ML20148A726
| ML20148A726 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 12/31/1987 |
| From: | UNION ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19302D320 | List: |
| References | |
| NUDOCS 8803210119 | |
| Download: ML20148A726 (190) | |
Text
.
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT s
)
CALLAWAY NUCLEAR PLANT UNION ELECTRIC COMPANY LICENSE NPF - 30 JULY - DECEMBER 1987 8803210119 880229 PDR ADOCK 05000483 R_,__
TABLE OF CONTENTS
1.0 INTRODUCTION
2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 2.2 Maximum Permissible Concentrations 2.3 Average Energy 2.4 Measurements and Approximations of Total Radioactivity 2.5 Batch Releases 2.6 Abnormal Releases 3.0
SUMMARY
OF GASEOUS RADIOACTIVE EFFLUENTS 4.0
SUMMARY
OF LIQUID RADIOACTIVE EFFLUENTS 5.0 SOLID WASTE 6.0 RELATED INFORMATION 6.1 Unplanned Releases 6.2 Changes to the Process Control Program 6.3 Changes to the Offsite Dose Calculation Manual 6.4 Major Changes to Radwaste Treatment Systems 6.5 Land Use Census Changes 6.6 Inoperability of Effluent Monitoring Instrucentation 7.0 METEOROLOGICAL DATA
8.0 ASSESSMENT
OF DOSES 8.1 Dose at the SITE BOUNDARY and Nearest Residence From Gaseous Effluents 8.2 Dose to the MEMBER OF THE PUBLIC from Activities Within the SITE BOUNDARY 8.3 Total Dose Due to the Uranium Fuel Cycle 8.4 Dose Due to Liquid Effluents
T Table lA Semiannual Sumnation of Gaseous Releases Table IB Semiannual Airborne Continuous and-Batch Releases Table 2A Semiannual Summation of Liquid Releases Table 2B Semiannual Liquid Continuous and Batch Releases Table 3 Solid Waste and Irradiated Fuel Shipments Table 4 Meteorlogical Data: Quarterly Totals of Hours at Each Wind Speed and Direction Table 5 Dose at the SITE BOUNDARY and Nearest Residence from Gaseous Effluents Table 6 Dose to the MEMBER OF THE PUBLIC from Activities within the SITE BOUNDARY Table 7 Total Dose Due to the Uranium Fuel Cycle Table 8 Dose Due tc Liquid Effluents Changes to the Process Control Program Changes to the Offsite Dose Calculation Manual l
l l
1.0 INTRODUCTION
This Semiannual Radioactive Effluent Release Report is for Union Electric Company's Callaway Plant and is submitted in accordance with the requirements of Technical Specification 6.9.1.7.
The report covers the period from July 1,
1987 through December 31, 1987.
This report includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant.
The information is presented in accordance with the format outlined in Appendix B of Regulatory Guide 1.21, Revision 1. June 1974.
All liquid and gaseous effluents discharged during this reporting period were in compliance with the limits of the Callaway Plant Technical Specifications.
1 L
r 2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits Specified as follows are the technical specification limits applicable to the release of radioactive material in liquid and gaseous effluents.
2.1.1 Fission and Activation Gases (Noble Gases)
The dose rate due to radioactive noble gases released,in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin.
The air dose due to noble gases released in gaseous effluents, from each crit. to areas at and beyond the site boundary shall be limited to the following:
a.
During any calendar quarter:
Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, b.
During any calendar year:
Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 :crad for beta radiation.
2.1.2 Radiciodine, Tritium, and Particulates The dose rate due to Iodine 131 and
- 133, tritium and all radionuclides in particulate form with half lives greater than eight (8) days released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 1500 mrem /yr to any organ.
The dose to a member of the public from Iodine 131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than eight (8) days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:
a.
During any calendar quarter: Less than or equal to 7.5 mrem to any organ and, b.
During any calendar year: Less than or equal to 15 mrem to any organ.
2
2.1.3 Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 microcuries/mi total activity.
The dose or dose commitment to an Individual from radioactive materials in liquid effluents released to unrestricted areas shall be limited:
a.
During any calendar quarter to less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ, and b.
During any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ, 2.1.4 Uranium Fuel Cycle Sources The annual (calendar year) dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.
2.2 Maximum Permissible Concentrations 2.2.1 The maximum permissible concentration values specified in 10CFR20, Appendix B, Table II, Column 2 are used to calculate release rates and permissible concentrations of liquid radioactive effluents at the unrestricted area boundary. A value of 2.0E-4 microcuries/ml is used as the MPC for dissolved and entrained noble gases in liquid effluents.
2.2.2 For gaseous effluents, maximum permissible concentrations are not directly used in release rate calculations since the applicable limits are stated in terms of dose rate at the unrestricted area boundary.
l 2.3 Average Energy This is not applicable to the Callaway Plant's radiological effluent technical specifications.
I 2.4 Measurements and Approximations of Total Radioactivity The quantification of radioactivity in liquid and gaseous effluents was accomplished by performing the sampling and radiological analysis of effluents in accordance with the requirements of Table 4.11-1 and Table 4.11-2 of the Callaway Plant Technical Specifications (See NUREG-1058, "Technical Specifications, Callaway Plant, Unit No.
1" (October, 1984)).
l 3
i
Gamma spectroscopy was the primary analysis technique used to determine the radionuclide composition and concentration of liquid and gaseous effluents.
Composite samples were analyzed for Sr-89, Sr-90, and Fe-55 by an independent laboratory.
Tritium and alpha were measured for both liquid and gaseous effluents using liquid scintillation counting and gas flow proportional counting techniques, respectively.
The total radioactivity in effluent releases was determined from the measured concentrations of each radionuclide present and the total volume of effluents discharged.
Gross beta or gamma radioactivity measurement techniques were not utilized to approximate the total radioactivity in effluents.
2.5 Batch Releases 2.5.1 Liquid Number of batch releases:
124 Total time period for batch releases:
3.774E4 minutes Maximum time period for a batch release:
1151 minutes Average time period for batch releases:
304 minutes Minimum time period for a batch release:
15 minutes Average stream flow during periods of release of effluent into a flowing stream:
76,957 cfs*
- Letter, L. A. Waite (US Geological Survey) to C. C. Graham (Union Electric Co.) dated 1-4-88.
2.5.2 Gaseous Total for the Non-Outage Reporting Period Related Number of batch releases 65 55 Total time period for batch releases 67,220 minutes 11,104 minutes Maximum time period for a batch release 24,836 minutes 791 minutes Average time period of batch releases 1,034 minutes 202 minutes Minimum time period for a batch release 9 minutes 60 minutes 2.6 Abnormal Releases 2.6.1 Liquid Number of releases: 0 Total Activity released:
0 4
{
L 2.6.2-Gaseous Number of releases:
1 Total Activity released: 1.54 E-4 Ci 3.0
SUMMARY
OF GASEOUS RADIOACTIVE EFFLUENTS 3.1-
.The quantities of radioactive material released in gaseous effluents are summarized in Table 1A and IB.
Note _that for this reporting period no gaseous effluents were considered as elevated _ releases.
4.0
SUMMARY
OF LIQUID RADIOACTIVE EFFLUENTS i~
4.1 The quantities of radioactive material released in liquid effluents are summarized in Table 2A and 2B.
5.0 SOLID WASTE 5.1 The quantities of radioactive material released in shipments of solid waste and irradiated fuel transported from the site during the reporting period are summarized in Table 3.
The activity and fractional abundance of each nuclide was determined-for each waste type by an independent laboratory based upon radiochemical analysis of samples of that waste type.
The curie amount of each nuclide listed in Table 3 was determined as the product of the fractional abundance and the total curies shipped.
Those' nuclides which comprise at least 1% of the total' activity for a particular waste type are presented in Table 3.
Additionally, as noted in the "Solid Waste Disposition" section of Table 3, nine total shipments were released with eventual disposal at the Beatty, NV disposal facility.
Two of these shipments are listed separately due to their being consigned initially to a vaste processor for supercompaction prior to disposal.
A third shipment was also released to the waste processor during the reporting period.
None of the vaste from this third shipment was disposed of in a burial facility during this period. This volume will be accounted for during the next reporting period.
6.0 RELATED INFORMATION 6.1 Unplanned Releases Unplanned releases are inadvertant or unanticipated releases of radioactive material, or releases of radioactive material via normal pathways without a release permit or proper authorization, or without proper sampling and
- analysis, or releases which are conducted in such a manner as to result in significant deviation from the requirements of the release permit.
There was one unplanned release during the reporting period.
5
On 9-22-87, I-131 activity was identified in an Auxiliary Boiler sample at a concentration of 3.8E-7 pCi/ml. Administrative controls had previously been placed on this system to ensure that boiler blowdown and drains would be routed to liquid radwaste if contaminated.
These controls were verified and operation of the Auxiliary Boiler was continued.
On 10-14-87 it was discovered that the Auxiliary Boiler was being continuously vented to atmosphere to prevent tripping the boiler on low load.
The boiler had been operated in this mode for approximately 21 days.
Operation of the boiler was immediately secured and samples were taken for analysis.
The concentration of I-131 was found to be 3.6E-7 p Ci/ml.
The boiler was drained to liquid radwaste, filled, and resampled to ensure that no activity was present.
On 10-17-87 the Auxiliary Boiler was started up and at 0937 activity was again detected at a concentration of lE-7 pCi/ml I-131.
Boiler operation was continued but without venting steam to atmosphere.
The activity was determined to be coming from the Secondary Liquid Waste Evaporator Vent Gas Cooler drains and the steam trap, Secondary Liquid Waste Evaporator density cell wash. Recycle of Radwaste Building steam loads to the Aux Boiler was secured and redirected to Radwaste systems for processing / discharge.
Identified corrective actions are: 1) Until the source of the contamination can be corrected, the Auxiliary Boiler will be sampled daily when operating; 2) If activity is present in the Auxiliary Boiler, it will be operated without blowdown or venting of steam; 3)
The possibility of a leak in the Secondary Liquid Waste Evaporator has been investigated and a design change has been initiated to redirect the two identified sources of contamination to contaminated radwaste drains, and, when repaired, will return to normal sytem lineup of the Auxiliary Steam System.
The dose at the SITE BOUNDARY was calculated to be 9.6E-5 mrem from the release of approximately 1.54E-4 Ci of I-131.
The calculated dose represents a small fraction (IE-3%) of the quarterly limit of Technical Specification 3.11.2.2.
This event did not adversely affect or endanger the health or safety of the public.
This event is documented by Incident Report 87-223, and a Safety Evaluation has been performed in accordance with 10CFR50.59.
6.2 Changes to the Process Control Program Revision 8 to the Callaway Process Control Program (PCP) was issued October 14, 1987.
This revision incorporated revised boundary conditions / ratios used in the development of batch solidification formulations, revised acceptance criteria for determining structural stability, and addition of full scale (55 gallon) test solidification.
Minor text revisions were required due to these changes. includes documentation of the fact that the change has been reviewed and found acceptable by the On-Site Review Committee (ORC).
6
6.3 Changes to the Offsite Dose Calculation Manual Revision 4 to the Callaway Plant's Of fsite Dose Calculation Manual (ODCM) was issued February 23, 1987, but was inadvertently not described in the previous Semiannual Radioactive Effluent Release Report, and is therefore being reported herein.
A complete copy of the ODCM (Rev. 4) is included with this report as Attachment 1.
There were no changes to the ODCM during the period July 1 -
December 31, 1987.
There were several minor clarifications which were incorporated into Rev. 4; however, these did not change the methodology, parameters, or intent, and are not further enumerated.
Pages 7 & 13: The definition of C and C were revised to delete the reference to a "monthly composide sample".
Although the minimum sampling frequency is defined by Technical Specification 3.11.1.1 as monthly..more frequent sampling may be performed.
Page 23: Added methodology for performing the 31-day dose projection required by Technical Specification 3.11.1.3.
This was not previously described in the ODCM, Page 24: Rev. 3 erroneously stated that radiation monitor setpoints were based on the "instantaneous concentration limits of 10CFR20, Appendix B, Table II, Column 1".
This has been revised to properly state that the setpoints are based on the instantaneous dose limits of Technical Specification 3.11.2.1.
It should be noted that there were no changes to the methodology or equations.
Page 65: Added methodology for performing the 31-day dose projection required by Technical Specification 3.11.2.4.
This was not previously described in the ODCM.
Pages 67,68,71,6 72: Revised the following to reflect current information regarding the use of areas within the SITE BOUNDARY: (1)
The description of the MEMBER OF THE PUBLIC; (2) The description of the utilization of areas within the SITE BOUNDARY; (3)
The description of the dose pathways for the MEMBER OF THE PUBLIC; (4)
Location for assessment of direct radiation dose from outdoor storage tanks and from the operation of the unit.
6.4 Major Changes to Radwaste Treatment Systems There were no major changes to Radwaste Treatment Systems during the reporting period.
7 t
6.5 Land Use Census Changes There were no changes in critical receptor locations for dosa calculations during the reporting period.
6.6 Inoperal;ility of Effluent Monitoring Instrumentation M.1 effluent monitoring instrumentation was OPERABLE within the Itmit2 specified by Specifications 3.3.3.9 and 3.3.3.10 during the reporting period.
7.0 METEOROLOGICAL DATA M;ceorological data for the year is presented in Table 4 as Cumulative Joint Frequency Distributions for both 10 and 60 meter elevations.
6.0 ASSESSMENT
OF DOSES The assessment of doses to the maximum exposed individual from Gaseofn and Liquid effluents was performed for locations repreneating the maximum dose.
In all cases, doses were well below Technit t Specification limits.
1.1 Lose, at the SITE BOUNDAR'.
and Nearest Residence From Gaseous gffluents Aa assessment of doses from gaseous effluents was performed in Jer.ordanc e witt. the Callaway Plant ODCM for the maximum exposed incividgl at the SITE BOUNDARY and Nearest Residence location with the birhest ground level concentration of radioactive material, b4 sed vpon actur:1 meteorological conditions existing during the ftxr.
Dosea were assessed at each location considering the noble rat skpesure i Whalation, ground plane, and ingestion pathways. The ingestion p t'r.m ys considered were the produce, vegetable, goat's milk, cow '3 m tlk, and meat pathways. This assessment was performed for each ige group, 5 Ich Ce Child age group receiving the highest dose.
Ike resu'ts of the asaessment for the Child age group are presented in Tabit 5.
It must se noted that the calculations for the SITE fiUlf.4RY location c onserva t'ively assume a hypothetical maximum eqcsed inaividual. vhile the eniculations for Nearest Residence are for a r%1 individual.
It is conservatively assumed that each ingestion pathway exists at the d*a boundary and the Nearest 9esidence locatMns..
8.2 Docg to the MEMBER OF THE P"P1 TC from Activities Within the SITE s
SOUh6ARY The t.s 4.s omen t oi
'( se to the 4EMlER 'sF THE a BLIC f rom ac tivities within the SILE BOUNDAhY wa: performed in accordance with Chapter 4 of the Calinway Plant ODCM.
The dase to tht MEMbuR '?F THE PUELIC from %tiv' ies within che SITE k UND'F.Y is presented in Table L n
..n
--..n.-
.o 8.3 Total Dose Due to the Uranium Fuel Cycle Since there are no other uranium fuel cycle facilities within 8 km of the Callaway Plant, the total dose to the most likely exposed MEMBER OF THE PUBLIC results f rom direct radiation and radioactive effluents from the Callaway Plant.
The methodology for assessing this dose is described in Chapter 4 of the Callaway Plant ODCM.
The Total Dose from the Uranium Fuel Cycle was evaluated for the MEMBER OF THE PUBLIC who may use portions of the area within the SITE BOUNDARY for purposes not associated with plant operations, and for the Nearest Resident, who is assumed to receive an insignificant dose from activities within the SITE B0UNDARY.
The Total Dose to the MEMBER OF THE PUBLIC is from the dose due to activities within the SITE BOUNDARY (Table 6) and the dose due to gaseous effluents at his residence. The food ingestion pathways ac not exist at the residence location.
The Total Dose at the Nearest Residence is due to the dose from gaseous effluents, assuming that each food ingestion pathway exists at this location (Table 5).
In each case, the whole body gamma dose from Noble Gases and ground plane exposure is added to the organ dose from the inhalation and ingestion pathways.
The Total Dose from the Uranium Fuel Cycle is presented in Table 7.
8.4 Dose Due to Liquid Effluents The total dose to the maximum exposed Individual from liquid effluents released from the Callaway Plant during the year is presented in Table C.
l l
TABLE 1A SEMIANNUAL SUMMATION OF GASEOUS RELEASES ALL AIRBORNE EFFLUENTS QUARTERS 3 AND 4, 1987
-=
UNIT QUARTER 3 QUARTER 4 EST TOTAL TYPE OF EFFLUENT ERROR %
===_______.._______.---__-- - - -
A.
FISSION AND ACTIVATION GASES
___.. _____ __..___ _________-____________===_
__=_________ __-____________--_..________...
1.
TOTAL RELEASE CURIES 9.35E2 1.14E2 20
==_______________________________-__________________________ ________________.
2e AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 1.18E2 1.43E1 3.
PERCENT OF TECH SPEC LIMIT 6.76E-3 8.24E-4 B.
RADIOI0 DINES 1.
TOTAL 10 DINE-131 CURIES 5.50E-5 6.36E-5 23 2.
AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 6.92E-3 8.00E-6 3.
PERCENT OF TECH SPEC LIMIT 6.59E-3 7.62E-6 C.
PARTICULATES l.
PARTICULATES (HALF-LIVES > 8 DAYS)
CURIES 1.54E-5 1.41E-6 30 2.
AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 1.94E-6 1.77E-7 3.
PERCENT OF TECH SPEC LIMIT 1.26E-7 1.15E-8 4.
GROSS ALPHA RADI0 ACTIVITY CURIES 2.45E-6 1.27E-6
- =_____________________________. _____________
D.
TRITIUM l.
TOTAL RELEASE CURIES 6.04E0 6.99E0 14 l
2.
AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 7.60E-1 8.79E-1 l
3.
PERCENT OF TECH SPEC LIMIT 5.00E-5 5.79E-5 1
i l
l l
l PAGE 1 of 1 I
TABLE IB SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES, 10 DINES, AND PARTICULATES QUARTERS 3 AND 4, 1987 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4
_ - - _ _. - _ - _ _. = = - - - - - - - - - -... _ _ _ _ _ _
- = = _ _ - _ _ _. - - - - - - _ - _ - - - _ _ - - -.. _ _.. - - __=-
1.
FISSION GASES
_=-_-____-_-___....--__-___ _-_____
Kr-85M CURIES 3.49E0 6.86E-2 1.41E-2 4.97E-5 Kr-85 CURIES 0
0 4.59E0 1.75El Kr-87 CURIES 4.76E-2 0
0 0
Kr-88 CURIES 3.65E0 0
0 0
Xe-131M CURIES 0
0 4.66E0 1.38El Xe-133M CURIES 3.11E0 0
2.38E0 3.43E-3 Xe-133 CURIES 4.12E2 3.00El 4.56E2 4.89El Xe-135M CURIES 3.70E-2 0
0 0
Xe-135 CURIES 4.35El 3.32E0 1.54E-1 1.73E-2 Xe-138 CURIES 0
0 0
0 Ar-41 CURIES 0
0 6.48E-1 5.80E-2 TOTAL FOR PERIOD CURIES 4.66E2 3.34El 4.68E2 8.03El 2.
10 DINES
=.____-_----___-_-_..__-__ -----
I-131 CURIES 1.96E-6 1.14E-5 5.30E-5 5.22E-5 I-133 CURIES 0
0 0
8.58E-10 1-135 CURIES 0
0 3.88E-7 0
TOTAL FOR PERIOD CURIES 1.96E-6 1.14E-5 5.34E-5 5.22E-5 3.
PARTICULATES H-3 CURIES 4.52E0 5.06E0 1.52E0 1.93E0 Co-58 CURIES 9.45E-6 1.44E-7 0
9.93E-10 Co-60 CURIES 8.47E-7 0
0 0
Rb-88 CURIES 7.94E-6 0
4.64E-4 1.96E-6 Sr-89 CURIES 0
0 0
0 Cs-134 CURIES 1.24E-6 0
0 0
Cs-137 CURIES 1.41E-6 0
0 0
Cs-138 CURIES 0
0 1.00E-4 0
Sr-90 CURIES 0
0 0
0 G ALPHA CURIES 6.19E-7 1.03E-6 1.83E-6 2.39E-7 TOTAL FOR PERIOD CURIES 4.52E0 5.06E0 1.52E0 1.93E0 PAGE 1 0F 1 l
l I
I l
TABLE 2A SEMIANNUAL SUMMATION OF LIQUID RELEASES ALL LIQUID EFFLUENTS QUARTERS 3 AND 4, 1987 UNIT QUARTER 3 QUARTER 4 EST TOTAL TYPE OF EFFLUENT ERROR %
... - = _ - -
A.
FISSION AND ACTIVATION PRODUCTS 1.
TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA)
CURIES 9.75E-2 3.61E-1 20
_ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - = = _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _. - - - = = = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _..... _ _ _ _ _ _ _ _ _ _ _ _
2.
AVERAGE DILUTED CONCENTRATION DURING PERIOD UCI/ML 1.50E-7 9.37E-7 3.
PERCENT OF APPLICABLE LIMIT 4.73 4.52 B.
TRITIUM 1.
TOTAL RELEASE CURIES 1.12E2 3.66El 14 2.
AVERAGE DILUTED CONCENTRATION DURING PERIOD UCI/ML 1.73E-4 9.66E-5 3.
PERCENT OF APPLICABLE LIMIT 5.76 3.22 C.
DISSOLVED AND ENTRAINED GASES 1.
TOTAL RELEASE CURIES 2.66E0 1.12E-2 27 2.
AVERAGE DILUTED CONCENTRATION DURING PERIOD UCI/ML 4.10E-6 2.96E-8 3.
PERCENT OF APPLICABLE LIMIT 2.05 1.49E-2
. _ = _
= - - -
- -.__________==
__..________________=_
__===.____________-
D.
GROSS ALPHA RADIOACTIVITY 1.
TOTAL RELEASE CURIES 5.64E-4 6.94E-4 29 E.
WASTE VOL RELEASED (PRE-DILUTION)
GAL 6.15E6 4.99E6 10
_________________ _____________. ___________________________=
F.
VOLUME OF DILUTION WATER USED GAL 1.65E8 9.51E7 10 PAGE 1 0F 1 m
TABLE 2B SEMIANNUAL LIQUID CONTINUOUS AND. BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED QUARTER 3 AND 4, 1987 CONTINUOUS RELEASES BATCH RELEASES =
NUCLIDE.
UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 ALL NUCLIDES H-3 CURIES 0
0 1.12E2 3.66El Cr-51 CURIES 0
0 1.61E-3 4.81E-2
_Mn-54 CURIES 0
0 2.79E-3 1.10E-2 Fe-55 CURIES 0
0 6.03E-4 9.96E Fe-59 CURIES 0
0 1.80E-4 3.83E-3 Co-57 CURIES 0
0 0
6.11E-4 Co-58 CURIES 0
0 6.55E-2 1.63E-1 Co CURIES 0
0 7.32E-3 4.86E-2 Rb-88 CURIES 0
0 3.22E-4 0
Sr-89 CURIES 0
0 0
1.77E-3
'Zr-95 CURIES 0
0 4.04E-4 7.44E-3
'Nb-95 CURIES 0
0' 7.18E-4 1.31E-2
-Mo-99 CURIES 0
0 9.47E-4 0
Tc-99M CURIES 0
0 1.09E-3 0
Ru-103 CURIES 0
0 0
6.38E-4 Ag-110M CURIES 0
0 1.54E-4 0
Sb-124 CURIES 0
0 0
7.76E-5 Sb-125 CURIES 0
0 0
1.82E-3 Sn-113 CURIES 0
0 0
7.20E-4 I-131 CURIES 0
0 8.78E-3 1.53E-3 I-133 CURIES 0
0 6.23E-5 0
Cs-134 CURIES 0
0 1.75E-3 1.98E-2 Cs-136 CURIES 0
0 1.12E-4 0
i Cs-137 CURIES 0
0 1.79E-3 2.57E-2 l
Cs-138 CURIES 0
0 4.53E-4 0
Ba-140 CURIES 0
0 1.70E-3 5.28E-5 l
La-140 CURIES 0
0 1.12E-4 8.37E-6 Ce-144 CURIES 0
0 2.90E-4 3.69E-3 Kr-85 CURIES 0
0 1.25E-3 0
Kr-85M CURIES 0
0 2.91E-4 0
Xe-131M CURIES 0
0 2.40E-2 4.64E-4 Xe-133 CURIES 0
0 2.56E0 1.06E-2 Xe-133M CURIES 0
0 3.80E-2 0
Xe-135 CURIES 0
0 3.96E-2 2.07E-4 Sr-90 CURIES 0
0 0
1.28E-3 G ALPHA CURIES 0
0 5.64E-4 6.94E-4 t
TOTAL FOR PERIOD CURIES 0
0 1.15E2 3.69El I
PAGE 1 0F 1 i
epe-w g--s-
=tw+q.-
.+u.eg e.
TABLE 3 SOLID WASTE & IRRADIATED FUEL SHIPMENTS QUARTERS 3 & 4, 1987 A.
SOLID WASTE SHIPPED 0FFSITE FOR BURIAL OR DISPOSAL (DOES NOT INCLUDE IRRADIATED FUEL)
TYPE OF WASTE 6-MONTH EST. TOTAL PERIOD ERROR (%)
3 a.
Spent resins, filter sludges 65.1 m
+/- 25%
evaporator bottoms, etc.
2.74E+01Ci Co-58 23%
6.21E+00 Ci Cs-137 16%
4.27E+00 Ci Fe-55 15%
4.14E+00 Ci Cs-134 11%
3.07E+00 Ci Co-60 10%
2.73E+00 Ci Ni-63 8%
2.15E+00 Ci Sb-125 7%
1.97E+00 Ci H-3 5%
1.47E+GO Ci Mn-54 2%
6.20E-01 Ci Sb-124 2%
4.73E-01 Ci 8
b.
Dry compressible waste, 113.1 m
+/- 25%
contaminated equipment,, etc.
7.46E0 Ci Cr-51 30%
2.26E+00 Ci Co-58 19%
1.43E+00 Ci Nb-95 12%
8.83E-01 Ci Fe-55 12%
8.60E-01 Ci C-14 8%
5.94E-01 Ci Zr-95 6%
4.40E-01 C1 Co-60 4%
3.30E-01 Ci Ni-63 3%
2.40E-01 Ci Mn-54 3%
2.15E-01 C1 Ce-144 1%
1.06E-01 Ci 8
c.
Irradiated components, control 0
m l
rods, etc.
O Ci I
8 d.
Other 0
m l
O Ci Solid Waste Disposition Number of Mode of Class of Solid Type of Shipments Transportation Destination Waste Shipped Container 7
truck Richland, WA A
LSA 7
truck Beatty, NV A
LSA 2
truck Beatty, NV (via SEG)
A LSA l
Page 1 of 2
e_
TABLE 3 (cont.)
Solidification Agent Cement (applicable to vaste type "a" only)
B.
