ML20138F331

From kanterella
Jump to navigation Jump to search
Annual Radioactive Effluent Release Rept Number 20,for Jan-Dec 1996
ML20138F331
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 12/31/1996
From:
WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20138E816 List:
References
20, NUDOCS 9705050356
Download: ML20138F331 (46)
v • d • e


Text

Attachment to WO 97-0045 i

PageIof36 1

Wolf Creek Nuclear Operating Corporation Wolf Creek Generating Station, Docket No: 50-482 Facility Operating License No: NPF-42 Annual Radioacth e Efiluent Release Report Report No. 20 Reporting Period: January 1,1996 - December 31,1996 9705050356 970430 DR ADOCK 0500 2

Attachment to WO 97-0045 Page 2 of 36 Table of Contents Page Executive Summary 3

Section I Liquid Radioactive Effluents 4

Dose Summary 8

Airborne Radioactive Effluents 10 Dose Summary 14 Section II Offsite Dose Calculation Manual Limits 16 Maximum Permissible Concentrations 16 Average Energy 17 Measurements and Approximations of Total Reactivity 17 Batch Releases 19 -

Continuous Releases 19 Doses to a Member of the Public from Activities inside the Site Boundary

-19 Additional Information 20 Effluent Concentration Limits 21 Solid Waste Shipments 22 Irradiated Fuel Shipments 24 Section 111 Meteorological Data llours at Each Wind Speed and Direction 25 Changes to llistorical Meteorological Data 34 Section IV Unplanned or Abnormal Releases 35 Offsite Dose Calculation Manual 35 Major Changes *o Radwaste Processing Systems 35 Land Use Census 35 Radioactive Shipments 35 Inoperability of Effluent Monitoring Instrumentation 35 j

Storage Tanks 36 1995 Meteorological Data Revision to Report No.19

]

Offsite Dose Calculation Manual

Attachment to WO 97-Os 45 Page 3 of 36 EXECUTIVE

SUMMARY

This Annual Radioactive Effluent Release Repon documents the quantities of liquid and gaseous effluents and solid waste released by the Wolf Creek Generating Station (WCGS) from January 1,1996, through December 31,1996. The format and content of this report are in accordance with Regulatory Guide 1.21, Revision 1.

Sect on I of this report provides a summary of the quantities of radioactive liquid and gaseous effluents for j

this reporting period. An elevated release pathway does not exist at WCGS, therefore, all airborne releases are considered to be ground level releases. The concurrent meteorological condition gaseous pathway dose determination is met by the WCGS Offsite Dose Calculation Manual (ODCM) methodology of assigning all gaseous pathways to a hypothetical individual residing at the highest annual X/Q and D/Q location.

This results in a conservative estimate of dose to a member of the public rather than determining each j

pathway dose for each release condition. A conservative error of thirty percent has been estimated in the ellluent data.

Sections 11, Ill, and IV provide additional information required by Regulatory Guide 1.21, Revision 1, and ODCM Section 7.2. Specifically :

i Section 11 includes supplemental information on ODCM limits, average energies of radionuclides, and e

total radioactivities for liquid and gaseous effluents; maximum permissible concentrations (MPCs);

continuous and batch releases; calculated doses; and solid waste disposal.

Section 111 documents WCGS meteorological data for wind speed, wind direction, and atmospheric e

stability. In addition, problems with the validation and verification process are explained.

Section IV provides additional information concerning changes to the ODCM manual, planned and unplanned releases, changes to radwaste treatment systems, land use census, monitoring instruments, radwaste shipments, and storage tank quantities.

J provides a corTection to 1995 meteorological data. provides an updated Offsite Dose Calculation Manual.

i

\\

Attachment to WO 97-0045 Page 4 of 36 Section 1 REPORT OF RADIOACTIVE EFFLUENTS (1996): LIQUID Type of Effluent Unit Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release (not including tritium, gases, alpha)

Ci 8.23 ] E-01 3.066E-01

2. Average Diluted Concentration During Period uCi/ml 6.280E-08 6.649E-09
3. Percent of Applicable Limit (1) 16.5 6.1 B. Tritium
1. Total Release Ci 2.163E+02 7.569E+01
2. Average Diluted Concentration During Period uCi/ml 1.650E-05 1.6414E-06
3. Percent of Applicable Limit (MPC) (2) 5.5E-01 5.5E-02 (ECL) 1.65E+00 1.6E-01 C. Dissolved and Entrained Gases
1. Total Release Ci 9.746E+00 1.283E-02
2. Average Diluted Concentration During Period uCi/ml 7.436E-07 2.781 E-10
3. Percent of Applicable Limit (3) 0.37 1.39E-04 D. Gross Alpha Radioactivity
1. Total Release Ci 2.794E-03 7.981 E-06 E. Volume of Waste Release (prior to dilution)

Liters 4.586E+07 8.340E+ 07 F. Volume of Dilution Water Used Liters 1.306E+10 4.603E+ 10 l

The applicable limit for the Wolf Creek Generating Station is 5 Curies per year.

(Reference 10 CFR 50, Appendix 1," Guides On Design Objectives For Light-Water

-Cooled Nuclear Power Reactors", paragiaph A.2). The value printed here is derived by dividing the total release Curies by 5 Curies and then multiplying the result by 100.

2 This value is derived by the following formula:

(Average Diluted Concentration)(100)

% of Applicable Limit =

(ECL, Appendix B, Table II / 210CFR20)

This value is derived by the following formula:

(Average Diluted Concentration)(100)

% of Applicable Limit =

(2E -4 from ODCM Section 2.1)

)

Attachment to WO 97-0045 Page5 of36 i

iti: PORT OF RADIOACTIVE EFFLUENTS (1996): LIQUID Type of Efiluent Unit Quarter 3 Quarter 4 i

A. Fission and Activation Products

1. Total Release (not including tritium, gases, alpha)

Ci 4.975E-G 3.146E-02

2. Average Diluted Concentration During Period uCi/ml 3.644E-09 4.132E-09
3. Percent of Applicable Limit (I) 9.95E-01 6.29E-01 l

B. Tritium

1. Total Release Ci 1.753E+02 7.264E+01
2. Average Diluted Concentration During Period uCi/ml 1.284E-05 9.539E-06
3. Percent of Applicable Limit (MPC) (2) 4.3 E-01 3.2 E-01 (ECL) 1.3E+00 9.5E-01 C. Dissolved and Entrained Gases
1. Total Release Ci 6.787E-03 7.555E-06
2. Average Diluted Concentration During Period uCi/mi 4.971 E-10 9.921 E-13
3. Percent of Applicable Limit (3) 2.48E-04 4.96E-07 D. Gross Alpha Radioactivity
1. Total Release Ci 8.918E-06 8.60E-06 E. Volume of Waste Release (prior to dilution)

Liters 2.788E407 1.775E+07 F Volume of Dilution Water Used Liters 1.362E+10 7.596E+09 The applicable limit for the Wolf Creek Generating Station is 5 Curies per year.

(Reference 10 CFR 50, Appendix 1," Guides On Design Objectives For Light-Water

-Cooled Nuclear Power Reactors", paragraph A.2). The value printed here is derived by dividing the total release Curies by 5 Curies and then multiplying the result by 100.

2 This value is derived by the following formula:

(Average Diluted Concentration)(100)

% of Applicable Limit =

(ECL, Appendix B, Table 11/ 210CFR20)

This value is derived by the following formula:

(Average Diluted Concentration)(100)

% of Applicable L.

.t =

tmi (2E-4 from ODCM Section 2.1) i j

Attachment to WO 97-0045 Page 6 of 36 LIQUID EFFLUENTS NUCLIDES Continuous Mode Batch Mode RELEASED Unit Quarter i Quarter 2 Quarter 1 Quarter 2 11-3 Ci 2.71 E-01 4.89E-01 2.16E+02 7.52E+01 Cr 51 Ci n/a n/a 7.96E-02 2.53 E-02 Mn-54 Ci

< l.69E-02

<7.49E-02 2.36E-02 4.83E-3 Fe-55 Ci

<3.38E-02

<l.50E-01 3.39E-01 1.09E-01 Fe-59 Ci

<l.69E-02

<7.49E-02 2.95E-03

' 3.12E-03 Co-57 Ci n/a n/a 1.33 E-03 3.53E-04 Co-58 Ci 4.llE-05

<7.49E 02 1.50E-01 5.76E-02 Co-60 Ci 5.82E-05

<7.49E-02 1.30E-01 2.59E-02 Zn-65 Ci

< l.69E-02

<7.49E-02

<3.64 E-04

<3.05E-04 Sr-89 Ci

<l.69E-02

<7.49E-03

<3.64 E-05

<3.05E-05 Sr-90 Ci

< l.69E-02

<7.49E-03 4.01 E-05 1.82E-12 1if-181 Ci n/a n/a 1.26E-04 n/a Nb-95 Ci n/a n/a 1.32E-02 7.39E-03 Zr-95 Ci n/a n/a 9.71E-03 4.22E-03 Mo-99 Ci

< l.69E-02

<7.49E-03 5.82E-04

<3.05 E-04 Ag-1IOm Ci n/a n/a 9.04E-04 1.22E-04 Sn-l l3 Ci n/a n/a 1.59E-03 3.64E-04 I

Sn-ll7m Ci n/a n/a 6.07E-04 n/a Sb-125 Ci n/a n/a 5.38E-02 6.14E-02 1 131 Ci 1.12E-05

