAMETERS FOR FULL SCALE SOLIDIFICATION 6.1 After successful completion of the test solidifications, CALCULATE the amounts of additives and solidification agents necessary, per cubic foot of waste per instructions in Section V of the Test Solidification Data Sheet (Items 21 through 29, Form STD-P-05-002-01) .

6.2 DETERMINE the amounts of additives and solidification agents to be added to the liner per instructions on the Solidification Calculation Sheet, (Items 5 through 13, Form STD-P-05-002-02).

NOTE: ENSURE that Section 6.0 is completed according to Steps 6.1 and 6.2 and verify this on Form STD-P-05-002-03.

55C 03/06/86 O .

I O

l l

STD-P-05-002 l Pcge 11 of 18 I

/ \

() CLASS A UNSTABLE AND STABLE, CLASS B OR C TEST SOLIDIFICATION DATA SHEET FOR OILY WASTE I. DETERMINATION OF QUANTITY OF WASTE TRANSFERRED TO THE LINER Volume of 011 plus Water to Add to Liner , ft3:

1 (1)

Volume of 011 to Add to Liner, ft3:

Item (1) __

x 0.40 = (2)

Volume of Water to Add to Liner, ft3:

Item (1) - Item (2) = (3)

Volume of Maysol 776 to Add to Liner, gallons 2:

Item (2) _ _ _ . x 0.2 x 7.48 = (4)

II. FABRICATED TEST SAMPLE PREPARATION Volume of 011 to be Solidified, al: (5)

Volume of Water Added to the Oil, ml: (6)

Volume of oil plus Water, ml: (7)

Quantity of Emulsifier to Add to Sample, ml or gms:

()i L

Item (5) x 0.20 m (8)

Initial pH: __, (9)

Quantity of Anti-Foan Agent Added to Sample, gms: (10) ,

Quantity of 50% NaOH Added to Sample, gms: ____ (11)

Quantity of Portland Type I Cement Added to Sample, gmn: (12)

Quantity of ASMS Added to Sample, gms: (13)

III. PRE-EMULSIFIED TEST SAMPLE PREPARATION Volume of Emulsified Waste that is to be Solidified, ml: (14)

Volume of Emulsified Waste that is 011 plus Water, ml:

Item (14) x .926 = (15)

Initial pH: (16)

Quantity of Anti-Foam Agent Added to Sample, ges: (17)

Quantity of 50% NaOH Added to Sample, gms: (18)

Quantity of Portland Type I Cement Added to Sample, gms: (19)

Quantity of ASMS Added to Sample, gms: (20)

Form STD-P-05-002-01 Sheet 1 of 4 i

STD-P-05-002

- Page 12 of 18 IV. SAMPLE INSPECTION Sample Cured for 24 Hours 3: 0 Yes a No Verified by Date Sample contains "No Free Liquid": 0 Yes a No Verified by Date Sample is a "Free Standing Monolith": 0 Yes O No

~

Verified by Date Sample resists Penetration: 0 Yes a No Verified by Date O

Additional batches solidified based on this sa"mple solidification:

Liner Waste Liner Waste Liner Waste No. Vol. Date No. Vol. Date No. Vol. Date l

Form STD-P-05-002-01 Sheet 2 of 4 l

l

STD-P-05-002

- Paga 13 of 18 V. PARAMETERS FOR FULL-SCALE SOLIDIFICATION A. From Fabricated Sample Data:

Quantity of Maysol 776:

(8) x 7.48 + (5) = gallons of emul- (21) sifier per ft 3 oil Quantity of Anti-Foam Agent:

(10) x 7.48 + (7) = gallons of anti- (22) foam per ft 3 of oil plus water Quantity of 50% NaOH:

(11) x 4.86 + (7) = gallons of 50% (23)

NaOH per ft3 of oil plus water Quantity of Portland Type I Cement:

(12) x 62.43 + (7) = pounds of cement (24) per ft3 of oil plus water Quantity of ASMS:

(13) x 62.43 + (7) = pounds of ASMS (25) per ft3 of oil plus water

3. From Pre-Emulsified Sample Data:

Quantity of Anti-Foam Agent:

(17) x 7.48 + (15) = gallons of anti- (26) foam per ft3 of oil plus water Quantity of 50% NaOH:

(18) x 4.86 + (15) = gallons of 50% (27)

NaOH per ft 3 of oil plus water Quantity of Portland Type I Cement:

(19) x 62.43 + (15) = pounos of cement (28) per ft3 of oil plus water Quantity of ASMS:

(20) x 62.43 + (15) = pounds of ASMS (29)

/~N per ft3 of oil plus water

! Form STD-P-05-002-01 Sheet 3 of 4

L STD-P-05-002 Page 14 of 18 FOOTNOTES 1

The volume of oil plus water cannot exceed the maximum volumes listed on the Solidification Data Tables for Class A Unstable and Stable, Class B or C Wastes, Form STD-P-05-002-04.

2 Quantity of emulsifier is 20% by volume of the oil.

3 If the sample is qualified in less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, note the total hours cured.

I l

1 O .

l l

l l

l i

l l

l l

Form STD-P-05-002-01 Sheet 4 of 4 i

\ -- _ _ _ _ _ . ___ ___ __. _ _ _ _ . _ . __ __ _ __. ._ _ . _ _

STD-P-05-002

. Pega 15 of 18 j' \

Q CLASS A UNSTABLE AND STABLE, CLASS B OR C SOLIDIFICATION CALCULATION SHEET Volume of 011 plus Water Added to Liner1 , f t3: '(1)

Volume of 011 Added to Liner, ft3: (2)  ;

Volume of Water Added to Liner, ft3: (3) )

Volume of Maysol 776 Added to Liner, gallons: (4) l Quantity of Haysol 776 to Add to Liner if Maysol 776 has not been Added:  !