IRRADIATED FUEL SHIPMENTS (DISPOSITION)
Number of Shipments Mode of Transportation Destination 0
N/A N/A i
l l
l l
t Page 2 of 2 L
m TABLE 4 MIC PAGE 1
0F 7
REPORT CATEGORY
- METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD
- QUARTER t 12 12:00AM JANUARY 1,
1987 REPORT START TIME
- 0*00 HRS =
REPORT END TIME
- 4343:59 HRS = 11:59PM JUNE 30, 1987 STABILITY CLASS
- A
' ELEVATION 10 METERS WIND SPEED (MPH) AT 10 METER LEVEL 1-3 1
4-7 8-12 13-18 19-24
>24
- TOTAL H
- 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01:
NME: 0.00E-01 ! 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01:
NE : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01:
EHE: 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01:
E
- 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01
0.0 0E-01
ESE: 1.00E CO 2.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 3.00E 001 SE : 0.00E-01 : 3.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 3.00E 00:
SSE: 0.00E-01 2.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.00E 001 S
- 0.00E-01 : 2.00E 00 : 2.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 5.00E 00:
SSW: 0.00E-01 : 1.00E 00 : 4.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 5.00E 00:
SW 1.00E 00 : 3.00E 00 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 : 4.00E 00 WSW: 0.00E-01 : 2.00E 00 : 2.00E 00 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 6.00E 00:
W
- 0.00E-01 : 1.00E 00 1.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.00E 00 WNW: 0.00E-01 : 0.00E-01 : 4.00E 00 O.00E-01 : 0.00E-01 : 0.00E-01 : 4.00E 00:
NW 0.00E-01 : 0.00E-01 : 5.00E 00 : 0.00E-01 : 0.00E-01 0.00E-01 : 5.00E 00:
NNW: 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01:
TOT: 2.00E 00 : 1.60E 01 : 1.90E 01 : 3.00E 00 : 0.00E-01 : 0.00E-01 : 3.90E 01:
PERIODS OF CALM (HOURS):
0.000E-01 HOURS OF INVALID DATA :
0.000E-01 APPROVED BY:
4 d.d *"
TITLE: SiMN t#%
DATE: %lil88
TABLE 4 HIC PAGE 2
0F 7
REPORT CATEGORY
- METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD
- QUARTER 4 12 REPORT START TIME
- 0:00 HRS = 12:00AM JANUARY 1,
1987 REPORT END TIME
- 4343:59 HRS = 11:59PM JUNE 30, 1987 STABILITY CLASS
- B ELEVATION 10 METERS WIND SPEED (MPH) AT 10 METER LEVEL l
1-3 4-7 8-12 13-18 19-24
>24
- TOTAL N
- 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01:
HNE: 0.00E-01 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 1.00E 00:
NE : 0.00E-01 : 0.00E-01 : 1.00E 00 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.00E 00:
ENE: 0.00E-01 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 1.00E 00:
E
- 0.00E-01 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.00E 00:
ESE: 0.00E-01 2.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 3.00E 00 SE : 0.00E-01 : 2.00E 00 1 1.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 3.00E 00:
SSE: 0.00E-01 : 2.00E 00 : 0.00E-01 : 1 00E 00 : 0.00E-01 : 0.00E-01 : 3.00E 00:
S
- 0.00E-01 : 2.00E 00 : 7.00E 00 : 1.00E 00 1 0.00E-01 : 0.00E-01 : 1.00E 01:
SSW: 0.00E-01 : 4.00E 00 : 7.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.10E 01 SW 0.00E-01 : 2.00E 00 6.00E 00 : 1 00E 00 : 0.00E-01 : 0.00E-01 : 9.00E 00:
WSW: 0.00E-01 1 0.00E-01 : 2.00E 00 : 0.00E-01 : 0.00E-01 0.00E-01 : 2.00E 001 W
- 0.00E-01 6.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 7.00E 00 WNW: 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01:
NW : 0.00E-01 : 1.00E 00 : 3.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 4.00E 00 NNW: 0.00E-01 1 0.00E-01 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.00E 00 TOT: 0.00E-01 : 2.40E 01 : 3.10E 01 : 3.00E 00 : 0.00E-01 : 0.00E-01 : 5.80E 01:
PERIODS OF CALM (HOURS):
0.000E-01 HOURS OF INVALID DATA :
0.000E-01 APPROVED BY: MM N h TITLE: M HM DATE: 7.b/88
TABLE 4 HIC PAGE 3
0F 7
REPORT CATEGORY
- METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD
- QUARTER 4 12 REPORT START TIME
- 0:00 HRS = 12:00AM JANUARY 1,
1987 REPORT END TIME
- 4343:59 HRS = 11:59PM JUNE 30, 1987 STABILITY CLASS
- C ELEVATION 10 METERS WIND SPEED (MPH) AT 10 METER LEVEL 1-3 4-7 8-12 13-18 19-24
>24
- TOTAL N
- 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.00E 00 : 0.00E-01 : 0.00E-31 : 2.00E 00 NNE: 0.00E-01 6.00E 00 : 3.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 9.00E 00:
NE : 0.00E-01 : 4.00E 00 : 3.00E 00 0.00E-01 : 0.00E-01 : 0.00E-01 7.00E 00:
ENE: 0.00E-01 ! 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01:
E
- 0.00E-91 : 3.00E 00 : 5.00E 00 0.00E-01 : 0.00E-01 : 0.00E-01 8.00E 00 ESE: 1.00E 00 : 1.00E 00 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 ! 4.00E 00 SE : 0.00E-01 : 6.00E 00 : 4.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 1.10E 01:
SSE: 0.00E-01 : 9.00E 00 9.00E 00 : 1.00E 00 : 0.00E-01 0.00E-01 : 1.90E 01:
S
- 0.00E-01 : 1.10E 01 : 1.10E 01 3.00E 00 : 0.00E-01 : 0.00E-01 : 2.50E 01:
SSW: 0.00E-01 : 1.00E 01 : 1.40E 01 :
00E-01 : 0.00E-01 0.00E-01 : 2.40E 01:
SW : 0.00E-01 : 7.00E 00 : 1.70E 01 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 2.50E 01:
WSW: 0.00E-01 : 3.00E 00 : 2.00E 00 2.00E 00 : 0.00E-01 : 0.00E-01 : 7.00E 00:
l W
0.00E-01 : 4.00E 00 : 3.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 7.00E 00:
WNW: 1.00E 00 : 3.00E 00 l 2.00E 00 0.00E-01 : 0.00E-01 : 0.00E-01 : 6.00E 00:
1 l
NW : 0.00E-01 : 1.00E 00 : 1.10E 01 : 0.00E-01 : 0.00E-01 0.00E-01 : 1.20E 01:
l NNW: 0.00E-01 : 2.00E 00 : 7.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 9.00E 00:
l TOT: 2.00E 00 : 7.00E 01 : 9.30E 01 : 1.00E 01 : 0.00E-01 : 0.00E-01 : 1.75E 02:
PERIODS OF CALM (HOURS):
0.000E-01 HOURS OF INVALID DATA :
1.000E 00 i
APPROVED BY: I2.6 h TITLE: S uN tWTS DATE: 2lt l B8 l
l t
TABLE 4 MIC PAGE 4
0F 7
REPORT CATECORY
- METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD
- QUARTER t 12 REPORT START TIME
- 0:00 HRS = 12:00AM JANUARY 1,
1987 REPORT END TIME
- 4343:59 HRS 11:59PM JUNE 30, 1987
=
STABILITY CLASS
- D ELEVATION 10 METERS WIND SPEED (MPH) AT 10 METER LEVEL l
1-3 4-7 8-12 13-18 19-24
>24
- TOTAL N
- 2.00E 00 : 6.00E 00 2.00E 01 : 4.00E 00 : 0.00E-01 : 0.00E-01 3.20E 01:
NNE: 2.00E 00 : 3.50E 01 : 6.50E 01 2.00E 00 0.00E-01 : 0.00E-01 1.04E 02:
NE : 9.00E 00 : 4.00E 01 : 5.20E 01 : 6.00E 00 : 0.00E-01 : 0.00E-01 : 1.07E 02:
EME: 6.00E 00 : 2.60E 01 : 4.00E 01 : 1.10E 01 : 0.00E-01 : 0.00E-01 : 8.30E 01:
E
- 2.00E 00 : 3.30E 01 4.40E 01 : 4.00E 00 : 3.00E 00 : 0.00E-01 8.60E 01 ESE: 5.00E 00 : 3.20E 01 : 1.40E 01 : 8.00E 00 : 0.00E-01 : 0.00E-01 5.90E 01:
SE : 3.00E 00 : 3.80E 01 2.40E 01 1 5.00E 00 : 0.00E-01 : 0.00E-01 : 7.00E 01:
SSE: 3.00E 00 1 2.80E 01 : 1.80E 01 : 3.00E 00 : 0.00E-01 : 0.00E-01 : 5.20E 01:
S
- 9.00E 00 : 3.50E 01 : 4.40E 01 : 7.00E 00 : 0.00E-01 : 0.00E-01 : 9.50E 01:
SSW: 4.00E 00 : 4.50E 01 3.40E 01 : 5.00E 00 : 1.00E 00 0.00E-01 : 0.90E 01:
SW 5.00E 00 : 4.70E 01 : 6.20E 01 7.00E 00 : 1.00E 00 0.00E-01 : 1.22E 02:
WSW: 6.00E 00 : 1.90E 01 : 2.70E 01 : 8.00E 00 : 1.00E 00 : 0.00E-01 6.10E 01:
W 5.00E 00 : 4.50E 01 : 3.20E 01 : 6.00E 00 : 1.00E 00 : 1.00E 00 : 9.00E 01:
WNW: 9.00E 00 : 2.50E 01 : 3.30E 01 : 2.00E 00 : 0.00E-01 : 1.00E 00 7.00E 01:
NW : 6.00E 00 3.00E 01 : 4.20E 01 : 6.00E 00 : 0.00E-01 : 0.00E-01 : 8.40E 01:
NNW: 1.00E 00 3.80E 01 : 4.60E 01 : 2.10E 01 : 5.00E 00 : 0.00E-01 : 1.11E 02:
TOT: 7.70E 01 5.22E 02 : 5.97E 02 : 1.05E 02 : 1.20E 01 : 2.00E 00 : 1.32E 03:
PERIODS OF CALM (HOURS):
0.000E-01 HOURS OF INVALID DATA :
1.300E 01 APPROVED BY:
(_/_,,6 Au A--
TITLE: M e975 DATE: thIB8
F TABLE 4 MIC PAGE 5
0F 7
REPORT CATEGORY
- METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD
- QUARTER t 12 REPORT START TIME
- 0:00 HRS 12:00AM JANUARY 1,
1907
=
REPORT END TIME
- 4343:59 HRS = 11:59PM JUNE 30, 1987 STABILITY CLASS
- E ELEVATION 10 METERS WIND SPEED (MPH) AT 10 METER LEVEL 1-3 1
4-7 8-12 13-18 19-24
>24
- TOTAL N
- 5.00E 00 : 2.00E 01 1.50E 01 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 4.10E 01:
NNE: 4.00E 00 : 4.80E 01 : 2.40E 01 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 7.70E 01 NE : 1.50E 01 : 4.00E 01 : 1.00E 01 : 4.00E 00 : 0.00E-01 : 0.00E-01 : 6.90E 01:
ENE: 1.90E 01 : 4.40E 01 : 3.50E 01 : 0.00E-01 : 0.00E-01 1 0.00E-01 : 9.00E 01:
E
- 2.10E 01 : 5.90E 01 : 3.70E 01 : 1.40E 01 : 4.00E 00 : 1.00E 00 : 1.36E 02:
ESE: 1.40E 01 : 5.00E 01 3.50E 01 : 1.70E 01 : 0.00E-01 : 0.00E-01 : 1.16L 02:
SE : 1.20E 01 : 5.80E 01 : 4.20E 01 : 1.00E 01 : 1.00E 00 0.00E-01 : 1.23E 02:
SSE: 5.00E 00 : 6.60E 01 : 3.00E 01 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 1.02E 02:
S
- 1.50E 01 6.80E 01 : 4.20E 01 : 3.00E 00 0.00E-01 : 0.00E-01 : 1.28E 02:
SSW: 1.00E 01 : 4.70E 01 : 2.50E 01 : 4.00E 00 : 0.00E-01 : 0.00E-01 : 8.60E 01:
SW : 5.00E 00 : 3.90E 01 : 3.40E 01 : 4.00E 00 : 0.00E-01 : 0.00E-01 : 8.20E 01:
WSW: 1.30E 01 : 3.00E 01 : 2.50E 01 : 4.00E 00 : 0.00E-01 : 0.00E-01 : 8.00E 01:
W 1.30E 01 : 4.50E 01 : 2.80E 01 : 7.00E 00 0.00E-01 : 0.00E-01 : 9.30E 01:
WNW: 1.10E 01 : 4.80E 01 : 3.30E 01 : 1.10E 01 : 1.00E 00 : 0.00E-01 : 1.04E 02:
NW : 9.00E 00 : 4.40E 01 : 4.10E 01 : 4.00E 00 : 0.00E-01 : 0.00E-01 : 9.00E 01:
NNW: 1.20E 01 4.80E 01 : 3.30E 01 : 4.00E 00 : 0.00E-01 : 0.00E-01 : 9.70E 01:
i TOT: 1.83E 02 : 7.62E 02 : 4.89E 02 : 8.90E 01 : 6.00E 00 : 1.00E 00 : 1.53E 03:
l l
PERIODS OF CALM (HOURS):
9.000E 00 l
HOURS OF INVALID DATA :
2.000E 00 APPROVED DY: C M v % -4 w TITLE: SuPV H 9rs DATE: clil es 1
i I
I L
p TABLE 4 MIC PAGE 6
0F 7
REPORT CATEGORY
- METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERXOD OF RECORD
- QUARTER $
12 REPORT START TIME
- 0:00 HRS = 12:00AM JANUARY 1,
1987 REPORT END TIME
- 4343:59 HRS = 11:59PM JUNE 30, 1987 STABILITY CLASS
- F ELEVATION 10 METERS WIND SPEED (MPH) AT 10 METER LEVEL 1-3 4-7 8-12 13-18 19-24
>24
- TOTAL N
- 3.00E 00 : 7.00E 00 : 0.00E-01 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 1.10E 01:
NNE: 7.00E 00 1.20E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.90E 01:
NE : 2.10E 01 : 2.10E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 4.20E 01:
ENE: 2.10E 01 : 2.10E 01 : 8.00E 00 0.00E-01 : 0.00E-01 : 0.00E-01 : 5.00E 01:
E
- 1.70E 01 : 1.60E 01 : 7.00E 00 : 4.00E 00 : 0.00E-01 : 0.00E-01 : 4.40E 01 ESE: 1.90E 01 : 2.10E 01 : 4.00E 00 : 4.00E 00 : 2.00E 00 : 0.00E-01 1 5.00E 01:
SE : 1.20E 01 : 6 10E 01 : 7.00E 00 : 1.00E 00 0.00E-01 : 0.00E-01 : 8.10E 01:
SSE: 9.00E 00 : 9.20E 01 : 5.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 1.06E 02:
S
- 1.70E 01 7.30E 01 8.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 9.00E 01:
SSW: 1.00E 01 : 5.50E 01 : 1.30E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 7.80E 01:
SW : 1.30E 01 : 3.20E 01 : 1.70E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 6.20E 01:
WSW: 1.80E 01 : 3.10E 01 : 3.00E 00 0,00E-01 : 0.00E-01 : 0.00E-01 : 5.20E 01:
W
- 9.00E 00 : 2.90E 01 : 2.00E 00 1.00E 00 : 0.00E-01 : 0.00E-01 : 4.10E 01:
WNW: 1.10E 01 ! 2.00E 01 : 7.00E 00 : 1.00E 00 1 0.00E-01 : 0.00E-01 : 3.90E 01:
NW : 6.00E 00 : 3.90E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 4.50E 01:
NNW: 7.00E 00 : 1.20E 01 : 2.A0E 00 : 0.00E-01 : 0.00E-01 : 0 00E-01 : 2.10E 01:
TOT: 2.00E 02 : 5.42E 02 : 8.30E 01 : 1.20E 01 : 2.00E 00 : 0.00E-01 : 8.39E 02:
PERIODS OF CALM (!!OURS):
7.000E 00 HOURS OF INVAllD DATA :
4.000E 00 APPROVED BY: GMWA TITLE: S n (N pp F5 DATE: :2 b led
TABLE 4 MIC PAGE 7
0F 7
REPORT CATEGORY
- METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD
- QUARTER 4 12 REPORT START TIME
! 0:00 HRS = 12:00AM JANUARY 1,
1997 REPORT END TIME
- 4343:59 HRS = 11:59PM JUNE 30, 1987 STABILITY CLASS
- G ELEVATION 10 METERS WIND SPEED (MPH) AT 10 METER LEVEL l
1-3 4-7 8-12 13-18 19-24
>24
- TOT..L N
- 0.00E-01 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 0 00E-01 : 0.00E-01 : 1.00E 001 NNE: 1.30E 01 : 5.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.80E 01:
NE : 9.00E 00 : 5.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.40E 01:
ENE: 5.00E 00 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 7.00E 00:
E
- 8.00E 00 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 8.00E 00:
ESE: 7.00E 00 : 3.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 : 1.00E 01:
SE : 6.00E 00 3.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.00E 01:
SSE: 8.00E 00 : 1.50E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.30E 01:
l S
- 9.00E 00 : 1.20E 01 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.20E 01:
I SSW: 5.00E 00 : 1.90E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.40E 01:
l SW : 1.50E 01 : 1.90E 01 : 4.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 3.80E 01:
WSW: 7.00E 00 : 4.00E 00 2.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.30E 01:
l W
- 7.00E 00 : 4.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.10E 01:
l WNW: 2.00E 01 : 1.90E 01 : 0.00E-01 : 3.00E 00 0.00E-01 : 0.00E-01 : 4.20E 01:
l l
NW 4.00E 00 : 3.20E 01 : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 : 3.60E 01:
[
NNW: 2.00E 00 : 0.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.00E 01:
TOT: 1.25E 02 : 1.51E 02 : 8.00E 00 : 3.00E 00 : 0.00E-01 : 0.00E-01 : 2.87E 02:
l I
l PERIODS OF CALM (HOURS):
2.000E 00 I
HOURS OF INVALID DATA :
2.000E 00 90.1% OF TOTAL HOURS l
HOURS OF GOOD DATA 4.261E 03
=
l l
APPROVED BY: (. CC W /b -
TITLE: 66 tt9M DATE: 2); M 8 l
l l
TABLE 4 HID PAGE 1
0F 7
REPORT CATEGORY
- HETER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD
- QUARTER 4 12 12:00AM JANUARY le 1987 REPORT START TIME
- 0:00 HRS
=
REPORT END TIME
- 4343:59 HRS # 11:59PM JUNE 30, 1987 STADILITY CLASS
- A ELEVATION 60 METIRS WIND SPEED (hPH) AT 60 METER LEVEL 1-3 4-7 8-12 13-10 19-24
>24
- TOTAL N
- 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01:
HME: 0.00E-01 : 1.00E 00 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.00E 00:
NE ! 0.00E-01 : 0.00E-01
0.0 0E-01-
0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01:
ENE: 0.00E-01 ! 0.00E-01 : 0.00E-01 : 0.00E-01 0 00E-01 0.00E-01 : 0.00E-01 E
- 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01:
ESE: 0.00E-01 : 1 00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.00E 00:
SE : 0.00E-01 4.00E 00 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 4.00E 001 3SE! 0.00E-01 : 1.00E 00 0.00E-01 : 0.00E-01 ! 0.00E-01 : 0.00E-01 : 1.00E 00:
S
- 0.00E-01 : 3.00E 00 : 2.00E 00 : 2.00E 00 : 0.00E-01 : 0.00E-01 ; 7.00E 00:
GSW: 0.00E-01 : 2.00E 00 0.00E-01 : 4.00E 00 1 0.00E-01 : 0.00E-01 : 6.00E 00:
SW : 1.00E 00 1.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0 00E-01 : 2.00E 00:
WSW: 0.00E-01 : 0.00E-01 : 3.00E 00 : 0.00E-01 : 2.00E 00 : 0.00E-01 : 5.00E 00:
W 0.00E-01 : 1.00E 00 : 0.00E-01 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 3.00E 00:
WNW: 0.00E-01 : 0.00E-01 : 1.00E 00 : 3.00E 00 : 0.00E-01 : 0.00E-01 : 4.00E 00 NW : 0.00E-01 : 0.00E-01 : 1.00E 00 : 4.00E 00 : 0.00E-01 : 0.00E-01 : 5.00E 00:
NNW: 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01:
TOT: 1.00E 00 : 1.40E 01 : 7.00E 00 : 1.50E 01 : 2.00E 00 : 0.00E-01 : 3.90E 01:
PERIODG OF CdLM(HOURS):
0.000E-01 HOURS OF INVALID DA1A :
0.000E-01 i
APPROVED Di: 446 A44w TITLE: Sur/
HFT5 DATE: Eb M
TABLE 4 MID PAGE 2
0F 7
REPORT CATEGORY
- METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT
- iACH WIND SPEED AND DIRECTION PERZOD OF RECORD
- QUARTER i 12 REPORT START TIME
- 0:00 HRS = 12:00AM JANUARY 1,
1987 REPORT END TIME
- 4343:59 HRS = 11:59PM JUNE 30, 1907 STABILITY CLASS
- B ELEVATION 60 METERS WIND SPEED (MPH) AT 60 METER LEVEL l
1-3 4-7 8-12 13-18 19-24
>24
- TOTAL N
- 0.00c-01 1 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01:
NNE: 0.00E-01 : 1.00E 00 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.00E 00:
NE : 0.00E-01 : 0.00E-01 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.00E 00:
ENE: 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01:
E
- 0.00E-01 : 2.00E 00 1 0.00E-01 0.00E-01 0.00E-01 : 0.00E-01 : 2.00E 00:
ESE: 0.00E-01 : 2.00E 00 2.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 4.00E 00!
SE : 0.00E-01 : 0.00E-01 : 2.00E 00 1 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.00E 00:
SSE: 0.00E-01 : 3.00E 00 : 1.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 1 5.00E 00 S
- 0.00E-01 : 1.00E 00 : 3.00E 00 : 3.00E 00 : 0 00E-01 : 0.00E-01 :
7.
0E 00:
SSW: 0.00E-01 : 1.00E 00 : 8.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 1.00E 01:
----~~-----------------------------
SW : 0.00E-01 : 1.00E 00 : 4.00E 00 : 4.00E 00 : 1.00E 00 : 0.00E-01 : 1.00E 01:
WSW: 0.00E-01 : 0.0CE-01 2.00E 00 1 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.00E 00:
W 0.00E-01 : 1.00E 00 : 7.00E 00 1 0.00E-01 : 0.00E-01 : 0.00E-01 : 8.00E 00:
WNW: 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.00E 00 0.00E-01 : 0.00E-01 1.00E 00:
NW 0.00E-01 : 0.00E-01 : 1.00E 00 3.00E 00 : 0.00E-01 : 0.00E-01 : 4.00E 00:
NNW: 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 1.00E 00:
TOT: 0.00E-01 : 1.20E 01 : 3.10E 01 : 1.40E 01 : 1.00E 00 : 0.00E-01 : 5.80E 01:
PERIODS OF CALM (HOURS):
0.000E-01 HOURS OF INVALID DATA :
0.000E-01 APPROVED BY: ( (._ d 4 4,4 A -. -
TITLE: 5 H Al H@J DATE: 2/sl68
TABLE 4 MID PAGE 3
0F 7
REPORT CATEGORY
- METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD
- QUARTER 4 12 REPORT START TIME
- 0:00 HRS 12:00AM JANUARY 1,
1987
=
11:59PM JUNE 30, 1987 REPORT END TIME
- 4343:59 HRS
=
STABILITY CLASS
- C ELEVATION 60 METERS WIND SPEED (MPH) AT 60 METER LEVEL l
1-3 4-7 8-12 13-16 19-24
>24
- TOTAL N
- 0.00E-01 : 0.00E-01 : 0.00E-01 1.00E 00 1 0.00E-01 : 0.00E-01 : 1.00E 00:
NNE: 0.00E-01 : 3.00E 00 : 6.00E 00 : 4.00E 00 : 0.00E-01 : 0.00E-01 : 1.30E 01:
NE : 0.00E-01 : 4.00E 00 : 4.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 8.00E 00:
EHE: 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01:
E
- 0.00E-01 : 1.00E 00 l 2.00E 00 2.00E 00 : 0.00E-01 : 0.00E-01 5.00E 00 ESE: 1.00E 00 : 1.00E 00 1 0.00E-01 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 4.00E 00:
SE : 0.00E-01 : 7.00E 00 : 4.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 1.20E 01:
SSE: 0.00E-01 : 3.00E 00 : 1.20E 01 : 2.00E CO : 0.00E-01 : 0.00E-01 1.70E 01:
S
- 0.00E-01 : 9.COE 00 : 1.10E 01 : 5.00E 00 : 1.00E 00 : 0.00E-01 : 2.60E 01 SSW: 0.00E-01 3.00E 00 : 1.40E 01 : 6.00E 00 : 0.00E-01 : 0.00E-01 : 2.30E 01:
SW : 0.00E-01 : 4.00E 00 : 1.30E 01 : 6.00E 00 : 1.00E 00 : 0.00E-01 : 2.40E 01:
WSW: 0.00E-01 : 0.00E-01 : 3.00E 00 : 3.00E 00 : 0.00E-01 0.00E-01 : 6.00E 00:
W
- 1.00E 00 3.00E 00 : 4.00E 00 : 1.00E 00 : 1.00E 00 : 0.00E-01 : 1.00E 01 WNW: 0.00E-01 : 1.00E 00 : 3.00E 00 : 2.00E 00 0.00E-01 : 0.00E-01 : 6.00E 00 NW : 0.00E-01 : 0.voE-01 : 5.00E 00 : 5.00E 00 : 0.00E-01 : 0.00E-01 1.00E 01:
NNW: 0.00E-01 : 0.00E-01 : 1.00E 00 : 1.00E 01 : 0.00E-01 : 0.00E-01 : 1.10E 01:
l TOT: 2.00E 00 : 3.90E 01 : 8.20E 01 : 5.00E 01 : 3.00E 00 : 0.00E-01 : 1.76E 02:
\\
l l
PERIODS OF CALM (HOURS):
0.000E-01 HOURS OF INVALID DATA :
0.000E-01 APPROVED BY: M'M TI4 T: S u Al
+f F 7'S DATE: t[l/68 I
r l
l TABLE 4 l
I i
MID PAGE 4
0F 7
REPORT CATEGORY
- METER 0 LOGICAL DATA.
ObARTERLY TOTALS OF HOURS AT l
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD
- QUARTER 8 12 I
12:00AM JANUARY 1r 1987 REPORT START TIME
- 0:00 HRS
=
11:59PM JUNE 30, 1987 REPORT END TIME
- 4343:59 HRS
=
STABILITY CLASS
- 0 ELEVATION 60 METERS WIND SPEED (MPH) AT 60 METER LEVEL l
1-3 4-7 0-12 13-18 19-24
>24
- TOTAL N
- 0.00E-01 : 1.00E 00 : 1.60E 01 : 2.00E 01 : 2.00E 00 : 1.00E 00 : 4.00E 01:
I NNE: 2.00E 00 2.10E 01 5.80E 01 : 2.50E 01 : 0.00E-01 : 0.00E-01 : 1.06E 02:
NE : 5.00E 00 : 3.20E 01 : 5.00E 01 : 2.60E 01 : 1.00E 00 : 0.006 91 : 1.14E 02; 1
ENE: 3.00E 00 2 2.00E 01 : 4.40E 01 : 1.90E 01 : 3.00E 00 0.00E-01 : 8.90E 01:
l E
- 1.00E 00 : 1.70E 01 : 4.50E 01 : 1.00E 01 : 4.00E 00 : 2.00E 00 7.90E 01:
l l
ESE: 5.00E 00 : 3.60E 01 : 1.80E 01 : 9.00E 00 : 1.00E 00 : 0.00E-01 : 6.90E 01:
(
SE : 1.00E 00 : 2.90E 01 : 2.40E 01 7.00E 00 : 1.00E 00 : 0.00E-01 : 6.20E 01:
)
i SSE: 4.00E 00 2.30E 01 : 2 50E 01 : 1.40E 01 : 0.00E-01 : 0.00E-01 : 6.60E 01:
1 5
- 3.00E 00 : 2.60E 01 : 4.00E 01 : 2.10E 01 : 1.00E 00 : 0.00E-01 : 9.10E 01:
SSW: 5.00E 00 : 2.90E 01 : 4.40E 01 : 1.70E 01 : 2.00E 00 : C.00E-01 : 9.70E 01:
SW : 2.00E 00 : 1.80E 01 : 6.00E 01 : 2.60E 01 : 5 00E 00 : 1.00E 00 : 1.12E 02:
I WSW: 3.00E 00 : 1.90E 01 : 2.70E 01 : 1.60E 01 : 4.00E 00 : 3.00E 00 ; 7.20E 01:
W
- 1.00E 00 : 1.90E 01 : 3.10E 01 : 1.20E 01 : 5.00E 00 : 2.00E 00 : 7.00E 01:
1 WNW: 4.00E 00 : 2.80E 01 : 2.70E 01 : 2.00E 01 : 3.00E 00 : 1.00E 00 3.30E 01:
NW : 2.00E 00 : 2.20E 01 : 2.00E 01 : 2.60E 01 : 5.00E 00 : 0.00E-01 : 7.50E 01:
NNW: 3.00E 00 : 1.40E 01 : 3.50E 01 : 3.30E 01 ; 1.10E 01 : 6.00E 00 : 1.02E 02:
TOT: 4.40E 01 : 3.54E 02 : 5.64E 02 l 3.01E 02 ; 4.80E 01 : 1.60E 01 1.33E 03:
PERIODS OF CALM (HOURS):
0.000E-01 HOURS OF INVALID DATA :
1.000E 00 7 /sh6 APPROVED DY: C M W A- -
TITLE: S A/ t+PTJ DATE:
l
\\
---.------_____m...-.,,,..__.-
l l
TABLE 4 l
MID PAGE 5
0F l
REPORT CATEGORY
- METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT i
- EACH WIND SPEED AND DIRECTION PERT.00 0F RECORD
- QUARTER 1 12 REPORT START TIME
- 0:00 HRS 12:00AM JANUARY 1,
1987
=
11:59PM JUNE 30, 1987 REPORT END TIME
- 4343:59 HRS
=
STABILITY CLASS
- E ELEVATION 60 METERS i
l WIND SPEED (MPH) AT 60 METER LEVEL 1-3 4-7 8-12 13-18 19-24
>24
- TOTAL l
N
- 0.00E-01 : 6.00E 00 : 2.40E 01 : 1.00E 01 : 0.00E-01 : 0.00E-01 : 4.00E 01:
l l
UNE: 3.00E 00 : 1.10E 01 : 6.10E 01 : 1.50E 01 : 0.00E-01 : 0.00E-01 : 9.00E 01:
I I
NE : 7.00E 00 2.60E 01 4.30E 01 : 5.00E 00 : 1.00E 00 : 0.00E-01 : 8.20E 01:
1 l
ENE: 1.00E 00 : 1 30E 01 : 5.90E 01 : 2.20E 01 : 0.00E-01 : 0.00E-01 : 9.50E 01:
l E
- 4.00E 00 l 2.20E 01 : 6.80E 01 : 2.40E 01 : 8.00E 00 : 7.00E 00 : 1.33E 02:
~-------------------------------------------------------
ESE: 2.00E 00 : 1.70E 01 1 6.10E 01 : 3.10E 01 : 8.00E 00 : 0.00E-01 : 1.19E 02:
SE : 2.00E 00 : 2.20E 01 : 4.70E 01 : 4.10E 01 : 1.00E 01 : 1.00E 00 : 1.23E 0':
d SSE: 1.00E 00 : 2.00E 01 : 4.80E 01 : 2.70E 01 : 4.00E 00 : 0.00E-01 : 1.00E 02 S
- 2.00E 00 : 1.80E 01 : 4.70E 01 : 3.10E 01 : 4.00E 00 0.00E-01 : 1.02E 02:
SSW: 2.00E 00 : 1.30E 01 : 5.20E 01 : 3.60E 01 : 2.00E 00 : 0.00E-01 : 1.05E OZ:
SW : 1.00E 00 : 1.80E 01 : 3.50E 01 2 3.50E 01 : 4.00E 00 : 0.00E-01 9.30E 01:
i WSW: 1.00E 00 : 4.00E 00 : 3.10E 01 : 1.90E 01 : 6.00E 00 : 2.00E 00 6.30E 01:
I W
- 0.00E-01 : 1.50E 01 4.40E 01 : 3.20E 01 : 1.20E 01 : 1.00E 00 : 1.04E 02:
WNW: 1.00E 00 : 1.10E 01 : 4.00E 01 : 3.30E 01 : 0.00E 00 : 7.00E 00 : 1.00E 02:
i i
NW O.00E-01 : 1.00E 01 : 3.00E 01 : 3.20E 01 : 6.00E 00 : 0.00E-01 : 7.80E 01:
l NNW: 0.00E-01 : 1.40E 01 : 5.00E 01 : 4.50E 01 : 4.00E 00 : 1.00E 00 1 1.14E 02:
)
TOT: 2.70E 01 : 2.40E 02 : /.40E 02 : 4.38E 02 : 7.70E 01 : 1.90E 01 : 1.54E 03:
l PERIODS OF CALM (HOURS):
0.000E-01 i
HOURS OF INVALID DATA :
0.000E-01 APPROVED DY: d / 6 W A~--
TITLE: SwFv ff973 DATE: f_ b f
F TABLE 4 MID PAGE 6
0F 7
PEPORT CATEGORY
- METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD
- QUARTER t 12 REPORT START TIME
- 0:00 HRS = 12:00AM JANUARY 1r 1987 REPORT END TIME
- 4343:59 HRS = 11:59PM JUNE 30, 1987 STABILITY CLASS
- F ELEVATION 60 METERS WIND SP~ED(MPH) AT 60 METER LEVEL 1-3 4-7 0-12 13-18 19-24
>24
- TOTAL
. N
- 1.00E 00 : 2.00L 00 : 1.10E 01 3.00E 00 0.001-01 : 0.00E-01 : 1.70E 01:
NNE: 1.00E 00 : 4.00E 00 : 1.20E 01 : 1.00E 01 : 0.00E-01 : 0.00E-01 ! 2.70E 01:
NE' : 2.00E 00 : 5.00E 00 2.70E 01 : 2.00E 00 0.00E-01 : 0.00E-01 3.60E 01:
ENE: 0.00E-01 : 6.00E 00 : 3.00E 01 : 6.00E 00 : 0.00E-01 : 0.00E-01 : 4.20E 01:
E
- 3.00E 00 : 7.00E 00 : 3.80E 01 3.00E 00 : 2.00E 00 1 0.00E-01 : 5.30E 01 ESE: 0.00E-01 : 1.60E 01 3.70E 01 8.00E 00 : 2.00E 00 2.00E 00 : 6.50E 01:
SE : 2.00E 00 6.00E 00 2.90E 01 : 1.10E 01 : 0.00E-01 : 0.00E-01 : 4.80E 01:
SSE: 2.00E 00 : 1.50E 01 : 4.30E 01 : 2.10E 01 : 0.00E-01 : 0.00E-01 : 8.10E 01:
S
- 0.00E-01 : 1.10E 01 : 6.50E 01 : 1.80E 01 : 0.00E-01 : 0.00E-01 : 9.40E 01'
{
SSW: 0.00E-01 ! 5.00E 00 : 4.50E 01 4.60E 01 : 0.00E-01 : 0.00E-01 : 9.60E 01:
SW : 2.00E 00 2.00E 00 : 3.20E 01 : 4.70E 01 : 6.00E 00 : 0.00E-01 8.90E 01:
WSW: 0.00E-01 : 1.40E 01 : 1.90E 01 : 1.80E 01 : 1.00E 00 : 0.00E-01 : 5.20E 01:
W
- 0.00E-01 : 5.00E 00 : 2.30E 01 : 1.40E 01 : 0.00E-01 : 0.00E-01 : 4.20E 01:
l WNW: 1.00E 00 : 4.00E 00 : 1.90E 61 : 2.00E 01 : 3.00E 00 : 1.00E 00 : 4.80E 01:
l l
NW 0.00E-01 : 5.00E 00 7.00E 00 : 5.00E 00 : 0.00E-01 : 0.00E-01 : 1.70E 01; l
NNW: 1.00E 00
.00E 00 : 1.30E 01 : 1.60E 01 : 0.00E-01 : 0.00E-01 : 3.10E 01:
6 TOT: 1.50E 01 : 1.08E 02 : 4.50E 02 : 2.48E 02 : 1.40E 01 3.00E 00 : 8.30E 02 l
PERIODS OF CALM (HOURS):
0.000E-01 l
HOURS OF INVALID DATA :
1.200E 01 APPROVED BY: GMMM TITLE: 6u /N HF7-5 0 ATE: fdr le 8
TABLE 4 MID PAGE 7
0F 7
REPORT CATEGORY METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD
- QUARTER t ic REPORT START TIME
- 0:00 HRS = 12:00AM JANUARY 1,
1987 REPORT END TIME
- 4343:59 HRS = 11:59PM JUNE 30, 1907 STABILITY CLASS
- G ELEVATION 60 METERS WIND SPEED (MPH) AT 60 METER LEVEL l
1-3 4-7 0-12 13-18 19-24
>24
- TOTAL N
- 0.00E-01 : 1.00E 00 : 6.00E 00 3.00E 00 : 0.00E-01 : 0.00E-01 : 1.00E 01:
MNE: 0.00E-01 : 5.00E 00 : 6.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.10E 01:
NE : 0.00E-01 : 1.00E 00 4.00E 00 : 1.00E 00 0.00E-01 : 0.00E-01 : 6.00E 00:
ENE: 0.00E-01 : S.00E 00 : 1.00E 01 8.00E 00 : 0.00E-01 : 0.00E-01 : 2.10E 01:
E
- 0.00E-01 : 5.00E 00 : 5.00E 00 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 1.20E 01:
ESE: 0.00E-01 7.00E 00 : 3.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 1.10E 01:
SE : 0.00E-01 : 1.00E 01 : 0.00E-01 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 1.10E 01:
SSE: 1.00E 00 : 3.00E 00 : 5.00E 00 : 1.00E 00 : 0.00E-01 0.00E-01 : 1.00E 01:
S
- 0.00E-01 4.00E 00 : 1.10E 01 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 1.60E 01:
SSW: 0.00E-01 : 5.00E 00 : 1.10E 01 : 8.00E 00 : 0.00E-01 : 0.00E-01 : 2.40E 01:
SW : 0.00E-01 1.00E 00 : 1.50E 01 : 1.70E 01 : 1.00E 00 : 0.00E-01 : 3.40E 01:
WSW: 0.00E-01 : 3.00E 00 : 7.00E 00 : 1.00E 01 : 1.00E 00 : 0.00E-01 : 2.10E 01:
W
- 0.00E-01 4.00E 00 : 1.40E 01 : 3.00E 00 : 0.00E-01 : 0.00E-01 : 2.10E 01:
WNW: 0.00E-01 ! 0.00E-01 : 6.00E 00 : 7.00E 00 : 1.00E 00 2.00E 00 : 1.60E 01:
t NW 0.00E-01 : 2.00E 00 ! 1.90E 01 : 1.20E 01 : 0.00E-01 : 0.00E-01 : 3.30E 01:
NNW: 0.00E-01 : 0.00E-01 : 5.00E 00 : 2.10E 01 : 0.00E-01 : 0.00E-01 : 2.60E 01:
TOT: 1.00E 00 : 5.40E 01 : 1.27E 02 : 9.60E 01 : 3.00E 00 2.00E 00 : 2,83E 02:
PERIODS OF CALM (HOURS):
0.000E-01 HOURS OF INVALID DATA :
0.000E 00 HOURS OF GOOD DATA 4.262E 03 =
98.1% OF TOTAL HOURS APPROVED BY CM W A TITLE:
bed /V #97 5 DATE: 8// M i
TABLE 4 MIC PAGE 1
0F 7
REPORT CATEGORY
! METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT
! EACH WIND SPEED AND DIRECTION PERIOD OF RECORD
- QUARTER 4 34 L REPORT START TIME
- 4344:00 HRS = 12:00AM JULY 1, 1987 REPORT END TIME
! 8759:00 HRS = 11100PM DECEMBER 31, 1987
' STABILITY CLASS
- A
' ELEVATION 10 METERS WIND SPEED (MPH) AT-10 METER LEVEL 1-3 1
4-7 1
8-12 13-18 19-24
>24
! TOTAL t
N
- 0.00E-01 t-0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 1 0.00E-01 : 0.00E-01:
NNE: 0.00E-01 ! 0.00E-01 ! 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 1 0.00E-011 NE 1 0.00E-01 ! 0.00E-01 ! 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01:
ENE: 0.00E-01 ! 1.00E 00 1 0.00E-01 : 0.00E-01 1 0.00E-01 0.00E-01 : 1.00E 00:
E 8 0.00E-01 4.00E 00 0.00E-01 0.00E-01 0.00E-01 : 0.00E-01 ! 4.00E 00
- 2.00E 00 : 0.00E-01 : 0.00E-01 1 0.00E-01 1 0.00E-01 1 2.00E 00:
ESE '__O.00E-01 SE 1 0.00E-01 : 7.00E 00 : 3.00E 00 0.00E-01 1 0.00E-01.1 0.00E-01 : 1.00E 018-SSE! 0.00E-01 ! 7.00E 00 t 4.00E 00 1 0.00E-01 0.00E-01 : 0.00E-01 : 1.10E 01:
S t 0.00E-01 1.10E 01 1.80E 01 1 4.00E 00 1 0.00E-01 1 0.00E-01 : 3.30E 01:
SSW: 0.00E-01 7.00E 00 1.80E 01 : 1.00E 00 : 0.00E-01 : 0.00E-01 1 2.60E 01:
-SW : 0.00E-01 : 6.00E 00 5.00E 00 : 1.00E 00 : 0.00E-01 1 0.00E-01 1.20E-01:
WSW: 0.00E-01 ! 2.00E 00 : 1.00E 00 : 0.00E-01 1 0.00E-01 0.00E-01 : 3.00E 00:
W
! 0.00E-01 ! 3.00E 00 : 3.00E 00 0.00E-01 1 0.00E-01 : 0.00E-01 1 6.00E 001-WNW: 0.00E-01 : 0.00E-01 : 5.00E 00 2 00E 00 t 0.00E-01 : 0.00E-01 : 7.00E 001 NW ! 0.00E-01 0.00E-01 3.00E 00 : 4.00E 00 t 0.00E-01 : 0.00E-01 : 7.00E 001 NNW: 0.00E-01 : 0.00E-01 : 0.00E-01 1.00E 00 0.00E-01 ! 0.00E-01 ! 1 00E 00:
TOT 0.00E-01 1 5.00E 01 : 6.00E 01 1 1.30E 01 0.00E-01 0.00E-01 1 1.23E 02:
PERIODS OF CALM (HOURS):
0.000E-01 HOURS OF INVALID DATA :
2.000E 00
' APPROVED BY: GMM TITLE: SwJ, ers DATE : 2h la8
h TABLE 4' MIC PAGE 2
0F 7
REPORT CATEGORY
! METER 0 LOGICAL DATA..00ARTERLY TOTALS OF HOURS AT I EACH WIND SPEED AND DIRECTION l PERIOD OF' RECORD
! QUARTER #
34 REPORT START. TIME
- 4344800 HRS = 12100AM JULY 1, 1987 REPORT.END TIME t 8759100 HRS = 11:00PM DECEMBER 31, 1987 STABILITY CLASS
- B ELEVATION i
10 METERS WIND SPEED (MPH) AT 10 METER! LEVEL
.t 1-3 4-7 1
8-12 1
13-18 19-24
>24 1 TOTAL t
.N i 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 1 0.00E-01 1 0.00E-01 t 0.00E-011-NNE 1.00E 00 0.00E-01 1 0.00E-01 1 0.00E-01 0.00E-01 1 0.00E-01 t 1.00E 001 NE : 0.00E-01 1 0.00E-01 1 0.00E-01 1 0.00E-01't 0.00E-01 ! 0.00E-01 : 0.00E-011 ENE: 1.00E 00 : 2.00E 00 : 0.00E-01 1 0.00E-01 : 0.00E-01 0.00E-01 3.00E 001 E
7 0.00E-01 ! 1.00E 00 ! 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.00E 001 ESEt 1 00E 00 1 8.00E 00 1 0.00E-01 1 0.00E-01 : 0.00E-01 ! 0.00E-01 : 9.00E 001 SE : 0.00E-01 : 9.00E 00 1 2.00E 00 1 0.00E-01 : 0.00E-01 ! 0.00E-01 1 1.'10E Oil SSE: 0.00E-01 : 3.00E 00 3.00E 00 : 1.00E 00 0.00E-01 ! 0.00E-01 8 7.00E 001 S
- 0.00E-01 ! 7.00E 00 : 1.30E 01 1 2.00E 00 0.00E-01 1 0.00E-01 1 2.20E Oil SSW1 0.00E-01 : 1.00E 01 : 1.80E 01 : 4.00E 00 : 0.00E-01~
0.00E-01 : 3.20E 011 SW 7 0.00E-01 1 4.00E 00 1 1.10E 01 1 4.00E 00 ! 0.00E-01 1 0.00E-01 : 1.90E 011 i WSk! 0.00E-01 4.00E 00 : 6.00E 00 1 0.00E-01 : 0.00E-01 1 0.00E-01 : 1.00E 01:
l l
l W
! 0.00E-01 8 8.00E 00 : 8.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.60E 011 r
l WNWa 0.00E-01 : 7.00E 00 9.00E 00 1 2.00E 00 0.00E-01 : 0.00E-01 : 1.80E.018 i
. 'NW ! 0.00E-01 1 4.00E 00 t 9.00E 00 1 2.00E 00 : 0.00E-01 : 0.00E-01 : 1.50E 01:
i l
HNW8 0.00E-01 1 0.00E-01 1 0.00E-01 : 1.00E 00 1 0.00E-01 : 0.00E-01 1 1.00E 00:
j l
TOT! 3.00E 00 1 6.70E 01 7.90E 01 : 1.60E 01 : 0.00E-01 1 0.00E-01 1.65E 021 l
l PERIODS OF CALM (HOURS):
0.000E-01 l
HOURS OF INVALID DATA :
4.000E 00 1
1 1
l i
I APPROVED BY! CM *"
TITLE: SuW
++p r3 DATEt EllM8 l
1
f TABLE 4 MIC PAGE 3
0F 7
REPORT CATEGORY
- METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT l
EACH WIND SPEED AND DIRECTION PERIOD OF RECORD
! OUARTER t 34 i
REPORT START TIME
- 4344:00 HRS = 12:00AM JULY 1,
1987 REPORT END TIME
- 8759 00 HRS = 11:00PM DECEMBER 31, 1987 STABILITY CLASS
- C 3
ELEVATION 10 METERS WIND SPEED (MPH) AT 10 METER LEVEL 1-3 4-7 8-12 13-16 19-24
>24
- TOTAL N
- 0.00E-01 : 1.00E 00 1 00E 00 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.00E 00:
NNE: 0.00E-01 : 0.00E-01 : 0.00E-01 1.00E 00 : 0.00E-01 0.00E-01 : 1.00E 00:
NE % 0.00E-01 : 2.00E 00 : 0.00E-01 : 0.00E-01 0.00E-01 : 0 00E-01 : 2.00E 00:
ENE: 0.00E-01 ! 3.00E 00 1 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 ! 3.00E 00!