<l.50E-01 2.55E-03

<3.05E-04 Cs-134 Ci 3.61E-05

<7.49E-02 1.66E-03 9.33E-04 Cs-I V' Ci 3.0lE-05

<7.49E-02 3.21E-03 9.73E-04 Ce o41 Ci

<l.69E-02

<7.49E-02 1.91 E-04 6.IIE-05 Cc-144 Ci

<l.69E-02

<7.49E-02 2.30E-03 9.26E-04 Gross Alpha Ci

<3.38E-03

< l.50E-02 2.79E-03 7.98E-06 Ar-41 Ci

<3.38E-01

<l.50E+ 00

<7.28E-03

<6.llE-03 Kr-85m Ci

<3.38E-01

< l.50E+00

<7.28E-03

<6.llE-03 Kr-85 Ci

<3.38E-01

<l.50E+00 3.04E-01 (6. l lE-03 Kr 87 Ci

<3.38E-01

<l.50E+00

<7.28E-03

<6IIE-03 Kr-88 Ci

<3.38E-01

<l.50E+00

<7.28E-03

<6.llE-03 Xc 131m Ci

<3.38E-01

<l.50E+00 1.75E-01 1.16E-02 Xe 133m Ci

<3.38E-01

< l.50E+00 5.51E-02 (6.llE-03 Xe-133 Ci 1.17E-03

< l.50e+00 9.21 E+00 9.65E-04 Xe-135m Ci

<3.38E-01

< l.50E+00

<7.28E-03

<6. l l E-03 Xe-135 Ci

<3.38E-01

<l.50E+00 2.79E-03 7.98E-06 Tc-99m Ci n/a n/a 5.58E-04 n/a Ru-103 Cl n/a n/a 1.04E-03 1.17E-03 Ru-106 Ci n/a n/a 8.10E-04 n/a Sb-124 Ci n/a n/a 1.34E-03 2.820-03 Te-132 Ci n/a n/a 8.91E-05 n/a 1-132 Ci n/a n/a 1.28E-04 n/a Ha-140 Ci n/a n/a 5.18E-04 rva 1 a 140 Ci n/a n/a 1.29E-03 n/a Np-239 Ci n/a n/a 6.57E-04 n/a NOTE Less than values are calculated using the Lower Limit of Detection (LLD) values listed in Table 21 of the ODCM multiplied by the volume of waste discharged during the respective quarter.

The less than values are not included in the summation for the total release values.

1 j

Attachrnent to WO 97-0045 i

Page 7 of 36 LIQUID EFFLUENTS

)

NUCLIDES Continuous Mode Batch Mode RELEASED U_ni_t Quarter 3 Quarter 4 Quarter 3 Quarter 4 11-3 Ci 2.17E-01 1.75E-01 1.75E+02 7.25E+01 Cr-51 Ci n/a n/a 3.31 E-04 7.31 E-06 Mn-54 Ci

<l.62 E-02

<8.88E-03 1.43E-03 8.82E-04 i

Fe-55 Ci

<l.78E-02

<2.34E-01 1.42E-02 8.13E-03 i

Fe-59 Ci

<l.62 E-02

<8.88E-03

< l.41 E-04 3.42E-05 Co-57 Ci n/a n/a 4.99E-05 5.27E-05 t

Co-58 Ci

< l.62 E-02

<8,88 E-03 3.97E-03 5.49E-03 Co-60 Ci

< l.62E-02

<8.88E-03 9.52E-03 5.60E-03 Zn-65 Ci

<l 62E-02

<8.8SE-03

< l.41 E-04

<7.27E-05

)

Sr-89 Ci

< l.62 E-03

<8 88E-04

< l.41 E-05

<7.27E-06 Sr-90 Ci

<l 62E-03

<8.88 E-04 2.40E-07 1.43E-07 Sr 92 Ci n/a n/a n/a 2.11E-06 Nb-95 Ci n/a n/a 6.59E-04 1.54 E-03 Zr-95 Ci n/a n/a 2 88E-04 8.13 E-04 Mo-99 Ci

< l.62 E-02

<8.88E-03 ale-04

<7.27E-05 Ag-110m Ci n/a n/a n. iOE-05 4.20E-05 Sn-ll3 Ci n/a n/a 5.88E-05 1.45 E-04 Sb 124 Ci n/a n/a 2.70E-05 4.14 E-06 Sb-125 Ci n/a n/a 8.02E-03 5.84E-03 I-131 Ci

<3.24 E-02

< l.78 E-02 7.46E-05

<l.45 E-04 Cs-134 Ci

< l.62C-02

<8.88E-03 6.31E-03 1.02E-03 Cs-137 Ci

< l.62E-02

<8.88E-03 4.75 E-03 9.22E-04 Cc-141 Ci

< l.62E-02

<8.88E-03

<l.41 E-04

<7.27E-05 Cc-144 Ci

<l.62 E-02

<8.88(I-03

< l.41 E-04

<7.27E-05 Gross Alpha Ci

<3.24E-03

<l.78 E-03 S.92E-06 8.60E-06 Ar-41 Ci

<3.24 E-01

< l.78E-01

<2.82E-03

<l.45 E-03 Kr-85m Ci

<3.24 E-O i

< l.78E-O l

<2.82E-03

< l.45 E-03 Kr-85 Ci

<3.24E-01

< l.78E-01 5.63E-03

<145E-03 Kr-87 01

<3.24 E-01

<l 78E-01

<2.82E-03

<l.45 E-03 Kr-88 Ci

<3.24E-01

< l.78 E-01

<2.82E-03

< l.45 E-03 i

Xe-131m Ci

<3.24E-01

< l.78 E-01

<2.82E-03

<l.4 5 E-03 Xe-133m Ci

<3.24 E-01

< l.78E-01

<2.82E-03

<l.45 E-03 Xe-133 Ci

<3.24E-01

<l.78 E-01 1.16E-03 7.56E-06 Xe-135m Ci

<3.24E-01

< l.78 E-01

<2.82E-03

< l.4 5 E-03 Xe-135 Ci

<3.24E-01

< l.78 E-01

<2.82E-03

<l.45 E-03 Na-24 Ci n/a n/a n/a 1.30E-06 NOTE Less than values are calculated using C ower Limit of Detection (LLD) values listed in Table 2-1 of the ODCM multiplied by the *

. of waste discharged during the respective quarter.

The less than values are not include

.e summation for the total release values.

Attachment to WO 97-0045 Page 8 of 36 LIQUID CUMULATIVE DOSE

SUMMARY

(1996)

TABLE 1 I

ODCM CALCULATED ODCM LIMIT

% OF QUARTER i OF 1996 DOSE LIMIT 1OTAL DOSE (mrem) FOR BONE 4.63 E-02 5.00E+00 9.26E-01 TOTAL DOSE (mrem) FOR LIVER I.73E-01 5.00E+00 3.47E+00 TOTAL DOSE (mrem) FOR TOTAL !!ODY 1.52E-01 1.50E+00 1.02E+01 TOTAL DOSE (mrem) FOR TilYROID 1.13E-01 5.00E+00 2.27E+00 TOTAL DOSE (mrem) FOR KIDNEY 1.22E-01 5.00E+00 2.44E+00 TOTAL DOSE (mrem) FOR LUNG 1.08E-01 5.00E+00 2.17E+00 TOTAL DOSE (mrem) FOR GI-LLI 5.70E-01 5.00E+00 1.14 E+01 QUARTER 2 OF 1996 TOTAL L)OSE (mrem) FOR BONE 7.37E-03 5.00E+00 1.47E+01 TOTAL DOSE (mrem) FOR LIVER 1.44 E-01 5.00E+00 2.89E+00 TOl AL DOSE (mrem) FOR TOTAL BODY 1.41 E-01 1.50E400 9.40E+00 TOTAL DOSE (mrem) FOR TilYRO!D 1.32E-01 5.00E+00 2.64E+00 TOTAL DOSE (mrem) FOR KIDNEY 1.36E-01 5.00E+00 2.72E+00 TOTAL DOSE (mrem) FOR LUNG 4.06E-02 5.00E+00 8.12E-01 TOTAL DOSE (mrem) FOR GI-LLI 2.76E-01 5.00E+00 5.52E+00 QUARTER 3 OF 1996 TOTAL DOSE (mrem) FOR BONE 3.22E-02 5.00E+00 6.44 E-01 TOTAL DOSE (mrem) FOR LIVER 9.45E-02 5.00E+00 1.89E+00 TOTAL DOSE (mrem) FOR TOTAL BODY 8.00E-02 1.50E+00 5.33E+00 TOTAL DOSE (mrem) FOR TilYROID 3.41E-02 5.00E+00 6.82E-01 TOTAL DOSE (mrem) FOR KIDNEY 5.39E-02 5.00E+00 1.08E+00 1OTAL DOSE (mrem) FOR LUNG 4.06E-02 5.00E+00 8.12E-01 TOTAL DOSE (mrem) FOR GI-LLI 4.47E-02 5.00E+00 8.94 E-01 QUARTER 4 OF 1996 TOTAL DOSE (mrem) FOR BONE 6.36E-03 5.00E+00 1.27E-01 TOTAL DOSE (mrem) FOR LIVER 1.75E-02 5.00E+00 3.51 E-01 TOTAL DOSE (mrem) FOR TOTAL BODY 1.47E-02 1.50E+00 9.77E-01 TOTAL DOSE (mrem) FOR TilYah>lD 5.91 E-03 5.00E+00 1.18E-01 TOTAL DOSE (mrem) FOR KIDNEY 9.73E-03 5.00E+00 1.95E-01 TOTAL DOSE (mrem) FOR LUNG 7.21E-03 5.00E+00 1.44 E-01 TOTAL DOSE (mrem) FOR GI-LLI 2.71E-02 5.00E+00 5.42E-01 TOTALS FOR 1996 TOTAL DOSE (mrem) FOR BONE 9.23 E-02 1.00E+01 9.23E-01 TOTAL DOSE (mrem) FOR LIVER 4.30E-01 1.00E+0) 4.30E+00 TOTAL DOSE (mrem) FOR TOTAL 110DY 3.88E-01 3.00E+00 1.29E+01 TOTAL DOSE (mrem) FOR TilYROlD 2.86E-01 1.00E+0!