A. From Fabricated Sample Data:

(2) x = gallons (5) i Item (21) Form STD-P-05-002-01 l l

Quantity of Anti-Foam Agent to Add to Liner : 2 A. From Fabricated Sample Data:

(1) x = gallons (6) '

Item (22) Form STD-P-05-002-01

()

("%

B. From Pre-Emulsified Sample Data:

f.

(1) x w=~- l '*--*- 4 gallons (7)

Itc.m (26) Form STD-P-05-002-01 _

Quantity of 50% NaOH to Add to Liner 2:

A. From Fabricated Sample Data:  :

1 (1) x = gallons (8)

Item (23) Form STD-P-05-002-01 B. From Pre-Emulsified Sample Data:

(1) x = gallons (9) )

Item (27) Form STD-P-05-002-01 Quantity of Portland Type I Cement to Add to Liner: ,

l A. From Fabricated Sample Data: )

(1) x = pounds (10)

Item (24) Form STD-P-05-002-01 B. From Pre-Emulsified Sample Data:

(1) x = . pounds (11)

Item (28) Form STD-P-05-002-01 Form STD-P-05-002-02

,,.. . .c e

STD-P-05-002 Page 16 of 18

() Quantity of ASMS to Add to Liner:

From Fabricated Sample Data:

A.

(1) x = pounds (12)

Item (25) Form STD-P-05-002-01 B. From Pre-Emulsified Data:

(1) x = pounds (13)

Item (29) Form STD-P-05-002-01 FOOTNOTES 1 The volume of oil plus water cannot exceed the maximum volumes listed on the Solidification Data Tables for Class A Unstable and Stable, Class B or C Waste , Fo rm STD-P-05-002-04.

2 Reduce the quantity of total waste (oil + water) in the liner by 1 ft 3 for every 10 gallons of anti-foam plus 50% NaOH added to the liner. No adjust-ment is necessary for the first 10 gallons.

O .

l Fo rm STD-P-05-002-02  ;

C) Sheet 2 of 2 l l

t' STD-P-05-002 l Page 17 of 18 Date:

Liner No.:

PROCEDURE VERIFICATION SHEET l

Verified By:

Section 4.0, Determination of Quantity of Waste in the Liner to be Solidified, Steps 4.1 through 4.6 completed.

Section 5.3.1, For Fabricated Sample or Section  ;

5.3.2 for Non-Fabricated Samples, Test Solidifi- '

cation Steps 5.3.1.1 through 5.3.1.6 or Steps 5.3.2.1 through 5.3.2.9 completed.

Section 5.4., Solidification Acceptability, Steps 5.4.1 through 5.4.4 completed.

Section 6.0, Parameters for Full-Scale Solidifi-cation, Steps 6.1 and 6.2 completed.

O .

Form STD-P-05-002-03 Sheet 1 of 1

~

STD-P-05-002 Paga 18 of 18

/'N SOLIDIFICATION DATA TABLES FOR CLASS A UNSTABLE AND STABLE, CLASS B OR C OILY WASTE

, HN-100 M HN-100 LVM Series 1 1 Series 21 Series 3 S Series 32 Usable Liner Vol., 141.1 141.1 141.1 141.1 157.5 cu.ft.

Max. Waste Vol., (oil 85.3 82.0 93.7 93.7 104.6 plus water), cu.ft.

Max. Solidification Vol., 128.5 123.5 141.1 141.1 157.5 cu.ft.

Max. Rad Level 12 12 12 3 12 R/hr Contact For unshielded shipments, USE the Series 3 Cask data for the HN-100 or HN-100 LVM liners.

FOOTNOTES:

1 For less than A quantities of LSA waste, use data for Series 3 Cask.

~f , 2

.- 5

~' -

-

  • 2 For less than A quantities 2

of LSA waste. If the waste contains greater than A quantitles, the waste volume must be reduced to 103.4 cu.ft. due to wei ht limitations.

Form STD-P-05-002-04 Sheet 1 of 1 L.

q

f , (6 . ' NT-86-0403 m

M11 ting Addr:ss ^

Alabama Power Company 600 North 18th Street Post Office Box 2641 /

Birmingham Alabama 35291 g N Telephone 205 783-6090 '

R. P. Mcdonald Senior Vice President b khh h A $ ,* h M Fhntndge Building AlabamaPower

~a...,

August 26, 1986 Docket Nos. 50-348D 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 Radioactive Effluent Release Report N

Dear Dr. Grace:

The Joseph M. Farley huclear Plant Semi-Annual Radioactive Effluent Release Report for the period of January 1, 1986 through July 31, 1986 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 decumentation of changes made to the Farley Nuclear Plant Process Control Program. jll If ycu have any questions, please advise.

Yours very truly, id. .

R. P. Mcdonald

/-

RPMAiAT:etth Enclosures (2) xc: Director Office of Nuclear Reactor Regulation Director Office of Inspection and Enforcement Mr. L. B. Long Mr. G. F. Trowbridge Mr. W. H. Bradford Mr. E. A. Reeves

'}t1a

~

~Oficial Copy

, .

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