E
- 0.00E-01 : 5.00E 00 : 4.00E 00 0.00E-01 : 0.00E-01 0.00E-01 : 9.00E 00:
ESE: 1.00E 00 : 2.00E 00 0.00E-01 : 0.00E-01 : 0.00E-01 1 0.00E-01 1 3.00E 00:
SE : 0.00E-01 : 6.00E 00 : 5.00E 00 1 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.10E 01:
SSE: 0.00E-01 : 9.00E 00 1.00E 01 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 2.00E 01:
S
- 3.00E 00 : 8.00E 00 : 1.10E 01 1 4.00E 00 0.00E-01 1 0.00E-01 : 2.60E 01:
SSW: 1.00E 00 6.00E 00 : 3.00E 00 1.00E 00 0.00E-01 0.00E-01 1.10E 01:
SW 0.00E-01 : 1.10E 01 : 1.30E 01 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 2.60E 01:
WSW: 0.00E-01 : 8.00E 00 : 3.00E 00 1 2.00E 00 0.00E-01 0.00E-01 : 1.30E 01:
W
- 0.00E-01 1.40E 01 : 8.00E 00 1 0.00E-01 0.00E-01 0.00E-01 : 2.20E 01:
WNW: 0.00E-01 : 1.50E 01 : 5.00E 00 1 6.00E 00 0.00E-01 : 0.00E-01 2.60E 01:
NW 1.00E 00 : 7.00E 00 : 1.50E 01 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 2.50E 01:
i NNW: 0.00E-01 1.00E 00 1.30E 01 : 1.00E 00 : 0.00E-01 : 0.00E-01 1.50E 01:
TOT: 6.00E 00 9.80E 01 : 9.10E 01 : 2.00E 01 : 0.00E-01 0.00E-01 2.15E 02:
PERIODS OF CALM (HOURS):
0.000E-01 HOURS OF INVALID DATA :
0.000E-01 APPROVED BY:
W e^-
TITLE: M MM DATE: 2Mlas e
TABLE,4 MIC PAGE 4
0F 7
REPORT CATEGORY
- HETER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD
- QUARTER #
34 REPORT START TIME
- 4344!00 HRS = 12:00AM JULY 1, 1987 REPORT END TIME
- 8759:00 HRS = 11:00PM DECEMBER 31, 1987
' STABILITY CLASS
- D ELEVATION' 10 METERS WIND SPEED (MPH) AT 10 METER LEVEL'-
1-3 4-7 8-12 13-18 19-24
>24
- TOTAL N
- 2.00E 00 6.00E 00 t 1.40E 01 1 2.00E 00 t 0.00E-01 : 0.00E-01 : 2.40E 01:
NNE8 1.00E 00 1.90E 01 : 1.60E 01 1.00E 00 1 0.00E-01 1 0.00E-01 ! 3.70E 01:
NE : 5.00E 00-8.00E 00 6.00E 00 0.00E-01 ! 0.00E-01 0.00E-01 1.90E 01:
ENE! 1.00E 00 1 1.20E 01 2.00E 00 1 0.00E-01 8 0.00E-01 ! O.00E-01.: 1.50E 01:
E
- 1.00E 00 1 2.40E 01 1.30E 01 : 1.00E 00 0.00E-01 ! 0.00E-01 : 3.90E 01:
4 ESE: 3.00E 00 : 1.70E 01 : 2.10E 01 1 0.00E-01 0.00E-01 ! 0.00E-01 : 4.10E.01!
SE : 2.00E 00 1 2.30E 01 ! 2.10E 01 : 5.00E 00 : 0.00E-01 : 0.00E-01 5.10'E 01:
SSE: 3.00E 00 : 3.70E 01 : 2.30E 01 6.00E 00 1 0.00E-01 : 0.00E-01 : 6.90E Olt S
- 1.00E 01 : 2.60E 01 : 5.00E 01 1.00E 01 : 0.00E-01 ! 0.00E-01 : 9.60E 01:
i SSW: 8.00E 00 : 4.60E 01 : 3.00E 01 1 1.00E 00 1 0.00E-01 ! 0.00E-01 8.50E 01:
SW ? 3.00E 00 ! 2.80E 01 3.40E 01 : 1.00E 01 : 0.00E-01 : 0.00E-01 7.50E 011 WSW: 5.00E 00 1 2.30E 01 : 1 70E 01 8.00E 00 : 0.00E-01 ! 0.00E-01 5 30E 011 W
4.00E 00 3.00E 01 3.90E 01 : 8.00E 00 0.00E-01 : 0.00E-01 : 8.10E 01:
WNW: 6.00E 00 2.90E 01 : 4.80E 01 1.60E 01 : 4.00E 00 1 0.00E-01 1.03E 021 NW 2.00E 00 : 3.40E 01 : 5.00E 01 1 5.00E 00 : 1.00E 00 : 0.00E-01 9.20E 01:
NNW: 4.00E 00 : 2.40E 01 : 2.80E 01 4.00E 00 : 0.00E-01 : 0.00E-01 6.00E 01:
TOT: 6.00E 01 1 3.86E 02 4.12E 02 : 7.70E 01 : 5.00E 00 0.00E-01 9.40E 02:
PERIODS OF CALM (HOURS):
0.000E-01 HOURS OF INVALID DATA :
7.000E 00 APPROVED BY! M* A----
TITLE: %#4, rWS D ATE! 2hl88 I
TABLE 4 MIC PAGE 5
0F-7 REPORT' CATEGORY
- METER 0 LOGICAL DATA. -QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERIODa0F RECORD
- QUARTER 6 34 REPORT' START TIME
- 4344:00 HRS = 12:00AM JULY 1, 1987
- REPORT END TIME.
8759100 HRS = 11:00PM DECEMBER 31, 1987 i
STABILITY CLASS
- E ELEVATION
.10 METERS WIND SPEED (MPH) AT 10 METER LEVEL 1-3 1
4-7 I
8-12 13-18 19-24
>24
- TOTAL N
I 2.00E 00 1 2.30E 01 ! 3.10E 01 ! 3.00E 00 1 0.00E-01 : 0.00E-01 5.90E 01:
NNE! 6.00E 00 3 90E 01 2.70E 01 4.00E 00 0.00E-01 : 0.00E-01 : 7.60E 01:
NE : 7.00E 00 3.90E 01 : 2.70E 01 ! 1 00E 00 0.00E-01 : 0.00E-01 7.40E 01:>
ENE8 7.00E 00 1 2.20E 01 : 1.20E 01 0.00E-01 : 0.00E-01 1 0.00E-01 4.10E 01:
E
- 4.00E 00 3.60E 01 : 1.80E 01 1 0.00E-01 0.00E-01 0.00E-01 1 5.80E 01:
r ESE% 8.00E 00 1 5.80E 01 2.70E 01 0.00E-01 0.00E-01 : 0.00E-01 8 9.30E 01:
SE t 7.00E 00 9.30E 01 4.20E 01 1 3 00E 00 1 0.00E-01 : 0.00E-01 : 1.45E 02:
SSE: 1.30E 01 1 6.70E 01 ! 6.40E 01 1 2.00E 00~
0.00E-01 ! 0.00E-01 ! 1.46E 028 S
i 9.00E 00 : 1.01E 02 6.80E 01 9.00E 00 ! 0.00E-01 1 0.00E-01 : 1.87E 02:
SSW: 6.00E 00 3.40E 01 : 2.80E 01 ! 5.00E 00 1 0.00E-01 : 0.00E-01 : 7.30E 01:
l SW % 6.00E 00 3.10E 01 4.70E 01 9 00E 00 : 0.00E-01 : 0.00E-01 : 9.30E 01:
WSW 2.60E 01 : 2.40E 01 : 2.90E 01 7.00E 00 1 0.00E-01 : 0.00E-01 1 8.60E 01: -
W 1.10E 01 1 4.80E 41 8 6.80E 01 : 7.00E 00 ! 0.00E-01 ! 0.00E-01 : 1.34E 02:
l WNW: 1.70E 01 6.40E 01 : 4.00E 01 4.00E 00 1.00E 00 1 0.00E-01 ! 1.26E 02:
l ____________________________-_-_______-___-_____-__-----------__---_--__-----_--
l l
NW % 1.60E 01 : 5.90E 01 : 3.60E 01 3.00E 00 1 0.00E-01 1 0 00E-01 : 1.14E 02:
l NNW: 7.00E 00 : 4.30E 01 2.10E 01 I 7.00E 00 ! 0.00E-01 ! 0.00E-01 7.80E 01:
1 TOT: 1.52E 02 7.81E 02 5.85E 02 6.40E 01 : 1.00E 00 : 0.00E-01 : 1 58E 03:
l PERIODS OF CALM (HOURS):
2.000E 00 l
HOURS OF INVALID DATA I 0.000E-01 I
APPROVED BY: (Z4 ^"^~~~~
TITLE: St4 94 t+9TS DATE:d M 1
1 1'
l
i k
+
+
a TABLE 4 MIC PAGE 6-0F 7
REPORT CATEGORY t METER 0 LOGICAL DATA.
QUARTERLY TOTALS ON HOURS AT
- EACH WIND SPEED AND DIRECTION
- PERIOD OF RECORD-t' QUARTER 4 34
' REPORT START TIME t 4344t00 HRS = 12800AM JULY 1, 1987 REPORT END TIME
- 8759100 HRS = 11:00PM DECEMBER 71, 1987 STABILITY CLASS
- F ELEVATION i
10 METERS WIND SPEED (MPH) AT 10 METER LEVEL 1-3 4-7 8-12 13-18 19-24
>24 i TOTAL i
N
'5.00E 00 : 5.00E 00 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E -01 ! 1.00E Oil NNE: 5.00E 00 : 9.00E 00 0.00E-01 : 0.00E-01 1 0 00E-01 : 0.00E-01 : 1 40E 01:
NE : 1.40E 01 1 1.00E 01 1 0.00E-01 : 0.00E-01 0.00E-01' t 0.00E-01 1 2.40E 01:
ENEt 8.00E 00 : 4.00E 00 t 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 : 1.20E 01:
E t 1.40E 01 1.90E 01 1 0.00E-01 0.00E-01 : 0.00E-01 1 0.00E-01 ! 3.30E 01:
ESE% 1.70E 01 2.10E 01 3.00E 00 : 0.00E-01 1 0.00E-01 : 0.00E-01 4 10E'011 SE ! 1.50E 01 1 1.30E 02 ! 2.30E 01 1 0.00E-01 : 0.00E-01 1 0.00E-01 : 1.68E 02:
SSE8 2.00E 01 1 1.47E 02 1 2.30E 01 : 0.00E-01 0.00E-01 : 0.00E-01 : 1.90E 02:
S
- 1.50E 01 8.00E 01 1.10E 01 : 0.00E-01 1 0.00E-01 : 0.00E-01 : 1.06E 02!
SSW7 1.00E 01 3.80E 01 : 1.00E 01 1 0.00E-01 ! 0.00E-01 0.00E-01 1 5.80E 01:
SW 8 1.10E 01 ! 5.10E 01 t 2.20E 01 0.00E-01 ! 0.00E-01 1 0.00E-01 i 8.40E 01:
WSWa 1.20E 01 : 1.90E 01 : 3.00E 00 1 0.00E-01 ! 0.00E-01 1 0.00E-01 : 3.40E 011 W
- 2.50E 01 : 2.50E 01 : 2.00E 00 t 0.00E-01 1.00E 00 : 0.00E-01 1 5.30E 01:
WNW: 2.90E 01 : 3.60E 01 1 2.00E 00 1.00E 00 : 4.00E'00 0.00E-01 7.20E 01:
NW i 9.00E 00 3.80E 01 : 0.00E-01 : 0.00E-01 1 0.00E-01 ! 0.00E-01 : 4.70E 011 NNWS 1.30E 01 1 2.60E 01 1 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 1 3.90E 011 TOTt 2.22E 02 : 6.58E 02 i 9.90E 01 1.00E 00 t 5.00E 00 1 0.00E-01 1 9.85E 02:
PERIODS OF CALM (HOURS)*
3.000E 00 HOURS OF INVALID DATA :
1.000E 00 APPROVED BYi (M *"
TITLE: 6m f+ p r-J DATE: 2/8/88
~
n m.
TAB 13 4 HIC PAGE 7
0F 7-REPORT CATEGORY
- HETER 0 LOGICAL DATA.
QUARTERLY 10TALS OF HOURd l'
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD
- QUARTER 4 34 REPORT START TIME
- 4344 00 HRS = 12t00AM JULY in 1987 REPORT END TIME
- 8759:00' HRS = 11!0 BPM DECEMBER 31, 1937 STABILITY CLASS
- G ELEVATION 10 METERS WIND SPEED (MPH) AT 10 METER LEVEi 1-3 4-7 8-12 13-18 19-24
>24 t TOTAL N
- 1.00E 00 4.00E 00 1 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 5.00E 00:
NNE: 2.00E 00 3.00E 00 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 5.00E 00:
NE 8 4.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 5.00E 00:
ENE: 6.00E 00 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 6.00E 00:
E
- 4.00E 00 1 3.00E 00 : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 7.00E 001-ESE: 3.00E 00 : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 0.00E-01 : 3.00E 00:
SE : 1.10E 01 : 2.80E 01 : 0.00E-01 : 1.00E 00 1 0.00E-01 : 0.00E-01 4.00E 01:
SSE: 1.50E 01 : 2.50E 01 : 1.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 4.20E 011-
,S
- 2.20E 01 : 1.40E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 3.60E 01:
SSW8 1.30E 01 : 1.30E 01 1.00E 00 : 0.00E-01 : 0.00E-01 0.00E-01 2.70E 01:
SW 1.70E 01 3.50E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 5.20E 01:
WSW: 1.20E 01 3.00E 00 0.00E-01 : 0.00E-01 : 0.00E-01 1 0.00E-01 ! 1.50E 01:
W 1.40E 01 5.00E 00 : 0.00E-01 : 0.00E-01 0.00E-01 0.00E-01 : 1~.90E 01:
WNW8 1.50E 01 : 1.30E 01 : 0.00E-01 1 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.80E 01:
NW 5.00E 00 : 1.60E 01 : 0.00E-01 : 0 00E-01 : 0.00E-01 : 0.00E-01 : 2.10E 01:
NNW: 1.10E 01 : 2.10E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 1 3.20E 01:
TOT: 1.55E 02 : 1.84E 02 : 2.00E 00 : 2.00E 00 : 0.00E-01 : 0.00E-01 3.43E 02:
PERIODS OF CALH(HOURS):
5.000E 00 HOURS OF INVALID DATA i 1.000E 00 HOURS OF GOOD DATA 4.364E 03 =
98.8% OF TOTAL HOURS i
DATE: 2.M APPROVED BY: GM
- TITLE: kg ggn l
m y m_.
TABLE 4 MID
~PAGE 1-0F.
REPORT CATEGORY
! METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION
?ERIOD OF RECORD
- QUARTER 4-34 REPORT START TIME
- 4344!00 HRS = 12100AM JULY 1, 1987
' REPORT END TIME
- 8757:00 HRS = 11 00PM DECEMBER 31, 1987 STABILIT.Y CLASS i A ELEVATION 60 METERS WIND SPEED (MPH) AT 60 METER LEVEL
.t 1-3 4-7 0-12 13-18 8
19-24 i
>24 i TOTAL N
- 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 1 0.00E-01 : 0.00E-01 8 0 00E-01:
NNE: 0.00E-01 0.00E-01 : 0.00E-01 1 0.00E-01 1 0.00E-01 1 0.00E-01 ! 0.C)E-01:
NE : 0.00E-01 : 0.00E-01 1 0.00E-01 : 0.00E-01 1 0.00E-01 : 0.00E-01 : 0.00E-01:
ENE: 0.00E-01 1 1.00E 00 ! 1.00E 00 1 0.00E-01 1 0.00E-01 1 0.00E-01 1 2 00E 00:
E
- 0.00E-01 3.00E 00 ! 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 t-3.00E 001 ESE: 0.00E-01 : 2.00E 00 1 0.00E-01 : 0.00E-01 0.00E-01 0.00E-01 2.00E 001 SE ? 0.00E-01 : 2.00E 00 : 5.00E 00 t 0.00E-01 : 0.00E-01 t 0.00E-01 ! 7.00E 008 s
SSEt 0.00E-01 5.00E 00 : 7.00E 00 : 2.00E 00 : 0.00E-01 0.00E-01 1 1.40E 01:
S
- 0.00E-01 : 9.00E 00 t 1.30E 01 7.00E 00 : 1.00E 00 0.00E-01 1 3.00E 011 SSW1 0.00E-01 4.00E 00 1.20E 01 1.00E 01 : 0.00E-01 0.00E-01 : 2.60E 01:
SW 0.00E-01 7.00E 00 t 6.00E 00 4.00E 00 1 0.00E-0121 0.00E-01 ! 1.70E 0_18 WSW: 0.00E-01 : 0.00E-01 : 2.00E 00 : 0.00E-01 1 0 00E-01 1 0.00E-01 ! 2.00E 00:
W 0.00E-01 : ~ 0.00E-01 1 3.00E 00 2.00E 00 : 0.00E-01 : 0.00E-01 5.00E 00!
WNW8 0.00E-01 : 1.00E 00 : 1.00E 00 : 4.00E 00 t 1.00E 00 1 0.00E-01 t 7.00E 001 NW ! 0.00E-01 1 0.00E-01 0.00E-01 1 4.00E 00 : 1.00E 00 : 3.00E 00 8.00E 00!-
NNW: 0.00E-01 : 0.00E-01 1 0.00E-01 : 0.00E-01 : 2.00E 00 : 0 00E-01 2.00E 00:
TOT: 0.00E-01 : 3.40E 01 ! 5.00E 01 : 3.30E 01 1 5.00E 00 ! 3.00E 00
-1.25E 021 PERIODS OF CALM (HOURS):
0.000E-01 HOURS OF INVALID DATA :
0.000E-01 APPROVED BY: W N" TITLE: JuW W M DATEt 2/l b i
TABLE 4 MID PAGE 2
0F 7
REPORT CATEGORY
- METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT
! EACH WIND SPEED AND DIRECTION 3
PERIOD OF RECORD
- QUARTER 4 34 REPORT START TIME
- 4344800 HRS = 12t00AM JULY 1, 1987 REPORT END TIME
! 8759:00 HRS = 11:00PM DECEMBER 31, 1987 STABILITY CLASS
- B ELEVATION 60 METERS WIND SPEED (MPH) AT 60 METER LEVEL l
1-3 4-7 8-12 13-18 1
19-24
>24
- TOTAL t
N
- 0.00E-01 ! 0.00E-01 1 0.00E-01 1 0.00E-01 : 0.00E-01 ! 0.00E-01.1 0.00E-01 NNE: 0.00E-01 : 0.00E-01 0.00E-01 1 0.00E-01~! 0.00E-01 : 0.00E-01 : 0.00E-01:
NE ! 0.00E-01 : 1.00E 00 t 0.00E-01 : 0.00E-01 1 0.00E-01 : 0.00E-01 ! 1.00E 00.
ENE: 1.00E 00 ! 1.00E 00 1 0.00E-01 1 0.00E-01': 0.00E-01 0.00E-01 ! 2.00E 001 E
- 0.00E-01 1 2.00E 00 t 2.00E 00 0.00E-01 : 0.00E-01 : 0.00E-01 1 4.00E 00.
ESE! 1.00E 00 t 4.00E 00 t 0.00E-01 0.00E-01 1 0.00E-01 1 0.00E-01 : 5.00E 00:
___--______-__--__--_____---_____-_--_-_____--________-_-_________--_-_'1.30E Oil SE : 0.00E-01 : 9.00E 00 : 4.00E 00 0.00E-01 ! 0.00E-01 1 0.00E-01 l SSE: 0.00E-01 : 2.00E 00 : 4.00E 00 1 2.00E 00 8 0.00E-01 0.00E-01 1 8.00E 00:
S i 0.00E-01 : 9.00E 00 1 6.00E 00 t 6.00E 00 : 1.00E 00 0.00E-01 1 2.20E 011 1
SSW3 0.00E-01 1 6.00E 00 : 1.20E 01 1 7 00E 00 : 0.00E-01' 0.00E-01 ! 2.50E 011 SW 8 0.00E-01 ! 4 00E 00 t 1.20E 01 ! 1.00E 01 ! 3.00E 00 ! 0.00E-01 1 2.90E 01:
WSW8 0.00E-01 3.00E 00 t 6.00E 00 8 1.00E 00 1 0.00E-01 0.00E-01 ! 1.00E 011 1
I W
! 0.00E-01 1 1.00E 00 : 9.00E 00 t 3.00E 00 0.00E-01 ! 0.00E-01 1 1.30E 011 WNW: 0.00E-01 1 1.00E 00 1.30E 01 : 4.00E 00 : 1.00E 00 1 0.00E-01 1.90E Olt t
I 1
NW 0.00E-01 : 2.00E 00 1 3.00E 00 : 8.00E 00 1 0.00E-01 1 2.00E 00 1.50E 011 1
NNW8 0.00E-01 ! 0.00E-01 : 0.00E-01 ! 1.00E 00 2.00E 00 1 0.00E-01 3 00E 00 TOT! 2.00E 00 1 4.50E 01 : 7.10E 01 1 4.20E 01 7.00E 00 t 2.00E 00 1.69E 02!
l 1
PERIODS OF CALM (HOURS):
0.000E-01 HOURS OF INVALID DATA !
0.000E-01 l APPROVED BY! CM *C TITLE! W HP T7 D ATE ! 2/l/88 1
i I
TABLE 4-MID PAGE 3
0F 7
REPORT, CATEGORY
.: METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT'
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD
! QUARTER 6 -34 REPORT START TIME'
- 4344:00 HRS = 12:00AM JULY l t' 1987 REPORT END TIME
! 8759:00' HRS = 11:00PM DECEMBER 31,~1987 STABILITY CLASS
- C ELEVATION:
60 METERS WIND SPEED (MPH) AT 60 : METER LEVEL t 3 4-7 I
8-12 1
13-18 19-24
>24 l TOTAL.
t-N
! 0.00E-01 0.00E-01 : 1 00E 00 t 0.00E-01;: 0.00E-01Et 0.00E-01 : 1.00E 00:
NNE! 0 00E-01 1.00E 00 1 0.00E-01
-2.00E 00 : 0.00E-01 : 0.00E-01 3.00E 001 NE : 0.00E-01 ! 2.00E 00 1 0.00E-01 : 0.00E-01 !.0.00E-01 l'O.00E-01 t 2.00E 001 ENE: 0.00E-01 : 2.00E 00 0.00E-01 0.00E-01 : 0.00E-01 1 0.00E-01 : 2.00E 00:
E i 1.00E 00 6.00E 00 2.00E 00 : 0.00E-01 : 0.00E-01 1 0.00E-01 t 9.00E 001 ESE!'O.00E-01 1 2.00E 00 2.00E 00 1 0.00E-01 : 0 00E-01 : 0.00E-01 : 4.00E 00:
SE ~1 0.00E 2.00E100 t 6.00E 00 1 1.00E 00 1 0.00E-01 0.00E-01 t.9.00E 008 SSE: 1.00E 00 ! 7.00E 00 : 1.00E 01 ! 5.00E 00 : 0.00E-01 : 0.00E-01 2.30E 011 S
1 0.00E-01 1 7.00E 00 1.00E 01 ! 6.00E 00 : 0.00E-01 : 0.00E-01 : 2.30E-01:
l SSWt 1.00E 00 : 6.00E 00 4.00E 00 4.00E 00 : 0.00E-01 0.00E-01 : 1.50E 01:
i SW ! 0.00E-01 ! 1.00E 01 1 8.00E 00 : 7.00E 00 0.00E-01 1 0.00E-01 : 2'50E 011 l
WSW: 0.00E-01 1 4.00E 00 5.00E 00 t 2.00E 00 t 2.00E 00 1 0.00E-01 : 1.30E 01:
I l
l W
- 0.00E-01 : 6.00E 00 : 1.30E 01 0.00E-01 ! 0.00E-01 : 0 00E-01 1 1.90E 01:
WNW! 0.00E-01 7.00E 00 9.00E 00 : 4.00E 00 : 2.00E 00 : 1.00E 00 t 2.30E 01:
NW 0.00E-01 : 2.00E 00 1 1 30E 01 1 7.00E 00 t 3.00E 00 1 0.00E-01 : 2 50E 01 1
l NNW: 0.00E-01 1 2.00E 00 7.00E 00 9.00E 00 1.00E 00 1 0.00E-01 1.90E 01:
TOT: 3.00E 00 : 6.60E 01 ! 9.00E 01 1 4.70E 01 : 8.00E 00 : 1.00E 00 t 2.15E 02 PERIODS OF CALM (HOURS):
0.000E-01 HOURS OF INVALID DATA !
0.000E-01 z/i/86 APPROVED BY: M*
TITLE! 6aFV H 97'S DATE;
[
{
TABLE 4 MID PAGE 4
0F 7
REPORT CATEGORY
% METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION-PERIOD OF RECORD
- QUARTER t' 34 REPORT START TIME
- 4344:00 HRS = 12:00AM JULY 1, 1987 REPORT END TIME
- 8759:00 HRS = 11:00PM DECEMBER 31, 1987 STABILITY CLASS
- D ELEVATION 60 METERS WIND SPEED (MPH) AT 60 METER LEVEL
?
1-3 4-7 8-12 13-18 19-24
>24
- TOTAL N
- 0.00E-01 : 2.00E 00 : 1.30E 01 8.00E 00 0.00E-01 : 0.00E-01 ! 2.30E 01:
i NNE: 0.00E-01 : 1.90E 01 2.60E 01 9.00E 00 1 0.00E-01 : 0.00E-01:: 5.40E 01:
NE : 1.00E 00 8.00E 00 7.00E 00 0.00E-01 : 0.00E-01 0.00E-01 : 1.~60E 01:
l ENE: 1.00E 00 1.30E 01 : 3.00E 00 1 0.00E-01 0.00E-01 0.00E-01 : 1.70E 01:
E S 3.00E 00 : 1.50E 01 : 1.50E 01 : 4.00E 00 1 0.00E-01 0.00E-01 1 3.70E 01:
ESE: 1.00E 00 : 1.20E 01 : 2.10E 01 1 3.00E 00 : 0.00E-01 0.00E-01 3.70E 011t SE : 3.00E 00 : 1.60E 01 : 2.00E 01 6.00E 00 1 0.00E-01 : 0.00E-01 : 4.50E 01:
SSE: 1.00E 00 2.20E 01 : 3.20E 01 ! 1.30E 01 5.00E-00 : 0.00E-01 7.30E 01:
S 2 4.00E 00 2.30E 01 : 4.20E 01 1.80E 01 : 4.00E 00 : 0.00E-01 9.10E 01:
SSW: 3.00E 00 2.00E 01 : 3.50E 01 1.90E 01 : 0.00E-01 : 0.00E-01 : 7.70E 01:
SW 3.00E 00 1 2.90E 01 : 3.20E 01 : 2.10E 01 5.00E 00 0.00E-01 : 9.00E 01:
WSW: 2.00E 00 1 2.20E 01 : 1.10E 01 : 2.20E 01 : 2.00E 00 : 0.00E-01 : 5.90E 01:
W 1.00E 00 : _2.00E 01 : 2.20E 01 1.70E 01 : 6.00E 00 0.00E-01 : 6.60E 01:
l WNW: 1.00E 00 : 2.00E 01 : 2.80E 01 4.00E 01 : 1.30E 01 : 6.00E 00 1.08E 02:
\\
NW 0.00E-01 1.80E 01 : 3.00E 01 3.70E 01 1 2.00E 00 5.00E 00 : 9.20E 01:
NNW: 1.00E 00 : 1.50E 01 : 2.60E 01 1.90E 01 : 1.00E 00 0.00E-01 1 6.20E 01:
TOT: 2.50E 01 1 2.74E 02 3.63E 02 : 2.36E 02 : 3.80E 01 : 1.10E 01 : 9.47E 02!
t 1
l PERIODS OF CALM (HOURS):
0.000E-01 HOURS OF INVALID DATA 0.000E-01 t
l APPROVED BY: 4M
- TITLE:
gu py up r3 DATE: 2/1/ O l
l i
i t
i
TABLE 4 MID PAGE 5
0F 7
~ REPORT CATEGORY
! METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT t EACH WIND SPEED AND DIRECTION PERIOD OF RECORD
! OUARTER 4 34 REPORT START TIME
- 4344 00 HRS = 12:00AM JULY in 1987 REPORT END TIME I 8759:00 HRS = 11100PM DECEMBER 31, 1987 STABILITY CLASS
-: E ELEVATION 60 METERS t
WIND SPEED (MPH) AT 60 METER LEVEL i
1-3 4-7 8
8-12 13-18 19-24
>24 TOTAL N
! 1.00E 00 : 5.00E 00 2.70E 01 : 1.20E 01 1 1.00E 00 : 0.00E 4 60E 01:
NNE: 2.00E 00 t 1.50E 01 : 6.50E 01 : 2 90E 01 2.00E 00 0.00E-01-l 1.13E 02:
NE 112.00E 00 1 2.00E 01 4.80E 01 : 7.00E 00 1.00E 00 1 0.00E-01 7.80E 01 ENE: 0.00E-01 1.20E 01 : 2.30E 01 : 4.00E 00 ! 0.00E-01 : 0.00E-01 ! 3.90E 01:
E
- 4.00E 00 1.00E 01 ! 4 20E 01 ! 1.40E 01 0.00E-01 1 0.00E-01 1 7.00E 01:
i 7
ESE! 1.00E 00 ! 1.90E 01 5.00E 01 : 7.00E 00 1 0.00E-01 : 0.00E-01 : 7.70E 01:
SE : 1.00E 00 : 1.00E 01 6.60E 01 4.20E 01 : 2.00E 00 1 0.00E-01 ! 1.21E 02:
SSE: 4.00E 00 : 1.70E 01 : 6.10E 01 6 00E 01 : 0.00E-01 ! 0.00E-01 : 1.42E 02!
l S
- 1.00E 00 t 1.90E 01 : 7.60E 01 7 30E 01 ! 5.00E 00 1 0.00E-01 : 1.74E 021
.SSW: 3.00E 00 1 1,10E 01 : 3.70E 01 ! 4.20E 01 2.00E 00 1 0.00E-01 ! 9 50E~01:
SW 8 3.00E 00 : 1.50E 01 3.20E 01 ! 4.70E 01 6.00E 00 1 0.00E-01 : 1.03E 028-l WSW: 9.00E 00 1.40E 01 : 2.00E 01 : 2.80E 01 : 1.00E 01 1 3.00E 00 8 8.40E 011 l
l W
! 3.00E 00 2.00E 01 3.00E 01 4.70E 01 : 5.00E 00 ! 0.00E-01-t 1.05E 021 i __________________________________________________ -_____________________-______
l WNW8 3.00E 00 6.00E 00 6.20E 01 4.80E 01 : 1.20E 01 3.00E 00 1 34E 02:
l NW 2.00E 00 : 1.20E 01 4.70E 01 4.80E 01 : 5.00E 00 ! 0.00E-01 ! 1.14E 02:
1 i
l NNW8 0.00E-01 : 1.70E 01 4.90E 01 : 1.70E 01 : 6.00E 00 t 0.00E-01 1 8.90E Oi!
i TOT: 3.90E 01 2.22E 02 : 7.35E 02 1 5.25E 02 : 5.70E 01 1 6.00E 00 : 1.58E 031 l
PERIODS OF CALM (HOURS)!
1.000E 00 l
HOURS OF INVALID DATA !
0.000E-01 i
i
{
[
APPROVED BY: M. d M*h TITLE!
SM #f9TT DATE: 2 ///8 8 l
I l
i
TABLE 4 MID PAGE 6
0F 5
REPORT CATEGORY t METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT-
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD
! QUARTER #
34
. REPORT. START TIME
- 4344800 HRS = 12:00AM JULY 1, 1987 REPORT END TIME
! 8759:00 HRS = 11:00PM DECEMBER 31, 1987 STABILITY CLASS
! F
,; : ELEVATION 60 METERS WIND SPEED (MPH) AT 60 HETER LEVEL 1-3 4-7 t
8-12 13-18 19-24 1
>24
- TOTAL i
N
& 1.00E 00 1.2.00E 00 6.00E 00 : 1.00E 00 ! 0.00E-01 ! 0.00E-01 1 1.00E 01:
i I
NNE2 2.00E 00 1 1.00E 00 t 1.50E 01 ! 5.00E 00 : 0.00E-01 1 0 00E-01 2.30E 018 NE ! 3.00E 00 6.00E 00 1 1.50E 01 : 2.00E 00 1 0.00E-01 1 0.00E-01 : 2.60E 01:
l ENES 1.00E 00 t 4.00E 00 : 1.50E 01 1 0.00E-01 1 0.00E-01 1 0.00E-01 1 2.00E 01t E
! 2.00E 00 : 7.00E 00 1 2.10E 01 ! 2.00E 00 t 0.00E-01 1 0.00E-01 ! 3.20E 01:
ESE! 0.00E-01 4.00E 00 3.20E 01 t'4.00E 00 ! 0.00E-01 1 0.00E-01 ! 4.00E Ott y
SE -! 1.00E 00 t 4.00E 00 t 5.90E 01 ! 1 70E 01 ! 0.00E-01"t 0.00E-01 1 8.10E 01:
SSE: 1.00E 00 : 1.20E 01 7.90E 01 1 5.70E 01 ! 0.00E-01 : 0.00E-01 ! 1.49E 02t S
- 1.00E 00 : 1.30E 01 1 1.01E 02 8 4.50E 01 ! 0.00E-01 1 0.00E-01 1 1.60E 02:
SSW! 1.00E 00 t 7.00E 00 1 5.40E 01 4.00E 01 i~0.00E-01 8 0.00E-01 1 1.02E 02 SW 1.00E 00 : 9.00E 00 : 3.50E 01 : 4.20E 01 : 0.00E-01 ! 0.00E-01 1 8.70E-01 ~
t WSW: 1 00E 00 t 3.00E 00 2.90E 01 1 1.40E 01 1 2.00E 00 ! 0.00E-01 8 4.90E 01:
W t 0.00E-01 ! 1.40E 01 : 2.60E 01 : 8.00E 00 ! 0.00E-01 ! 0.00E-01 : 4.80E 01t' 1
WNW! 0.00E-01 ! 9.00E 00 1 2.70E 01 ! 1.90E 01 2 1.00E 00 t 5.00E 00 t 6.10E 018 NW ! 1.00E 00 3.00E 00 t 2.60E 01 : 2.20E 01 ! 0.00E-01 1 1.00E 00 t 5.30E 011 NNWS 0.00E-01 ! 1.10E 01 ! 1.20E 01 : 1.80E 01 ! 0.00E-01 : 0.00E-01 : 4.10E 01:
TOT! 1.60E 01 : 1 09E 02 5.52E 02 2 96E 02 1 3.00E 00 t 6.00E 00 t 9 82E 02ti l
PERIODS OF CALM (HOURS) 0.000E-01 t -HOURS OF INVALID DATA !
7.000E 00 t
i APPROVED BY: <- M M -
TITLE! $&A/ H N DATE: F)//88 t
I i
i l
i
,-..---m
~ -. -, -.... _
TABLE 4 HID PAGE 7
0F 7
REPORT CATEGORY
- METER 0 LOGICAL DATA.
QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION j
PERIOD OF RECORD
- QUARTER t 34 REPORT START TIME
- 4344:00 HRS = 12:00AM JULY 1, 1987 REPORT END TIME
- 8759:00 HRS 11:00PM DECEMBER 31, 1987
=
STABILITY CLASS
- G ELEVATION 60 METERS WIND SPEED (MPH) AT 60 METER LEVEL 1-3 4-7 8-12 13-18 19-24
>24
- TOTAL N
2 0.00E-01 : 3.00E 00 : 5.00E 00 3.00E 00 1 0.00E-01 : 0.00E-01 : 1.10E 01 '
____________________________________________________________________________-___ ~
NNES 1.00E 00 : 4.00E 00 : 1.00E 01 5.00E 00 0.00E-01 0.00E-01 : 2.00E'01:
_____________-_____.__________________________~__________________________________
NE : 1.00E-00 7.00E 00 : 1.10E 01 : 1.00E 00 1 0.00E-01 0.00E-01 : 2.00E 01:
I ____ _ _ $____
__I____
__I_____
__I_____ _ __I ____ _ __I______
E
- 0.00E-01 2.00E 00 2.00E 00 : 4.00E 00 0.00E-01 : 0.00E-01 : 8.00E 00:
ESE: 2.00E 00 : 3.00E 00 1 2.00E 00 1 0.00E-01 : 0.00E-01 : 0.00E-01 7.00E 00:
SE : 1.00E 00 1 2.00E 00 3.00E 00 : 2.00E 00 : 1.00E 00 : 0.00E-01 : 9.00E 00:
SSE: 2.00E 00 7.00E 00 8.00E 00 : 1.00E 00 : 1.00E 00 : 0.00E-01 : 1.90E 01:
S
- 0.00E-01 : 8.00E 00 : 3.00E 01 3.00E 00 : 0.00E-01 : 0.00E-01 : 4.10E 01:
SSH: 2.00E 00 : 9.00E 00 3.00E 01 : 1.00E 00 0.00E-01 1 0.00E-01 1 4.20E 01:
SW 0.00E-01 : 1.10E 01 : 2.00E 01 : 2.00E 01 : 0.00E-01 : 0.00E-01 : 5.10E 01:
WSW: 1.00E 00 : 1.30E 01 : 6.00E 00 : 9.00E 00 0.00E-01 : 0.00E-01 : 2.90E 01:
W 1.00E 00 : 1.00E 01 : 7.00E 00 : 3.00E 00 1 0.00E-01 : 0.00E-01 : 2.10E 01:
WNW: 1.00E 00 5.00E 00 1 2.00E 00 : 6.00E 00 : 0.00E-01 : 0.00E-01 : 1.40E 01:
NW 8 0.00E-01 : 5.00E 00 : 4.00E 00 : 1.10E 01 : 0.00E-01 : 0.00E-01 : 2.00E 01:
NNW: 1.00E 00 ! 3 00E 00 6.00E 00 5.00E 00 : 0.00E-01 0.00E-01 : 1.50E 01:
l TOT: 1.40E 01 : 9.60E 01 : 1.49E 02 : 7.40E 01 : 2.00E 00 0.00E-01 : 3.35E 02:
PERIODS OF CALM (HOURS):
1.000E 00 HOURS OF INVALID DATA :
1.300E 01 HOURS OF GOOD DATA 4.359E 03 =
98.7% OF TOTAL HOURS l
APPROVED BY: CM N' TITLE: Su vV t1P TS DATE:2/l/98 i
TABLE 5 DOSE AT THE SITE BOUNDARY AND NEAREST RESIDENT FROM GASEOUS EFFLUENTS 1987 ORGAN SITE BOUNDARY NEAREST RESIDENT Location:
2.2Km NNW Location:
2.9 km NNW Age Group: Child Age Group: Child DOSE
% LIMIT DOSE
%_ LIMIT Gamma Air 4.0E-2 0.4 2.6E-2 N/A Dose (mrad)
Beta Air 9.6E-2 0.5 6.2E-2 N/A Dose (mrad)
Whole Body (crem)*
2.5E-2 N/A 1.6E-2 N/A Skin (mrem) 6.6E-2 N/A 4.2E-2 N/A Bone (arem) 2.8E-4 N/A 1.7E-4 lE-3 Liver (mrem) 6.6E-3 N/A 4.2E-3 3E-2 Total Body (mrem) 6.4E-3 N/A 4.0E-3 3E-2 Thyroid (mrem) 5.9E-2 N/A 3.7E-2 2E-1 Kidney (mrem) 6.5E-3 N/A 4.2E-3 3E-2 Lung (arem) 6.3E-3 N/A 3.9E-3 3E-2 GI-LLI (mrem) 6.3E-3 N/A 4.0E-3 3E-2 l
[
- Noble Gas Exposure Only l
l l
Page 1 of 1 i
TABLE 6 DOSE TO THE MEMBER OF THE PUBLIC FROM ACTIVITIES WITHIN THE SITE BOUNDARY 1987 ORGAN EFFLUENTS DOSE DIRECT RADIATION DIRECT RADIATION TOTAL DOSE WITHIN THE SITE FROM THE UNIT FROM OUTSIDE TANKS FOR THE YEAR BOUNDARY (mrem)
(mrem)
(mrem)
(mrem)
Skin 3.1E-3 5E-4 8E-3 1.2E-2 Bone 1.2E-3 SE-4 8E-3 9.7E-3 Liver 1.4E-3 5E-4 8E-3 9.9E-3 Total Body 1.4E-3 SE-4 8E-3 9.9E-3 Thyroid 2.3E-3 5E-4 8E-3 1.1E-2 Kidney 1.4E-3 SE-4 8E-3 9.9E-3 Lung 1.4E-3 5E-4 8E-3 9.9E-3 GI-LLI 1.4E-3 SE-4 8E-3 9.9E-3 Page 1 of 1
TABLE 7 TOTAL DOSE DUE TO THE URANIUM FUEL CYCLE 1987 ORGAN DOSE TO THE NEAREST
% LIMIT DOSE TO THE MEMBER OF
% LIMIT RESIDENT (mrem) 40CRF190 THE PUBLIC (mrem) 40CFR190 Skin 4.2E-2 2E-1 4.2E-2 2E-1 Bone 1.6E-2 6E-2 2.4E-2 lE-1 Liver 2.0E-2 8E-2 2.4E-2 1E-1 Total Body 2.0E-2 8E-2 2.4E-2 1E-1 Thyroid 5.3E-2 7E-2 2.5E-2 3E-2 Kidney 2.0E-2 8E-2 2.4E-2 1E-1 Lung 2.0E-2 8E-2 2.4E-2 1E-1 GI-LLI 2.0E-2 8E-2 2.4E-2 lE-1 l
l I
i l
l l
l l
l t
Page 1 of 1
TABLE 8 DOSE DUE TO LIQUID EFFLUENTS 1981 Organ Dose Limit *
% Limit (mrem)
(mrem)
BONE 1.3E-1 10 1
LIVER 2.3E-1 10 2
TOTAL BODY 1.7E-1 3
6 THYROID 8.9E-3 10 9E-2 KIDNEY 7.5E-2 10 8E-1 LUNG 2.6E-2 10 3E-1 GI-LLI 1.7E-1 10 2
- Annual Dose Limits of Technical Specification 3.11.1.2.
i l
i i
l l
Page 1 of 1
ATTACHMENT 1 CHANGES TO THE PROCESS CONTROL PROGRAM f
I l
l t
I l
l
s "PCP" Date October 9, 1987 Revision 8
O' n+1213 5g,'%
y b
b
--.s t u 1;;l M
- 0 k
p.-r!j,f:Ub 8 dd3h
+
8tzggt$
^
W UNION ELECTRIC COMPANY CALLAWAY PLANT PROCESS CONTROL PROGRAM
/d[/J!O Approved:
w
/Chariman, ORC Da'tel ORC Meeting number Reviewed:
N M/
/ tM7 Su7rintendent, Radwaste
/Datie
/O!/2-Prepared by Date INFORc/: AT;0N C.LY LNCONTROLLED COPl in a me-se i -
m mM
DISCLOSURE STATEMENT The Formulations contained in this doct.nent arc considered proprietary to Union Electric Company and its installed Solid Radwaste System supplier and shall not be duplicated, used, or disclosed outside the Nuclear Regulatory Commission in whole or in part.
{
t l
PCP Rev. 8 10/87
This document contains the following:
Pages 1
through 11 Attachraents 1
through 4
PCP Rev. 8 10/87
TABLE OF CONTENTS Section Page Number
1.0 Purpose and Scope
1 2.0 Definitions 1
3.0 10CFR61 Compliance Methodology 2
4.0 Administrative Controls 2
5.0 Collection and Analysis of Samples 3
5.1 General Requirements 3
5.2 Collection of Samples 4
5.3 Chemical Analysis of Waste Samples 5
S.4 Radiochemical Analysis of Waste Samples 5
6.0 Test Solidification and Acceptance Criteria 6
6.1 Waste Conditioning 6
6.2 Test Solidification 6
6.3 Test Solidification Acceptability 7
7.0 Process Formulations 8
7.1 General Requirements S
7.2 Spent Resins / Charcoal 8
7.3 Chemical Drain Tank Wastes 9
7.4 Evaporator Bottoms 9
8.0 Radioactive Waste Processing Using 9
Contracted Vendor Services 8.1 General Requirements 9
8.2 Control of Vendor Procedurec and Documentation 10 9.0 References 11 l
t I
l l
l 1-l PCP Rev. 8 10/87 1
LIST OF ATTACHMENTS - Resin Solidification Formulations (PROPRIETARY)
' - Concentrated Wastes (Non-Borated) Solidification (PROPRIETARY) - Concentrated fates ' Berated) Solidification (PROPRIETARY) - Sodium Metasilicate Addition (PROPRIETARY) l a
l j PCP Rev. 8 10/87
RECORD OF REVISIONS Revision Number Revision Date Reason for Revision Rev. O October 1983 Initial issue.
Rev. 1 February 1984 Incorporation of NRC review comments.
Rev. 2 December 1984 Revised to generic, non-procedural format; updating of formulations for solidification of wastes.
Rev. 3 March 1985 Added solidification nomogram for concentrated borated wastes and renumbered attachments; clarified sample analysis documentation requirements.
Rev. 4 August 1985 Incorporated Class A "unstable" resin solidification formulation (based upon in-plant testing).
Rev. 5 March 1986 Update solidification formulation nomograms; revised coversheet and "preface" portion of document; removed section dealing with solidification agents from document; made formulations l
propietary documents.
i Rev. 6 April 1986 Incorporated section l
dealing with control l
of ver: dor services for packaging of solid radioactive wastes; revised l
purpose to agree more closely l
with wording shown in Technical l
Specification definition for "Process Control Program" Rev. 7 June 1987 Revised section dealing with contracted vendor services l
to clarify type of services involved.
iii PCP Rev. 8 10/87
RECORD OF REVISIONS l
Rev. 8 September 1987 Revised recorded boundary l
conditions / ratios for batch l
solidification; revised l
acceptance criteria for l
structural stability incor-
-l porated wording regarding l
full scale test solidi-l fication; minor text l
wording changes.
i l
- iv -
PCP Rev, 8 10/87
~
CALLAWAY PLANT PROCESS CONTROL PROGRAM MANUAL (PCP) 1.0 PURPOSE AND SCOPE 1.1 The purpose of the Process Control Program (PCP) is to provide reasonable assurance and documentation that the processing and pack-aging of solid radioactive wastes based on actual or simulated wet solid wastes will be accomplished in such a way as to assure com-pliance with 10CFR20, 10CFR61, 10CFR71, the Radiological Effluent Technical Specifica-tions, Federal and State regulations, burial ground requirements, and other requirements governing the disposal of the radioactive wastes.
1.2 The PCP contains the sampling, tests, analyses, and formulation determination by which waste classification and solidifica-tion of radioactive wastes from liquid sys-tems is assured.
1.3 Processing of radioactive wastes using con-tracted vendor services will be controlled
~
in accordance with Section 8.0 of the Cal-laway Plant PCP.
2.0 DEFINITIONS l
2.1 Solidification - The conversion of wet l
wastes into a form that meets shipping and I
burial ground requirements.
2.2 Batch - A specified quantity of waste j
material requiring soldification any portion of which would have the same physical and chemical characteristics as the whole.
1 2.3 Waste Classification - The determination of waste class as outlined in 10CFR61 by radionuclide isotopic analysis and/or cor-relation with measured nuclides.
l PCP Rev. 8 10/87 !
3.0 10CFR61 COMPLIANCE METHODOLOGY l 3.1 All packaged radioa tive wastes generated at the Callaway Plant shall meet the require-ments of Title 10 Code of Federal Regula-tions Part 61 (10CER61).
3.2 Waste Classification (10CFR61.55) require-ments shall be met by the methodology esta-blished in plant operating procedure (s) gov-erning Waste Classification.
3.3 Waste Characterization (10CFR61.56) require-ments shall be met by a combination of the methodology stated in the Process Control Program (Section 6.0) and related Callaway Plant Operating Procedures.
Stability requirements stated in 10CFR61.56 (b) and by burial site shall be met and ensured prior l
to shipping packaged radioactive waste off-site for burial.
3.4 Additionally, the use of NRC-approved topi-cal reports may be utilised in meeting spe-cific requirements of 10CFR61.
4.0 ADMINISTRATIVE CONTROLS 4.1 All samples shall be handled in accordance with applicable Callaway Plant procedures and in keeping with ALARA principles.
4.2
' Test samples containing radioactive waste and contaminated disposable labware utilized in the performance of the methods described in the PCP shall be disposed of as radioac-tive waste.
4.3 The establishment of effective administra-tive controls governing the use and disposal of oils, greases and chelating agents shall be utilized as a means to control and/or limit the production of wastes containing l
these substances.
In the event that chemi-cal analysis of process wastes for these substances is impractical due to physical restrictions or analtytical constraints, determination of their presence (or absence) shall be made utilizing appropriate evalua-l tion techniques.
i PCP Rev. 8 l
10/87 :
{
5.0 COLLECTION AND ANALYSIS OF SAMPLES 5.1 GENERAL REQUIREMENTS 5.1.1 As required by Radiological Effluent Techni-cal Specification 3.11.3, the PCP shall be used to verify the solidification of at least one representative test sample from at least every tenth batch of each type of wet radioactive waste processed.
5.1.2 For the purpose of the Callaway Plant PCP, a batch shall consist of a particuiar amount of liquid wastes / sludges requiring solidifi-cation (ie., the amount of waste content within a tank requiring solidification, or, the amount of waste content within two tanks requiring solidification if the contents of the two tanks are to be solidified together within a common drum).
If new material is added to a tank's contents which is curren-tly being processed, a new batch is created and further sampling must be performed prior to solidification.
5.1.3 If any sample fails to solidify, solidifica-tion of the batch under test shall be suspended until such time as additional test samples can be obtained, alternative solid-ification parameters can be determined in accordance with the Process Control Program, and a subsequent test verifies l
solidification.
Solidification of the batch may then be resumed using the alternative solidification parameters determined.
5.1.4 If the initial test sample from a batch of j
waste fails to verify solidification, then representative test samples shall be col-lected from each consecutive batch of the t
same type of waste until three (3) conse-cutive initial test specimens demonstrate solidification.
l 5.1.5 For high activity wastes, where handling samples could result in personnel radiation exposures which are inconsistent with ALARA l
principles, representative non-radioactive l
samples may be test solidified.
These sam-l ples shall be as close to the actual waste i
and chemical properties as possible.
Typi-cal unexpended mixed bead resin may be used to simulate the spent bead resin.
l PCP j
Rev. 8 10/87 l l
5.1.6 Where practical, all chemicals used to con-dition or solidify waste (or simulated waste) in solidification tests shall be identical to the actual chemicals to be used in full scale solidification.
~
5.2 COLLECTION OF SAMPLES l
5.2.1 Sample Analysis Documentation 5.2.1.1 Pertinent information on the characteristics of test sample solidification shall be recorded in order to verify solidification of subsequent batches of similar waste without retesting.
5.2.1.2 The test sample data for waste shall in-clude, but is not limited to:
the type of wastes solidified; percent total solids; pH; l
amount of oil in the sample.
5.2.1.3 Additionally, recorded information will in-clude the batch number, waste type, waste classification, total waste received, total portland cement added, total sodium metasil-icate added and the date solidified.
5.2.1.4 If waste pretreatment is necessary prior to actual batch solidification per the results of section 6.1, the agent used and amount added shall be recorded.
5.2.2 Taking Samples 5.2.2.1 A sample (s) of the waste tank's contents requiring solidification shall be taken in order to determine the actual process formu-lation for solidification, any pretreatment of the waste needed prior to solidification, and the waste classification of the final solidified waste product.
5.2.2.1.1 Sample sizes, as determined by the Radwaste Department, shall be compatible with the standard size samples used for radioactivity and chemical analysis.
5.2.2.1.2 If the radioactivity levels are too high to permit full size samples to be taken, then smaller samples shall be taken with the results corrected accordingly.
PCP Rev. 8 10/87 4
5.2.2.2 Sufficient sampling lead time should be al-lotted prior to the planned waste solidifi-cation of a batch to allow adequate time to complete the required testing and verifica-tion of solidification, as applicable.
5.2.2.3 The contents of the waste tanks that are to be solidified shall be recirculated (mixed) prior to sampling to ensure that a represen-tative sample is obtained.
5.2.2.4 If the contents of more than one tank are to be solidified in the same drum, then repre-sentative samples of each tank should be drawn.
5.2.2.4.1 These samples should be of a sufficient com-position that if "X" percent of the total waste to be solidified is to be taken trom one of the tanks, then the sample taken from that tank should be the same percenta;e in the composite sample.
5.2.2.4.2 The samples taken of each should be mixed in the proper proportions to yield a standard size sample as described in 5.2.2.1.1.
5.3 CHEMICAL ANALYSIS OF WASTE SAMPLES 5.3.1 Evaporator bottoms and chemical wastes shall be analyzed for total sclids, oil content, boric acid concentration and pH.
5.3.2 Spent resin beads and,cha. coal shall be characterized by analyzing the water sur-rounding the beads and charcoal for oil con-tent and pH.
Boric acid concentration of spent resin beads shall be determined by an assay of the boric acid separated from the anion bead resin.
5.3.3 Results of chemical analysis shall be documented.
5.4 RADIOCHEMICAL ANALYSIS OF WASTE SAMPLES 5.4.1 A gamma isotopic analysis will be performed on each batch to be solidified.
PCP Rev. 8 10/87 _.
5.4.2 This analysis will be used to determine ac-ceptability for solidification as well as waste classification of the waste to be solidified (see Section 7.0).
5.4.3 The results of the gamma isotopic analysis shall be recorded on/ attached to the docu-mentation package.
6.0 TEST SOLIDIFICATION AND ACCEPTANCE CRITERIA 6.1 WASTE CONDITIONING 6.1.1 Prior to the test sample solidification, the pH of the tank shall be adjusted to a range of 7 to 9 pH.
6.1.1.1 Should adjustment be necessary, the agent and quantity used shall be recorded.
6.1.2 If oil is present in quantities greater than 1% by volume, dilution of the batch to below 1% is required prior to solidification.
6.1.2.1 If reduction of the oil content is impossi-ble or impractical, solidification of the batch shall not be attempted using the Stock Solidification System, but shall be accom, plished using a bulk processing method.
6.2 TEST SOLIDIFICATION 6.2.1 Whenever pretreatment of a batch is neces-sary, the tank contents shall have the required pretreatment accomplished prior to pulling the sample for test. solidification analysis.
l 6.2.2 A test solidification container shall be l
prepared with a mixing device.
This test l
solidification container could either be a l
small sample container, or, in certain ap-l plications, a full scale drum when actual l
full scale testing of a batch may be l
required or desirable.
6.2.3 The appropriate proportional amount of port-land cement and sodium metasilicate, as ap-plicable, determined from the appropriate solidification formulation nomograms / charts (Attachments 1 through 4) shall be added.
PCP Rev. 8 10/87 6.2.4 A known representative volume of the waste shall be transferred to the test solidifica-tion container.
6.2.5 Mixing of the waste, portland cement and sodium metasilicate shall be initiated.
Af-ter appropriate mixing or when a homogenous mixture is obtained, the cement / waste mix-l ture shall be allowed to stand for a speci-fied time period.
6.2.6 Any free liquid observed on the top of the l
test solidification shall be decanted into a clear volumetric beaker (cylinder).
The amount of liquid decan'ted shall be used to calculate the percent free liquid.
Results of this analysis shall be documented.
6.3 TEST SOLIDIFICATION ACCEPTABILITY 6.3.1 The test sample solidification will be con-sidered acceptable from a free liquid stand-point if the amount of free liquid is the lessor of either 1% by volume or burial site limits.
6.3.2 The test sample solidification will be con-sidered acceptable from a solid mass stand-l point (i.e.,
structural stability) if the l
surface of the sample resists penetration j
when probed with a spatula or comparable l
firm object.
6.3.3 If either or both of the above checks fail to meet the stated criteria, the waste sam-pie aniysis and/or the sample solidifica-i tion formula shall be verified as being correct.
6.3.3.1 If this verification shows an error in waste sample analysis or sample solidification l
formula,a corrected solidification formula l
shall be obtained and sample solidification l
performed using this corrected formula.
6.3.3.2 In the event that the analysis and formula previously derived and used are correct, al-ternative solidification parameters shall be determined before solidification can proceed.
(
PCP l
Rev. 8 10/87 l
1 6.3.4 If the initial test solidification of a batch is. unacceptable, then a representative sample shall be test solidified on each sub-sequent batch of the same type of waste un-til three consecutive test samples demon-strate solidification.
6.3.5 If a test sample fails to protide acceptable solidification of waste, equal volumes of dry cement and water shall be mixed to en-sure that the problem is not due to a bad batch of cement.
7.0 PROCESS FORMULATIONS 7.1 GENERAL REQUIREMENTS l 7.1.1 Prior to batch solidification of the waste to be solidified, waste classification and acceptability for near-surface disposal shall be determined.
This will involve cal-culating the activity within the projected waste drums using the isotopic analysis determined per section 5.4 and the actual solidification formulas to be used.
7.1.2 Solidification formulations are based upon use of formulations / nomograms shown as Attachments 1 through 4 dependant upon the chemical analysis and type of waste to be solidified.
7.1.2.1 Instructions for use of these nomograms shall be described in plant operating procedures.
7.2 SPENT RESINS / CHARCOAL 7.2.1 Spent resins / charcoal shall be solidified utilizing the formulations of Attachment 1, Resin Solidification Formulas, and the oper-ating sequences specified in plant operating procedures.
7.2.2 In the event that the boric acid assay of the bead resin yields boric acid in excess of 33.33 mg/ml, a corresponding amount of sodium metasilicate per Attachment 4, Sodium Metasilicate Addition, shall be added.
I PCP l
Rev. 8 10/87 _
v 7.3 CHEMICAL DRAIN TANK WASTES 7.3.1 Chemical Drain Tank Wastes shall be solidi-fied utilizing the formulation nomogram of, Concentrated Wastes (Non-Borated) Solidification, and the oper-ating sequences specified in plant operating procedures.
7.3.2 In the event the boric acid analysis of the waste sample yields boric acid in excess of 33.33 mg/ml, solidification shall be based upon the formulation nomogram of, Concentrated Wastes (Borated)
Solidification, with a corresponding amount of sodium metasilicate per Attachment 4, Sodium Metasilicate Addition, added.
7.4 EVAPORATOR BOTTOMS 7.4.1 Evaporator Bottoms shall be solidified util-izing the formulation nomogram of, Concentrated Wastes (Non-Borated) Solidification, and the oper-ating sequences specified in plant operating procedures.
7.4.2 In the event the boric acid antlysis of the waste sample yields boric acid in excess of 33.33 mg/ml, solidification shall be based upon the formulation nomogram of
-, Concentrated Wastes (Borated)
Solidification, with a corresponding amount of sodium metasilicate per Attachment 4, Sodium Metasilicate Addition, added.
8.0 RADIOACTIVE WASTE PROCESSING USING CON-TRACTED VENDOR SERVICES 8.1 GENERAL REQUIREMENTS 8.1.1 As required by Technical Specification 3/4.11.3.c, contracted vendor services shall be provided to process and package radioac-tive wastes to the required waste form to satisfy the applicable transportation and disposal requirements for those instances when the installed solid radioactive waste system is incapable of processing these wastes.
PCP Rev. 8 10/87 9_
8.1.2 Contracted vendor services will be esta-blished for the packaging of wet radioactive wastes by vendor solidification and/or dewatering.
l 8.1.3 Contracted vendor services may be exercised when, in the opinion of plant management, any of the following conditions exist:
8.1.3.1 The installed system is declared out-of-service thereby reducing or eliminat-ing the capability of Callaway Plant to ef-ficiently and legally package radioactive wastes in accordance with all applicable requirements governing the disposal of the wastes; or, 8.1.3.2 The installed system is incapable of packag-ing these wastes in accordance with any of the applicable requirements (e.g.,
10CFR61.)
governing the disposal of these wastes; or, 8.1.3.3 When processing and packaging economics show an increased cost efficiency of vendor processing versus installed system processing.
8.1.4 Specific programmatic controls for these services will be handled in accordance with the vendor's Quality Assurance program.
This program shall be approved by Union Electric Quality Assurance prior to imple-mentation of the contracted services.
8.2 CONTROL OF VENDOR PROCEDURES AND DOCUMENTA-TION 8.2.1 Vendor Procedure Control 8.2.1.1 Vendor procedures covering equipment setup, operation, and removal shall be reviewed and approved in accordance with plant adminis-trative procedures prior to implementation.
l l
1 I
PCP l
Rev. 8 l
10/87
-lo-
8.2.1.2 Vendor procedures covering the vendor's Pro-cess Control Program (PCP) in addition to the review and approval mentioned above shall also be reviewed and approved by the Onsite Review Committee prior to implementation.
8.2.1.2.1 The vendor PCP shall provide for the sam-pling, tests, analyses and formulation determination, where applicable, as required by plant Technical Specifications covering the Callaway Plant PCP.
8.2.1.2.2 Results of all testing and analyses shall be documented, as necessary, to ensure com-pliance with the vendor PCP and all applica-ble transportation and burial ground requirements governing these wastes.
8.2.2 Control of Vendor Documentation 8.2.2.1 Copies of all documentation attesting to compliance with the requirements of the ven-dor PCP as well as any plant operating procedures utilized in support of the con-tracted vendor service shall be retained by the plant for inclusion in plant files.
8.2.2.2 Documentation containing proprietary in-formation shall be appropriately handled and controlled to ensure the required degree of confidentiality is met.
9.0 REFERENCES
9.1 STOCK EQUIPMENT COMPANY, General Process l
Control Program (M-135-0457) 9.2 10CFR2O 9.3 10CFR61 9.4 10CFR71 9.5 Reg. Guide 8.8 9.6 Radiological Effluent Technical Specifica-tion 3.11.3 l
l l
PCP Rev. 8 10/87 )
ATTACHMENT 2 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL i
1 4
l l
i l
l
Roar. 4 gfcNC04 ISSUED FEB 251987..
UNION ELECTRIC COMPANY ACCOUNTABLE Hp[i,SER CALLAWAY PLANT
/
OFFSITE DOSE CALCULATION MANUAL
.2,23/p7 6 4/ f Approved:
Au I
Chairman, ORC I
/
Date ORC meeting Reviewed:
/hd ff/7
~
Super 1r epd nt, Health Physics 2atle I
Prepared By:
6M h 2 //J /87 Supervisor, H.
P. Tech. Support Date l
l l
l 1
R'v. 4 I !
This document contains the following:
Pages 1
through 104 Tables 1
through 12 Figures 4.1, 5.1A, 5.1B, 5.2A,. 5.2B, 5.3 4
i 1
i
,--..---...-;-w_~.--.
r:
Rev. 4 Table of Contents Page 1.0 PURPOSE AND SCOPE 1
2.0 LIQUID EFFLUENTS 2
l 2.1 TECHNICAL SPECIFICATION 3.3.3.10 2
2.2 LIQUID EFFLUENT MONITORS 2
2.2.1 Continuous Liquid Effluent Monitors 4
2.2.2 Radioactive Liquid Batch Release Effluent Monitors 5
2.3 ODCM METHODOLOGY FOR THE DETERMIN-ATION OF LIQUID EFFLUENT MONITOR SETPOINTS 6
2.3.1 Development of ODCM Methodology for the Determination of Liquid Effluent Monitor Setpoints 6
2.3.2 Summary, Setpoint Determination Methodology for Liquid Effluent Monitors 12 2.4 LIQUID EFFLUENT CONCENTRATION MEASUREMENTS 12 l 2.4.1 Technical Specification 3.11.1.1 12 2.4.2 Liquid Effluent Concentration Measurements 12 2.5 INDIVIDUAL DOSE DUE TO LIQUID EFFLUENTS 13 l 2.5.1 Technical Specification 3.11.1.2 13 2.5.2 The Maximum Exposed Individual 13 2.5.3 ODCM Methodology for Determining Dose Contributions from Liquid Effluents 13
-i-
Rov. 4 Table-of Contents (continued)
Page
-2.5.3.1 Calculation of Dose Contributions 13 2.5.3.2 Dose Factor Related to Liquid Effluents 15 2.5.4 Summary, Determination of Individ-ual Dose Due to Liquid Effluents 17 2.6 LIQUID RADWASTE TREATMENT SYSTEM 21 l 2.6.1 Technical Specification 3.11.1.3 21 2.6.2 Description of the Liquid Radwaste Treatment System 21 2.6.3 Operability of the Liquid Radwaste Treatment System 21 3.0 GASEOUS EFFLUENTS 22 3.1 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATION 3.3.3.11 22 l
3..
TECHNICAL SPECIFICATION 3.11.2.1 22 3.3 GASEOUS EFFLUENT MONITORS 22 3.3.1 Continuous Release Gaseous Effluent Monitors 23 3.3.2 Batch Release Gaseous Monitors 25 3.4 ODCM METHODOLOGY FOR THE DETERMIN-ATION OF GASEOUS EFFLUENT MONITOR SETPOINTS 26 3.4.1 Development of ODCM Methodology for the Determination of Gaseous Effluent Monitor Setpoints 26 3.4.1.1 Total Body Dose Rate Setpoint Calculations 26 3.4.1.2 Skin Dose Rate Setpoint Calculation 28 3.4.1.3 Gaseous Effluent Monitors Setpoint Determination 29
=
R.v. 4 Table of Contents (continued)
Page 3.4.2 Summary, Gaseous Effluent Monitors Setpoint Determination 31 3.5 ODCM METHODOLOGY FOR DETERMINIFG DOSE CONTRIBUTIONS FROM GASEOUS EFFLUENTS 31 3.5.1 Determination of Dose Rate 31 3.5.1.1 Noble Gases 31 3.5.1.2 Radionuclides Other Than Noble Gases 32 3.5.2 Individual Dose Due to Noble Gases 38 l 3.5.2.1 Technical Specification 3.11.2.2 38 3.5.2.1.1 Noble Gases 38 l 3.5.2.2 Technical Specification 3.11.2.3 39 3.5.2.2.1 Radionuclides Other Than Noble Gases 40 3.6 GASEOUS RADWASTE TREATMENT SYSTEM 61 l 3.6.1 Technical Specification 3.11.2.4 61 3.6.2 Description of the Gaseous Radwaste Treatment System 61 3.6.3 Operability of the Gaseous Radwaste Treatment System 61 4.0 DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES 62
[ 4.1 TECHNICAL SPECIFICATION 3.11.4 62 4.2 ODCM METHODOLOGY FOR DETERMINING DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES 62 4.2.1 Identification of the MEMBER 63 OF THE PUBLIC
-111-
R v. 4 Table of Contents (continued)
Page 4.2.1.1 Utilization of Areas Within the SITE BOUNDARY 63 4.2.2 Total Dose From Gaseous Effluents 64 4.2.3 Total Dose From Direct Radiation 64 4.2.3.1 Direct Radiation From Outside Storage Tanks 64 4.2.3.2 Direct Radiation From the Reactor 67 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 68 l 5.1 TECHNICAL SPECIFICATION 3.12.1 68
5.2 DESCRIPTION
OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 68 6.0 DETERMINATION OF ANNUAL AVERAGE AND SHORT TERM ATMOSPHERE DISPERSION PARAMETERS 84 6.1 ATMOSPHERE DISPERSION PARAMETERS 84 6.1.1 Long Term Dispersion Estimates 84 6.1.1.1 The PUFF Model 84 6.1.1.2 The Straight-Line Gaussian Diffusion Model 85 6.1.1.2.1 Mixed Mode and Elevated Release Model 86 6.1.1.2.2 Gound-Level Release Model 86 i
6.1.1.2.3 Decay, Depletion, and Deposition Methodology 87 I
6.1.2 Short Term Dispersion Estimates 88 6.1.2.1 The Determination of the Slope Factor (S) 90 7.0 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 94 i
-iv-
Rev. 4 Table of Contents (continued) r Page 8.0 IMPLEMENTATION OF ODCM METHODOLOGY 96 9.0 REFF.<ENCES 97-9
-V-
R'v. 4 List of Fiqures Figure 4.1 Site Area Closed to Public Use Figure 5.1A Airborne & TLD Sampling Network Figure 5.1B Airborne & TLD Sampling Network Figure 5.2A Location of Aquatic Sampling Stations Figure 5.2B Location of Aquatic S$mpling Stations Figure 5.3 Food Products Sampling Locations
-vi-
Rev; 4 List of Tables Page Table 1 Ingestion Dose Commitment Factor.
(A,) for Adult Age Group 19 1
Table 2 Bioaccumulation Factor (BF ) Used 1
in the Absence of Site-specific Data 22 Table 3 Dose Factors for Exposure to A Semi-Infinite Cloud of Noble Gases 33 Table 4 Dose Parameter (P ) for Radio-g nuclides Other Than Noble Cases 38 Table 5 Pathway Dose Factors (R ) for Radionuclides Other Than Noble Cases 46 Table 6 Radiological Environmental Monitoring Program 73 Table 7 Reporting Levels for Radioactivity Concentrations in Environmental Samples 81 Table 8 Maximum Values for the Lower Limits of Detection 82 l
Table 9 Highest Annual Average Atmospheric l
Dispersion Parameters - Radwaste l
Building Vent 92 Table 10 Highest Annual Average Atmospheric Dispersion Parameters - Unit Vent 93 Table 11 Short Term Dispersion Parameters 94 Table 12 Application of Atmospheric Dispersion Parameters 95 l
-vil-
R*v.
4 Record of Revisions Revision Number Date Reason for Revision Rev. O March 1983 Rev. 1 November 1983 Revised to support the current RETS submittal and to incorporate NRC Staff comments Rev. 2 March 1984 Revised to incorporate NRC Staff comments Rev. 3 June 1985 Revised to incorporate errata identified by ULNRC-803 and changes to the Environmental Monitoring Pie, gram.
Incorporate results of 1984 Land use Census.
l Rev. 4 February 1987 Minor clarifications, l
incorporated 31-day l
proj ected dose methodology.
I change in the utilization I
of areas within the Site s
l Boundary.
-viii-
Rrn. 4 1.0 PURPOSE AND SCOPE The Offsite Dose Calculation Manual (OLCM) describes the methodology and parameters used in the calculation of offsite doses and dose rates due to radioactive liquid and gaseous effluents and in the calculation of liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints.
The CDCM also contains a list and description of the specific sample locations for the radiological environmental monitoring program.
Changes in the calculational methodologies or paramet-ers will be incorporated into the ODCM and documented in the Semi Annual Radioactive Effluent Release Report.
The ODCM does not replace any station implementing procedures.
4 1-1
,g
-r
Rev. 4 2.0 LIQUID IFFLUENTS t 2.1 Technical Specification 3.3.3.10 4
The radioactive liquid effluent monitoring instrumenta-tion channels shall be OPERABLE with their alarm / trip l setpoints set to ensure that the limits of Technical Specification 3.11.1.1 are not exceeded.
The alarm / trip setpoints of these channels shall be ad-justed to the values determined in accordance with the methodology and parameters in'the ODCM.
2.2 Liquid Effluent Monitors Gross radioactivity monitors which provide for au-tomatic termination of liquid effluent releases are 4
present on the liquid effluent lines.
Flow rate meas-1 urement devices are present on the liquid effluent lines and the discharge line (cooling tower blowdown).
1 Setpoints, precautions, and limitations applicable to the operation of the Oallaway Plant liquid effluent monitors are provided in the appropriate Plant Proca-dures, which are contained in Volume 6 of the Plant operating Manual.
Setpoint values are calculated to asnure that alarm and trip actions occur prior to ex-i ceeding the Maximum Permissible Concentration (MPC) limits in 10 CFR Part 20 at the release point to the UNRESTRICTED AREA.
The calculated alarm and trip ac-tion setpoints for the liquid effluent line monitors and flow measuring devices must satisfy the following equation:
i i
l cf
~ C F+f (2.1) l i
Where:
C=
the liquid effluent concentration limit (MPC) l implementing Technical Specification 3.11.1.1 for the site in (vCi/ml).
e=
The setpoint, in (vC1/ml), of the radioactiv-ity monitor measuring the radioactivity concentration in the effluent line prior to -
~
- =x -.
m R v. 4 dilution and subsequent release; the setpoint, which is inversely proportional to the volumetric flow of the affluent line and directly proportional to the volumetric flow of the dilution stream plus the effluent stream, represents a val e, which, if ex-coeded, would result in concentrations exceed-ing the.'.imits of 10 CFR Part 20 in the UNRES-TRICTED AREA.
f=
The flow setpoint as measured at the radiation monitor location, in volume per unit time, but in the same units as F, below.
F=
The dilution water flow setpoint as measured prior to the release point, in volume per unit time.
(If (F) is large compared to (f), then F + f = F).
(Ref. 9.8.1)
If no dilution is provided, then c $ C.
The radioactive liquid waste stream is diluted by the plant discharge line prior to entry into the Missouri River.
Normally, the dilution flow is obtained from the cooling tower blowdown, but should this become unavailable, the plant water treatment facility sup-plies the necessary dilution flow via a bypass line.
The batch release limiting concentration (c) which cor-responds to the liquid radwaste effluent line monitor setpoint is to be calculated using methodology from the expression above.
Thus, the expression for determining the setpoint on the liquid radwaste effluent line monitor becomes:
c$
C(F + f)
(VCi/ml) f (2.2) l 4 e
i
~
_ _ _ = _ __-___ _ _
n Asv. 4 2.2.1 Continuous Liquid Effluent Monitors The radiation detection monitors associated with conti-nuous liquid effluent releaaea are (Ref. 9.6.1, 9.6.2):
Monitor I.D.
Description l
BM-RE-52 Steam Generator Blowdown Discharge Monitor l
LE-RE-59 Turbine Building Drain Monitor These affluent streams are not considered to be radi-oactive unless radioactivity has been detected by the associated effluent radiation monitor or by laboratory analysis.
The sampling frequency, minimum analysis frequency, and type of analysis performed are as per l Technical Specification Table 4.11-1.
The steam generator blowdown discharge monitor conti-nuously monitors the blowdown discharge pump outlet to detect radioactivity due to system demineralizer break through and to provide backup to the steam generator blowdown process radioactivity monitor to prevent dis-charge of radioactive fluid.