2.86E+00 TOTAL DOSE (mrem) FOR KIDNEY 3.21E-01 1.00E+01 3.21E+00 TOTAL DOSE (mrem) FOR LUNG 2.90E-01 1.00E+01 2.90E+00 TOTAL DOSE (mrem) FOR GI-LLI 9.18E-01 1.00E+0i 9.18E+00

1. Based on ODCM Section 2.2 which restricts dose to the whole body to less than or equal to 1.5 mrem per quarter and 3.0 mrem per year, Dose restriction of any organ is less than or equal to 5 mrem per quarter and 10 mrem per year.

l l

I

Attachment to WO 97-0045 Page 9 of 36 LIQUID CUMULATIVE DOSE

SUMMARY

(1996) i TABLE 2 A.

Fission and Activation Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Products (not including i1-3, gases, alpha) 1 1.

Total Release -(Ci) 8.23 E-01 3.07E-01 4.97E-02 3.15E-02 1.21E+00 2.

Maximum Organ Dose (mrem) 4.71 E-01 1.44 E-01 6.10E-02 2.13E-02 6.48E-Ol 3.

Organ Dose Limit (mrem) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00P DI 4.

Percent of Limit 9.43 E+00 2.87E+00 1.22E+00 4.26E-01 6.48E+00 IL Tritium 1.

Total Release -(Ci) 2.16E+02 7.57E+01 1.75E+02 7.26E+01 5.40E+02 2.

Maximum Organ Dose (mrem) 9.89E-02 1.32E-01 3.35E-02 5.81E-03 2.70E-01 3.

Organ Dose Limit (mrem) 5.00E+0n 5.00E+00 5.00E+00 5.00E+00 1.00E+0i 4.

Percent of Limit 1.98E+00 2.64 E+00 6.70E-01 1.16E-01 2.70E400 This table is included to show the correlation between Curies released and the associated calculated maximum organ dose. WCGS ODCM methodology is used to calculate the maximum organ dose which assumes that an individual drinks the water and eats the fish from the discharge point. ODCM Section 2.2 organ dose limits are used. The less than values are not included in the summation for the total release values.

Attachment to WO 97-0045 Page 10 of 36 REPORT OF RADIOACTIVE EFFLUENTS (1996): AIRilORNE Unit Quarter 1 Quarter 2 A. Fission and Activation Gases

1. Total Release Ci 1.43 E+03 7.446E+00
2. Average Release Rate for Period uCi/sec 1.819E+02 9.471 E-01
3. Percent of ODCM Limit (1) 1.17E+00 1.01E-02 B. lodines
1. Total lodine-131 Ci 5.536E-05 3.427E-05
2. Average Release Rate for Period uCi/sec 7.041 E-06 4.359E-06 3
3. Percent of Applicable Limit (2) 5.5 E-03 3.4E-03 C. Particulates
1. Particulates with Half-lives > 8 days Ci 6.883 E-08 1.068E-06
2. Average Release Kato for Period uCi/sec 8.754E-09 1.358E-07
3. Percent of ODCM Limit (3) 1.72E-07 7.58E-06
4. Gross Alpha Radioactivity Ci 0.00E+00 0.00E+00 D. Tritium 1 Total Release Ci 5.763 E+00 7.258E+00 2 Average Release Rate for Period uCi/sec 7.330E-01 9.231E-01 3 Percent of ODCM Limit (4) 5.48E-02 6.95E-02
1. The percent of ODCM limit for fission and activation gases is calculated using the following methodology:

(Qtrly Total Beta Airdose)(100)

(Qtrly Total Gamma Airdose)(100)

% of ODCM Limit =

10 mrad 5 mrad i

The largest value calculated between Gamma and Beta airdose is listed as the % of J

ODCM Lin it.

2. The percent of ODCM limit for iodine is calculated using the following methodology:

(Total Curies oflodine-131)(100)

% of ODCM Limit =

1 Curie

3. The percent of ODCM limit for particulates is calculated using the following methodology:

(Ilighest Organ Dose Due to Particulates)(100)

% of ODCM L..imit =

7.5 mrem

4. The percent of ODCM limit for tritium is calculated using the following methodology:

4 (Ilighest Organ Dose Due to 11 - 3)(100)

% of.ODCMLimit =

7.5 mrem NOTE This type of methodology is used since the WCGS ODCM ties release limits to doses rather than Curie release rates.

-.. ~. -... -.. -

~-

i i

Attachment to WO 97-0045 Page 11 of 36 REPORT OF RADIOACTIVE EFFLUENTS (1996): AIRBORNE i

Unit Quarter 3 Quarter 4 A. Fission and Activation Gases

1. Total Release Ci 1.369E+00 9.327E+00 j;
2. Average Release Rate for Period uCi/sec 1.722E.')1 1.173E+00 l
3. Percent ofODCM Limit (1) 7.94 E-03 1.27E-02 B. lodines
1. Total lodine-131 Ci 0.00E+00 0.00E+00 3
2. Average Release Rate for Period uCi/sec 0.00E+00 0.00E+00 3, Percent of Applicable Limit (2) 0.00E+00 0.00E+00 3

C. Particulates

1. Particulates with IIalf-lives > 8 days Ci 0.00E+00 0.00E+00
2. Average Release Rate for Period uCi/sec 0.00E+00 0.00E+00
3. Percent of ODCM Limit (3) 0.00E+00 0.00E+00
4. Gross Alpha Radioactivity Ci 0.00E+00 0.00E+00 l

D. Tritium 1 Total Release Ci 1.651 E+01 1.081E+01 4

2 Average Release Rate for Period uCi/sec 2.077E+00 1.36E+00 3 Percent of 0DCM Limit (4) 1.55E-01 1.01 E-01 l

1. The percent of ODCM limit for fission and activation gases is calculated using the following j

methodology:

(Qtrly Total Beta Airdose)(100)

(Qtrly Total Gamma Airdose)(100)

% of ODCM Limit =

or j

10 mrad 5 mrad 4

The largest value calculated between Gamma and Beta airdose is listed as the % of i

ODCM Limit.

f

2. The percent of ODCM limit for iodine is calculated using the following methodology:

(Total Curies oflodine-131)(100) j

% of ODCM Limit =

1 Curie i

3. The percent of ODCM limit for particulates is calculated using the following methodology:

(Highest Organ Dose Due to Particulates)(100)

% of ODCM Limit =

i 7.5 mrem j

4. The percent of ODCM limit for tritium is calculated using the following methodology:

(Highest Organ Dose Due to H -3)(100)

% ofODCMLimit =

1 7.5 mrem i

NOTE l

1 This type of methodology is used since the WCGS ODCM ties release limits to doses rather than i

Curic release rates.

i 1

i 3

v

Attachment to WO 97-0045 Page 12 of 36 GASEOUS EFFLUENTS NUCLIDES RELEASED Continuous Mode Batch Mode Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 1.Fisssion and Activation Gases Ar 41 Ci n/a n/a 4.23E-02 7.51 E-02 Kr 85 Ci n/a n/a 1.93 E+02 7.23 E+00 Kr-85m Ci n/a n/a n/a n/a Kr-87 Ci

<2.26E+01

<2.38 E+01

<2.64E+00

<9.21 E-03 Kr-88 Ci

<l.97E+01

<2.08E+01

<2.30E+00

<8.02E-03 Xe-131m Ci 1.52E+00 n/a 1.59E+00 n/a Xe-133 Ci 1.41 E+02

<l.71 E+02 1.04E+03 5.85E-02 Xe-133m Ci

<3.74E+01

<3.95E+01

<4.38 E+00

<l.52E-02 Xe-135 Ci 1.29E+00

<3.64E+00 1.60E-03 0.00E+00 Xe-138 Ci

<5.70E+02

<6.01 E+02

<6.66E+01

<2.32E-01 Total for Period Ci 1.44E+02 0.00E+00 1.29E+03 7.45 E+00

2. Italogens (Gaseous) 1-131 Ci 5.54E-05 3.43 E-05

<2.65E-05

<9.24 E-08 1-133 Ci

<2.27E-02

<2.39E-02

<2.65E 03

<9.24E-06 Total for Period Ci 5.54E-05 3.43 E-05 0.00E+00 0.00E+00

3. Particulates and Tritium 11-3 Ci 4.33 E+00 7.15E+00 1.43 E+00 1.12E-01 Mn-54 Ci

<2.27E-03

<2.39E-03

<2.65 E-04

<9.24 E-07 Fe-59 Ci

<2.27E-03

<2.39E-03

<2.65 E-04

<9.24E-07 Co-57 Ci 6.88E-08

<2.39E-03

<2.65E-04

<9.24E-07 i

Co-58 Ci n/a 1.07E-06 n/a n/a Co-60 Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24 E-07 Zn-65 Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24E-07 Mo-99 Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24 E-07 Cs-134 Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24E-07 Cs-137 Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24E-07 i

Ce-141 Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24E-07 Ce-144 Ci

. <2.27E-03

<2.39E-03

<2.65E-04

<9.24 E-07 Sr-89 Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24E-07 Sr-90 Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24 E-07 Gross Alpha Ci

<2.27E-03

<2.39E-03

<2.65E-04

<9.24 E-07 Total for Period Ci 4.33 E+00 7.15E+00 1.43 E+00 1.12E-01 NOTE Less than values for Noble Gases are calculated using the Lower Limit of Detection (LLD) values obtained at WCGS multiplied by the volume of air discharged during the respective quarter. For the Italogens and Particulates the ODCM LLD values are used.

Attschment to WO 97-0043 Page 13 of 36 i

i j

GASEOUS EFFLUENTS l

NUCLlDES RELEASED Continuous Mode Batch Mode j

Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 l

1.Fisssion and Activation Gases i

Ar-41 Ci n/a n/a 5.37E-01 1.09E-01 Kr-85 Ci n/a n/a n/a 9.09E+00 j

Kr-85m Ci n/a n/a n/a n/a l

Kr 87 Ci

<2.52E+01

<2.78 E+01

<6.72E-02

< l.19E-02 l

Kr-88 Ci.