The sample point is located on the discharge of the pump in order to moni-tor-discharge or recycled blowdown fluid and upstream of the discharge isolation valve to permit termination of the radioactive release prior to exceeding the in-stantaneous concentration limits of 10 CFR Part 20.
The high radioactivity alarm / trip (alarm and trip) set-point initiates control room alarm annunciation and au-7 tomatic isolation of the blowdown isolation valves and the blowdown discharge valve.
The turbine building drain effluent monitor is provided to monitor turbine building liquid effluents prior to release to the environs.
The fixed-volume detector as-sembly continuously monitors the drain effluent line upstream of the drain line isolation valve.
The high radioactivity alarm / trip setpoint initiates control room annunciation and automatic isolation of the drain line isolation valve to prevent the release of radioac-tive fluids.
The sample location ensures that all potentially radioactive turbine building liquid ef-fluents are monitored prior to discharge.
Each monitor channel is provided with a two level sys-tem which provides sequential alarms on increasing 4 -u-,-._-.._-
~. -
Rev. 4 Each monitor channel is provided with a two level sys-tem which provides sequential alarms on increasing radioactivity levels.
These setpoints are designated as alert setpoints and alarm / trip setpoints.
(Ref.
9.6.3)
The alarm / trip setpoints are determined through the use l of Equation (2.2) methodology to ensure that Technical Specification 3.11.1.1 limits are not exceeded at the UNRESTRICTED AREA.
The alert setpoints have been ad-ministratively established below the alarm / trip set-points, thus providing an additional margin of safety.
The alarm / trip sotpoint calculations are based on the minimum dilution flow rate (cooling tower blowdown, 5000 gpm), the maximum effluent stream flow rate, and the actual isotopic analysis.
Due to the possibility of a simulataneous release from more than one release pathway, a portion of the totel site release limit is allocated to each pathway.
The determination and usage of the allocation factor is discussed in Section 2.3.1.
In the event the alarm / trip setpoint is reached, the radiation monitor setpoint (c), will be reevaluated us-ing the actual dilution flow rate (F), the actual ef-fluent stream flow rate (f), and the actual isotopic analysis.
This evaluation will then be used to ensure that Radiological Effluent Technical Specification 3.11.1.1 limits were not exceeded.
2.2.2 Radioactive Liquid Batch Release Effluent Monitor The two radiation monitors which are associated with the liquid effluent batch release systems are (Ref.
9.6.4, 9.6.5):
MONITOR I.D.
Description l
EB-RE-18 Liquid Radwaste Discharge Monitor l
EF-RE-45 Secondary Liquid Waste System Monitor The liquid radwaste radiation monitor continuously monitors the discharge of the liquid radwaste process-ing system to prevent the discharge of radioactive fluid to the environs.
The fixed-volume detector as-sembly continuously monitors the system discharge line upstream of the discharge valve.
The high radioactiv-.
Rr.v. 4 ity alarm / trip setpoint initiates control room alarm annunciation and automatic isolation of the liquid rad-waste system discharge valve to terminate discharge.
The sample point is located to ensure that all potenti-ally radioactive fluids from the liquid radwaste processing system are monitored prior to discharge.
The secondary liquid waste system discharge radioactiv-ity monitor continuously monitors secondari liquid waste system effluents prior to discharge to the environs.
The fixed-volume detector assembly monitors the discharge line upstream of the discharge isolation valve.
The high radioactivity alarm / trip setpoint ini-tiates control room alarm annun,ciation and automatic isolation of the secondary liquid waste system dis-charge valve to prevent the discharge of radioactive fluid.
The sample location ensures that all potenti-ally radioactive sourcer from the system are monitored prior to discharge.
The setpoint for these monitors is determined according to the methodology described by Equation (2.2) and is a function of the dilution flow rate (F), the radioactive effluent line flow rate (f) and the tank liquid ef-fluent concentration, as determined by a pre-release isotopic analysis.
Based on these factors, a setpoint is calculated for the appropriate monitor to ensure I that Technical Specification 3.11.1.1 limits a.c not exceeded at the UNRESTRICTED AREA (Figure 5.2A,.
2.3 CDCM Methodolegy for the Determination of Liquid Effluent Monitor Setpoints The dependence of the setpoint (c), on the radionuclide distribution, yields, calibration, and monitor paramet-i ers, requi res that several variables be considered in I
setpoint calculations.
(Ref. 9.8.1) 1 l
2.3.1 Development of ODCM Methodology for the Determination of Liquid Effluent Monitor Setpoints l
The isotopic concentration of the release being consid-l ered must be determined.
This is obtained from the sum l
of the measured concentrations as determined by the l analysis required per Technical Specifications Table 4.11-1:
1 i
l l l
l
.1__
l Rev. 4
+C (2.3)
C = (I (C )1) + C, + C3+Ct F
T g
g Where:
CT=
the total concentration of radionuclides as determined by the analysis of the waste sample.
I(C )1 = the sum of the concentrations (C ) of each g
g measured gamma emitting nuclide observed by gamma-ray apectroscopy of the waste sample.
C,*
=
the measured concentrations (C,) of alpha em-itting nuclides observed by gross alpha l
analysis.
C*=
the measured concentrations of Sr-89 and Sr-90 s
in liquid waste as determined by analysis of the quarterly composite sample.
C*=
the measured concentration of H-3 in liquid t
l waste.
C*=
the measured concentration of Fe-55 in liquid F
waste as determined by analysis of the quar-terly composite sample.
The C term is included in the analysis of each batch; q
l terms for alpha, Sr-89, Sr-90, Fe-55, and tritium are included as appropriate.
- Values for these concentrations will be based on previous composite sample analyses as required by l Table 4.11-1 of Technical Specifications.
The measured radionuclide concentrations are used to calculate a Dilution Factor (F ), which is the ratio of d
total dilution flow rate to tank flow rate required to l assure that the limiting concentrations of Technical Specification 3.11.1.1 are met at the point of discharge.
This is referred to as the required Dilu-tion Factor and is determined according to:..
-_a
Rsv. 4 (C )1 C,
C,
+
+
C
+
C g
+
t F
Fd=i
+ F 4
g (MPC,)g
s Nhere:
l C,
C,, C,,
C, C g
t F=
measured concentrations as defined in 2.3.1.1.
Terms C,, C,,
C, and C F
t will be included in the calculation as appropriate.
= are limiting concentra-g F,
t tions of the appropriate radionuclides from 10CFR 20, Appendix B, Table II, Column 2.
For dissolved or entrained noble gases, the concentration shall be limited to
~
2x10 ' VCi/ml total activity.
F, =
the safety factor; a conservative factor used to compensate for statistical fluctuations and errors of measurements.
(For example, F3 = 0.5 corresponds to a 100 percent variation.)
Default value is F
= 0.9.
g Rav. 4 For the case Fd<1, the m nit r tank effluent concen-tration meets the limits of Radiological Effluent Tech-nical Specification 3.11.1.1 without dilution and the effluent may be released at any desired flow rate.
If Ed > 1 then dilution is required to ensure compliance l with Technical Specification 3.11.1.1 concentration limits.
If simultaneous releases are occuring or are anticipated, a modified dilution factor (Fdn), must be determined so that available dilution flow may be ap-portioned among simultaneous discharge pathways.
Fdn = Fd+F, (2.5)
Where:
F, =
the allocation f actor which will modify the required dilution factor such that simultaneous liquid releases may be made l
without exceeding the limits of Technical Spe-cification 3.11.1.1.
The most straight-forward determination of the alloca-tion factor is:
l F, = f (2.6) l Where:
n=
the number of liquid discharge pathways for which Ed > 1 and which are planned for simultaneous release.
However, this value for F, may be unnecessarily res-trictive in that all release pathways are apportioned the same fraction of the available dilution stream,
_g.
Rcv. 4 regardless of the relative concentrations of each of the sources.
Since the radionuclide concentration of the two conti-nuous sources is less than that of the batch release source, it is acceptable to allocate smaller portions of the dilution stream to the continuoue releases and a larger portion to the batch releases.
Therefore, F, is necessarily defined as a flexible quantity with a default value of 1/n.
Prior to initi-ating a simultaneous release, a check must be made to assure that the sum of the allocation factors assigned to pathways for the simultaneous release is 5 1.
The calculated maximum permissible waste tank effluent flow rate, (f,,x), is based on the modified dilution factor, (Fdn), and the effective dilution flow rate, (F,gg).
The effective dilution flow rats is given by:
F,fg = (0.9)F, (2.7)
Where:
F, =
the cooling tower blowdown flow rate and/or bypass dilution flow.
A conservative value for F, would be the minimum allow-able cooling tower blowdown of 5000gpm which is used as a default value.
l l
I 1
1 1 n _,, _. _ - _ _
Rtv 4
Having established the values of F.i and F,gg, the cal-d culated maximum permissible waste tank flow rate can be calculated by.
F
+f F
f,,x 5
eff p,
eff (for fp << F,gg)
(2.8)
F F
dn dn i
Where:
f
= the expected undiluted effluent flow rate.
p Thus, the effluent flow rate is set at or below f,,x.
Even though the value of f,,x may be larger than the actual effluent pump capacity, (f ),
it does represent p
the upper limit to the effluent flow rate whereby the l requirements of Technical Specification 3.11.1.1 may still be met.
If F 51, the effluent flow rate set-d i
point may be assigned any value since the waste tank l
l effluent concentration meets the limits of Technical Specification 3.11.1.1 without dilution and the release may be made without regard to the setpoints for other release pathways.
For those discharge pathways selected to be secured during the release under consid-eration, the flow rate setpoint should be set at as low l
a value as practicable to detect any inadvertent l
release.
l l
The liquid radiation monitor setpoint may now be deter-mined based on the values of C, and f,,x, which were T
l specified to provide compliance with the limits of Technical Specification 3.11.1.1.
The monitor response is primarily to gamma radiation, therefore, the actual setpoint is based on I(Cg)1 The 1
calculated monitor setpoint concentration is determined as follows:
11 -
Rsv. 4 c = A I(Cg)1 Ci_
i ml (Refer to Note (2.9)
Following)
Where:
A=
Adjustment factor which will allow the set-point to be established in a practical manner for convenience and to prevent spurious alarms.
A = # max (Refer to Note (2.10) f Following) p If A > 1: Calculate c and determine the maximum value for the actual monitor setpoint (uci/ml).
If A 5 1:No release may be made.
This condition must i
be flagged and the operator instructed to re-evaluate F and F,gg (i.e.,
reduce effluent dn i
flow rate or return radwaste for reprocessing).
i NOTE If Fd < 1, no further dilution is required and the release may be made without regard to available dilu-tion or to other releases made simultaneously.
How-ever, it is necessary to establish a monitor setpoint which will provide alarm should the release concentra-l
[ tion inadvertently exceed Technical Specification l
3.11.1.1 limits.
This can be accomplished by esta-L blishing the adjustment factor as follows:
l A=
1 (2.11)
Fd l.
O
Rev. 4 2.3.2 Summary, Setpoint Calculation Methodology for Liquid Effluent Monitors The methodology described in 2.3.1 is used to determine setpoints for each of the radiation monitors assigned I an effluent monitoring function.
The limiting release concentration can be increased by reducing the dis-l charge flow-rate and by increasing the cooling tower blowdown flow-rate.
2.4 Liquid Effluent Concentration Measurements l 2.4.1 Technical Specification 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-04 pCi/ml total activity.
2.4.2 Liquid Effluent Concentra1 ton Measurements Liquid batch releases are discharged as a discrete volume and each release is authorized based upon the sample analysis and the dilution flow rate existing in the discharge line at time of release.
To assure re-presentative sampling, each liquid monitor tank is isolated and thoroughly mixed by recirculation of tank contents prior to sample collection.
The methods for mixing, sampling, and analyzing each batch are outlined in applicable plant procedures.
The allowable release rate limit is calculated for each batch based upon.the pre-release analysis, dilution flow-rate, and other procedural conditions, prior to authorization for i
release.
The radwaste liquid effluent discharge is monitored prior to entering the dilution discharge line and will automatically be terminated if the pre-selected alarm / trip setpoint is exceeded.
Concentra-l tions are determined primarily from the gamma isotopic, l
l H-3,
& gross alpha analyses of the liquid batch sample.
l For Sr-89, Sr-90, & Fe-55, the measured concentration from the previous composite analysis is used.
Compo-site samples are collected for each batch release and l
l quarterly analyses are performed in accordance with l Technical Specification Table 4.11-1.
13 -
i l
l l
.m.
~
- - - *. u
~, au Rav. 4
. K -"
j,.,
Dose contrib&tions rom liquids discharged as conti-
~
nuous releases are determined by utilizing the last measured values of samples required in accordance with l Technical Specifications Table 4.11-1.
2.5 Individual Dose Due to Liquid Effluents 2.5.1 Radiological Effluent Technical Specification 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, to UNRESTRICTED AREAS shall be limited:
a.
During any calendar quarter to less than or equal to 1.5 mrem to the whole body and less than or equal to 5 mrem to any organ, and b.
During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
2.5.2 The Maximum Exposed Individual The cumulative dose determination considers the dose contributions from the maximum exposed individual's consumption of fish and potable water, as appropriate.
Normally, the adult is considered to be the maximum ex-posed individual.
(Ref. 9.8.3, 9.8.4)
The Callaway Plant's liquid effluents are discharged to the Missouri River.
As there are no potable water in-takes within 50 miles of the discharge point (Ref.
9.7.1, 9.6.6), this pathway does not require routine evaluation.
Therefore, the dose contribution from fish consumption is expected to account for more than 95% of the total man-rem dose from discharges to the Missouri River.
Dose from recreational activities is expected to contribute the additional 5%, which is considered to be negligible.
(Ref. 9.6.7) 1 -
Rnv. 4 2.5.3 ODCM Methodology for Determining Dose Contributions From Liquid Effluents 2.5.3.1 Calculation of Dose Contributions The dose contributions for the total time period m
IAt g t=1 are calculated at least once each 31 days and a cumula-tive summation of the total body and individual organ doses is maintained for each calendar quarter.
These dose contributions are calculated for all radionuclides identified in liquid effluents released to UNRESTRICTED AREAS using the following expression (Ref. 9.8.3) m D = I (A I At C F)
(2.12) g g
gg g
i g,y Where:
the cumulative dose commitment to the total t =
body or any organ, t,
from the liquid ef-l fluents for the total period l
m IAt t
j t=1 i
in mrem.
the length of the tth time period over which At =
g C
and F are averaged for all liquid 1g g
releases, in hours.
the average measured concentration of radionu-C
=
ig
- clide, 1,
in undiluted liquid effluent during time period At from any liquid release, in g
l (pCi/ml).
1 m.
r L
Rnv. 4 the site related ingestion dose commitment A
=
1 factor to the total body or any organ t for each identified principal gamma and beta emit-l ter listed in Technical Specifications, l
Table 4.11-1, (in mrem /hr) per (uCi/ml).
These f actors are given in Table 1, as derived through the use of Equation (2.16).
Ft =
the near field average dilution factor for C gg during any liquid effluent release.
f l
t=
' max l
(f, + f,,x) 89.77 l Where:
l f
=
maximum undiluted effluent flow rate during max i
the release i
f, =
average flow rate from the site discharge j
structure to unrestricted receiving waters l
(dilution flow) l 89.77 =
site specific applicable factor for the mixing l
effect of the discharge structure. (Ref 9.5.1) l The term C is the undiluted concentration of radioac-gg tive material in liquid waste at the common release l point determined in accordance with Technical Specifi-l cation 3.11.1.1, Table 4.11-1, "Radioactive Liquid l Waste Sampling and Analysis Program".
All dilution f actors beyond the sample point (s) are included in the F term.
g 16 -
Rsv. 4 2.5.3.2 Dose Factor Related to Liquid Effluents Calcuiating dose contributions via Equation (2.13) requires the use of a dose factor A for each nuclide, gt i, which embodies the dose factors, pathway transfer factors (e.g., bioaccumulation factors), pathway usage factors, and dilution factors for the points of pathway origin.
The adult total body dose factor and the maxi p mum adult organ dose factor for each radionuclide is used from Table E-11 of Regulatory Guide 1.109; thus, Table 1 contains critical organ dose factors for various organs.
The dose factor is calculated accord-ing to (Ref. 9.8.4):
f w/ w
- F i) i
(
)
A it o
Where:
composite dose parameter for the total body or A
=
it critical organ of an adult for nuclide, i, for all appropriate pathways, as (mrem /hr) per (pCi/ml).
k, =
units conversion factor, derived.according to:
1.14E05 = (1E06pci/pCi x 1E03ml/kg) + 8760 hr/yr.
adult fish consumption factor, equal to U
=
F 21kg/yr (Regulatory Guide 1.109, Table E-5).
BFg=
Bioaccumulation factor for nuclide, i, in fish (Table 2), as (pCi/kg) per (pCi/t).
DF1=
Dose conversion factor for nuclide, i, for adults in pre-selected organ, t,
as (mrem /pC1)
(Regulatory Guide 1-109, Table E-11).
receptor individual's water consumption by age U
=
y group as per Regulatory Guide 1.109, Table E-5.
For adults, U
= 730kg/yr.
y -.
Rnv. 4 dilution factor from the near field area D
=
within one-quarter mile of the release point to the potable water intake for the adult water consumption.
NOTE The nearest municipal potable water intake downstream from the liquid effluent discharge point into the Mis-souri River is located near the city of St. Louis, Mo.,
approximately 78 miles downstream.
As there are cur-rently no potable water intakes within 50 river miles of the discharge point, the drinking water pathway is not included in dose estimates to the maximally exposed individual, or in dose estimates to the population.
Should future water intakes be constructed within 10 river miles downstream of the discharge point, then this manual will be revised to include this pathway in dose estimates.
(Ref. 9.6.6).
Therefore, it is not necessary to evaluate (U /Dy) at this time, and y
Equation (2.13) simplies to:
A
=k (U BF )DF (2.14) g o
F f
1 Inserting the appropriate usage factors from Regulatory Guide 1.109 into Equation (2.14) yields the following expression:
A
= 1.14E05 (21BF )DF (2.15) gt g
1 or A
= 2.39E06 x BF x DF (2.16) gt 1
1 18 -
v Rev. 4 2.5.4 Summary, Determination of Individual Dose Due to Liquid Effluents The dose contribution for the total time period m
IAt t
t=1 is determined by calculation at least once per 31 days and a cumulative summation of the total body and organ doses is maintained for each calendar quarter.
The l projected dose contribution from liquid effluents for which radionuclide concentrations are determined by l periodic composite and grab sample analysis, may be ap-l proximated by using the last measured value.
Dose con-tributions are determined for all radionuclides identi-fied in liquid effluents released to UNRESTRICTED AREAS.
Nuclides which are not detected in the analyses are reported as "less than" the nuclide's Minimum Detectable Activity (MDA) and are not reported as being present at the LLD level for that nuclide.
The "less than" values are not used in the required dose calculations.
l l
19 -
l l
r
Rev. 4 TABLE 1 INGESTION DOSE COMMITMENT FACTOR (Ah) FOR ADULT AGE GROUP (mrem-hr per uci-ml) i I
I l Total l l
l l
l lNuclidel Bone I Liver i Body i Thyroid l Kidney I Lung l GI-LLI l l H-3 lNo Data l2.26E-01 l2.26E-01l2.26E-01 l2.26E-01l2.26E-01l2.26E-011 l C-14 l3.13E+04l6.26E+03 l6.26E+03l6.26E+03 l6.26E+03l6.26E+03l6.26E+03l l Na-24 l4.07E+02l4.07E+02 l4.07E+02l4.07E+02 l4.07E+0214.07E+02l4.07E+02l l P-32 l4.62E+07l2.87E+06 l1.78E+06lNo Data (No Data lNo Data l5.19E+06l l Cr-51 lNo Data INo Data l1.27E+00l7.62E-01 l2.81-01 l1.69E+00l3.2-E+02l l Mn-54 lNo Data l4.38E+03 l8.35E+02]No Data l1.30E+03lNo Data l1.34E+04]
l Mn-56 lNo Data l1.10E+02 l1.95E+01lNo Data l1.40E+02lNo Data l3.52E+03l l Fe-55 l6.57E+02l4.54E+02 l1.06E+02lNo Data lNo Data l2.53E+02l2.61E+02l l Fe-59 l1.04E+03l2.44E+03 l9.34E+02lNo Data lNo Data l6.81E+02l8.13E+03]
l Co-58 lNo Data'l8.94E+01 l2.00E+02lNo Data lNo Data lNo Data.ll.81E+03l l Co-60 lNo Data l2.57E+02 15.66E+02lNo Data lNo Data lNo Data l4.82E+03l l Ni-63 l3.11E+04l2.15E+03 l1.04E+03lNo Data lNo Data lNo Data l4.49E+02l l Ni-65 l1.26E+02l1.64E+01 l7.48E+00lNo Data lNo Data lNo Data l4.16E+02]
l Cu-64 lNO Data l1.00E+01 l4.69E+00lNo Data l2.52E+01lNo Data 18.52E+02l l Zn-65 l2.32E+04l7.38E+04 l3.33E+04lNo Data l4.93E+04lNo Data l4.65E+04l l Za-69 l4.93E+01l9.44E+01 l6.56E+00lNo Data l6.13E+01lNo Data l1.42E+01l l Br-83 lNo Data lNo Data l4.04E+01lNo Data lNo Data lNo Data 15.81E+01]
l Br-84 lNo Data lNo Data l5.26E+01]No Data lNo Data lNo Data [4.13E-04l l Br-85 lNo Data lNo Data l2.15E+00lNo Data lNo Data lNo Data l 0
l l Rb-86 lNo Data l1.01E+05 l4.71E+04lNo Data lNo Data lNo Data l1.99E+04l l Rb-88 lNo Data l2.90E+02 l1.54E+02lNo Data lNo Data lNo Data l4.00E-09l l Rb-89 lNo Data l1.92E+02 l1.35E+02lNo Data lNo Data lNo Data l1.12E-11l l Sr-89 l2.21E+04lNo Data l6.35E+02lNo Data lNo Data lNo Data l3.55E+03l l Sr-90 l5.44E+05lNo Data l1.34E+05lNo Data lNo Data (No Data l1.57E+04l l Sr-91 l4.07E+02lNo Data l1.64E+01lNo Data lNo Data lNo Data l1.94E+03l l Sr-92 l1.54E+02lNo Data !6.68E+00lNo Data lNo Data lNo Data l3.06E+03l l Y-90 l5.75E-01lNo Data l1.54E-02lNo Data lNo Data lNo Data l6.10E+03l l Y-91M [5.44E-03lNo Data l2.10E-04lNo Data lNo Data lNo Data l1.60E-02]
l Y-91 l8.43E+00lNo Data l2.25E-01lNo Data lNo Data lNo Data l4.64E+03l i
l l Y-92 l5.05E-02lNo Data l1.48E-03lNo Data lNo Data lNo Data l8.85E+02l l Y-93 l1.60E-01lNo Data 14.42E-03lNo Data lNo Data lNo Data l5.08E+03l l
l Zr-95 l2.40E-01l7.70E-02 l5.21E-02lNo Data l1.21E-01lNo Data l2.44E+02l l Zr-97 l1.33E-02l2.68E-03 l1.22E-03lNo Data l4.04E-03lNo Data 18.30E+02.l l Nb-95 14.47E+02l2.48E+02 l1.34E+02lNo Data l2.46E+02lNo Data l1.51E+06l l Mo-99 lNo Data l1.03E+02 l1.96E+01lNo Data l2.33E+02lNo Data l2.39E+02]
l l Tc-99Ml8.87E-0312.51E-02 13.19E-01lNo Data l3.81E-01l1.23E-02l1.48E+01l l Tc-101l9.11E-03l1.31E-02 l1.29E-01lNo Data l2.36E-01l6.70E-03l 0
l l Ru-103l4.42E+00lNo Data l1.90E+00lNo Data l1.69E+01lNo Data l5.17E+02l l Ru-105l3.68E-01lNo Data l1.45E-01]No Data 14.76E+00lNo Data l2.25E+02l l Ru-106l6.57E+01lNo Data 18.32E+00lNo Data l1.27E+02lNo Data l4.25E+03l l
r Rev. 4 TABLE 1 (Continued)
INGESTION DOSE COMMITMENT FACTOR (Ag) FOR ADULT AGE GROUP (mrem-hr per pei-ml) l l
l l Total l
l l
l l
lNuclidel Bone l
Liver l Body i Thyroid l Kidney l Lung l GI-LLI l lTe-125Ml2.57E+0319.30E+02 l3.44E+02l7.72E+02 l1.04E+04]No Data l1.02E+04l
[Te-127Mj6.47E+03l2.32E+03 l7.90E+02l1.66E+03 l2.63E+04lNo Data 12.17E+04l lTe-127 l1.05E+02l3.78E+01 l2.28E+01l7.80E+01 l4.29E+02lNo Data 18.30E+03l lTe-129Ml1.10E+04l4.11E+03 11.74E+03l3.78E+03 l4.6CE+04lNo Data l5.54E+04l lTe-129 l3.01E+01l1.13E+01 17.33E+00l2.31E+01 l1.26E+02lNo Data l2.27E+01l lTe-131Ml1.66E+03l8.09E+02 l6.75E+02l1.28E+03 l8.21E+03lNo Data l8.03E+04l lTe-131 l1.89E+01l7.88E+00 l5.96E+00l1.55E+01 l8.25E+01lNo Data l2.67E+00l lTe-132 l2.41E+0311.56E+03 l1.47E+03l1.72E+03 11.50E+04lNo Data l7.38E+04l lI-130 l2.71E+01l8.01E+01 l3.16E+01l6.79E+03 l1.25E+02lNo Data l6.89E+01l lI-131 l1.49E+02l2.14E+02 l1.22E+02l7.00E+04 l3.66E+02lNo Data l5.64E+01l lI-132 l7.29E+00l1.95E+01 l6.82E+00l6.82E+02 l3.11E+01lNo Data [3.66E+001 lI-133 l5.10E+0118.87E+01 12.70E+01l 1.30E+04 l1.55E+02lNo Data l 7.97E+01]
lI-134 l3.81E+00ll.03E+01 l3.70E+00l1.79E+02 l1.64E+01lNo Data l9.01E-03l lI-135 l1.59E+0114.16E+01 l1.54E+01l2.75E+03 l6.68E+01lNo Data l4.70E+01l lCs-134 l2.98E+05l7.09E+05 l5.80E+05lNo Data l2.29E+05l7.62E+04l1.24E+04l lCs-136 l3.12E+04l1.23E+05 l8.86E+04lNo Data l6.85E+0419.39E+03l1.40E+04l lCs-137 l3.82E+05l5.22E+05 l3.42E+05lNo Data l1.77E+05l5.89E+04l1.01E+04l lCs-138 l2.64E+02l5.22E+02 12.59E+02lNo Data l3.84E+02l3.79E+01l2.23E-03l lBa-139 l9.29E-01l6.62E-04 l2.72E-02lNo Data l6.19E-04l3.76E-04l1.65E+00l lBa-140 l1.94E+02l2.44E-01 l1.27E+01lNo Data l8.31E-02l1.40E-01l4.00E+02l lBa-141 l4.50E-01l3.40E-04 l1.52E-02lNo Data l3.16E-04l1.93E-04l2.12E-101 l
lBa-142 12.04E-0112.09E-04 l1.28E-02lNo Data l1.77E-0411.19E-041 0
l lLa-140 l1.50E-01l7.53E-02 l1.99E-02lNo Data lNo Data lNo Data l5.53E+03l lLa-142 l7.65E-03l3.48E-03 l8.66E-04lNo Data (No Data lNo Data l2.54E+01l lCe-141 l 2.24E-02l1.51E-02 l1. 72E-03 lNo Data l7.03E-03lNo Data 15.78E+01l lCo-143 l3.94E-03l2.92E+00 l3.23E-04lNo Data l1.28E-03lNo Data l1.09E+02l l
lCe-144 11.17E+00l4.88E-01 l6.26E-02lNo Data l2.89E-01lNo Data l3.94E+02l 1
lPr-143 15.50E-01l2.21E-01 12.73E-02lNo Data l1.27E-01lNo Data l2.41E+03[
lNd-147 l3.76E-0114.35E-01 l2.60E-02lNo Data l2.54E-01lNo Data l2.09E+031 lW-187 l2.96E+02l2.47E+02 l8.64E+01lNo Data lNo Data lNo Data l8.09E+04[
lNp-239 l2.84E-02l2.80E-03 11.54E-03lNo Data 18.72E-03lNo Data l5.74E+02) 1 - _. _
Rcv. 4 TABLE 2 BI0 ACCUMULATION FACTOR (BF ) USED IN THE ABSENCE 1
OF SITE-SPECIFIC DATA" (pCi/kg) per (pCi/ liter)
BF 1 Element Fish (Freshwater)
H 9.0 E - 01 C
4.6 E + 03 Na 1.0 E + O2 P
1.0 E + 05 Cr 2.0 E + O2 Mn 4.0 E + O2 Fe 1.0 E + O2 Co 5.0 E + 01 Ni 1.0 E + O2 Cu 5.0 E + 01 Zn 2.0 E + 03 Br 4.2 E + O2 Rb 2.0 E + 03 Sr 3.0 E + 01 Y
2.5 E + 01 Zr 3.3 E + 00 Nb 3.0 E + 04 Mo 1.0 E + 01 Tc 1.5 E + 01 Ru 1.0 E + 01 Rh 1.0 E + 01 Te 4.0 E + O2 I
1.5 E + 01 Cs 2.0 E + 03 Ba 4.0 E + 00 La 2.5 E + 01 Ce 1.0 E + 00 Pr 2.5 E + 01 Nd 2.5 E + 01 W
1.2 E + 03 Np 1.0 E + 01 (a)
Values taken from Regulatory Ou.de 1.109, Rev 1, Table A-1. -.. -
Rev. 4 2.6 LIQUID RADWASTE TREATMENT SYSTEM l 2.6.1 Technical Specification 3.11.1.3 The LIQUID RADWASTE TREATMENT SYSTEM Shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivty when the projected doses due to the liquid effluent, to UNRESTRICTED AREAS, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31 day period.
l 2.6.2 OPERABILITY Of The LIQUID RADWASTE TREATMENT SYSTEM The LIQUID RADWASTE TREATMENT SYSTEM is capable of varying treatment, depending on waste type and product desired.
It is capable of concentrating, gas strip-ping, and distillation of liquid wastes through the use of the evaporator system.
The demineralization system is capable of removing radioactive ions from solutions to be reused as makeup water.
Filtration is performed on certain liquid wastes and it may, in some cases, be the only required treatment prior to release.
The sys-tem has the ability to absorb halidas through the use of charcoal filters prior to their release.
The design and operation requirements of the LIQUID RADWASTE TREATMENT SYSTEM provide assurance that releases of radioactive materials in liquid effluents will be kept "As Low As Reasonably. Achievable" (ALARA).
The OPERABILITY of the LIQUID RADWASTE TREATMENT SYSTEM ensures this system will be available for use when liquids require treatment prior to their release to the environment.
OPERABILITY is demonstrated through com-l pliance with Technical Specifications 3.11.1.1 and 3.11.1.2.
l Projected doses due to liquid releases to UNRESTRICTED l AREAS are determined each 31 days by dividing the cum-I mulative annual total by the number of elapsed months.
l l
l
(
23 -
l
Rav. 4 3.0 GASEOUS EFFLUENTS l 3.1 Technical Specification 3.3.3.11 The radioactive gaseous effluent monitoring instrumen-tation channels shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specifica-tion 3.11.2.1 are not exceeded.
The Alarm / Trip Set-points of these channels shall be adjusted to the values determined in accordance with the methodology and parameters in the ODCM.
l 3.2 Technical Soecification 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:
a.
For noble gases:
Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin, and b.
For Iodine - 131 and 133, for tritium, and for all radionuclides in particulate form with half lives greater than 8 days:
Less than or equal to 1500 mrem /yr. to any organ, from the inhalation pathway only.
3.3 Gaseous Effluent Monitors Noble gas activity monitors, iodine monitors, and par-ticulate monitors are present on the containment build-ing ventilation system, plant unit ventilation system, and radwaste building ventilation system.
The alarm / trip (alarm & trip) setpoint for any gaseous effluent radiation monitor is determined based on the I instantaneous noble gas total body and skin dose rate I limits of Technical Specification 3.11.2.1, at the SITE i BOUNDARY location with the highest annual average X/Q l value. (Figure 5.1B)
Each monitor channel is provided with a two level sys-tem which provides sequential alarms on increasing radioactivity levels.
These setpoints are designated as alert setpoints and alarm / trip setpoints.
(Ref.
9.6.3)
Rev. 4 The radiation monitor alarm / trip setpoints for each release point are based on the radioactive noble gases in gaseous effluents.
It is not considered practicable to apply instantaneous alarm / trip setpoints to inte-grating radiation monitors sensitive to radiciodines, radioactive materials in particulate form and radionu-clides other than noble gases.
Conservative assump-1 tions may be necessary in establishing setpoints to ac-count for system variables, such as the measurement system efficiency and detection capabilities during no rmal, anticipated, and unusual operating conditions, the variability in release flow and principal radionu-clides, and the time lag between alarm / trip action and the final isolation of the radioactive effluent.
(Ref.
l 9.8.6.) Technical Specifications Table 4.3-13 provides the instrument surveillance requirements, such as cali-bration, source checking, functional testing, and chan-nel checking.
3.3.1 Continuous Release Gaseous Effluent Monitors The radiation detection monitors associated with conti-nuous gaseous effluent releases are (Ref. 9.6.8, 9.6.9):
Monitor I.D.
Description l
GT-RE-21 Unit Vent i
GH-RE-10 Radwaste Building Vent The Unit Vent monitor continuously monitors the ef-fluent from the unit vent for particulate, iodine (halogen), and gaseous radioactivity.
The unit vent, via ventilation exhaust systems, continuously purges various tanks and sumps normally containing low-level radioactive aerated liquids that can potentially gener-ate airborne activity.
The exhaust systemr which supply air to the unit vent are from the fuel building, auxiliary building, the ac-cess control area, the containment purge, and the con-denser air discharge.
Rev. 4
- ~-
All of these systems are filtered before they exhaust to the unit vent.
The unit vent monitor measures ac-tual plant effluents and not inplant concentrations.
Thus, the system continuously monitors downstream of the last point of potential radioactivity entry.
The monitoring system consists of an off-line, three-way airborne radioactivity monitor.
An isokinetic sampling probe is located downstream of the last point of poten-tial radioactivity entry for sample collection.
The sample extracted by the isokinetic no :le is passed through the fixed filter (particulate), charcoal filter (iodine), and fixed-volume (gaseous) detector assem-blies and then through the pumping system for discharge back to the unit vent.
Indication is provided on the radioactivity monitoring system CRT in the control room.
l The Radwaste Building Ventilation effluent monitor con-l tinuously monitors for particulate, halogen, and gaseous radioactivity in the effluent duct downstream of the exhaust filter and fans.
The sample point is located downstream of the last possible point of radi-oactive influent, including the waste gas decay tank discharge line.
The flow path provides ventilation ex-haust for all parts of the building structure and com-ponents within the building and provides a discharge path for the waste gas decay tank release line.
These components represent potential sources for the release of gaseous and air particulate and iodine activities in addition to the drainage sumps, tanks, and equipment purged by the waste processing system.
The monitoring system consists of a fixed filter par-ticulate monitor, an iodine monitor, and gaseous activ-ity monitor.
The sample is extracted through an isokinetic no::le to ensure that a representative sample of the air is ob-tained prior to release to the environment.
After l
passing through the fixed filter (particulate), char-coal filter (halogen), and fixed-volume (noble gas) detector assemblies and the pumping system, the sample is discharged back to the exhaust duct.
Indication is provided on the radiation monitoring system CRT in the control room.
l This monitor will isolate the waste gas decay tank dis-l charge line if the radioactivity release rate is above l
l l l
l 1
l t
Rov. 4.
the present limit when the wasto gas discharge valve has been deliberately or inadvertently opened.
The continuous gaseous effluent monitor setpoints are established using the methodology described in Section 3.4.
Since there are two continuous gaseous effluent release points, a fraction of the total MPC will be al-located to each release point.
Neglecting the batch releases, the plant Unit Vent monitor has been allo-cated 0.7 MPC and the Padwaste Building Vent monitor has been allocated 0.3 MPC.
These will be changed as required, but limited to 1 MPC.
Therefore, a particu-lar monitor reaching the fractional MPC setpoint would not necessarily mn T the MFC limit at the site boundary is being exceeded.
he alarm only indicates that the specific release ssint is contributing a greater frac-tion of the MFC limit than was allocated to the associ-ated monitor and will necessitate an evaluation of both systems.
3.3.2 Batch Releasa, gaseous Monitors The radiation monitors associated with batch release gaseous effluents are (Ref.
9.6.9, 9.6.10, 9.6.11):
Monitor I.D.
Description l
GT-RE-22 Containment Purge Syctem Monitors l
GT-RE-33 l
GT-RE-31 Containment Atmosphere Radioactivity l
GT-RE-32 Monitors l
GH-RE-10 Radwaste Building Vent The Containment Purgo System continuously monitors the contatament purge exhaust duct during purge operations l
for particulate, iodine, and gaseous radicactivity.
The purpose of these monitors is to isolate the con-tainment purge system on high gaseous activity via the ESFAS.