<2.19E+01

<2.42E+01

<5.85E-02

<l.03 E-02

);

Xe-131m Ci n/a n/a n/a n/a Xe-133 Ci 5.10E-01 1.07E-01 6.65E-02 1.05E-02 l

Xe-133m Ci

<4.17E+01

<4.61 E+0 !

<l.llE-01

<l.97E-02 l

Xe-135 Ci 2.55E-01 9.03E-03

<l.02E-02

<l.81 E-03 i

Xe-138 Ci

<6.34 E+02

<7.01 E+02

<l.69E+00

<2.99E-01 Total for Period Ci 7.65 E-01 1.loE-01 6.04E-01 9.21 E+00 i

1-lalogens (Gaseous)

}

l-131 Ci

<2.53E-04 '

<2.79E-04

<6.74E-07

<l.19E-07 l

l-!23 Ci

<l.80E+02

<2.79E-02

<6.74 E-05

<l.19E-05 l

Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i

}

3. Particulates and Tritium l

4 11-3 Ci 1.28E+01 1.05 E+01 3.71 E+00 3.54E-01

)

i Mn-54 Ci

<2.53 E-03

<2.79E-03

<6.74E-06

< l.19E-06 Fe-59 Ci

<2.53 E-03

<2.79E-03

<6.74E-06

<l.19E-06 Co-58 Ci

<2.53 E-03

<2.79E-03

<6.74 E-06

<l.19E-06

{

Co-60 Ci

<2.53 E-03

<2.79E-03

<6.74E-06

<l.19E-06

{

Zn-65 Ci

<2.53 E-03

<2.79E-03

<6.74E-06

<l.19E-06 Mo-99 Ci

<2.53 E-03

<2.79E-03

<6.74E-06

<l.19E-06 j

Cs-134 Ci

<2.53 E-03

<2.79E-03

<6.74E-06

<l.19E-06 Cs-137 Ci

<2.53 E-03

<2.79E-03

<6.74E-06

<l.19E-06

(

Ce-141 Ci

<2.53 E-03

<2.79E-03

<6 74E-06

< l.19 E-06 Ce-144 Ci

<2.53 E-03

<2.79E-03

<6.74 E-06

<l.19E-06 l

Sr-89 Ci

<2.53E-03

<2.79E-03

<6.74 E-06

<l.19 E-06 Sr-90 Ci

<2.53 E-03

<2.79E-03

<6.74 E-06

<l.19E-06

}

Gross Alpha Ci

<2.53E-03

<2.79E-03

<6.74E-06

<l.19E-06

{

Total for Period Ci 1.28E+0) 1.05E+01 3.71 E+00 3.54E-01

)

(

l NOTE Less than values for Noble Cases are calculated using the Lower Limit of Detection (LLD) values obtained at WCGS multiplied by the volume of air discharged during the respective quarter. For 2

the llalogens and Particulates the ODCM LLD values are used.

l i

1 1

i i

't m

r-..r r

'e--t w

Attachment to WO 97-0045 Page 14 of 36 G ASEOUS CUMULATIVE DOSE

SUMMARY

(1996)

Table 1 ODCM CALCULATED DOSE ODCMI

% OF LIMIT QUARTER 1 OF 1996 LIMIT TOTAL DOSE (mrem) FOR BONE 9.64 E-05 7.50E+00 1.28E-03 4

TOTAL DOSE (mrem) FOR LIVER 4.17E-03 7.50E+00 5.56E-02 TOTAL DOSE (mrem) FOR TOTAL BODY 4.13E-03 7.50E+00 5.51 E-02 TOTAL DOSE (mrem) FOR TIIYROID 3.59E-02 7.50E+00 d.79E-01 TOTAL DOSE (mrem) FOR KIDNEY 4.23E-03 7.50E+00 5.64L?-02 TOTAL DOSE (mrem) FOR LUNG 4.07E-03 7.50E+00 5.43 E-02 1OTAL DOSE (mrem) FOR GI-LLJ 4.08E-03 7.50E+00 5.44E 02 QUARTER 2 OF 1996 TOTAL DOSE (mrem) FOR llONE 5 99E-05 7.50E+00 7.99E-04 TOTAL DOSE (mrem) FOR LIVER

$.19E-03 7.50E+00 6.92 E-02 l

TOTAL DOSE (mrem) FOR TOTAL IlODY 5.17E-03 7.50E+00 6.89E-02 TOTAL DOSE (mrem) FOR TilYROID 2.49E-02 7.50E+00 3.32E-01 TOTAL DOSE (mrem) FOR KIDNEY 5.23E-03 7.50E+00 6.97E-02 TOTAL DOSE (mrem) FOR LUNG 5.13E-03 7.50E+00 6.84E-02 TO FAL DOSE (mrem) FOR Gl-LLI 5.14E-03 7.50E+00 6.85E-02 QUARTER 3 OF 1996 TOTAL DOSE (mrem) FOR llONE 0.00E+00 7.50E+00 0.00E+00 TOTAL DOSE (mrem) FOR LIVER I.17E-02 7.50E+00 1.56E-01 TOTAL DOSE (mrem) FOR TOTAL I!ODY 1.17E-02 7.50E+00 1.56E-01 TOTAL DOSE (mrem) FOR TilYROID 1.17E-02 7.50E+00 1.56E-01 TOTAL DOSE (mrem) FOR KIDNEY 1.17E-02 7.50E+00 1.56E-01 TOTAL DOSE (mrem) FOR LUNG 1.17E-02 7.50E+00 1.56E-01 i

TOTAL DOSE (mrem) FOR GI-LLI 1.17E-02 7.50E+00 1.56E-01 QUARTER 4 OF 1996 TOTAL DOSE (mrem) FOR BONE 0.00E+00 7.50E+00 0.00E+00 l

TOTAL DOSE (mrem) FOR LIVER 7.64 E-03 7.50E+00 1.02E-01 TOTAL DOSE (mrem) FOR TOTAL BODY 7.64 E-03 7.50E+00 1.02E-01 TOTAL DOSE (mrem) FOR TilYROID 7.64E-03 7.50E+00 1.02E-01 TOTAL DOSE (mrem) FOR KIDNEY 7.64 E-03 7.50E+00 1.02E-01 j

TOTAL DOSE (mrem) FOR LUNG 7.64E-03 7.50E+00 1.02E-01 l

TOTAL DOSE (mrem) FOR GI-LLI 7.64 E-03 7.50E+00 1.02E-01 j

TOTALS FOR 1996 j

10TAL DOSE (mrem) FOk llONE 1.56E-04 1.50E+00 1.0,E-03 TOTAL DOSE (mrem) FOR LIVER 2.87E-02 1.50E+00 1.91 E-01 TOTAL DOSE (mrem) FOR TOTAL llODY 2.86E-02 1.50E+00 1.9] E-01 TOTAL DOSE (mrem) FOR TilYROlD 8.01 E-01 1.50E+00 5.34 E-01 TOTAL DOSE (mrem) FOR KIDNEY 2,88E-02 1.50E+00 1.92E-01 TOTAL DOSE (mrem) FOR LUNG 2.85E-02 1.50E+00 1.90E-01 TOTAL DOSE (mrem) FOR GI-LLI 2.85E-02 1.50E+00 1.90E-01

1. Based on WCGS ODCM Section 3.2.2 which restricts dose during any calendar quarter to less than or equal to 7.5 mrem to any organ and during any calendar year to less than or equal to 15 mrem to any organ.

Attachment to WO 97-0045 Page 15 of 36 GASEOUS CUMULATIVE DOSE

SUMMARY

(1996)

TABLE 2 Nuclides Released Quarter I Quarter 2 Quarter 3 Quarter 4 Total A.

Fission and Activation Gases 1.

Total Reanse -(Ci) 1.43E+03 7.45E+00 1.37E+00 9.33 E+00 1.45 E+03 2.

Total Gamma Airdose (mrad) 3.00E-02 5.97E-05 3.97E-04 8.56E-05 3.05E-02 3.

Gamma Airdose Limit (mrad) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01 4.

Pcceent of Gamma Airdose Limit 6.00E-01 1.19E-03 7.94 E-03 1.71E-03 3.05 E-01 5.

Total Heta Airdose (mrad) 1.17E-01 1.0lE-03 2.09E-04 1.27E-03 1.19E-01 6.

Heta Airdose Limit (mrad) 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01 7.

Percent of Beta Airdose Limit (mrad) 1.17E+00 1.01 E-02 2.09E-03 1.27E-02 5.96E-01 H.

Particulates 1.

Total Particulates (Ci) 6.88E-08 1.07E-06 0.00E+00 0.00E+00 1.14 E-06 2.

Maximum organ Dose (mrem) 1.29E-08 5.69E-07 0.00E+00 0.00E+00 5.82E-07 3.

Organ Dose Limit (mrem) 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 4.

Percent of Limit 1.72E-07 7.58E-06 0.00E+00 0.00E+00 3.88E-06 C.

Tritium 1.

Total Release (Ci) 5.76E+00 7.26E+00 1.65E+0i 1.08E+01 4.03E+01 2.

Maximum Organ Dose (mrem) 4.llE-03 5.21E-03 1.16E-02 7.55E-03 2.85 E-02 3.

Organ Dose Limit (mrem) 7.50E400 7.50E+00 7.50E+00 7.50E+00 1.50E+01 4.

Percent of Limit 5.48E-02 6.95E-02 1.55 F-01 1.01E-01 1.90E-01 D.

lodine 1.

Total 1-131,1 133 (Ci) 5.54 E-05 3.43 E-05 0.00E+00 0.00E+00 8.96E-05 2.

Maximum Organ Dose (mrem) 3.19E-02 1.97E-02 0.00E+00 0.00E+00 5.16E-02 3.

Organ Dose Limit (mrem) 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+0!

4.

Percent of Limit 4.25E-01 2.63 E-01 0.00E+00 0.00E400 3.44 E-01 This table is included to show the correlation between Curies released and the associated calculated maximum organ dose. The maximum organ dose is calculated using WCGS ODCM methodology which assumes that an individual actually resides at the release point. ODCM Section 3.2.2 orgr.n dose limits are used.

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

.. _ _ _ _ _. _.. ~... _. _.. _ _ _ _ _ _ _ _ _ _

3 Attachment to WO 97-0045 l

j Page 16 of 36 i

Section II 1

Supplemental Information i

1.

Offsite Dose Calculation Manual Limits

]

A.

For liquid waste emuents l

A.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to lhe concentrations specified in 10CFR20.

j Appendix B, Table 11, Column 2, for radiomslides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to j

2 x 10dmicroCurie/mL total activity.

A.2 The dose or dose commitment to MEMBER OF Tile PUBLIC from radioactive j

materials in liquid emuents released, from each unit, to UNRESTRICTED AREAS shall

{

be limited:

4 I

During any calendar quarter to less than or equal to 1.5 mrems to the whole body a.

and to less than or equal to 5 mrems to any organ and b.

During any calendar year to less than or equal to 3 n' rems, to the whole body, and to l

l less than or equal to 10 mrems to any organ.

l

)

B.

For gaseous waste effluents 1

B.1 The dose rate due to radioactive material released in gaseous effluents from the site to area at and beyond the SITE BOUNDARY shall be limited to the following:

a.

For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than I

j or equal to 3000 mrems/yr to the skin, and i

b.

For lodine-131, lodine-133, tritium, an.1 all radionuclides in particulate for.n with half-lives greater than 8 days: Less that or equal to 1500 mrems/yr to any organ.

l B.2 The air dose due to noble gases released in gaseous emuents, from each unit, to areas at

]

and beyond the SITE BOUNDARY shall be limited to the followmg.

i I

}

a.

During any calendar quarter: Less thar, or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and b.

During any calendar year: Less than or equal to 10 mrads for gamma radiatior. and less than or equal to 20 mrads for beta radiation.

l i

j B.3 The dose from lodine 131, Iodine-133, tritium, and a radionuclide in particulate form with half-lives greater than 8 days in gast ous emuents released to area at and beyond the j-SITE BOUNDARY shall be limited to the following:

l During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and a.

b.

During any calendar' year: Less than or equal to 15 mrems to any organ.

2.

Ma*.imum Permissible Concentrations (MPC's)

Water - covered in Section 1.A.

j Air - covered in Section 1.B.

i 4

k 4

1 4 -, _.

~ _

Attachment to WO 97-0045 Page 17 of 36 3.

Average Energy Average energy of fission and activation gaseous effluents is not applicable. See ODCM Section 3.1.2 for the methodology used in determining the release rate limits from noble gas releases.

4.

Measurements and Approximations of Total Radioactivity A.

Liquid Effluents Liquid Release Type Sampling Frequency Method of Analysis Type of Activity Analysis

1. Batch Waste Release P

Tank Each Batch P.ll.A.

Principal Gamma Emitters P

P.11. A.

1-131 Each Batch

a. Waste Monitor Tank P

P.fl.A.

Dissolved and Entrained One Batch /M Gases (Gamma Emitters) b, Secondary Liquid P

L.S.

11-3 Waste Monitor Tanks Each Batch S.A.C.

Gross Alpha P

O.S.L.

Sr-89, Sr-90

2. Continuous Releases Daily P.11.A.

Principal Gamma Emitters Grab Sample P.11.A.

1-131

a. Steam Generator M

P.li.A.

Dissolved and Entrained Blowdown Grab Sample Gases (Gamma Emittera)

b. Turbine Building Daily L.S.

11-3 Sump / Waste Water Grab Sample S.A.C.

Gross Alpha Treatment

c. Lime Sludge Pond Daily O.S.L.

Sr-89, Sr-90 Grab Sample o,3,L, pe.55 P= prior to each batch S.A.C.= scintillation alpha counter M= monthly O.S.L.= performed by an offsite laboratory L.S.= Liquid scintillation detector P.11.A.= gamma spectrum pulse height analysis using a liigh Purity Germanium detector

_ _ -. ~. -

. ~ _

1 Attachment to WO 97-0045 Page 18 of 36 8.

G:seous Weste Effluents Gaseous Release Type Sampling Frequency Method of Analysis Type of Activity Analysis Waste Gas Decay Tank P

P.ll.A.

Principal Gamma Emitters Each Tank Grab Sample j

Containment Purge or P

P.li.A.

Principal Gamma Emitters Vent Each Purge Grab Gas Bubbler and L.S.

11-3 (oxide)

Sample Unit Vent M

P.li.A.

Principal Gamma Emitters Grab Sample Gas Bubbler and L.S.

11-3 (oxide) j Radwaste Building Vent M

P.II.A.

Principal Gamma Emitters i

Grab Sample l

For Unit Vent and Continuous P.ll.A.

1 131 Radwaste Building Vent 1 133 i

release types listed above

)

Continuous P.li.A.

Principal Gamma Emitters i

Particulate Sample Continuous S.A.C.

Gross Alpha j

l Composite Particulate Sample Continuous O.S.L.

Sr-89, Sr-90 Composite

/

Particulate Sample i

P= prior to each batch S.A.C.= scintillation alpha counter M= monthly O.S.L.= performed by an offsite laboratory l

L.S.-liquid scintillation detector P.II.A.= gamma spectrum pulse height analysis j

using a liigh Purity Germanium detector i

i 4

i s

y h

I 4

4 I

h 4

l i

1 4

a J

4 Attachment to WO 97-0045 Page 19 of 36 5.

Batch Releases A batch release is the discontinuous release of gaseous or liquid effluents which takes place over a finite period of time usually hours or days.

There were 74 gaseous batch releases during the reporting period. The longest gaseous batch release lasted 8,546 minutes, while the shortest lasted 58 minutes. The average release lasted 942 minutes with a total gaseous batch release time of 69,735 minutes.

There were 105 liquid batch releases during the reporting period. The longest liquid batch release lasted 275 rainutes, while the shortest lasted 79 minutes. The average release lasted 90 minutes with a total liquid batch release time of 9,426 minutes.

6.

Continuous Reicases 4

A continuous release is a release of gaseous or liquid effluent which is essentially, uninterrupted for extended periods during normal operation of the facility.

There were four release pathways designated as continuous releases during this reporting period:

Steam Generator Blowdown, Turbine Building sump, Waste Water Treatment, and Lime Sludge Pond. There were two gas release pathways designated as continuous releases: Unit Vent and Radwaste Building Vent.

7.

Doses to a Member of the Public from Activities Inside the Site Boundary 4

Four activities by members of the public were considered in this evaluation: personnel making deliveries to the plant, workers at the Construction Administration Building located outside of the i.

restricted area, the access road south of the Radwaste Building and the lake during times when fishing was allowed. The dose calculated for the maximum exposed individual for these three activities was as follows:

Plant Deliveries 5.67E-02 mrem Construction Administration Workers 1.57E-02 mrem Access Road Users 9.50E-03 mrem Lake 5.42E-02 mrem i

The plant delivery calculations were based on deliveries 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> / week for 50 weeks / year. The Construction Administration Building occupancy was based on normal working hours of i

2000/ year. The usage factor for the access road South of the Radwaste Building was 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> / year. The dose to fishermen on the lake was based upon 1152 hours0.0133 days <br />0.32 hours <br />0.0019 weeks <br />4.38336e-4 months <br /> (17. hours for each day fishing was allowed).

Pathways used in the calculation were gaseous inhalation, submersion, and ground plane. All calculations were performed in accordance with the methodology and parameters in the ODCM.

4

Attachment to WO 97-0045 Page 20 of 36

8. AdditionalInformation On July 12,1996 the ODCM required particulate and iodine sample for the Radwaste Vent was sampled late. The sample is required every 7 days. Sample collection staned on July 3,1996 and was not changed until July 12,1996. This caused the sample to be taken 4.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> past the required 7 days plus the 25% allowed grace period. The sample dates were changed due to the July 4th holiday. As a corrective action Chemistry does not change the sample dates to accommodate plant holidays.

License Event Report (LER 96-019) was written to address missed ODCM required samples during a greater than 15% power change in less than one hour. The Unit Vent must be sampled for particulate and iodine concentration daily for seven days if the reactor coolant dose equivalent iodine increased by a factor of three or the Unit Vent noble gas concentration increased by a factor of three. It was determined that when the ODCM was a pan of the Technical Specifications that Chemistry did not sample the Unit Vent as described when the Reactor Coobi Dose Equivalent Iodine had increased by a factor of three. This LER was reviewed in NRC Inspection Report 97 01. A Noncited Violation (NCV) was issued to this ever.t. The NCV was also closed in Inspection Report 97-01.

See Section IV, " Additional Information," Subsection 2 for explanation of gaseous detector calibration source error for calibrations required by ODCM.