These monitors also serve as backup indication j
for personnel protection and reactor coolant pressure boundary leakage detection for the containment at-mosphere radioactivity monitors.
l The sample points are located outside the containment between the containment isolation dampers and the con-tainment purge filter adsorber unit.
l l w
l Rev. 4 i
Each monitor is provided with two isokinetic nozzles to ensure that representative samples are obtained for both normal purge and minipurge flow rates.
The sample is extracted through the selected nozzle and then passed through the selector valve, the fixed filter (particulate), charcoal filter (iodine), and fixed-volume gaseous detectors.
The sample then passes through the pumping system ara is discharged back to the duct.
Indication is provided for each monitor on individual indicators on the radioactivity monitoring system con-trol panel and, through isolated signals, on the radio-activity monitoring system CRT in the control room.
The Containment Atmosphere Radioactivity monitors, con-tinuously monitor the containment atmosphere for par-ticul'a te, iodine, and gaseous radioactivity.
They isolate the containment purge system on high gaseous activity via the ESFAS.
These monitors also serve for reactor coolant pressure boundary leakage detection and for personnel protection.
The containment atmosphere radioactivity monitors provide backup indication for the containment purge monitors.
Samples are extracted from the operating deck level (El. 2047'-6") through sample lines which penetrate the containment.
The monitors are located as close as possible to the containment penetrations to minimize the length of' the sample tubing and the effects of sam-ple plate out.
The sample points are located in areas which ensure that representative samples are obtained.
Each sample passes through the penetration, then through the fixed filter (particulate), charcoal filter (todine), and fixed-volume gaseous detector assemblies.
After passing through the pumping system, the sample is discharged back to the containment through a separate penetration.
Indication is provided for each monitor on individual indicators on the radioactivity monitoring system con-l trol panel and, through isolated signals, on the radio-activity monitoring system CRT in the control room.
The Radwaste Building Vent monitors are described in Section 3.3.1.
The batch gaseous effluent monitors setpoints are nor-mally established using the methodology described in Section 3.4.
l i
l l l
L
Rcv. 4 A pre-release isotopic analysis is performed for each batch release to determine the identity and quantity of the principal radionuclides.
The alarm / trip setpoint(s) are adjusted accordingly to ensure that the limits of Radiological Effluent Technical Specification 3.11.2.1 are not exceeded.
3.4 ODCM Methodology for the Determination of Gaseous f
Effluent Monitor Setpoints 3.4.1 Development of ODCM Methodology for the Determi-nation of Gaseous Effluent Monitor Setpoints The alarm / trip setpoint for gaseous effluent monitors is determined based on the lesser of the total body dose rate and skin dose rate, as calculated for the SITE BOUNDARY.
3.4.1.1 Total Body Dose Rate Setpoint Calculations l To ensure that the limits of Technical Specification 3.11.2.1 are met, the alarm / trip setpoint based on the total body dose rate is calculated according to:
S 5D R
(3.1) tb tb tb s a Where:
Stb =
the alarm / trip setpoint based on the total body dose rate (VCi/cc).
IDtb =
Technical Specification 3.11.2.1 limit of 600 mrem /yr, contarvatively interpreted as a con-tinuous release over a one year period.
the safety factor; a conservative factor used E =
s to compensate for statistical fluctuations and errors of measurement.
(For example, F, = 0.5 corresponds to a 100% variation.)
Default value is F
= 1.0.
s F, =
the allocation factor which will modify the required dilution factor such that simultaneous gaseous releases may be made without exceeding the limits of Radiological _.
Rnv. 4 Effluent Technical Specification 3.11.2.1.
The default value is 1/n, where n is the num-ber of pathways planned for release.
Rtb =
factor used to convert dose rate to the ef-fluent concentration as measured by the ef-fluent monitor, in (pCi/cc) per (mrer,'yr) to the total body, determined according +.o:
Rtb *
- II
'9 )
1 1]
(3.2) 9 i
Where:
C=
monitor reading of a noble gas monitor cor-responding to the sample radionuclide concen-trations for the batch to be released.
Concentrations are determined in accordance l
with Technical Specifications Table 4.11-2.
The mixture of radionuclides determined via grab sampling of the effluent stream or source is correlated to a calibration factor to determine monitor response.
The monitor response is based on concentrations, not release rate, and is in units of (pC1/cc).
X/Q =
the highest calculated annual average relative concentration for any area at or beyond the 3
SITE BOUNDARY in (sec/m ),
g,g,,
g, Tables 9, 10, and 12.
K1=
the total body dose factor due to gamma emis-sions for each identified noble gas radionu-3 clide, in (mrem /yr) per (uCi/m ).
(Table 3)
Q1=
rate of release of noble gas radionuclide, i, in (pCi/sec)..
Rev. 4 Q
is calculated as the product of the ven-1 tilation path design flow rate and the meas-ured activity of the effluent stream as deter-mined by grab sampling.
Flow rates for the ventilation pathways can be found in ref-erences 9.6.21, 9.6.22, 9.6.23, and 9.6.24.
3.4.1.2 Skin Dose Rate Setpoint Calculation l To ensure that the limits of Technical Specification 3.11.2.1 are met, the alarm / trip setpoint based on the skin dose rate is calculated according to:
l l
D,R F,F, (3.3)
S s
3 Where:
F, and F, are as previously defined in Section 3.4.1.1.
S, =
the alarm / trip setpoint based on the skin dose rate.
l D, =
Technical Specification 3.11.2.1 limit'of 3000 mrem /yr, conservatively interpreted as a con-tinuous release over a one year period.
l l
31 -
Rev. 4 R, =
factor.used to convert dose rate co the ef-fluent concentration as measured by the ef-fluent monitor, in (uci/cc) per (mrem /yr) to the skin, determined according to:
R, = C + [(X7Q) I (L1 + 1.1M ) Q )
(3.4) 1 1
i Where:
L1=
the skin dose factor due to beta emissions for each identified noble gas radionuclide, in 3
(mrem /yr) per (uci/m ).
(Table 3) 1.1 =
conversion factor:
1 mrad air dose = 1.1 mrem skin dose.
M1=
the air dose factor due to gamma emissions for each identified noble gas radionuclide, in 3
(mrad /yr) per (pCi/m ).
(Table 3)
C, (X/Q) and Q are as previously defined.
g 3.4.1.3 Gaseous Effluent Monitors Setpoint Determination The results of Equation (3 1) and Equation (3.3) are compared.
The setpoint is then selected as the lesser of the two values.
l E12Y-c h TABLE 3 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFIN11E CLOUD OF NOBL E GASES" Total Body Camma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor ks Le Ms Ne j
Radionuclide (ares /yr) per (PCl/m3) (area /yr) per (PCl/m3) (arad/yr) per (pCi/m3) (erad/yr) per (PCl/m3)
.i Mr-83m 7.56 E-02 1.93 [+01 2.88 E+02 K r-85m 1.17 [+03 1,46 E+03 1.23 C+03 1.97 E+03 Kr-85 1.61 E+01 1.34 [+03 1.72 E+01 1.95 E+03 Kr-87 5.92 E+03 9.73 E+03 6.17 E+03 1.03 C+04 Kr-88 1.47 E+04
- 2. s7 [+03 1.52 E+04 2.93 E+03 Kr-89 1.66 [+04 1.01 [+04 1.73 E+04 3.06 E+04 Kr-90 1.56 [+04 7.29 E+03 1.63 E+04 7.83 [+03 Xe-131m 9.15 E+01 4.76 [+02 1.56 C+02 1.11 E+03 Xe-133m 2.51 E+02 9.94 E+02 3.27 E+02 1.48 [+03 Xe-133 2.94 [+02 3.06 E+02 3.53 E+02 1.05 E+03 Xe-135m 3.12 E+03 7.11 [+02 3.36 E+03 7.39 E+02 Xe-135 1.81 E+03 1.86 E+03 1.92 E+03 2.46 E+03 Xe-137 1.42 E+03 1.22 E+04 1.51 [+03 1.27 E+04 Xe-138 8.83 [+03 4.13 [+03 9.21 [+03 4.75 E+03 A r-41 8.84 E+03 2.69 E+03 9.30 E+03 3.28 E+03 (a) 1he listed dose factors are derived f rom Reg. Guide 1.109, Table B-1 (Rev.
1, 1977).
i
)
l I
i d
\\
)
1.
4
Rzv. 4 3.4.2 Summary, Gaseous Effluent Monitors Setpoint Detarmination The gaseous effluent monitors setpoints are calculated according to equations (3.1) and (3.3), as described in Section 3.4.
However, it should be noted that a batch release will alter the flow rate characteristics at the 1
Unit Vent and therefore the concentration as sensed by the monitor.
For example, in the case of a mini-purge, the setpoint for the Unit Vent monitor must be re-calculated to include both the continuous and batch sources.
3.5 ODCM Methodology for Determining Dose Contributions From Gaseous Effluents Dose rate calculations are performed for gaseous ef-fluents to ensure compliance with Radiological Effluent Technical Specification 3.11.2.1 as stated in Section 3.2.
3.5.1 Detemnination of Dose Rate The following methodology is applicable to the location (SITE BOUNDARY or beyond) characterized by the values of the parameter (X/Q) which results in the maximum total body or skin dose rate.
In the event that the analysis indicates a different location for the total body and skin dose limitations, the location selected for consideration is that which minimizes the allowable release values.
(Ref. 9.8.7)
The factors K,
L, and M relate the radionuclide air-g 1
g borne concentrations to various dvse rates, assuming a semi-infinite cloud model, and are tabulated in Table 3.
3.5.1.1 Noble Gases The release rate limit for noble gases is determined according to the following general relationships (Ref.
9.8.7):
1 tb " I IK ((X/9)9 )) $ 500 mrem /yr (3.5)
D i
1 i
. \\
l Rev. 4 1 + 1.1 M )((X/Q)Q )] 5 3000 mrem /yr (3.6)
D,
=I ((L g
1 i
Where:
Dtb =
Total body dose rate, conservatively averaged over a period of one year.
Kg=
Total body dose factor due to gamma emissions for each identified noble gas radionuclide, in 3
(mrem /yr) per (uCi/m ).
(Table 3)
(X/Q) =
The highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY.
Refer to Tables 9, 10, and 12.
Qg =
The release rate of noble gas radionuclides, i, in gaseous effluents, from all vent releases in (uCi/sec).
Q is calculated as the product of the ven-1 tilation path design flow rate and the meas-ured activity of the effluent stream as deter-mined by grab sampling.
Flow rates for the ventilation pathways can be found in ref-erences 9.6.21, 9.6.22, 9.6.23, and 9.6.24.
D, =
Skin dose rate, conservatively averaged over a period of one year.
Lg=
Skin dose factor due to beta emissions for each identified noble gas radionuclide, in 8
(mrem /yr) per (uCi/m ) (Table 3 ).
1.1 =
Units conversion factor; 1 mrad air dose = 1.1 mrem skin dose.
M1=
Air dose factor due to gamma emissions for each identified noble gas radionuclide, in 8
(mrad /yr) per (uC1/m ) (Table 3). l
Rtv. 4 3.5.1.2 Radionuclides Other Than Noble Gases The release rate limit for Iodine-131 and-133, for tri-tium, and for all radioactive materials in particulate form with half lives greater than 8 days is determined according to (Ref. 9.8.8):
D, = I P ((X/Q)Q ] 5 1500 mrem /yr (3.7) g g
i Where:
D, =
Dose rata to any critical organ, in (mrem /yr).
Pg=
Dose parameter for radionuclides other than noble gases for the inhalation pathway for the child, based on the critical organ, in (mrem /yr) pe/ (uCi/m').
(Table 4)
Qg=
The release rate of radionuclide, i, in gaseous effluents, from all vent releases, in (uCi/sec).
Q is calculated as the product cf g
the ventilation path design flow rate and the measured activity of the effluent stream as determined by grab sampling.
Flow rates for the ventilation pathways can be found in ref-
~
erences 9.6.21, 9.6.22, 9.6.23, and 9.6.24.
(X/Q) i s
- a. a previously defined.
The dose parameter (P1) includes the internal dosimetry of radionuclide, i, and the receptor's breathing rate, which are functions of the receptor's age.
Therefore the child age gcoup has been selected as the limiting age group.
l l l
[
Rnv. 4 For the child exposure, separate values of P are tabu-1 lated in Table 4 for the inhalation pathway.
These values were calculated according to (Ref. 9.8.9):
Pg = K' (BR) DFA (3.8) 1 Where:
K' Units conversion factor: luci = 1E06 pCi.
=
BR=
The breathing rate of the maximum exposed child age group, 3700 m'/yr.
(Regulatory Guide 1.109, Table E-5).
DFA1=
The maximum organ inhalation dose factor for the child age group for the ith radionuclide, in (mrem /pci).
The total body is considered as an organ in the selection of DFA.
1 (Regulatory Guide 1.109, Table E-9)
Note:
All radiciodines are assumed to be released in elemental form.
(Ref.9.8.8)
Rev. 4 TABLE 4 DOSE PARAMETER (P ) TOR RADIONUCLIDES OTHER THAN NOBLE GASES
- g Inhalation Pathway 3
(arem/yr) per (pCi/m )
l l
l l Total l l
l l
l lNuclidel Bone i Liver i Body l Thyroid i Kidney l Lung i GI-LLI l l H-3 l ND l1.12E3 11.12E3 l1.12E3 l1.12E3 l1.12E3 l1.12E3 l
l C-14 l3.59E4 -l6.73E3 l6.73E3 [6.73E3 l6.73E3 l6.73E3 l6.73E3 l
I Na-24 l1.61E4 l1.61E4 l1.61E4 l1.61E4 l1.61E4 l1.61E4 l1.61E4 l l P-32 12.60E6 l1.14E5
[9.88E4.l ND l ND l ND l4.22E4 l l Cr-51 l ND l ND
[1.54E2 l8.55El l2.43E1 l1.70E4 l1.08E3 l
l Mn-54 l ND
[4.29E4 l9.51E3 l ND l1,00E4 l1.58E6 l2.29E4 l l Mn-56 l ND l1.66E0 l3.12E-1 l ND l1.67E0 l1.31E4 11.23E5 l
l Fe-55 T4.74E4 12.52E4 l7.72E3 l ND l ND l1.11ES l2.87E3 l
l Fe-59 l2.07E4 l3.34E4 l1.67E4 l ND l ND l1.27E6 l7.07E4 l l Co-58 l ND l1.77E3 13.16E3 l ND l ND l1.11E6 l3.44E4 l l Co-60 l ND l1.31E4 l2.26E4 l ND l ND l7.07E6 l9.26E4 l l Ni-63 l8.21ES M.63E4 l2.80E4 l ND l ND l2.75ES l6.33E3 l l Ni-65 l2.99E0 l2.96E-1 l1.64E-1 l ND l ND l8.18E3 l8.40E4 l
l Cu-64 l ND
[1.99E0 l1.07E0 l ND l6.03E0 l9.58E3 l3.67E4 l l Zn-65 l4.26E4 T1.13E5 l7.03E4 l ND l7.14E4 l9.95ES l1.63E4 l l Zn-69 l6.70E-2 19.66E-2 l8.92E-3 l ND 15.85E-2 l1.42E3 l1.02E4 l l Br-83 l ND l ND 14.74E2 l ND l ND l ND l
0 l
l Br-84 l ND l ND l5.48E2 l ND l ND l ND l
0 l
l Br-85 l ND l ND l2.53E1 l ND l ND l ND l
0 l
l Rb 86 l ND l'. 98E5 l1.14E5 l ND l ND l ND
[7.99E3 l
l Rb-A8 l ND j5.62E2 l3.66E2 l ND l ND l
ND l1.72E1 l
l Rb-89 l ND a3.45E2 12.90E2 l ND l ND l
ND l1.89E0 l
l Sr-89 15.99ES ND l1.72E4 l ND l ND l2.16E6 l1.67ES l
l Sr-90 l1.0128 l ND l6.44E6 l ND l ND l1.48E7 l3.43E5 l
l Sr-91 l1.21E2 l rD l4.59E0 l ND l ND l5.33E4 l1.74E5 l
Rnv. 4 TABLE 4 (Cont'd.)
DOSE PARAMETER (P ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES
- 1 Inhalation Pathway 8
(mrem /yr) per (pC1/m )
l l
l l Total l l
l l
l lNuclidel Bone l Liver i Body l Thyroid l Kidney 1 Lung i GI-LLI i l Sr-92 11.31El l
ND l5.25E-1 l ND l ND l2.40E4 l2.42E5 l
l Y-90 l4.11E3 l ND l1.11E2 l ND l ND l2.62ES, l2.68E5 l l Y-91m l5.07E-1 l ND l1.84E-2 l ND l ND l2.81E3 l1.72E3 l l Y-91 l9.14E5 l ND l2.44E4 l ND l ND l2.63E6 l1.84E5 l
l Y-92 l2.04E1 l ND l5.81E-1 l ND l ND l2.39E4 12.39ES l
l Y-93 l1.86E2 l ND l 5.11E0 l ND l ND l7.44E4 l3.89ES l
l Zr-95 l1.90E5 l4.18E4 l3.70E4 l ND 15.96E4 l2.23E6 l6.11E4 l l Zr-97 l1.88E2 12.72E1 11.60E1 l ND l3.89El l1.13E5 l3.51ES l
l Nb-95 12.33E4 19.18E3 l6.55E3 l ND l8.62E3 l6.14E5 l3.70E4 l l Mo-99 l ND l1.72E2 l4.26El l ND l3.92E2 l1.35ES l1.27ES l
l Tc-99ml1.78E-3 l3.48E-3 l5.77E-2 l ND
[5.07E-2 l9.51E2 l4.81E3 l l Tc-101l8.10E-5 l8.51E-5 l1.08E-3 l ND
[1.45E-3 l5.85E2 l1.63E1 l l Ru-103l2.79E3 l ND l1.07E3 l ND l7.03E3 l6.61ES l4.48E4 l l Ru-105l1.53E0 l ND 15.55E-1 l ND l1.34E0 l1.59E4 l9.95E4 l l Ru-106l1.36ES l ND l1.69E4 l ND l1.84E5 l1.43E7 14.29ES l
lAg-110ml1.69E4 11.14E4 l9.14E3 l ND l2.12E4 l5.48E6 ll.00E5 l
lTe-125ml6.73E3 l2.33E3 19.14E2 l1.92E3 l ND l4.77ES
{2. GFt l
lTe-127ml2.49E4 18.55E3 l3.02E3 l6.07E3 l6.36E4 l1.48E6 l7.14E4 l lTe-127 l2.77E0 l9.51E-1 l6.11E-1 l1.96E0 l7.07E0 l1.00E4 15.62E4 l lTe-129ml1.92E4 l6.85E3 l3.04E3 l6.33E3 l5.03E4 l1.76E6 l1.82E5 l
lTe-129 l9.77E-2 l3.50E-2 l2.38E-2 l7.14E-2 l2.57E-1 l2.93E3 l2.55E4 l lTe-131 mil.34E2 15.92E1 l5.07El l9.77El l4.00E2 l2.06ES l3.08E5 l
lTe-131 l2.17E-2 18.44E-3 l6.59E-3 l1.70E-2 l5.88E-2 l2.05E3 l1.33E3 l
lTe-132 l4.81E2 l2.72E2 l2.63E2 13.17E2 11.77E3 l3.77E5 l1.38E5 l
lI-130 l8.18E3 l1.64E4 l8.44E3 l1.85E6 l2.45E4 l ND l5.11E3 l l
i l
( !
R*v. 4 TABLE 4 (Cont'd.)
DOSE PARAMETER (P ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES
- g Inhalation Pathway 3
(nrem/yr) per (uCi/m )
l l
l l Total l
l l
l l
lNuclidel Bone 1 Liver i Body l Thyroid i Kidney I Lung l GI-LLI l lI-131 l4.81E4 l4.81E4 l2.73E4 l1.62E7 l7.88E4 l ND l2.84E3 l lI-132 l2.12E3 l4.07E3 l1.88E3 l1.94E5 l6.25E3 l ND 13.20E3 l lI-133 l1.66E4 l2.03E4 l7.70E3 13.85E6 13.38E4 l ND l5.48E3 l lI-134 l1.17E3 12.16E3 l9.95E2 l5.07E4 l3.30E3 l ND 19.55E2 l lI-135 l4.92E3 l8.73E3 14.14E3 l7.92E5 l1.34E4 l ND
[4.44E3 l lCs-134 16.51E5 l1.01E6 l2.2SES l ND l3.03E5 l1.21ES 13.85E3 l lCs-136 16.51E4 l1.71ES l1.16ES l ND l9.55E4 l1.45E4 l4.18E3 l i
lCs-137 l9.07ES l8.2SES l1.28E5 l ND l2.72E5 l1.04E5 l3.62E3 l lCs-138 l6.33E2 18.40E2 l5.55E2 l ND l6.22E2 l6.81El l2.70E2 l lBa-139 l1.84E0 l9.84E-4 l5.37E-2 l ND
[8.62E-4 l5.77E3 l5.77E4 l lBa-140 l7.40E4 l6.48E1 l4.33E3 l ND l2.11El 11.74E6 11.02E5 l lBa-141 l2.19E-1 l1.09E-4 16.36E-3 l ND l9.47E-5 l2.92E3 l2.75E2 l l-lBa-142 l5.00E-2 l3.60E-5 l2.79E-3 l ND l2.91E-5 l1.64E3 l2.74E0 l
}-
lLa-140 l6.44E2 l2.25E2 l7.55El l ND l ND l1.83E5 l2.26ES l lLa-142 l1.30E0 l4.11E-1 l1.29E-1 l ND l ND l8.70E3 l7.59E4 l lCe-141 l3.92E4 l1.95E4 l2.90E3 l ND l8.55E3 l5.44E5 l5.66E4 l lCo-143 l3.66E2 l1.99E2 12.87El l ND l8.36El l1.15E5 l1.27ES l
lCe-144 l6.77E6 l 2.12E6 l3.61ES l ND l1.17E6 11.20E7 l3.89ES l
lPr-143 l1.85E4 15.55E3 l9.14E2 l ND l3.00E3 l4.33E5 l9.73E4 l lPr-144 l5.96E-2 l1.85E-2 l3.00E-3 l ND l9.77E-3 l1.57E3 l1.97E2 l lNd-147 l1.08E4 18.73E3 l6.81E2 l ND 14.81E3 l3.28E5 18.21E4 l lW-187 l1.63E1 l9.66E0 l4.33E0 l ND l ND l 4.11E4 l9.10E4 l lNp-239 l4.66E2 l3.34E1 l2.35El l ND l9.73E1 l5.81E4 16.40E4 l (a) The child age group determination; Table E-9 Reg. Guide 1.109, Rev. 1, 1977.__
Rsv. 4 3.5.2 Individual Dose Due To Gaseous Effluents l 3.5.2.1 Technical Specification 3.11.2.2 The air dose due to noble gases released in gaseous ef-fluents, to areas at and beyond the SITE BOUNDARY shall be limited to the following:
a.
During any calendar quarter:
Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, b.
During any calendar year:
Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
3.5.2.1.1 Noble Gases The air dose at the SITE BOUNDARY due to noble gases released from the site is determined according to the following methodology (Ref. 9.8.10):
During any calendar quarter, for gamma radiation:
(X/q) q )] $5 mrad (3.9)
D
= 3.17 E-08 I (Mg ((X/Q) Q1+
g 9
i During any calendar quarter, for beta radiation:
b ' 3.17 E-08 I (Ng ((X/Q) Qg + (X/q) q1)) 510 mrad (3.10)
D i
During any calendar year, for gamma radiation:
D
= 3.17 E-08 I (Mg ((X/Q) Qg+ (X/q) q1)) 5 10 mrad (3.11) 9 i
l l
During any calendar year, for beta radiation:
D3 = 3.17 E-08 I (N1 {(X/Q) Qg + (X/q) q1}] $ 20 mrad (3.12) i l l
p,-
t
~ ' - ' ' - - '
Rev. 4 Where:
Air dose from gamma radiation due to noble D
=
9 gases released in gaseous effluent.
Db=
Air dose from beta radiation due to noble gases released in gaseous effluents.
(X/q) =
The relative concentration for areas at or beyond the SITE BOUNDARY for short-term releases (equal to or less than 500 hrs / year).
Refer to Tables 9, 10, 11, and 12.
qi =
The average release of noble gas radionu-clides, i, in gaseous effluents from all vent releases for short-term releases (equal to or less than 500 hrs / year), in (uC1).
Releases are cumulative over the calendar quarter or year, as appropriate.
Ng=
The air dose factor due to beta emissions for each identified noble gas radionuclide, i, in (mrad /yr) per (uCi/m'). (Table 3)
Q1=
The average release of noble gas radionu-
- clides, 1,
in gaseous effluents from all vent releases for long-term releases (greater than 500 hrs / year), in (uci).
Releases are cumula-tive over the calendar quarter or year, as appropriate.
(X/Q) =
The highest calculated annual average relative concentration for areas at or beyond the SITE BOUNDARY for long-term releases (greater than 500 hrs /yr).
Refer to Tables 9,
10, and 12.
3.17E-08 = The inverse of the number of seconds per year.
M is as previously defined. (Refer to Section 3.4.1.2) y...
Rov. 4 1 3.5.2.2 Technical Specification 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous ef-fluents released, to areas at and beyond the SITE BOUN-DARY shall be limited to the following (Ref. 9.8.10):
a.
During any calendar quarter:
Less than or equal to 7.5 mrem to any organ and, b.
During any calendar year:
Less than or equal to 15 mrem to any organ.
3.5.2.2.1 Radionuclides Other Than Noble Gases The dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous ef-fluents released, to areas at and beyond the SITE BOUN-DARY, is determined according to the following expressions:
During any calendar quarter:
Dg = 3.17E-08 I Rg [W Qg + w q ] $ 7.5 mrem (3.13) l g
j i
l t
During any calendar year:
D1 = 3.17E-08 I Rg (W Qg + w q1] $ 15 mrem (3.14) i Where:
Dg=
Dose to a MEMBER OF THE PUBLIC from radionu-clides other than noble gases.
Q1=
The releases of radionuclides, radioactive materials in particulate form, and radionu-clides other than noble gases, 1, in gaseous effluents, for all vent releases for long-term releases (greater than 500 hrs /yr), in (uC1). l i
l
l Rev.-4
~-
Releases are cumulative over the calendar quarter or year as appropriate.
qi =
The releases of radionuclides, radioactive materials in particulate form and radionu-clides other than noble gases, i, in gaseous effluents for all-vent releases for short-term releases (equal to or less than 500 hrs /yr),
in_(uci).
Releases are cumulative-over the calendar-quarter or year as appropriate.
4 R1=
The dose factor for_each identified radionu-8 clide, i, in m (mrem /yr) per. (uCi/sec) 'or 4
8 (mrem /yr) per (pCi/m ). (Table 5)
W=
The dispersion parameter for estimating the dose to an individual at the controlling loca-tion for long-term releases (greater than 500 hrs /yr):
W = (X/Q) for the inhalation and tritium pathways, 8
in(sec/m ).
W ='(D/Q) for the food.and ground plane pathways, in(meters"8).
Refer to Tables 9, 10, and 12.
w=
The dispersion parameter for estimating the dose to an individual at the controlling loca-tion for short-term releases (equal to or less than 500 hrt/yr):
w = (X/q) for the inhalation pathway, 8
in(sec/m )
w = (D/q) for the food and ground plane pathway, in (meters *8).
Refer to Tables 9, 10, 11, and 12.
3.17 E-08
= The inverse of the number i
of seconds per year, i
(D/Q) =
the average relative deposition of the ef-fluent at or beyond the SITE BOUNDARY, consid-ering depletion of the plume during transport, l
for long term releases (greater than 500 hrs /yr), in (meters"8).
44 -
Rnv. 4 (D/q) =
the relative deposition of the effluent at or beyond the SITE BOUNDARY, considering deple-tion of the plume during transport, for short term releases (less than or equal to 500 hrs /yr), in (meters ~2).
Note:
For the direction sectors with existing pathways within 5 miles from the site, the appropriate R values 1
are used.
If no real pathway exists within 5 miles from the center of the building complex, the cow-milk R value is used, and it is assumed that this pathway g
exists at the 4.5 to 5.0 mile distance in the limiting-case sector.
If the R for an existing pathway within 1
5 miles is less than a cow-milk R at 4.5 to 5.0 miles, g
then the value of the cow-milk R at 4.5 to 5.0 miles g
is used. (Rev. 9.8.10.)
Although the annual average relative concentration (X/Q) and the average relative deposition rate (D/Q) are generally considered to be at the approximate receptor location in lieu of the SITE BOUNDARY for these calculations, it is acceptable to consider the ingestion, inhalation, and ground plane pathways to coexist at the location of the nearest residence with the highest value of (X/Q).
(Ref. 9.8.10)
The Total Body dose from ground plane deposition is added to the dose for each individual organ.
(Ref. 9.11.3)
. l
'R v. 4 TABLE 5 PATINAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN -NOBLE GASES g
Inhalation Pathway 8
(ares /yr) per (pCi/m )
l l
l l Total l
l l
l l
lNuclidel Bone I Liver
!- Body l Thyroid l Kidney l Lung i GI-LLI l l H-3 l' ND l1.12E3 l 1.12E')
l1.12E3 11.' 12E3 l1.12E3 l1.12E3 l l C-14 l3.59E4 l6.73E3 l6.73E3 l6.73E3 l6.73E3 16.73E3 -l6.73E3 l
.l Na-24 l1.61E4 11.61E4 l1.61E4 l1.61E4 l1.61E4 l1.61E4 l1.61E4 l l P-32 l2.60E6 l1.14E5 l9.88E4 l ND l ND l ND l4.22E4 l-l Cr 51 l ND l ND l1.54E2 18.55El 12.43E1 l1.70E4 l1.08E3 l-l Mn-54 l-ND l4.29E4 19.51E3 l ND l1.00E4 l1.58E6 l2.29E4 l l Mn-56 l ND l1.66E0 l3.12E-1 l ND l1.67E0 l1.31E4 l1.23E5 l
l Fe-55 14.74E4 l2.52E4 l7.72E3 l ND l ND l1.11E5 l2.87E3 l
l Fe-59 l2.07E4 l3.34E4 l1.67E4 l ND l ND 11.27E6 l7.07E4
.l l Co-58 l ND ll.77E3 l3.16E3 l ND l ND l1.11E6 l3.44E4 l l Co-60 l ND l1.31E4 l2.26E4 l ND l ND l7.07E6 l9.26E4 l l Ni-63 l8.21ES l4.63E4 l2.80E4 l ND l ND l2.75ES l6.53E3 l
l Ni-65 l2.99E0 l2.96E-1 l1.64E-1 l ND l ND l8.18E3 l8.40E4 l l Cu-64 l ND l1.99E0 l1.07E0 l ND l6.03E0 l9.58E3 l3.67E4 l l Zn-65 l4.26E4 l1.13E5 l7.03E4 l ND l7.14E4 l9.95ES l1.63E4 l l Zn-69 l6.70E-2 l9.66E-2 l8.92E-3 l ND l5.85E-2 11.42E3 l1.02E4 l l Br-83 l ND l ND l4.74E2 l ND l ND l ND l
0 l
l Br-84 l ND l ND
[5.48E2 l ND l ND l ND l
0 l
l Br-85 l ND l ND l2.53E1 l ND l ND l ND l
0 l
l Rb-86 l ND l1.98E5 l1.14E5 l ND l ND l ND l7.99E3 l l Rb-88 l ND l5.62E2 l3.66E2 l ND l ND l ND l1.72E1 l l Rb-89 l ND l3.45E2 l2.90E2 l ND l ND l ND ll.89E0 l l Sr-83 l5.99ES l ND l1.72E4 l ND l ND l2.16E6 l1.67ES l
l Sr-90 l1.01E8 l ND l6.44E6 l ND l ND l1.48E7 l3.43E5 l
l Sr-91 l1.21E2 l ND l4.59E0 l ND l ND l5.33E4 l1.74E5 l
i Rev. 4 TABLE 5 (Cont'd.)
PATHWAY DOSE FACTORS (R ) TOR XADIONUCLIDES OTHER THAN NOBLE GASES g
Inhalation Pathway 3
(mram/yr) per (uci/m )
l l
l l Total l l
l l
l lNuclidel Bone i Liver l Body l Thyroid l Kidney l Lung l GI-LLI l l Sr-92 l1.31El l ND l5.25E-1 l ND l ND l2.40E4 l2.42E5 l
l Y-90 l4.11E3 l ND l1.11E2 l ND l ND l2.62ES, l2.68E5 l
l Y-91m l5.07E-1 l ND l1.84E-2 l ND l ND l2.81E3 l1.72E3 l
l Y-91 l9.14E5 l ND l2.44E4 l ND l ND l2.63E6 l1.84E5 l
l Y-92 l2.04E1 l ND l5.81E-1 l ND l ND l2.39E4 l2.39ES l
l Y-93 l1.86E2 l ND l5.11E0 l ND l ND l7.44E4 l3.89E5 l
l Zr-95 ll.90E5 14.18E4 l3.70E4 l ND 15.96E4 l2.23E6 l6.11E4 l l Zr-97 l1.88E2 l2.72E1 l1.60E1 l ND l3.89El l1.13E5 l3.51ES l
l Nb-95 l2.33E4 19.18E3 l6.55E3 l ND l8.62E3 l6.14E5 l3.70E4 l l Mo-99 l ND l1.72E2 l4.26El l ND l3.92E2 l1.35E5 l1.27ES l
l Tc-99 mil.78E-3 l3.48E-3 l5.77E-2 l ND l5.07E-2 l9.51E2 l4.81E3 l
l Tc-101l8.10E-5 l8.51E-5 l1.08E-3 l ND ll.45E-3 l5.85E2 l1.63E1 l
l Ru-103l2.79E3 l ND ll.07E3 l ND l7.03E3 l6.62E5 l4.48E4 l l Ru-105l1.53E0 l ND 15.55E-1 l ND l1.34E0 l1.59E4 l9.95E4 l l Ru-106l1.36ES l ND l1.69E4 l ND l1.84E5 l1.43E7 14.29ES l
lAg-110ml1.69E4 l1.14E4 l9.14E3 l ND l2.12E4 15.48E6 l1.00E5 l
lTe-125ml6.73E3 l2.33E3 l9.14E2 11.92E3 l ND l4.77ES l3.38E4 l lTe-127ml2.49E4 l8.55E3 l3.02E3 l6.07E3 l6.36E4 l1.48E6 J7.14E4 l lTe-127 l2.77E0 l9.51E-1 l6.11E-1 l1.96E0 l7.07E0 l1.00E4 l5.62E4 l lTe-129 mil.92E4 l6.85E3 l3.04E3 l6.33E3 l5.03E4 l1.76E6 l1.82E5 l
lTe-129 l9.77E-2 l3.50E-2 l2.38E-2 l7.14E-2 l2.57E-1 l2.93E3 l2.55E4 l
[Te-131ml1.34E2 l5.92E1 l5.07El 19.77El 14.00E2 l2.06ES l3.08E5 l
lTe-131 l2.17E-2 !8.44E-3 16.59E-3 l1.70E-2 l5.88E-2 l2.05E3 11.33E3 l lTe-132 l4.81E2 l2.72E2 l2.63E2 l3.17E2 l1.77E3 13.77ES l1.38E5 l
lI-130 [8.18E3 l1.64E4 l8.44E3 11.85E6 12.45E4 l ND l5.11E3 l
~
Rsv. 4 G.
~
.u.
,,.~
'~
TABLE 5 (Cont'd.)
PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
Inhalation Pathway 8
(mres/yr) per (VCi-m )
l l
l l Total l l
l l
l lNuclidel Bone l Liver i Body l Thyroid l Kidney I Lung l GI-LLI l lI-131 l4.81E4 l4.81E4 l2.73E4 l1.62E7 l7.88E4 l ND l2.84E3 l lI-132 l2.12E3 l4.07E3 l1.88E3 l1.94E5 16.2SE3 l ND l3.20E3 l lI-133 l1.66E4 l2.03E4 l7.70E3 13.85E6 l3.38E4 l ND l5.48E3 l lI-134 l1.17E3 l2.16E3 l9.95E2 l5.07E4 l3.30E3 l ND l9.55E2 l lI-135 l4.92E3 l8.73E3 l4.14E3 17,92E5 l1.34E4 l ND l4.44E3 l lCs-134 l6.51E5 l1.01E6 l2.25E5 l ND l3.03E5 l1.21E5 l3.85E3 l lCs-136 l6.51E4 l1.71ES l1.16E5 l ND l9.55E4 l1.45E4 14.18E3 l lCs-137 l9.07ES l8.2SE5 l1.28E5 i ND l2.72E5 l1.04E5 13.62E3 l lCs-138 l6.33E2 l8.40E2 l5.55E2 l ND l6.22E2 l6.81El l2.70E2 l lBa-139 l1.84E0 l9.84E-4 l5.37E-2 l ND j8.62E-4 l5.77E3 l5.77E4 l lBa-140 l7.40E4 l6.48E1 l4.33E3 l ND l2.11El l1.74E6 l1.02E5 l
lBa-141 l2.19E-1 l1.09E-4 l6.36E-3 l ND l9.47E-5 l2.92E3 l2.75E2 l lBa-142 l5.00E-2 13.60E-5 l2.79E-3 l ND l2.91E-5 l1.64E3 l2.74E0 l lLa-140 l6.44E2 l2.25E2
[7.55El l ND l ND l1.83E5 l2.26E5 l
lLa-142 l1.30E0 l4.11E-1 l1.29E-1 l ND l ND
[8.70E3 17.59E4 l lCo-141 l3.92E4 l1.95E4 l2.90E3 l ND l8,55E3 l5.44E5 l5.66E4 l lCo-143 l3.66E2 l1.99E2 l2.87El l ND l8.36El l1.15ES l1.27ES l
l lCo-144 l6.77E6 l2.12E6 l3.61ES l ND l1.17E6 l1.20E7 13.89ES l
lPr-143 l1.85E4 15.55E3 l9.14E2 l ND l3.00E3 l4.33E5 l9.73E4 l lPr-144 l5.96E-2 l1.85E-2 l3.00E-3 l ND l9.77E-3 l1.57E3 l1.97E2 l
lNd-147 [1.08E4 l8.73E3 l6.81E2 l ND l4.81E3 l3.28E5 l8.21E4 l lW-187 l1.63E1 l9.66E0 l4.33E0 l ND l ND l4.11E4 l9.10E4 l lNp-239 l4.66E2 13.34E1 l2.35El l ND l9.73E1 15.81E4 l6.40E4 l l
(a) The child age group determination; Table E-9 Reg. Guide 1.109, Rev. 1, 1977 i
l l
l !
l L
Rov. 4 TABLE 5 (Contd. )
PATINAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
Ground Plane Pathway 8
(M mrem /yr) per (pCi/sec)
Nuclide Total Body Skin Na-24 1.19E7 1.39E7 Cr-51 4.65E6 5.51E6 Mn-54 1.39E9 1.63E9 Mn-56 9.03E5 1.07E6 Fe-59 2.72E8 3.20E8 Co-58 3.79E8 4.44E8 Co-60 2.15E10 2.53E10 Ni-65 2.97ES 3.45ES Cu-64 6.07ES 6.88E5 2n-65 7.47E8 8.59E8 Br-83 4.87E3 7.08E3 Br-84 2.03E5 2.36E5 Rb-86 8.99E6 1.03E7 Rb-88 3.31E4 3.78E4 Rb-89 1.23E5 1.48E5 Sr-89 2.16E4 2.51E4 Sr-91 2.15E6 2.51E6 Sr-92 7.77ES 8.63E5 Y-90 4.49E3 5.31E3 Y-91m 1.00E5 1.16ES Y-91 1.07E6 1.21E6 l
Y-92 1.80E5 2.14E5 Y-93 1.83E5 2.51ES Zr-95 2.45E8 2.84E8 Zr-97 2.96E6 3.44E6 Nb-95 1.37E8 1.61E8 Mo-99 3.98E6 4.62E6 Tc-99m 1.84E5 2.11E5 Tc-101 2.04E4 2.26E4 Ru-103 1.08E8 1.26E8 Ru-105 6.36ES 7.21E5 l
Ru-106 4.22E8 5.07E8 Ag-110m 3.44E9 4.01E9 Te-125m 1.55E6 2.13E6 i
Te-127m 9.16E4 1.08E5
Rev. 4 TABLE 5 (Contd.)
Ground Plane Pathway 8
(M mrem /yr) per (WCi/sec)
Nuclide Total Body Skin Te-127 2.98E3 3.28E3 Te-129m 1.98E7 2.31E7 Te-129 2.62E4 3.10E4 Te-131m 8.03E6 9.46E6 Te-131 2.92E4 3.45E4 Te-132 4.23E6 4.98E6 I-130 5.51E6 6.69E6 I-131 1.72E7 2.09E7 I-132 1.23E6 1.45E6 I-133 2.45E6 2.98E6 I-134 4.47E5 5.30E5 I-135 2.51E6 2.93E6 Cs-134 6.86E9 8.00E9 Cs-136 1.53E8 1.74E8 Cs-137 1.03E10 1.20E10 Cs-138 3.59ES 4.10E5 Ba-139 1.06ES 1.19ES Ba-140 2.05E7 2.35E7 Ba-141 4.15E4 4.73E4 Ba-142 4.44E4 5.06E4 La-140 1.92E7 2.18E7 La-142 7.40E5 8.89ES Ce-141 1.37E7 1.54E7 Ce-143 2.31E6 2.63E6 Ce-144 6.96E7 8.04E7 Pr-144 1.84E3 2.11E3 Nd-147 8.41E6 1.01E7 V-187 2.36E6 2.74E6 Np-239 1.71E6 1.98E6....
Rev. 4 TABLE 5 (Contd.)
PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
MEAT PATWAY 8
(m mres/yr) per (pC1/sec) l l
l l Total l
l l
l l
lNuclidel Bone l Liver i Body 1 Thyroid i Kidney I Lung i GI-LLI l l H-3 l ND l2.34E2 l2.34E2 l2.34E2 l2.34E2 l2.34E2 l2.34E2 l
l C-14 l3.83E8 l7.67E7 17.67E7 17.67E7 17.67E7 l7.67E7 l7.67E7 l
l Na-24 l1.78E-3 l1.78E-3 l1.78E-3 11.78E-3 l1.78E-3 l1.78E-3 11.78E-3 l l P-32 l7.41E9 l3.47E8 l2.86E8 l ND l ND l ND l2.05E8 l
l Cr-51 l ND l ND l8.79E3 l4.88E3 l1.33E3 l8.91E3 l4.66ES l
l Mn-54 l ND l8.01E6 l2.13E6 l ND l2.25E6 l ND l6.72E6 l
l Mn-56 l ND l
0 l
0 l ND l
0 l ND l
0 l
l Fe-55 l4.57E8 12.42E8 l7.51E7 l ND l ND l1.37E8 l4.49E7 l
l Fe-59 l3.76E8 l6.09E8 l3.03E8 l ND l ND l1.76E8 l6.34E8 l
l Co-58 l ND l1.64E7 l5.02E7 l ND l ND l ND l9.58E7 l
l Co-60 l ND l6.93E7 l2.04E8 l ND l ND l ND l3.84E8 l
l Ni-63 [2.91E10 l1.56E9 19.91E8 l ND l ND l ND l1.05E8 l
l Ni-65 l 0
l 0
l 0
l ND l ND l ND l
0 l
l Cu-64 l ND l2.97E-7 l1.79E-7 l ND l7.17E-7 l ND l1.39E-5 l 1 Zn-65 l3.75E8 l1.00E9 l6.22E8 l ND l6.30E8 l ND l1.76E8 l
l Zn-69 l 0
1 0
l 0
l ND l
0 l ND l
0 l
l Br-83 l ND l ND l ND l ND l ND l ND l ND l
l Br-84 l ND l ND l ND l ND l ND l ND l ND l
l Br-85 l ND l ND l ND l ND j ND l ND l ND l
l Rb-86 l ND 15.82E8 l3.58E8 l ND l ND l ND l3.74E7 l
l Rb-88 l ND l
0
[
0 l ND l ND l ND l
0 l
l Rb-89 l ND l
0 l
0 l ND l ND l ND l
0 l
l Sr-89 l4.82E8 l ND l1.38E7 l ND l ND l ND l1.86E7 l
l Sr-90 l1.04E10 l ND l2.64E9 l ND l ND l ND l1.40E8 l
l Sr-91 12.40E-10l ND l
0 l ND l ND l ND l5.29E-10l -
O
R-v. 4 TABLE 5 (Contd. )
PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
4 MEAT PATHWAY 8
(m mram/yr) per (9Ci/sec) l l
l l Total l
l l
l l
lNuclidel Bone i Liver i Body l Thyroid l Kidney l Lung i GI-LLI l l Sr-92 l 0
l ND l
0 l ND l ND l ND l
0 l
l Y-90 l1.71E2 l ND
[4.59E0 l ND l ND l ND
[4.88E5 l
l Y-91t l 0
l ND l
0 l ND l ND l ND l
0 l
l Y-91 l1.80E6 l ND l4.82E4 l ND l ND l ND l2.40E8 l
l Y-92 l 0
l ND l
0 l ND l ND l ND l
0 l
l Y-93 l 0
l ND l
0 l ND l ND l ND l1.55E-7 l l Zr-95 l2.66E6 l5.85ES l5.21E5 l ND
[8.38E5 l ND
[6.11E8 l
l Zr-97 l3.20E-5 l4.63E-6 l2.73E-6 l ND l6.65E-6 l ND l7.02E-1 l l Nb-95 13.09E6 l1.20E6 l8.61E5 l ND l1.13E6 l ND l2.23E9 l
l Mo-99 l ND l1.15ES l2.84E4 l ND l2.46ES l ND l9.51E4 l l Tc-99ml 0
l 0
l 0
l ND l
0 l
0 l
0 l
l Tc-101l 0
l 0
l 0
l ND l
0 l
0 l
0 l
l Ru-103l1.55E8 l ND l5.96E7 l ND l3.90E8 l ND l4.01E9 l
l Ru-1051 0
l ND l
0 l ND l
0 l ND l
0 l
l Ru-106l4.44E9 l ND 15.54E8 l ND l5.99E9 l ND
[6.90E10 l lAg-110ml8.40E6 l5.67E6 l4.53E6 l ND l1.06E7 l ND l6.75E8 l
lTe-125ml5.69E8 11.54E8 l7.59E7 l1.60E8 l ND l ND
[5.49E8 l
lTe-127ml1.77E9 l4.78E8 l2.11E8 l4.24E8 15.06E9 l ND l1.44E9 l
lTe-127 l4.11E-10ll.11E-10 l 0
l2.85E-10 l1.17E-9 l ND l1.61E-8 l lTe-129ml1.79E9 l4.99E8 12.77E8 15.76E8 15.25E9 l ND l2.18E9 l
lTe-129 l 0
l 0
l 0
l 0
l 0
l ND l
0 l
lTe-131ml7.00E2 l2.42E2 l2.58E2 l4.98E2 l2.34E3 l ND 19.8253 l lTe-131 l 0
l 0
l 0
l 0
1 0
l ND l
0 l
lTe-132 l2.09E6 l9.26ES l1.12E6 l1.35E6 18.60E6 l ND 19.33E6 l
lI-130 l3.04E-6 l6.13E-6 l3.16E-6 l6.76E-4 l9.17E-6 l ND l2.87E-6 l l
l l 1 1
R v. 4 TABLE 5 (Contd.).
PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
MEAT PATHWAY 1
(m mrem /yr) per (uC1/sec) l l
l l Total l l
l l
l lNuclidel Bone !
Liver i Body i Thyroid l Kidney i Luna l GI-LLI l lI-131 l1.66E7 l1.66E7 19.46E6 l5.50E9
-l2.73E7 l ND l1.48E6 l lI-132 l 0
l 0
l 0
l 0
l 0
l ND l
0 l
lI-133 l6.16E-1 l7.61E-1 l2.88E-1 l1.41E2 l1.27E0 l ND l3.07E-1 l lI-134 l 0
1 0
l 0
l 0
l 0
i ND l
0 l
lI-135 l 0
l 0
l 0
l 0
l 0
l ND l
0 l
lCs-134 l9.22E8 l1.51E9 l3.19E8 -l ND l4.69E8 11.68E8 18.16E6 l lCs-136 l1.61E7 14.43E7 l2.86E7 l ND l2.36E7 l3.51E6 l1.56E6 l lCs-137 l1.33E9 l1.28E9 l1.88E8 l ND l4.16E8 l1.50E8 l7.99E6 l lCs-138.l 0
l 0
l 0
l ND l
0
.l 0
l 0
l lBa-139 l 0
l 0
l 0
l ND l
0 l
0 l
0 l
lBa-140 14.38E7 l3.84E4 l2.56E6 l ND l1.25E4 l2.29E4 12.22E7 l
lBa-141 l 0
l 0
l 0
l ND l
0 l
0
.l 0
l lBa-142 l 0
l 0
1 0
l ND l
0 l
0 l
0 l
l lLa-140 15.69E-2 l1.99E-2 l6.70E-3 l ND l ND l ND 15.54E2 l
lLa-142 l 0
l 0
l 0
l ND l ND l ND l
0 l
lCo-141 l2.22E4 l1.11E4 l1.64E3 l ND l4.85E3 l ND l1.38E7 l
l lCo-143 l3.17E-2 l1.72E1 l2.49E-3 l ND l7.21E-3 l ND l2.52E2 l j
lCe-144 l2.32E6 l7.26ES l1.24E5 l ND l4.02E5 l ND l1.89E8 l lPr-143 l3.35E4 l1.00E4 l1.66E3 l ND 15.44E3 l ND l3.61E7 l
lPr-144 l 0
l 0
l 0
l ND l
0 l ND l
0 l
lNd-147 l1.17E4 l9.50E3 l7.35E2 l ND l5.21E3 l ND l1.50E7 l
lW-187 l3.35E-2 l1.98E-2 l8.91E-3 l ND l N3 l ND l2.79E0 l lNp-239 l4.20E-1 13.02E-2 l2.12E-2,l ND
[8.72E-2 l ND l2.23E3 l 1 _
{
Rev. 4 TABLE 5 (Contd.)
PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
Grass-Cow-Milk Pathway 2
(m mrem /yr) per (uci/sec) l l
l l Total l l
l l
l lNuclidel Bone
! Liver i Body l Thyroid 1 Kidney I Lung l GI-LLI l l.
l ND l1.57E3 11.57E3 l1.57E3 l1.57E3 11.57E3 l1.57E3 l l C-14 l1.19E9 l2.39E8 12.39E8 l2.39E8
[2.39E8 12.39E8 l2.39E8 l l Na-24 l8.89E6 l8.89E6 l8.89E6 l8.89E6
[8.89E6 [8.89E6 [8.89E6 l l P-32 l7.77E10 l3.64E9 13.00E9 l ND l ND l NL l2.15E9 l l Cr-51 l ND l ND l1.03E5 l5.65E4 l1.56E4 l1.04E5 l5.40E6 l l Mn-54 l ND l2.10E7 l5.59E6 l ND
[5.88E6 l ND l1.76E7 l
l Mn-56 l ND l1.29E-2 12.90E-3 l ND l1.56E-2 l ND l1.86E0 l.
l Fe-55 l1.12E8 l5.93E7 l1.84E7 l ND l ND l3.35E7 l1.10E7 l
l Fe-59 l1.20E8 l1.94E8 l9.69E7 l ND l ND l5.64E7 l2.02E8 l
l Co-58 l ND l1.21E7 l3.71E7 l ND l ND l ND 17.07E7 l
l Co-60 l ND l4.32E7 l1.27E8 l ND l ND l ND l2.39E8 l l Ni-63 l2.69E10 l1.59E9 l1.01E9 l ND l ND l ND l1.07E8 l l Ni-65 l1.P E0 l1.56E-1 l9.01E-2 l ND l ND l ND l1.91El l
l Cu-64 l J
l7.46E4 l4.51E4 l ND l1.80E5 l ND l3.50E6 l l Zn-65 l4.13E9 l1.10E10 l6.85E9 l ND l6.94E9 l ND l1.93E9 l
l Zn-69 l 0
l 0
l 0
l ND l
0 l ND l1.12E-9 l l Br-83 l ND l ND l ND l ND l ND l ND l ND l
l Br-84 l ND l ND l ND l ND l ND l ND l ND l
l Br-85 l ND l ND l ND l ND l ND l ND l ND l
l Rb-86 l ND l8.80E9 15.41E9 l ND l ND l ND
[5.66E8 l l Rb-88 l ND l
0 l
0 l ND l ND l ND l
0 l
l Rb-89 ND l
0 l
0 l ND l ND l ND l
0 l
l Sr-89 6.62E9 l ND l1.89E8 l ND l ND l ND l2.56E8 l
l Sr-90 l1.12E11 l ND l2.83E10 l ND l ND l ND l1.51E9 l
l Sr-91 l1.30E5 l ND l4.92E3 l ND l ND l ND l2.88E5 l._
Rev. 4 TABLE 5 (Contd.)
PATINAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
Grass-Cow-Milk Pathway (a mrem /yr) per (pCi/sec)
.l l
l l Total l l
l l
l lNuclidel Bone l Liver l Body l Thyroid i Kidney l Lung l GI-LLI l l Sr-92 l2.18E0 l ND
[8.75E-2 l ND l ND l
ND l4.13E1 l l Y-90 l 3.22E2 l ND l8.62E0 l ND l ND l
ND l9.17E5 l
.l Y-91m l 0
l ND l
0 l ND l ND l
ND l
0 l
l Y-91 l3.90E4 l ND l1.04E3 l ND l F9 l
ND
[5.20E6 l l
l Y-92 l2.53E-4 l ND l7.24E-6 l ND l ND l
ND l7.31E0 l
}
l Y-93 l1.05E0 l ND l2.90E-2 l ND l ND l
ND l1.57E4 l l Zr-95 l3.83E3 l8.42E2 l7.50E2 l ND l1.21E3 l
ND 18.79ES l
l Zr-97 l1.92E0 l2.77E-1 l1.64E-1 l ND l3.98E-1 l ND l4.20E4 l l Nb-95 l3.18E5 l1.24E5 l8.84E4 l ND l1.16ES l
ND l2.29E8 l l Mo-99 l ND
[8.14E7 l2.01E7 l ND l1.74E8 l ND l6.73E7 l l Tc-99ml1.32E1 l2.59El l4.29E2 l ND l3.76E2 l1.32E1 l1.47E4 l l Tc-101l 0
l 0
l 0
l ND l
0 l
0 l
0 l
l Ru-103l4.28E3 l ND l1.65E3 l ND l1.08E4 l ND l1.11ES l l Ru-105l3.82E-3 l ND l1.39E-3 l ND l3.36E-2 l ND l2.49E0 l l Ru-106l9.24E4 l ND l1.15E4 l ND l1.2SES l
ND l1.44E6 l lAg-110ml2.09E8 l1.41E8 11.13E8 l ND l2.63E8 l
ND
.ll.68E10 l lTe-125ml7.38E7 l2.00E7 19.84E6 l2.07E7 l ND l
ND l7.12E7 l
lTe 127ml2.08E8 l5.60E7 l2.47E7 l4.97E7 l5.93E8 l ND l1.68E8 l lTe-127 l3.05E3 l8.22E2 16.54E2 l2.11E3 l8.67E3 l
ND l1.19ES l
l lTe-129ml2.71E8 l7.57E7 l4.21E7 l8.74E7 l7.96E8 l ND l3.31E8 l
lTe-129 l 0
l 0
l 0
l 0
l2.90E-9 l ND l6.17E-8 l lTe-131ml1.60E6 15.53E5
[5.89ES l1.14E6 l5.35E6 l ND l2.24E7 l
l lTe-131 l 0
l 0
1 0
l 0
l 0
l ND l
0 l
l lTe-132 l1.02E7 l4.52E6 l5.46E6 l6.58E6 l4.20E7 l
ND
[4.55E7 l lI-130 l1.73E6 l3.49E6 l1.80E6 l3.84E8 l5.22E6 l
ND l1.63E6 l l
f Rw.4 TABLE 5 (Contd.)
PATHVAY DOSE FACIORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
Grass-Cow-Milk Pathway 8
(m mrem /yr) per (VCi/sec) l l
l l Total l
l l
l l
lNuclidel Bone i Liver i Body l Thyroid l Kidney l Lung ! GI-LLI l lI-131 11.30E9 l1.31E9 l7.45E8 l4.33E11 l2.15E9 l ND l1.17E8 l lI-132 l6.02E-1 l1.11E0 l5.08E-1 l5.13E1 l1.69E0 l ND l1.30E0 l lI-133 11.74E7 l2.15E7 l8.13E6 l3.99E9 l3.58E7 l ND lB.66E6 l
lI-134 l 0
l 0
l 0
l 0
l 0
l ND l
0 l
lI-135 l5.40E4 l9.72E4 l4.60E4 l8.61E6 l1.49ES l ND l7.40E4 l lCs-134 12.26E10 l3.72E10 17.84E9 l ND l1.15E10 l4.13E9 l2.00E8 l
lCs-136 ll.01E9 l2.77E9 l1.79E9 l ND l1.43E9 l2.20E8 19.74E7 l
lCs-137 13.22E10 l3.09E10 l4.56E9 l ND l1.01E10 l3.62E9 l1.93E8 l lCs-138 l 0
l 0
l 0
l ND l
0 l
0 l
0 l
lBa-139 l1.89E-7 l 0
l5.48E-9 l ND l
0 l
0 ll.09E-5 l lBa-140 l1.17E8 l1.03E5 l6.84E6 l ND 13.34E4 l6.12E4 l5.93E7 l
lBa-141 l 0
l 0
l 0
l ND l
0 l
0 l
0 l
lBa-142 l 0
l 0
1 0
l ND l
0 l
0 1
0 l
lLa-140 l1.95El l6.80E0 l2.29E0 l ND l ND l ND l1.90E5 l
lLa-142 l 0
l 0
l 0
l ND l ND l ND l2.90E-6 l lCo-141 l2.19E4 l1.09E4 l1.62E3 l ND l4.78E3 l ND l1.36E7 l lCo-143 l1.87E2 l1.02E5 l1.47El l ND 14.26El l ND l1.49E6 l lCo-144 l1.62E6 l5.09ES l8.66E4 l ND l2.82E5 l ND l1.33E8 l lPr-143 l7.19E2 l2.16E2 l3.57El l ND l1.17E2 l ND 17.75ES l lPr-144 l 0
l 0
l 0
l ND l
0 l
ND l
0 l
l Nd-14') l4.45E2 l3.61E2 l2.79El l ND l1.98E2 l ND l5.71E5 l
lW-187 l2.91E4 l1.73E4 l7.73E3 l ND l ND l ND l2.42E6 l lNp-239 l1.72E1 l1.23E0 l8.68E-1 l ND l3.57E0 l ND 19.14E4 l,
Rev. 4 TABLE 5 (Contd.)
PATHVAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
Grass-Goat-Milk Pathway 2
(m mrem /yr) per (pCi/sec) l l
l l Total l
l l
l l
lNuclidel Bone l Liver i Body i Thyroid i Kidney l Lung i GI-LLI l l H-3 l ND l3.20E3 13.20E3 l3.20E3 l3.20E3 l3.20E3 13.20E3 l l C-14 l1.19E9 l2.39E8 l2.39E8 l2.39E8 12.39E8 l2.39E8 l2.39E8 l l Na-24 l1.07E6 l1.07E6 l1.07E6 l1.07E6 l1.07E6 l1.07E6 l1.07E6 l l P-32 l9.33E10 l4.37E9
'l3.60E9 l ND l ND l ND l2.58E9 l l Cr-51 l ND l ND l1.23E4 l6.78E3 l1.87E3 l1.25E4 16.48E5 l l Mn-54 l ND l2.52E6 l6.70E5 l ND l7.06ES l ND l2.11E6 l l Mn-56 l ND l1.54E-3 13.49E-4 l ND l1.87E-3 l ND l2.24E-1 l l Fe-55 11.45E6 l7.71ES 12.39E5 l ND l ND l4.36E5 l1.43E5 l
l Fe-59 l1.56E6 l2.53E6 l1.26E6 l ND l ND l7.33E5 l2.63E6 l l Co-58 l ND l1.45E6 14.45E6 l ND l ND l ND l8.49E6 l l Co-60 l ND l5.18E6 l1.53E7 l ND l ND l
ND l2.87E7 l l Nt-63 l3.56E9 l1.90E8 l1.21E8 l ND l ND l
ND l).28E7 l
[ Ni-65 ll.99E-1 l1.87E-2 l1.09E-2 l ND l ND l ND l2.29E0 l l Cu-64 l ND l8.31E3 15.02E3 l ND l2.01E4 l ND
[3.90E5 l
l Zn-65 l4.96E8 l1.32E9 l8.22E8 l ND
[8.33E8 l ND l2.32E8 l l Zn-69 l 0
l 0
l 0
l ND l
0 l ND l1.35E-10l l Br-83 l ND l ND l ND l ND l ND l ND l ND l
l Br-84 l ND I ND l ND l ND l ND l
ND l ND l
l Br-85 l ND l ND l ND l ND l ND l hT l ND l
l Rb-86 l ND l1.06E9 l6.50E8 l ND l ND l ND l6.80E7 l
l Rb-88 l h3 l
0 l
0 l ST l hT l hT l
0 l
l Rb-89 l ND l
0 l
0 l ND l ND l hD l
0 l
l Sr-89 l1.39E10 l ND l3.97E8 l ND l ND l ND l5.38E8 l
l Sr-90 l2.35E11 l ND l5.95E10 l ND l ND l ND l3.16E9 l l Sr-91 l2.74E5 l ND l1.03E4 l ND l ND l
ND l6.04E5 l
i...
Rev. 4 TABLE 5 (Contd.)
PATlWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
Grass-Goat-Milk Pathway 8
(m mrem /yr) per (uci/sec) l i
l l Total l
l l
l l
lNuclidel Bone i Liver I Body 1 Thyroid l Kidney l Lung i GI-LLI l l Sr-92 l4.58E0 l ND l1.84E-1 l ND l ND l ND l8.68E1 l l Y-90 13.87El l ND l1,03E0 l ND l ND l ND
{1.10E5 l
l Y-91m l 0
l ND l
0 l ND l ND l ND l
0 l
l Y-91 l4.68E3 l ND l1.2SE2 l ND l ND l ND l6.24E-5 l l Y-92 l3.04E-5 l ND l8.69E-7 l ND l ND l ND l8.77E-1 l l Y-93 l1.27E-1 l ND l3.48E-3 l ND l ND l ND ll.89E3 l
l Zr-05 l4.60E2 l1.01E2 l9.00E1 l ND l1.45E2 l ND l1.05E5 l
l Zr-97 l2.30E-1 l3.33E-2 l1.96E-2 l ND l4.78E-2 l ND l5.04E3 l
l Nb-95 l3.81E4 l1.48E4 l1.06E4 l ND l1.39E4 l ND l2.75E7 l
! Mo-99 l ND 19.76E6 l2.42E6 l ND l2.09E7 l ND l8.08E6 l
l Tc-99ml1.59E0 l3.11E0 l5.15El l ND l4.52E1 l1.58E0 l1.77E3 l
l Tc-101l 0
l 0
l 0
l ND l
0 l
0 1
0 l
l Ru-103l5.14E2 l ND l1.98E2 l ND l1.29E3 l ND l1.33E4 l l Ru-105l4.58E-4 l ND l1.66E-4 l ND l4.03E-3 l ND l2.99E-1 l l Ru-106l1.11E4 l ND l1.38E3 l ND l 1.50E6 l ND ll.72E5 l
lAg-110ml2.51E7 l1.69E7 l1.35E7 l ND l3.15E7 l ND l2.01E9 l
lTe-125ml8.85E6 l2.40E6 11.18E6 12.48E6 l ND l ND l8.54E6 l
lTe-127ml2.50E7 l6.72E6 l2.96E6 l5.97E6 l7.12E7 l ND l2.02E7 l
-lTe-127 l3.66E2 19.86El l7.85El l2.53E2 l1.04E3 l ND l1.43E4 l lTe-129ml3.25E7 l9.09E6 l5.05E6 l1.05E7 l9.55E7 l ND l3.97E7 l
lTe-12! l 0
l 0
l 0
l 0
l 0
l ND
[7.40E-9 l lTe-131ml1.92E5 16.64E4 l7.07E4 l1.37ES l6.43E5 l ND l2.69E6 l lTe-331 l 0
l 0
l 0
l 0
l 0
l ND l
0 l
lTe-132 l1.23E6 l5.42E5 16.55ES l7.90E5 l5.04E6 l ND lS.46E6 l lI-130 l2.07E6 l4.19E6 l2.16E6 l4.61E8 l6.26E6 l ND l1.96E6 l
R*v. 4 i
TABLE 5 (Contd.)
PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
Grass-Goat-Hilk Pathway 2
(m mrem /yr) per (uCi/sec) l l
l l Total l
l l
l l
lNuclidel Bone l Liver l Body l Thyroid i Kidney l Lung l GI-LLI l lI-131 l1.56E9 l1.57E9 l8.94E8 l5.20E11 l2.58E9 l ND l1.40E8 l
lI-132 l7.22E-1 l1.33E0 l6.10E-1 l6.15El l2.03E0 l ND l1.56E0 l lI-133 12.09E7 12.58E7 l9.76E6 l4.79E9 l4.30E7 l ND l1.04E7 l
lI-134 l 0
l 0
l 0
[
0 l
0 l
ND l
0 l
lI-135 l6.48E4 l1.17ES l5.52E4 l1.03E7 l1.79E5 l ND l8.88E4 l lCs-134 l6.79E10 l1.11E11 l2.35E10 { ND l3.45E10 l1.24E10 l6.01E8 l lCs-136 l3.03E9 l8.32E9 l5.38E9 l ND l4.43E9 l6.61E8 l2.92E8 l lCs-137 l9.67E10 19.26E10 l1.37E10 l ND l3.02E10 l1.09E10 l5.80E8 l lCs-138 l 0
l 0
l 0
l ND l
0 l
0 l
0 l
lBa-139 l2.27E-8 l 0
l 0
l ND l
0 l
0 l1.31E-6 l lBa-140 l1.41E7 l1.23E4 l8.20E5 l ND
!4.01E3 l7.34E3 l7.12E6 l
lBa-141 1 0
l 0
l 0
l ND l
0 l
0 l
0 l
lBa-142 l 0
l 0
l 0
l ND l
0 1
0 l
0 l
lLa-140 l2.34E0 l8.17E-1 l2.75E-1 l ND l ND l ND l2.28E4 l lLa-142 l 0
1 0
l 0
l ND l ND l ND l3.49E-7 l lCe-141 l2.62E3 l1.31E3 l1.94E2 l ND l5.74E2 l ND l1.63E6 l
lCo-143 l2.2SE1 l1.22E4 l1.77E0 l ND l5.12E0 l ND ll.79E5 l
lCo-144 l1.95ES l 6.11E4 l1,04E4 l ND l3.38E4 l ND l1.59E7 l
lPr-143 l8.62E1 l2.59El 14.28E0 l ND l1.40E1 l ND l9.30E4 l lPr-144 l 0
l 0
l 0
l ND l
0 l ND l
0 l
l lNd-147 l5.34E1 14.33E1 l3.35E0 l ND l.". 3 7E l l ND l6.85E4 l lW-187 l3.49E3 12.07E3 l9.27E2 l ND l ND l ND l2.90E5 l
lNp-239 l2.06E0 l1.48E-1 l1.04E-1 l ND l4.28E-1 l ND l1.10E4 l i
I 4 r
._-.r-
-, _..m.._.
m,,
Rev. 4 TABLE 5 (Contd.)
PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
Vegetation Pathway 8
(m mrem /yr) per (yCi/sec) l l
l l Total l
l l
l l
lNuclidel Bone l
Liver l Bedy l Thyroid l Kidney l Lung i GI-LLI l l H-3 l ND l4.01E3 14.01E3 l4.01E3 l4.01E3 l4.01E3 l4.01E3 l
l C-14 l8.89E8 l1.78E8 l1.78E8 l1.78E8 l1.78E8 l1.78E8 l1.78E8 l
l Na-24 l3.75E5 l3.75E5 l3.75E5 13.75ES 13.75ES l3.75E5 l3.75E5 l
l P-32 l3.37E9 ll.57E8 l1.30E8 l ND l ND l
ND l9.30E7 l
l Cr-51 l ND l ND l1.17ES l6.50E4 11.78E4 l1.19ES 16.21E6 l
l Mn-54 l ND l6.65E8 l1.77E8 l ND l1.86E8 l ND
[5.58E8 l
l Mn-56 l ND l1.88E1 l4.24E0 l ND l2.27El l
ND l2.72E3 l
l Fe-55 l8.01E8 l4.25E8 l1.32E8 l
ND l ND l2.40E8 l7.87E7 l
l Fe-59 l3.97E8 l6.43E8 l3.20E8 l ND l ND l1.86E8 l6.69E8 l
l Co-58 l ND l6.44E7 l1.97E8 l ND l ND l
ND l3.76E8 l
l Co-60 l ND l3.78E8 l1.12E9 l
ND l ND l ND l2.10E9 l
l Ni-63 l3.95E10 l2.11E9 l1.34E9 l
ND l ND l ND l1.42E8 l
l Ni-65 l1.05E2 l9.89E0 l5.77E0 l ND l ND l ND l1.21E3 l
l Cu-64 l ND l1.10E4 l6.64E3 l ND l2.66E4 l ND l5.16ES l
l Zn-65 l8.12E8 12.16E9 l1.35E9 l ND l1.36E9 l ND l3.80E8 l
l Zn-69 l1.09E-5 l1.57E-5 l1.45E-6 l ND l9.52E-6 l ND
[9.11E-4 l l Br-83 l ND l ND l5.37E0 l ND l ND l ND l
0 l
l Br-84 l ND l ND l
0 l ND l ND l ND l
0 l
l Br-85 l ND l ND l
0 l ND l ND l ND l
0 l
l Rb-86 l ND
[4.58E8 l2.82E8 l ND l ND l ND l2.94E7 l
l Rb-88 l ND l
0 l
0 l ND l ND l ND l
0 l
l Rb-89 l ND l
0 l
0 l ND l ND l ND i
0 l
l Sr-89 l3.59E10 l ND l1.03E9 l ND l ND l ND l1.39E9 l
l Sr-90 l1.24E12 l ND l3.15E11 l ND l ND l ND l1.67E10 l l Sr-91 l5.24E5 l ND l1.98E4 l ND l ND l ND l1.16E6 l
I -
~
Rev. 4 TABLE 5 (Contd.)
PATINAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
Vegetation Pathway 8
(m mremifr) per (pC1/sec) l l
l l Total l
l l
l l
lNuclidel Bone,..
Liver i Body i Thyroid i Kidney l Lung l GI-LLI l l Sr-92 l7 !3E2 l ND l2.92E1 l ND l ND l ND l1.38E4 l l Y-90 l2.31E4 l ND l6.18E2 l ND l ND l ND l6.57E7 l
l Y-91m l8.87E-9 l ND l3.23E-10] ND l ND l ND l1.74E-5 l l Y-91 l1.86E7 l ND l4.99ES l ND l ND l ND l2.48E9 l
l Y-92 l1.58E0 l ND l4.53E-2 l ND l ND l
ND l4.58E4 l l Y-93 l3.01E2 l ND l8.25E0 l ND l
ND.
I ND l4.48E6 l l Zr-95 l3.86E6 l8.45ES 17.55E5 l ND l1.21E6 l ND l8.84E8 l
l Zr-97 l5.70E2 l8.24E1 l4.86El l ND l1.18E2 l ND l1.25E7 l
l Nb-95 l4.10E5 11.SiE5 l1.14E5 l ND l1.50E5 l ND l2.95E8 l
l Mo-99 l ND l7.71E6 l1.91E6 l ND l1.65E7 l ND l6.3856 l l Tc-99ml4.71E0 l9.24E0 l1.53E2 l ND l1.34E2 l4.69E0 l5.26E3 l
l Tc-101[
0 l
0 l
0 l ND l
0 l
0 l
0 l
l Ru-103l1.54E7 l ND l5.90E6 l ND l3.87E7 l ND
[3.97E8 l
l Ru-105l9.16El l ND l3.32E1 l ND l8.05E2 l ND l5.98E4 l l Ru-106l7.45E8 l ND l9.30E7 l ND
01E9 l ND l1.16E10 l lAg-110mj3.22E7 l'.17E7 ll.74E7 l ND l4.05E7
- W l2.58E9 l
lTe-125ml3.51E8 l9.50E7 l4.67E7
[9.84E7 l ND l ND
[3.38E8 l lTe-127ml1.32E9 l3.56E8 l1.57E8 l3.16E8 l3.77E9 l ND l1.07E9 l
lTe-127 l1.00E4 12.69E3 l2.14E3 l6.91E3 l2.84E4 l ND l3.90E5 l
lTe-1-29ml8.38E8 l2.34E8 11.30E8 l2.70E8 l2.46E9 l ND l1.02E9 l
lTe-129 l1.16E-3 l3.23E-4 l2.75E-4 l8.26E-4 l3.39E-3 l ND
[7.20E-2 l lTe-131ml1.54E6 l5.33E5 l5.68E5 l1.10E6 l5.16E6 l ND l2.16E7 l
lTe-131 l 0
1 0
l 0
l 0
l 0
l ND l
0 l
lTe-132 l6.98E6 l3.09E6 l3.73E6 l4.50E6 l2.87E7 l ND l3.11E7 l
lI-130 j6.16E5 l1.24E6 l6.38E5 l1.37E8 11.86E6 l ND l5.79E5 l
i l
t l
1 l
61 -
l l
Rtv. 4 TABII 5 (Contd.)
PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g
Vegetation Pathway 2
(m mrem /yr) per (pCi/sec) l l
l l Total l
l l
l l
lNuclical Bone l
Liver i Body l Thyroid i Kidney !