Attachment to WO 97-0045 Page 21 of 36 Effluent Concentration Limits l

j Nuclides Curies Average Diluted 10 CFPJO ECL

% of ECL Concentration (mci /ml) 1 11-3 5.40E+02 6.71 E-06 1.00E-03 6.71 E-01 Cr-51 1.05E-01 1.30E-09 5.00E-04 2.61 E-04 1

Mn-54 3.07E-02 3.81 E-10 3.00E-05 1.27E-03 Fe-55 4.50E-01 5.59E-09 1.00E-04 5.59E-03 Fe-59 6.1DE-03 7.58E-11 1.00E-05 7.58E-04 Co-57 1.78E-03 2.21 E-11 6.00E-05 3.69E-05 Co-58 2.17E-01 2.70E-09 2.00E-05 1.35E-02 Co-60 1.71 E-01 2.12E-09 3.00E-06 7.08E-02 Sr-90 4.05E-05 5.03E-13 5.00E-07 1.01 E-04 Sr-92 2.11 E-06 2.62E-14 4.00E-05 6.55E-08 Zr-95 1.50E-02 1.86E-10 2.00E-05 9.32E-04 Nb-95 1.55 E-01 1.93E-09 3.00E-05 6.42E-03 Ru-103 2.21 E-03 2.75E-I l 3.00E-05 9.15E-05 Ag-110M 1.08E-03 1.34E-11 6.00E-06 2.23E-04 Sn-113 2.16E-03 2.68E-11 3.00E-05 8.94E-05 Sn-117M 6.07E-04 7.54E-12 3.00E-05 2.51 E-05 Sb-124 4.19E-03 5.20E-11 7.00E-06 7.44E-04 Sb-125 1.29E-01 1.60E-09 3.00E-05 5.34E-03 l-131 2.67E-03 3.32E-11 1.00E-06 3.32E-03 Cs-134 9.96E-03 1.24 E-10 9.00E-07 1.37E-02 Cs-137 8.30E-03 1.03 E-10 1.00E-06 1.03 E-02 La-140 1.29E-03 1.60E-11 9.00E-06 1.78E-04 Ce-144 3.23E-03 4.01E-11 3.00E-06 1.34 E-03 i

lif-181 1.26E-04 1.57E-12 2.00E-05 7.83 E-06

)

Kr-85 3.10E-01 3.85E-09 2.00E-04 1.93E-03 Xe-131M 1.87E-01 2.32E-09 2.00E-04 1.16E-03 Xe-133 9.2 ] E+00 1.14E-07 2.00E-04 5.72E-02 Xe-133M 5.51 E-02 6.84E-10 2.00E-04 3.42E-04 l

Xe-135 3.01 E-03 3.74E-11 2.00E-04 1.87E-05 l

Tc-99m 5.58E-04 6.93 E-12 1.00E-03 6.93E-07 Ru-106 8.10E-04 1.01 E-I l 3.00E-06 3.35 E-04 Te-132 8.91 E-05 1.I1E-12 9.00E-06 1.23 E-05 l

l-132 1.28E-04 1.59E-12 1.00E-04 1.59E-06 Ba-140 5.18E-04 6.43E-12 8.00E-06 8.04E-05 Np-239 6.57E-04 8.16E-12 2.00E-05 4.08E-05 Na-24 1.30E-06 1.61 E-14 5.00E-05 3.23E-08 l

l

{

...- ~~ -.-.

Attachment to WO 97-0045 j

Page 22 of 36 1

i.

l l

SOLID WASTE SHIPMENTS A.

SOLID WASTE SillPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) i 1.

Type of waste Unit I-Year Est. Total Period Error %

)

i

a. Spent resins, filter sludges, m3' l.94E+01

)

evaporator bottoms, etc.

Ci 1.66E+03 2.50E+01 i

b. Dry compressible waste, m3*

3.10E+02 i

contaminated equip. etc.

Ci 4.69E-01 2.50E+01 l

]

c. Irradiated components, m3' O.00E+00 j

control rods, etc.

Ci 0.00E+00 0.00E+00

d. Other m3' O.00E+00 Ci 0.00E+00 0.00E+00 1
  • m3 = cubic meters 2.

Estimate of major nuclide composition (by type of waste).

a.

Spent resin, filter sludges, evaporator bottoms, etc.

Waste Nuclide Percent Class Name Abundance Curies All Fe-55 52.619 %

8.73E+02 Ni-63 16.414 %

2.72E+02 Co-60 13.293 %

2.20E+02 Cs-137 8.I15 %

1.35E+02 C 14 0.383 %

6.35E+00 Sr-90 0.113 %

1.87E+00 Pu-241 0.010 %

1.68E-01 H3 0.002 %

3.34E-02 Cm-242 0.000 %

2.01 E-03 1-129 0.000 %

0.00E+00 Tc-99 0.000 %

0.00E+00 Nb-94 0.000 %

0.00E+00 Ni-59 0.000 %

0.00E+00

Attachment to WO 97-0045 Page 23 of 36 b.

Dry compressible waste, contaminated equipment, etc.

j Waste Nuclide Percent Class Name Abundance Curies All Co-58 44.193 %

2.07E-01 Ni-63 16.831 %

7.89E-02 Cs-134 11.813 %

5.53E-02 Cs-137 8.187 %

3.84E-02 Co-60 6.865 %

3.22E-02 11-3 0.395 %

1.85E-03 C-14 0.130 %

6.1IE-04 Sr-90 0.037 %

1.74E-04 j

Pu-241 0.020 %

9.58E-05 Cm-242 0.000 %

1.81 E-06 1129 0.000 %

0.00E+00 Tc-99 0.000 %

0.00E+00 Nb-94 0.000 %

0.00E+00 Ni-59 0.000 %

0.00E+00 c.

Irradiated components, control rods, etc.

None d.

Other j

none 3.

Solid Waste Disposition Number of Shipments Mode of Transportation Destination j

6 Truck Barnwell, SC j

5 Truck SEG/Barnwell,SC 4.

Class of Solid Waste i

a.

Class A, Class B, Class C-Corresponding to 2a b.

Class A - corresponding to 2b c.

Not applicable d.

Not applicable 5.

Type of container a.

LSA (Strong, tight), Type A, Type B - corresponding to 2a b.

1.. A (Strong, tight)- corresponding to 2b c.
b. t applicable d.

Not applicable 6.

Solidification Agent a.

Not applicable b.

Not applicable c.

Not applicable d.

Not applicable

Attachment to WO 97 0045 Page 24 of 36 B.

IRRADIATED FUEL SillPMENTS (Disposition)

There were no irradiated fuel shipments during this period.

i l

i i

I i

i i

l i

i J

I..

Attachment to WO 97-0045 Page 25 of 36 S:ction III Meteorological Data l

llOURS AT EACil WIND SPEED AND DIRECTION All gaseous releases at the WCGS are ground level releases. The meteorological data supplied in these tables covers the period from January 1,1996 through December 31,1996 and indicates the number of j

hours at each wind speed and direction for each stability class.

Attachment to WO 97-0045 i

Page 26 of 36 9

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

January 1 through December 31,1996 STABILITY CLASS:

A ELEVATION 10 Meters Wind Direction 1 to 3 4 to 7 8 to 12 13 to 18 19 to 24

>24 TOTAL N

O 3

6 1

1 0

11 NNE 1

3 3

1 0

0 8

NE O

1 1

0 0

0 2

ENE O

4 1

2 0

0 7

E O

1 3

3 0

0 7

ESE O

2 1

0 0

0 3

SE O

2 2

1 0

0 5

SSE O

O 5

5 1

0 11 S

0 1

2 9

2 0

14 SSVV 1

1 2

4 1

0 9

SW 0

3 2

0 0

0 5

WSW 0

0 1

0 0

0 1

W 0

2 8

0 0

0 10 WNW 0

1 3

1 0

2 7

NW 0

2 5

0 5

1 13 NNW 1

2 7

3 1

0 14 VARIABLE TOTAL 3

28 52 30 11 3

127 Period of calm (hours):

2

Attachment to WO 97-0045 Page 27 of 36 l

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

January 1 through December 31,1996 l

STABILITY CLASS:

B ELEVATION 10 Meters Wind j

Direction 1 to 3 4 to 7 8 to 12 13 to 18 19 to 24

>24 TOTAL N

0 3

11 5

1 0

20 1

NNE O

7 4

4 0

0 15 NE 1

6 7

0 0

0 14 ENE O

4 7

0 0

0 11 E

0 2

7 2

0 0

11 ESE O

1 6

2 0

0 9

SE O

4 6

3 0

0 13 SSS 1

5 6

1 0

0 13 S

0 11 17 18 3

0 49 SSW 0

5 6

12 8

0 31 SW 1

5 1

1 0

0 8

WSW 2

1 1

0 0

1 5

W 0

6 7

3 0

0 16 WNW 1

7 5

8 2

7 30 NW 1

4 11 11 13 13 53 NNW 0

3 9

10 5

2 29 VARIABLE TOTAL 7

74 111 80 32 23 327 Period of calm (hours):

1

Attachment to WO 97-0045 Page 24 of 36 l

\\

HOURS AT EACH WIND SPEED AND DIRECTION l

PERIOD OF RECORD:

January 1 through December 31,1996 STABILITY CLASS:

C l

ELEVATION 10 Meters 1

Wind Direction 1 to 3 4 to 7 8 to 12 13 to 18 19 to 24

>24 TOTAL l

N 0

6 4

22 1

0 33 i

l NNE 2

7 7

0 2

0 18 j

NE 0

13 1

0 0

0 14 ENE O

3 5

2 0

0 10 E

O 6

10 2

0 0

18 ESE O

3 6

4 0

0 13 SE O

3 3

6 0

0 12 SSE 1

16 12 6

0 0

35 S

0 6

16 17 3

0 42 SSW 1

7 7

9 1

4 29 SVV 3

3 3

2 0

0 11 WSW 0

5 1

0 0

0 6

W 0

8 1

1 0

3 13 WNW 1

15 0

7 4

1 28 NW 2

3 8

33 10 14 70 NNW 0

1 2

11 4

4 22 VARIABLE TOTAL 10 105 86 122 25 26 374 Period of calm (hours):

5 j

Attachment to WO 97-0045 Page 29 of 36 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

January 1 through December 31,1996 STABILITY CLASS:

D ELEVATION 10 Meters Wind Direction 1 to 3 4 to 7 8 to 12 13 to 18 19 to 24

>24 TOTAL N

1 39 84 129 25 0

278 j

NNE 5

26 79 55 0

0 165 NE 3

53 33 1

0 0

90 ENE 5

70 57 11 1

0 144 E

1 43 82 16 2

1 145 1

ESE 0

32 78 13 1

0 124 SE 1

28 38 34 1

0 102 SSE 4

44 84 70 18 4

224 S

5 36 75 143 47 14 320 SSW 0

24 43 42 20 10 139 SVV 2

11 12 5

3 0

33 WSW 7

18 17 3

4 0

49 VV 4

14 19 9

4 2

52 WNW 5

13 42 53 11 2

126 NVV 4

16 63 88 29 1

201 NNW 3

26 70 124 34 3

260 VARIABLE TOTAL 50 493 876 796 200 37 2452 Period of calm (hours):

23

Attachment to WO 97-0045 Page 30 of 36 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

January 1 through December 31,1996 STABILITY CLASS:

E 3

i ELEVATION 10 Meters i

Wind Direction 1 to 3 4 to 7 8 to 12 13 to 18 19 to 24

>24 TOTAL N

5 34 69 37 8

1 154 NNE 10 48 52 13 3

0 126 NE 13 48 17 3

1 0

82 ENE 12 60 31 12 2

0 117 l

E 2

56 45 4

2 0

109 ESE 3

71 72 8

0 0

154 SE 7

78 69 15 2

0 171 SSE 10 60 143 108 48 17 386 S

7 65 144 214 98 13 541 SSVV 8

50 57 34 15 2

166 SVV 7

50 24 7

0 1

89 WSW 5

31 16 6

1 1

60 VV 9

42 35 17 3

2 108 WNW 3

28 42 8

5 3

89 NVV 8

37 44 27 24 0

140 NNW 9

33 66 26 21 0

155 VARIABLE TOTA 1 118 791 926 539 233 40 2647 Period of calm (hours):

17

...__.____.=_.____-.__._._m l

Attachm:nt to WO 97-0045 Page 31 of 36 l

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

January 1 through December 31,1996 l

STABILITY CLASS:

F ELEVATION 10 Meters Wind j

Direction 1 to 3 4 to 7 8 to 12 13 to 18 19 to 24

>24 TOTAL N

3 27 10 1

0 0

41 i

NNE 10 44 7

0 0

0 61

)

NE 29 24 0

1 0

0 54 ENE 14 49

'l 1

0 0

67 E

8 64 14 1

0 0

87 ESE 5

74 19 0

0 0

98 SE 5

63 14 0

0 0

82 SSE 3

44 48 20 11 2

128 1

S 5

16 33 36 17 2

109 SSVV 6

15 5

3 1

0 30 SW 6

20 2

1 0

0 29 WSW 2

16 1

0 0

0 19 W

4 3

0 0

0 0

7 WNW 7

5 1

1 1

0 15 NW 6

27 11 1

0 0

45 NNW 6

31 11 0

0 0

48 VARIABLE TOTAL 119 522 179 66 30 4

920 Period of calm (hours):

25

.______..m_

l Attachment to WO 97-0045 Page 32 of 36 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

January 1 through December 31,1996 STABILITY CLASS:

G ELEVATION 10 Meters i

Wind Direction 1 to 3 4 to 7 8 to 12 13 to 18 19 to 24

>24 TOTAL i

N 7

25 1

1 0

0 34 NNE 1

44 1

4 1

0 51 NE 17 22 0

1 0

0 40 l

ENE 5

52 8

0 0

0 65

}

E 9

62 6

0 0

0 77 ESE 4

46 0

0 0

0 50 l

l SE O

18 2

0 0

0 20 i

SSE 2

13 10 0

0 0

25 S

3 9

11 3

0 0

26 SSW 2

9 1

0 0

0 12 j

SW 2

4 0

0 0

0 6

I WSW 1

2 1

1 0

0 5

I W

3 1

0 0

0 0

4 i

WNW 1

1 0

0 0

0 2

1 NW 2

4 0

0 0

0 6

i j

NNW 3

19 3

0 0

0 25 VARIABLE l

TOTAL 62 331 44 10 1

0 448 i

Period of calm (hours):

16 1

i i

_ - -. =

Attachment to WO 97 0045 Page 33 of 36 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

January 1 through December 31,1996 STABILITY CLASS:

ALL ELEVATION 10 Meters 4

Wind Direction 1 to 3 4 to 7 8 to 12 13 to 18 19 to 24

>24 TOTAL N

16 137 185 196 36 1

571 NNE 29 179 153 77 6

0 444 NE 63 167 59 6

1 0

296 ENE 36 242 112 28 3

0 421 E

20 234 167 28 4

1 454 ESE 12 229 182 27 1

0 451 SE 13 196 134 59 3

0 405 SSE 21 182 308 210 78 23 822 S

20 144 298 440 170 29 1101 SSW 18 111 121 104 46 16 416 SVV 21 96 44 16 3

1 181 WSW 17 73 38 10 5

2 145 VV 20 76 70 30 7

7 210 WNW 18 70 93 78 23 15 297 4

NW 23 93 142 160 81 29 528 NNW 22 115 168 174 65 9

553 VARIABLE TOTAL 369 2344 2274 1643 532 133 7295 Period of calm (hours):

89 Hours of Missing Data :

1400

Attachment to WO 97-0045 Page 34 of 36 l

In order to calculate the above data, input is used from three different instruments, wind speed, wind direction and vertical temperature difference, for each hourly average. Input from all three instruments must be of good quality or the hour will be classined as missing. The instrument data cannot be considered good if any one of the three instrument is marked out of service in the Equipment Out of Service Log, or if the computer L.!own or does not read a valid input. Thus, the hours of missing data value in the above table is a sum total of all the hours in which the input of at least one of the three instruments is considered unavailable. Ilowever, each instrument, by itself, was available at least 90 percent of the time as required by Regulatory Guide 1.21.

Changes to llistorical Meteorological Data Clarification Concerns l

The 1995 meteorological data, as transmitted last year, contained several data conversions that were inconsistent with true data. The "A" ttability class was the most noticeable, with an inordinate amount of values classified as Class "A" that were in effect, not class "A" The data transmitted as 1995 data has been revised to correct the problem. (See Attachment 1)

Verification and Validation Process Concerns in 1990, the Plant Modification Request (PMR 1479) revised one of our computer systems, from the Radiological Release Information System (RRIS) to the Nuclear Plant Information System (NPIS). The RRIS contained a computer program that was used for meteorological data verification and validation based on Safety Regulatory Gui& l.23 Revision 1. This verification and validation program, that was formerly in the RRIS system, was not subsequently included in the NPIS system. During the last NRC inspection on the Meteorological System, there was a concern about the way data was being verified. To track this concern, PIR 96-1897 was generated. While evaluating this Performance Improvement Request,

)

Engineering became aware of the fact that the computer program for data verification and validation was dropped from the NPIS. Engineering has reviewed the Updated Safety Analysis Report Table 2.3-29b,

" Data Recovery Statistics" for March 1980 to March 1981, and Semi and Annual Radioactive Release Reports from July 1985 to December 1990 to assure that the data recovery percentage is greater than 90 percent. Also, the 1995 and 1996 Equipment Out of Service Logs, the Surveillance Technical Specifications, and computer down time was used to generate the data being presented with this report.

Based upon this review, WCGS determined that the 90 percent availability requirement for the j

Meteorological Program has been met.

WCGS is in the process of investigation and corrective action for this concern, including corrective action to ensure that the program for data verification and validation is being used. The program that will be in

)

place, will include a computer program for the verification and validation process. It will be available before the next report is generated. The next report will have the 1997 data, as well as data from 1990 to 1996. The 1995 and 1996 data will be included since, in all probability, the data will be different based upon the way the new program is generated.

Attachment to WO 97-0045 Page 35 of 36 Section IV Additional information 1.

Unplanned or Abnormal Releases There were no abnormal releases during this reporting period.

2.

Offsite Dose Calculation Manual (ODCM)

The ODCM was revised, converted to a new format, approved, and issued on February 12,1996.

The new procedure, AP 07B-003, Revision 0, "Offsite Dose Calculati a Manual," is included with this report as " Attachment 2".

During a final review of Surveillance Test Specification CH-014 for the Low, Mid and High Range detector calibration, an error was found on the last transfer source calibration on the Low range detector. A primary calibration for gaseous detectors is performed using XE-133 gas.

Transfer source activities determined during this calibration are then used on future 18 month calibrations as required by the ODCM. The procedure states that the most recent primary calibration is to be used to determine which transfer sources are required for the current calibration. The transfer source calibration performed in 1995 appears to have been performed using the primary calibration transfer sources from 1989 instead of 1991. The transfer source calibration performed in 1996 used the correct primary calibration, which was performed in 1991.

The error was on the conservative side and there was no operability or reportability concern.

Performance improvement Request 96-2315 was generated to track resolution.

i 3.

Major Changes to Radwaste Processing Systems There were no major changes made to the Radioactive Waste Processing Systems in 1996 that were not previously reported in the 1995 or earlier Annual Radiological Effluent Reports.

4 Land Use Census There were no new locations for dose calculation identified during this report period.

5.

Radioactive Shipments There were eleven shipments of radioactive waste during this report period. The shipments went by truck to Barnwell, South Carolina.

6.

Inoperability of Effluent Monitoring Instrumer.tation There were no events that involved inoperable liquid or gaseous effluent monitoring instrumentation not being corrected within the time specified in former Technical Specification 3.3.3.11. (Note: Former Technical Specification 3.3.3.11 " Explosive Gas Monitoring System" was relocated to the Wolf Creek Generating Station Updated Safety Analysis Report (USAR) on October 2,1995. Technical Specification requirements for the program are now covered by Section 6.8.5.a," Explosive Gas and Storage Tank Radioactivity Monitoring Program.")

w.

o

Attachment to WO 97-0045 Page 36 of 36 7.

Storage Tanks There were no events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specification 3.11.1.4 or 3.11.2.6. (Note: Technical Specification 3.11.1.4, " Liquid Effluents--Liquid IIoldup Tanks", and Technical Specification 3.11.2.6, " Gas Storage Tanks",

were relocated to the Wolf Creek Generating Station USAR on October 2,1995. Technical Specification requirements for the program are now covered by Section 6.8.5.a," Explosive Gas and Storage Tank Radioactivity Monitoring Program.")

l l

l I

i h

1 i

1 ATTACilMENT I I

I 1

I 1

i i

i i

1

J b

HOURS AT EACH WIND SPEED AND DIRECTION i

PERIOD OF RECORD:

January 1 through December 31,1995 STABILITY CLASS:

A ELEVATION 10 Meters 1

Wind l

Direction 1 to 3 4 to 7 8 to 12 13 to 18 19 to 24

>24 TOTAL l

N O

O 3

6 1

0 10 l

NNE 0

1 4

0 0

0 5

NE 1

4 0

0 0

0 5

1 ENE O

4 1

0 0

0 5

i E

O 3

1 2

0 0

6 l

i ESE 0

0 4

0 0

0 4

SE O

1 3

3 1

0 8

SSE O

5 15 6

2 1

29 S

0 5

15 12 7

0 39 SSW 0

3 8

4 2

0 17 SW 0

2 2

1 0

0 5

WSW 0

6 0

1 2

0 9

i W

0 2

1 0

2 0

5 l

WNW 0

6 4

2 5

1 18 NW 0

5 3

10 4

0 22 i

NNW 0

1 4

4 1

0 10 l

VARIABLE j

TOTAL 1

48 68 51 27 2

197 i

i Period of calm (hours):

1 1

4 e

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

January 1 through December 31,1995 STABILITY CLASS:

B ELEVATION 10 Meters Wind Direction 1 to 3 4 to 7 8 to 12 13 to 18 19 to 24

>24 TOTAL N

0 4

13 16 4

0 37-NNE O

2 13 2

0 0

17 NE O

12 1

0 0

0 13 ENE O

9 5

0 0

0 14 E

O 8

9 1

0 0

18 ESE 1

2 3

1 0

0 7

SE 2

7 6

5 0

0 20 SSE O

11 39 13 5

2 70 S

0 8

31 34 9

0 82 SSVV O

10 18 19 1

0 48 SW 1

2 4

3 0

1 11 WSW 1

8 3

2 2

4 20 l

W 1

10 6

6 4

6 33 l

WNW 0

11 5

6 6

4 32 i

NW 1

9 21 11 10 1

53 NNW 0

7 21 18 10 1

57 VARIABLE TOTAL 7

120 198 137 51 19 532 Period of calm (hours):

0

4 i

HOURS AT EACH WIND SPEED AND DIRECTION l

PERIOD OF RECORD:

January 1 through December 31,1995 STABILITY CLASS:

C 4

i ELEVATION 10 Meters Wind 4-Direction 1 to 3 4 to 7 8 to 12 13 to 18 19 to 24

>24 TOTAL N

0 2

25 12 3

1 43 i

NNE O

6 16 1

0 0

23 i

j NE 2

16 5

0 0

0 23 j

ENE 1

5 4

4 0

0 14 j

E O

11 6

4 0

0 21 1

ESE O

1 7

1 0

0 9

SE O

11 11 2

1 0

25 i

l SSE 0

14 33 16 7

0 70 i

i S

0 13 24 28 13 2

80

]

SSW 0

5 13 18 6

0 42 l

SW 0

2 5

1 0

1 9

WSW 1

1 5

7 1

1 16 j

W 2

10 8

7 3

4 34

)

WNW 0

10 7

3 7

1 28 4

NVV 0

9 19 14 5

1 48 1

j NNW 2

11 21 12 4

0 50 VARIABLE i

j TOTAL 8

127 209 130 50 11 535 1

1' s

j Period of calm (hours):

0 i

1 4

HOURS AT EACH WIND SPEED AND DIRECTION l

PERIOD OF RECORD:

January 1 through December 31,1995 STABILITY CLASS:

D ELEVATION 10 Meters i

j Wind j

Direction 1 to 3 4 to 7 8 to 12 13 to 18 19 to 24

>24 TOTAL N

4 51 103 87 29 2

276 2

NNE 13 45 69 46 3

0 176 i

NE 5

40 26 6

0 0

77 i

ENE 7

36 39 12 1

0 95 E

6 34 58 19 0

0 117 ESE 5

32 53 25 2

0 117 2

1 SE 5

34 54 29 4

0 126 l

SSE 1

39 78 82 16 2

218 l

S 5

37 135 110 28 8

323 i

SSW 2

34 56 60 20 1

173 i

)

SW 5

27 19 17 2

2 72

)

l WSW 5

10 23 19 16 3

76 VV 6

28 30 25 27 10 126 4

i WNW 5

16 61 62 24 3

171 I

NW 5

31 117 75 19 5

252 i

NNW 6

63 117 81 24 1

292 l

l VARIABLE I

TOTAL 85 557 1038 755 215 37 2687

)

I Period of calm (hours):

11 i

i i

l

}

i

l HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

January 1 through December 31,1995 STABILITY CLASS:

E ELEVATION 10 Meters Wind Direction 1 to 3 4 to 7 8 to 12 13 to 18 19 to 24

>24 TOTAL i

N 11 60 58 76 15 0

220 NNE 13 44 50 20 1

0 128 NE 15 56 12 1

0 0

84 i

ENE 9

45 30 2

0 0

86 1

l l

E 2

46 43 6

0 0

97

}

ESE 5

60 45 1

0 0

111 I

l SE 4

87 82 28 5

0 206 1

SSE 7

82 239 176 42 6

552 I

S 3

52 268 164 33 12 532 l

SSW 5

52 55 59 12 4

187 SW 5

56 14 7

4 0

86 WSW 4

26 22 8

0 0

60 W

5 33 41 9

3 0

91 WNW 1

40 49 10 4

1 105 NW 6

80 40 25 9

2 162 NNVV 7

54 61 47 33 4

206 VARIABLE TOTAL 102 873 1109 639 161 29 2913 Period of calm (hours):

11

1 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

January 1 through December 31,1995 STABILITY CLASS:

F ELEVATION 10 Meters Wind Direction 1 to 3 4 to 7 8 to 12 13 to 18 19 to 24

>24 TOTAL N

2 31 27 5

0 0

65 NNE 11 44 27 0

0 0

82 NE 16 36 0

0 0

0 52 l

ENE 8

64 8

0 0

0 80 E

4 57 21 0

1 0

83 ESE 6

112 5

0 0

0 123 SE 3

107 30 2

0 0

142 SSE 4

55 70 8

0 0

137 S

0 14 33 13 0

0 60 i

SSVV 6

8 4

0 0

0 18 j

SW 1

22 8

0 0

0 31 i

V!5W 8

12 4

0 0

0 24 W

3 5

2 0

0 0

10 WNW 2

10 2

1 0

0 15 NVV 2

36 16 10 0

0 64 NNW 10 50 31 0

0 0

91 VARIABLE TOTAL 86 663 288 39 1

0 1077 Period of calm (hours):

4 L

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

January 1 through Decembo ' 31,1995

)

STABILITY CLASS:

G ELEVATION 10 Meters Wind Direction 1 to 3 4 to 7 8 to 12 13 to 18 19 to 24

>24 TOTAL N

4 21 6

0 0

0 31 i

NNE 5

56 9

0 0

0 70 i

NE 25 26 0

0 0

0 51 ENE 8

41 3

1 0

0 53 E

6 63 3

1 0

0 73 ESE 3

81 3

0 0

0 87 SE 5

36 6

0 0

0 47 SSE 1

9 4

1 0

0 15 S

1 4

0 0

0 0

5 SSW 3

2 1

0 0

0 6

SW 0

2 0

0 0

0 2

WSW 3

2 0

0 0

0 5

W 2

0 0

0 0

0 2

WNW 1

4 3

4 0

0 12 j

NW 4

13 2

0 0

0 19

]

NNW 6

30 9

3 0

0 48 VARIABLE TOTAL 77 390 49 10 0

0 526 Period of calm (hours):

1

HOURS AT EACH WIND SPEED AND DIRECTION I

PERIOD OF RECORD:

January 1 through December 31,1995 STABILITY '.? LASS:

ALL ELEVATION 10 Meters i

N Wind i

Direction 1 to 3 4 to 7 8 to 12 13 to 18 19 to 24

>24 TOTAL N

21 169 235 202 52 3

682 NNE 42 198 188 69 4

0 501 NE 64 190 44 7

0 0

305 ENE 33 204 90 19 1

0 347 E

18 222 141 33 1

0 415 l

ESE 20 288 120 28 2

0 458 i

SE 19 283 192 69 11 0

574 SSE 13 215 478 302 72 11

~1091 S

9 133 506 361 90 22 1121 SSW 16 114 155 160 41 5

491

]

SW 12 113 52 29 6

4 216 WSW 22 65 57 37 21 8

210 W

19 88 88 47 39 20 301 WNW 9

97 131 88 46 10 381 4

l NW 18 183 218 145 47 9

6.20 l

NNVV 31 216 264 165 72 6

754 VARIABLE TOTAL 366 2778 2959 1761 505 98 8467 Period of calm (hours):

28 Hours of Missing Data :

265

-_.+.a a

4-_

a a

J

_+--...- -

4

-4

%.s

,d.d a

  1. a..

A.

4 Je

,.-%.ma..e

.,, a.s

.a ATTACilMENT 2 f

i t

i 4

i a

d a

4 4

)

k a

i a

i a

l 4

i a

4 1

e 1

9 i

6 I

1 i

4 e

4 A

1 I

1m I

i 4

Retrieved from "https://kanterella.com/w/index.php?title=ML20138F331&oldid=4201226"