Lung l GI-LLI l lI-131 l1.43E8 l1.44E8 18.17E7 l4.75E10 l2.36E8 l
ND ll.28E7 l
lI-132 l8.58E1 l1.58E2 l7.25El l7.31E3 l2.41E2 l ND l1.86E2 l lI-133 l3.56E6 l4.40E6 l1.67E6 l8.18E8 l7.34E6 l ND l1.77E6 l lI-134 11.55E-4 l2.88E-4 l1.32E-4 16.62E-3 l4.40E-4 l ND l1.91E-4 l lI-135 l6.62E4 l1.13E5 15.33E4 l9.97E6 l1.70E5 l ND l8.58E4 l lCs-134 l1.60E10 l2.63E10 l5.55E9 l ND l8.15E9 l2.93E9 l 1.42E8 l lCs-136 l8.17E7 l2.25E8 11.45E8 l ND l1.20E8 l1.78E7 l7.90E6 l lCs-137 l2.39E10 l2.29E10 13.38E9 l ND l7.46E9 12.68E9 l1.43E8 l lCs-138 l 0
l 0
l 0
l ND l
0 1
0 l
0 l
lBa-139 l4.80E-2 l2.56E-5 l1.39E-3 l ND l2.24E-5 l1.51E-5 l2.77E0 l lBa-140 l2.77E8 l2.42E5 l1.62E7 l ND l7.89E4 l1.45E5 11.40E8 l lBa-141 l 0
l 0
l 0
l ND l
0 l
0 l
0 l
lBa-142 l 0
l 0
l 0
l ND l
0 l
0 l
0 l
lLa-140 l3.25E3 l1.14E3 l3.83E2 l ND l ND l ND l3.17E7 l lLa-142 l2.50E-4 l7.98E-5 l2.50E-5 l ND l ND l ND jl.58E1 l lCe-141 l6.56ES l3.27E5 l4.86E4 l ND l1.43E5 l
ND l4.08E8 l lCe-143 l1.72E3 l9.31ES l1.35E2 l ND l3.91E2 l ND l1.36E7 l lCe-144 l1.27E8 l3.98E7 l6.78E6 l ND l2.21E7 l ND l1.04E10 l lPr-143 l1.46ES l4.38E4 l7.2SE3 l ND l2.37E4 l ND l1.58E8 l lPr-144 l 0
l 0
l 0
l ND l
0 l ND l
0 l
lNd-147 l7.17E4 l5.81E4 l4.50E3 l ND l3.19E4 l ND l9.20E7 l
lW-187 16.4 E4 l3.83E4 l1.72E4 l ND l ND l ND l5.38E6 l lNp-239 l2.';5E3 l1.83E2 11.29E2 l ND l5.30E9 l ND l1.36E7 l
l
, t.
Rev. 4 TABLE 5 NOTES The values presented in Table 5 were calculated ac-cording to the methodology and guidance provided in NUREG 0133, Rev. 0 (1978),
Specific parameters utilized are:
Parameter Value Reference SF 0.7 Ref. 9.11.2 f
1.0 Ref. 9.8.2 p
f, 1.0 Ref. 9.8.2 H
8.0 g/m' Ref. 9.8.2 f
1.0 Ref. 9.8.5 g
f 0.76 Ref. 9.8.5 g
i.
~.
Rev. 4 The cumulative critical organ doses for a monthly, quarterly or annual ovaluation are based on the calcu-lated dose contribution from each specified time period occurring during the reporting period.
3.6 Gascous Radwaste Treatment System l 3.6.1 Technical Specification 3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areae at and beyond the SITE BOUNDARY would exceed:
a.
0.2 mrad to air from gamma radiation, or b.
0.4 mr:d to air from beta radiation, or c.
O.3 mrem to any organ of an Individual 3.6.2 Description of the Gaseous Radwaste Treatment System The gaseous radwaste treatment system and the ventila-tion exhaust system are available for use whenever gaseous effluents require treatment prior to being released to the environment.
The gaseous radwaste treatment system is designed to allow for the retention of all gaseous fission products to be discharged from the reactor coolant system.
The retention system con-sists of eight (8) waste gas decay tanks, six (6) for use during normal operations and two (2) for use during shutdown conditions.
These systems will provide roas-onable assurance that the releases of radioactive materials in gaseous effluents will be kept ALARA.
{
- l l
1 l
t
Rev. 4 3.6.3 OPERABILITY of the Gaseous Radwaste Treatment System The OPERABILITY of the gaseous radwaste treatment sys-tem ensures this system will be available for use when gases require treatment prior to their release to the environment.
OPERABILITY is demonstrated through com-l pliance with Technical Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.
l Projected doses (gamma air, beta air, and organ dose) l due to gaseous effluents at or beyond the SITE BOUNDARY l are determined each 31 days by dividing the cumulative l annual total by the number of elapsed months.
m Rev. 4 4.0 DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES l 4.1 Technical Specification 3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactiv-ity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.
4.2 ODCM Methodology for Determining Dose and Doso Commitment frcm Uranium Fuel Cycle Sources The annual dose or dose commitment to a MEMBER OF THE PUBLIC for Uranium Fuel Cycle Sources is determined as:
a)
Dose to the total body due to gamma ray expo-sure from immersion in a cloud of radioactive noble gases and direct radiation from the unit and outside storage tanks; b)
Dose to the skin due to beta radiation from immersion in a cloud of radioactive noble gases; c)
Thyroid dose due to inhalation and ingestion of radiciodines.
d)
Organ dose due to inhalation and ingestion of radioactive material.
Since the doses via liquid releases are very conserva-tively evaluated, there is reasonable assurance that no real individual will receive a significant dose from radioactive liquid release pathways (<1 mrem fyr/
reactor).
Therefore, only doses to individuals via airborne pathways and doses resulting from direct radi-ation are considered in determining compliance to 40 CFR 190.
(Ref. 9.12.3)
It should be noted that there are no other Uranium Fuel Cycle Sources within 8km of the CallAway Plant.
The annual dose or dose commitment to a MEMBER OF THE PUBLIC from Uranium Fuel Cycle Sources, is determined whenever the calculated doses from the release of radi-oactive materials in liquid or gaseous effluents exceed,
Rev. 4 l twice the limits of Technical Specifications 3.11.1.2a, 3.11.1.26, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a, or 3.11.2.3b.
(Ref. 9.12.1 and 9.12.2.)
For those situa-tions where these limits are not exceeded by substan-tial amounts, it should be possible to demonstrate con-tinued compliance with 40 CER 190 through reevaluation of the exceeded Appendix I design objective dose using more realistic assumptions.
(Ref. 9.12.3 and 9.12.4.)
4.2.1 Identification of the MEMBER OF THE PUBLIC The MEMBER OF THE PUBLIC is considered to be a real in-dividual, including all persons not occupationally as-sociated with the Callaway Plant, but who may use por-tions of the plant site for recreational or other pur-poses not associated with the plant.
(Ref. 9.13.1 and 9.8.11.)
Accordingly, it is necessary to characterize this individual with respect to his utilisation of areas both within and at or beyond the SITE BOUNDARY and identify, as far as possible, major assumptions which can be reevaluated as previsously mentioned.
4.2.1.1 Utilization of Areas Within the SITE BOUNDARY The Union Electric Company has entered into an agreement with the State of Missouri Department of Con-servation for management of the residual lands sur-rounding the Callaway Plant, including some areas l within the SITE BOUNDARY.
Under the terms of this l agreement, certain areas have been opened to the public l for low intensity recreational uses (hunting, hiking, l sightseeing, etc.) but recreational use is excluded in i an area immediately surrounding the plant site (Refer j to Figure 4.1).
Much of the residual lands within the l SITE BOUNDARY are leased to area farmers by the Depart-l ment of Conservation to provide income to support l management and development costs.
Activities conducted l under these leases are primarily comprised vf farming 1 (animal feed), grazing, and forestry.
(Ref 9.7.2, l
9.7.4, 9.14, 9.14.1).
l Based on the utilization of areas within the SITE BOUN-l DARY, it is reasonable to acsume that the maximum ex-l posed member of the public is a farmer.
The current i tenant has estimated that he spends approximately l 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> per year working in this area (Ref 9.5.6).
1 Occupancy of areas within the SITE BOUNDARY is assumed l to be averaged over a period of one year. 1
R6v. 4 l Any reevaluation of assumptions should include a reev-aluation of the occupancy period at the locations of l real exposure (e.g. a real individual would not simultaneously exist at each point of maximum I exposure).
4.2.2 Total Dose from Gaseous Effluents The annual dose to a MEMBER OF THE PUBLIC from gaseous effluents is determined through the use of the m.etho-dology presented by equations (3.11), (3.12), and (3.14), using the appropriate atmospheric dispersion parameters from Table 9 and Table 10 for the maximum l exposed real individual.
Doses are evaluated for the l plume exposure, inhalation, and grass-cow-meat l pathways.
P 4.2'.3 Total Dose from Direct Radiation l 4.2.3.1 Direct Radiation Dose from Outside Storage Tanks The Refueling Water Storage Tank (RWST) has the highest potential for receiving significant amounts of radiosc-tive materials, and constitutes the only potentially significant source of direct radiation dose from out-side storage tanks to a MEMBER OF THE PUBLIC. (Ref.
9.6.17, 9.6.18, 9.5.19, and 9.6.20.)
The direct radiation dose from the RWST is determined by isotopic measurement of the tank contents and calcu-I lation of the direct dose ucing the methodology pre-l sented below.
Direct radiation dose from the RWST to a MEMBER OF THE l PUBLIC is determined at the nearest point of the Owner l Controlled Area fence which }has been determined to bes not obscured by signifi-cant plant structures.
This 450 meters from the RWST.
The RWST is approximately 12 meters in diameter, 14 meters in height with a capacity of approximately 1,514,000 liters.
(Ref. 9.6.20.)
The walls are of type 304 stainlass steel and have an average thickness of.87 cm.
(Ref. 9.16.1.)
Assuming that the RWST approximates a point source at this distance, and neglecting attenuation provided by the walls of the tank, the exposure rate from monoen- -
Rsv. 4 ergetic gamma radiation is given by:
ER = BAT exp( p, d)
(4.1) 2 d
Where:
ER
= Exposure rate at distance d from a point source of strength A, (in Roentgens / hour).
B
= Buildup factor.
A
= Activity of the source, (in Curies).
d
= Distance from the source, (in meters).
p
= Linear attenuation coefficient for air, in en (m-1).
T
= Exposure rate constant, (in R - m /Ci -
hr.).
The exposure rate constant P is given by:
T = K f Ep, (4.2)
Where:
E
= Energy of the gamma radiation, in (MeV).
p,
= Linear absorption coefficiene for air, (in
~1).
m t
l f
= Number of photons emitted per disintegration.
K
= Constant, 1.49 E04 R - m /hr - MeV - C1.
T
= Is as previously defined.
I For nuclides emitting multiple gamma rays, equation (4.1) becomes:
ER = KA IB1 (fg g p,1) exp (-p d)
I4'3)
E eni 1
2 d
Where:
B
= Buildup factor for ith photon.
f 1
i ---.
Rev. 4 E
= Energy of the ith photon, (in MeV).
g 9,1
= Linear absorption coefficient for air, for the ith photon, (in m~1).
p
= Linear attenuation coefficient for air, for eni
~
the ith photon, (in m
).
fi
= Number of ith photons emitted per disintegration.
ER, K,A, and d are as previously defined.
For photon energies in the range of 60 kev to 2 MeV, the value of the linear absorption coefficient for air is relatively constant (+ 15%), therefore, equation (4.3) can be approximated as:
ER = K'A IB (f
E) exp (-peni )
I4'4) d g
g g
2 i
d Where:
2 K'
= A constant, 0.48 R-m /hr - MeV - Ci.
ER, A, d, f,E, B,
and p are as previously f
g g
eni defined.
Through the use of equation (4.4), the exposure rate for a particular nuclide can be determined.
The total exposure rate from the RWST is calculated as:
ER total = $ ER)
(4.5)
ERtotal
= Total exposure rate at the location of the MEMBER OF THE PUBLIC from the RWST, (in Roentgen / hour).
ER)
= Calculated exposure rate from the jth nuclide, (in Roentgen /hr).
l The total direct radiation dose rate from the RWST to a MEMBER OF THE PUBLIC is given by:
l DRtotal =ERtotal (4.6) !
L
Rsv. 4 Where:
DR
=
a se ra e fr m e
(n total rem,hr).
ER is as previously defined.
total The direct radiation dose to a MEMBER OF THE PUBLIC is then determined for a specific time period:
(DRtotal) (t)
(4.7)
D
=
DR D
= Direct radiation dose to a MEMBER OF DR THE PUBLIC for the specific time inter-val, (in rem).
l 3.01
= Occupancy factor (1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> / year +
365.25 days / year), (in hours / day).
t
= Length of specific time period, (in days).
DR is as previously defined.
total l 4.2.3.2 Direct Radiation Dose from the Reactor The maximum direct radiation dose from the Unit to a l MEMBER OF THE PUBLIC has been determined to be 7E-2 mrads/ calendar year, based on a point source of primary coolant N-16 in the steam generators.
This source term was then projected onto the inside surface of the con-l tainment domt, taking credit for shielding provided by l the containment dome and for distance attenuation.
No l credit was allowed for shielding by other buildings.
A number of gammas per second was generated and then con-verted to a dose rate at the given distance by use of ANSI /ANS-6.6.1, "Calculation and Measurement of Direct and Scattered Gamma Radiation from LWR Nuclear Power Plant 1979".
This method considers attenuation and bu-11 dup in sir.
The final value is based on one unit l operating at 100% Power.
The distance was determined l to be 367 meters, which is approximately the closest l point of the boundary of the Owner Controlled Area l fence, which is not obscurred by significant plant I structures.
(Ref. 9.16.4) i
.______--_m_-_u_-__.____._._
Rev. 4 The maximum direct radiation dose from the Unit to a MEMBER OF THE PUBLIC due to activities within the SITE l BOUNDARY is thus approximately 9E-3 mrads per year, as-l suming a maxiiaum occupancy of 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> per year.
i i
l l
i I
I if l;
s' li if d *l,-
i c'
- 7 r
ll s'
"g n
f,f $ :h
=i xx\\\\\\
n z
"' ' ** k'W.-
//
i, s
i
='
g
~.
y e
.\\
d'
!s I
at s
9 sg h
n-x et 5 5
\\$
E
=L Y
IJ!
su t
--~
l r
l y
=
~*;
s c'o.N o
4 N
I L
.g
/y,
,[,
I
/
s
/
/
/
k 5
I
/
e*
i N
,a l
i
?
I I
3 i
gy
~..
L
Rev. 4 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 5.1 Radiological Effluent Technical Specification 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.
(ODCM Table 6).
5.2 Description of the Radio.'.ogical Environmental Monitoring Program The Radiological Enviormental Monitoring Program is in-tended to act as a background data base for preopera-tion and to supplement the radiological effluent release monitoring program during plant operation.
Radiation exposure to the public from the various spe-cific pathways and direct radiation can be adequately evaluated by this program.
Some deviations from the sampling frequency'may be necessary due to seasonal unavailability, hazardous conditions, or other legitimate bases.
Efforts are made to obtain all required samples within time frame outlines.
Any deviation (s) in sampling frequency or location is documented in the Annual Radiological En-vironmental Operating Report.
The Environmental samples are collected and analyzed at the frequency outlined in Table 6.
Reporting levels and 1cwer limits of detection (LLD) are outlined in Ta-bles 7 and 8.
Samples collected under the monitoring program are analyzed by an independent, third-party laboratory.
This laboratory is required to participate in the En-vironmental Protection Agency's (EPA) Environmental Radioactivity Laboratory Intercomparison Studies (Crosscheck) Program or an equivalent program.
Partic-ipation includes all of the determinations (sample medium - radionuclide combination) that are offered by the EPA and that are also included in the monitoring program...-
3 Rev. 4 TABLE 6 RADIOLOGICAL ENVIRONMENTAL MONITORING IROGRAM NUMBER Of REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPl[__
SAMPLE LOCATIONS COLLECTION FREQUENCY OF ANALYSIS 1.
Direct Radiationb 40 routine monitoring station either At least once per 92 Camma Dose with two or more dosimeters or with
- days, one instrument for measuring end recording dose rato continuously, placed as follows:
An inner ring of sixteen stations, one in each meteorological sector in the genera l area of the SITE BOUNOARY.
' Station Codq_
lector 11te Description Location 4
A O.6 Miles East of Hwy O and CC Junction 1.9 mi. # 354* N 47 8
County Road 335, 0.9 Miles South or O.9 mi. # 20* NNE Hwy O l
l 48 C
Plant Security and Wildifre Management 0.5 mi. # 47* NE Area Sign Post (Heavy Haul Road) r 5
D Prims ry Meteorological Tower 1.3 mi. @ 76* ENE l
49 E
Callaway Electric Cooperetive Utility 1.7 mi. e 94* E Polo No. 06959 52 f
Light Polo Near East Plant Security 0.3 al. # 111* ESE fence 51 C
Located in the "Y" of the Paltroad 0.7 mi. @ 132' SE Spur, NW of Sludge Lagoon 50 H
lleavy llaul Road, Intake /Di scha rge 1.1 mi. @ 157* SSE Pipe l ine Ma rke r 7
J Callaway Electric Cooperative utility 1.3 mi. e 173* S Polo No. 18715 l
37 K
Piezometer M8 and M6 0.5 mi. 4 204* SSW 43 L
Plant Security and Wildlife Management 0.5 mi. @ 224* SW l
Area Sign (Heavy Haul Road) l _-
~
ETY, h TABLE 6 (Continuedt RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Station Code Sector Site Descrigtlon Location 44 H
Callaway Electric Cooperative Utility 1.7 al. # 249* WSW Polo No. 18769 6
N Akers farn 1.8 al. # 277* W 45 P
NW Side or Intersection or CC and AD 0.9 al. 4 287* WNW 3
Q Callaway Electric Cooperative Utilty 1.6 ml. # 322' NW
.I Polo No. 18450 46 R
0.3 Mile South of the CC and 0 Junction 1.5 ml. 4 333' NNW An outer ring of sixteen stations, one in each meteorological sector in the 6-to 8-km range f rom the site 36 A
Callaway Electric Cooperative utility 4.9 al. # 8' N Polo No. 19137 21 8
Callaway Electric Cooperative utility 3.8 al. 4 28' NNE Pole No. 19100 20 C
Callaway Electric Cooperative Utility 4.8 al. G 45* NE.
Pole No. 12630 16 D
Ca l l away E l ec t r i c Coope ra t i ve U t i l i ty 4.1 al. # 75* ENE Pole No. 12976 17 E
0.5 Miles East of Itwy D, 1.5 Miles 4.0 ml. # 88* E Soutti of Hwy D and 0 Junction 15 F
Lamb Farm 4.2 al. 8 117* ESE 11 C
City or Portland 5.0 al. e 136* SE 10 H
Callaway Electric Cooperative Utility 4.0 mi. # 156' SE Polo No. 12179 9
J NW Clde of the Heavy Haul Road and 3.7 al. # 181* S Hwy 94 Junction 30 K
City or Steedman 4.5 ml. # 203* SSW 42 L
Callaway Electric Cooperative Utility 4.4 ml. # 230* SW Pole No. 06326 i.
l
4 Boy. 4 TA8LE 6 (Continued 1 i
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Station Code Sectqr Site DescrIDt lon Location 12 M
D. Bartley Fara 5.1 al. 8 241* WSW 41 N
Callaway Electric Cooperative utility 4.8 mi. e 227' W Pole No. 18239 40 P
Callaway Electric Cooperative Utility 4.2 mi. 8 291* WNW Pole No. 18145 5
39 Q
Callaway tiectric Cooperative utility 5.4 ml. e 312' NW Pole No. 17516 38 R
Callaway Electric Cooperative Utility 4.5 ml. # 334' NNW Pole No. 34708 Eight Stations to be placed in special interest areas such as population centers, nearby resi-donces, schools, and in 1 or 2 a rea s to se rve a s cont rol sta t ions.
33 Ci ty or llans Pra i r ie 7.3 mi. e 271* W 31 City of Hokane 7.6 ml. # 218* SW 26 Town of Americus 12.1 al. 8 82* E 27 Town or 81urrton 9.5 ml. 8 112* ESE 35 City or Toledo 5.8 al. e 340' NNW 23 City or Yucatan 6.7 el. # 14' NNE 11 City of Portland 5.0 ml. e 13o* SE 20 City of Readsville 4.8 al. e 45' NE 34 ( P-Con t ro l )
2.5 Miles South of O and C 9.5 ml. e 291* WNW Junction 1 (Q-Control)
City Limits or Fulton on Itwy Z 10.6 ml. 8 311* NW PoYm M TABtE 6 (Continued)
RApR LOGICAL ENVIRONMENTAL MONITORING PROGRAM Station Cod 2_
Sector Site Description Location
- 2. Airborne Radiolodine Canistegl Radiolodine and Samples from rive locations Continuous operations of Analyze at least once Pa rt icula tes sampl'er with sasple per 7 days for 1-131.
col. rction as required by dust loading, but at least once per 7 days.
Three samples f rom close to the three SITE BOUNDARY locations, Pa rticula te Sampler:
in dirrerent sectors, of the highest calculated annual ave rage Analyze for gross beta g round level D/Q.
radioactivity > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change. Perform gamma isotopic analysind on those samples for which the gross beta activity i s > 10 times the yearly mean of control samplos.
Pe rfo rm gamma isotopic analysis 8 on composite samples (by location) at least once per 92 days.
A-1 0
Primary Meteorological Tower 1.3 mi. # 76* ENC A-8 8
County Road 4t8, 0.9 mi.
.9 mi. # 20* NNE South of Highway 0 B-3 A
O.6 mile east or Highway O 1.9 al. # 355' NNW and CC Junction One sample f rom the communi ty with the highest D/Q A-9 R
Community or Reform 1.7 mi. e 336' NNW One sample from a control location, as for example 15-30 km distant and in the luast prevalent wind d i rec t ion.
Rev. 4 T ABLE 6 (Continuedl RADIOLOGICAL (NVIRONMENTAL MONITOHING PROGRAM Station Code Secto r Site Cescription Location A-7 Q
C. Bartley rare 9.5 mi. 4 312* NW
- 3. Waterborne
- a. Surface
- One sample upstream Composite samplef over a Gamma Isotopic analysisd period of less than or of each sample.
Tritium equal to 31 days, analysis or composite sample at least once 501 H
84 rect upstream of discharge, 4.8 al. # 144* SE
~
north bank One sample downstream S02 G
1.1 elles downstream or discharge, 5.2 al. # 133* SE north bank
- b. Drinking One sample or each of Composite sample over I-131 analysis on each one to three or the 2-week period when composite when the dose nearest water supplies 1-131 analysis is calculated for the consumption.
within 10 miles downstream, pe r fo rmed, monthly or the wa te r i s g rea te r that could be irTected by composite otherwi se.
than 1 arem per year its discha rge.
Composite for gross beta and gamma isotopic analysis One sample from a control monthly. Composite for location.
tri tium analysi s quarterly.
As there are no drinking water intakes within 10 miles downstream of the discharge point, the drinking water pathway a s currently not included as part or the Callaway Plaut Radiological Environmental Monitoring Program. Should future water intakes be constructed within 10 river miles downstream of the discharge point, then the program will be revised to include this pathway.
(Rer. 9.6.6)
- c. Sediment One sample f rom downstream Semiennually Camma isotopic analysis (d) from area with existing or semiannually.
Shoreline potential rec rea t iona l value. !
Rev. 4 TABLE 6 (Continued)
RAOIOLOGICAL E NVIRONMENTAL HONITORING PROGRAM Station Code Sector 11Le_Pescription Location C
C 1.0 river mile downstream 5.1 al. # 135' SE of dischargo, north bank 4.
Inges';on
- a. Misk Samples from milking animals Semimonthly when Gamma isotopic ( d) and 1-131 in three location within anicals are on analysis semimonthly when I
5 km distance having the pasture, monthly at animals are on pasture; h8 ghost dose potential g.
fr other times.
monthly at other times.
there are none, then one sansee f rom milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem por year One sample from milking animals at a costrol location, 15 to 30 km distant and in the least prevalent wind direction.
Due to a lack of allk animals which satisfy these requirements, the milk pathway is currently not included as a part of the Callaway Plant Radiological Environmental Honitoring Prog ram.
Should the Annual Land Use Census identify the existence of milking animals in locations which satisfy these requirements, then the program will be revised to include this pathway.
b.
Fish one sample of each Sample in season, or Gamma isotopic analysisd comme rc ia l ly and semiannually if they on edible portions.
recreationally important a re not seasonal.
species in vicinity of plant discharge area.
C G
1.0 river mile downstream 5.1 al. # 135' SE o f d i scha rgo, north bank One sample or same species in a rea s no t influenced by plant discharge.. _ _ __ _ _.
i
?
s s
1 3
)
1 d
I
(
s d
e n
s a
y l
)
)
an 8
d no
(
(
ait c
c 4
lCr i
ip o
p pp o
o t
t t
v oe o.
o.
e sl ss ss R
ib Ii ii s
s i
n ay W
ay E
ad ihs t
ma N N ma W
S me ml N
ml S
mon n
an an S
Co ita io Ca Ga
'4
'6 4
wd 5
e p
4 5 4
1 dd 3 3 2
euee 2
e gl rg e e o
h anta l
.. le e
n
)
rcur e
(
hirh b
l l
b i
is c oc) a a a l
m t
a l
a t
syfs7 l
8 8 i 5
9 s
il i
i c
e dtdd7 a
a ol 4
v nl v
1 1
v 1
r neue9 a
a M
a eroh A
h erhtd n
n R
bus n e
e G
f c fa h
h O
o e
.o w
w 6
R vt P
e aomm.
ly ly m
hnaa7 G
re h
h N
i ssgr9 t
t t
I eiot n
n R
t t
rs.
o o
O A
sePnf M
M i
T ap we d
I wygoR e
N tnd(
u O
t i i
M ners n
t L
lal oee ptl p n
A p mii y o
T anmt C
N dso 0
Mre 8
f E
ius el M
6 N
qil vp O
ihaim E
R r
lttra s
sl L
I o
,n B
V h
e0 na A
M m
ctm1 s oou winQ T
f a
inn i ttn/t e
hionh L
rk a
n worit aaDo ro A
tn e de pih nfc n
rat C
sa r yi e n vte ooodl oe ed 5hn G
u hr q
gEwu fthl ees I
pb abub ienid i
l tvi h
1 ti oacece cd wk O
n h c o ydi e rr l
e tatil g aann L
o st a nel v ealdc l
I t
ler esat a thaen eseeid-n eowitit O
i o
s ahh accti rdg sedi ro nmo k
i in famgc wsic hnetrrnl fbrte n
m D
p A
m, ol oiis i gu o ti v s r p u p m e o gnlr r
r crrhe. yd o r t k
eo om.
r r r
aais a
s eg se eosd otaatsgsd f
r leantv c
re ll l t f
rr tra a a e
vr pasi nag dhine neene e
pll oseni.
F e frwtd b d
iiroge t
D ia mptsiwr etdos sel nehekm r n m e t d pi n m t
e c scu rth afR v
ler rggl r e a aia tir e
rh aici a
t aci odneiaio k h sstmtcl o l
i
- 6. i ndtenc igo ee prawrhrmf c e e k s e pf z
t s
eioatas tbr mroor e r e e eeg armr a S
0d nrrhali rmn airrifvfe B M nhe0eiae l
l O p pt w pd raase S d b gd o ai p Otv3ldsp iel eb rPk st al r
asytl o
enani t
rwwiw c
s aoa e
t dl rm ea R A L
S H
c o
l u
nsatr d
eCag o
el wo r
rie r
P amhnp to d
er ie n
o refth oe o
evoat id F
hi g
to trtinrre 6 7 3
aC t
c s0arh S
A A 5 pi t V V V
!l
R TABLE 6 fcontinus..
TABLE NOTATION (a)
Devia t ions a re pe rmi t ted f rom the required sampling schedule if specimens are unobtalpable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons.
O r specimens are unobtainable due to sampling equipment ma t runction, every errort sha11 be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report.
It is recogn!2Jd that, at times, it may not be possible or practical to continue to obtain samples-or the media or choice at the cost desired location or time.
In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program.
Identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining repiccoment samples in the next Semi-Ane*al Hadioactive Errluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).
(b)
One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place or, or in addition to, integ rating dosimeters. For the purpose or this table, a thermoluminescent dosloeter (ILD) is considered to be one phosphor; two or more phosphors in a pachot are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The 40 stations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limittations; e.g., at an ocean site, some sectors will be over water so that the number of dosimeters may be reduced accordingly. The frequency or analysis or readou. for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal rading.
(c)
The purpose of this.amplo is to obtain background informatin. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted.
(d)
Gamma isotopic analysis is defined as the identification and quantification or gamma-emitting radionuclides that may be attributable to the effluents from the facility.
(e)
The "upstream" sample shall be taken at a distance beyond significant influence or the di scha rge.
The "downstream" sample shall be taken in an a rea beyond, but near the mixing zone.
(f)
In this program, constant volume sample aliquots are collected at t i me i nte rva l s tha t a re short (e.g.,
hourly) relative to the compositlog period (e.g., monthly).
(g)
The dose shall be calculated for the maximum organ and age group. using the methodology and parameters in the 00CM.
(h)
I f ha rvest occurs more than once a yea r, sampling shall be performed during each discrete ha rvest.
Or ha rvest occurs cont kauously, sampling shall be monthly. Attention shall be paid to including samples or-tuberous and root food products...
1 lh
,llIlll llll 4
)
v tt e
ce 0 0 0 R
uw 0 0 0 0,
0, d
1 S
o, E
rg 1
2 L
Pk P
/
M dl A
oC S
op F(
L d
A e
T s
N
)
u E
l M
/
s N
kl i
O lC 0
p 3
0 0 R
i l
l M(
3 6 7 3
/
Y lC N
E p
N 0
I t
0 e
0, S
w N
0 O
0 0 0 0 0 0 3
0 0 0 0 0 0 I
)
0, 0,
0, 0,
0, 0,
r T
s g
A o
l k
R e
/
0 0 0 0 1
2 T
v hl 3
1 3
1 e
7 N
e sC u
E L
p i
l E
C F(
a L
N g
v B
O n
A C
i a
T t
Y r
e s
T o
t e
2 I
p a
l 8
V e
l) p I
R u3 m
T cJ a
C i/
s A
tl O
rC r
ap e y DI P(
t t
A 9 0 0 a i 1
2 w v R
es ne 0
i H
rs e
t 0
oa c c F
bC a a r
f S
ir r r L
Ao u e E
s t
V h
E r
g L
o u F
a G
d N
I
. s T
s u R
0 0 0 0 0 0 2 0 0 0 e
l O
0 0 0 0 0 0 3
5 0 l
p 3 4 2
p P
)
0, 0,
0, 4
m t
E l
R r/
0 1
1 a n ei 2
s e tC r
ap r a W(
e p
ta w y t
g i
n v i i 0
k t
s 4 9 8 0 -
3 3
3 i c 5
4 n
9 1
4 7 1
a r
i 3 5 5 5 6 b 1
1 1
a d
l s
N L
a y
H n e o o -
l s s -
r t
M f
C C r C C a o o l
a Z
B F
T nA l
llll1lllll ll1ill iIl i'
i.
11l
Rnv. 4 TABLE 8 (CONTINUED)
TABLE NOTATION (a)
The LLD-i;s defined for purposes of compliance with the Radiological Effluent Technical Spe-cifications as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, 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):
LLD =
4.66 Sb E 'V*
2.22
'Y
- oxp (-lat)
Where:
LLD =
The lower limit of detection as defined above (as picocurie per unit mass or volume).
Sb=
The standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute).
E=
The counting efficiency (as counts per disintegration).
V=
The sample size (in units of mass or volume).
2.22 =
The number of disintegrations per minute per picocurie.
Y=
The fractional radiochemical yield (when applicable).
X=
The radioactive decay constant for the par-ticular radionuclide and, l 1
Rsv. 4 At =
the elapsed time between sample collection (or end of the smaple collection period) and time of counting (for environmental samples, not plant effluent samples).
Typical values of E, V, 7 and At shall be used in the calculations.
It should be recognized that the LLD is defined as a a priori (before the fact) limit representing the capa-bility of a measurement system and not as an a posteriori (after the fact) limit fer a particular measurement.
Analyses are performed in such a manner that the stated LLDs are achieved under routine conditions.
Occassionally background fluctuations, unavoidable small sample sizes, the presence of inter-fering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.
(b)
This list does not mean that only these nu-clides are to be considered.
Other pesks that are identifiable, together with those of the above nuclides, shall also be anlayzed and reported in the Annual Radiological Environ-mental Operating Report.
(c)
Required detection capabilities for thermolu-minescent dosimeters used for environmental measurements shall be in accordance with the reccommendations of Regulatory Guide 4.13, I
Revision 1, July 1977.
8';
32 E!
E s>h. o' 5 2
m l
j'i i'jllj i
.; i g'l 33 vZ l3o<..
h,f
.J1 o
t o
E d
/
[ !/ w$
= " "
~~
--.),
ggg.....n
?!h \\
w~
]> v>a
.t o<>v w
n.
y
/,.
n p
, r * )
\\~ / k F"
_tll N.a'Mjhy s:5 1
8
/:
8 %id
- A.
s
\\..
g,:
- 8/<
~
x 3
l, h
=
y
~y...
th
.m f) d6;g i
A [ ',\\. jj
/
/
x
m l
NW
' NNW \\
g, N NNE
~ENE C E FO R,Mg
'B-3
[
f N
A-9 h46 N
A-8 c
(_ _,
RESTRICTED AREA BOUNDARY WNW 47 (SITE BOUNDARY FOR GASEOUS EFFLUENT A-1 45
-Bpoj 48 J5 _I f
52 E
[
448 e
7
/
WSW N
850
\\
78 ESE
\\
SW COUNTY f
R D. 4 5 9 -
+ R AILRO AD SPUR s
OUNT'Y RD.468 RTLAND
/
[
my y
SSw y
o i
e
\\
9 CHUTE
\\E STEEDMAN O
2000 0
20d0 UNION ELECTRIC CO.
SSE C ALLAWAY PLANT AIRBORNE & TLD LEGEND.
5 MILE RADIUS
NW NNW N
NNE NE WNW ENE xN
/
NREFORM
/
W
\\
[
E SIT
)
A, Ny
'{p o
D@
WSW o
ESE v
/
o SE 1.8+&@
~
Of*
O SO1
+
\\
'='
,.. m.,)
\\@*
AG
' MISSOURI RIVER SSW s%g @ ss g
DISCHARGE POINT 4fg#
s RA to (RESTRICTED AREA BOUNDARY FOR EOLum RtvER LIQUID EFFLUENTS)
CH AMOIS LEGEND:
6 TOWNS
-- -INTERMITTENT STRE AMS CONTINUOUS STREAMS 4
AQUATIC SAMPLING STATIONS 1
o, j
O COMPOSITE SURFACE WATER MILES UNION ELECTRIC CO.
CALLAWAY PLANT LOC ATION OF AQUATIC S AMPLING STATIONS FIGURE 5.2 A REV 4
-A
_,,p.+1-
--,w
--e w
w
8!
O.
C T
8 4
C T
N A
v CA U
e 4
IL Q'
n v S RP A
m S
T i
G f
E CY F
YO a
EA O
s S
sIW M
LW a.
1 ut s 4 l
o uR EA N
e s
0 L
O A
OE N
I t
H
- t. C A L
T T
C.
S&W OA A
n T
IC C
u N
o T
S U'
O s
L e
4 6
4 j
4A KER RIA A.E N
GUW s
O A
l lA T
S tau S SR O M NE)
SGH OTA E4A I
A 2 T
s WF AW.6 N
Mt T
PL l", !
S E ).
T
- y HAf NN E
EF Y OE HO E
IDM T
S S
UT RE8 WS H t
/
EWP ECE V
I X
cAf
- d N E A TE p,'o A /
U O (H rHUG t
I O
- o i*
OW EN
'A' E
W E
N S
EVAH W
EN
\\
i de E
[H t
N AM LH E
HS E
A
/_ D A
uK eS uA OH S
SB A
SE MN.
s
.T FOC i E
7 d
Lf 9Ui 1
2 S,HS 8,0 h
H
)
Y E
d EY N
P E
s Lv!
N A
l
(
NHO3 iU i
M.
i ECeS nSS s
i A Q
o s
4 m
FHt OPA E
n4 u
AK A
1 i
5 E
g0 c
H.
T S
HGHi b*.,
\\
'CH g
S OOTU DO YYS 0
b J. HEW 1
H t
ARs 3 i
E S
W \\"*
W/
\\
SvO N
W i
UHT S
W N
N W
3 N
i
E
- ' o 3 a. s 5
ou o >. go W<
f 4
N O
w W
l}
x3 83 i
~;k E et 1:
5*
- ll l!
I i'
u i 'l t
wZ 100=
! n!.
.a!!
r a
I-I
)*
l
/pff.
~
m a rs r--Sp.wm...
lj
%']
M l
g el!
o
\\
l
!
- material, t
- ions of wind speed wind direction, and atmospheric stability.*
- In lieu of submission, the Union Electric Company has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.
9.0 REFERENCES
9.1 Title 10, "Energy", Chcpter 1, Code of Federal Regulations, Part 20; U.S. Government Printing Office, Washington, D.C. 20402.
9.2 Title 10, "Energy", Chapter 1, Code of Federal Rogulations, Part 50, Appendix I; U.S. Govern-ment Printing Office, Washington, D.C. 20402.
9.3 Title 40, "Protection of Environment", Chapter 1, Code of Federal Regulations, Part 190; U.S.
Government Printing Office, Washington, D.C.
- 20402, i
9.4 Callaway Technical Specifications, Section 3.3.3.9, 3.3.3.10, 3/4.11, 3/4.12, and 6.9.1.7 as submitted to the U.S. Nuclear Regulatory Commisation, August 1983.
9.5 Communications 9.5.1 Letter NEO-54, D.W. Capone to S.E. Milten-berger, dated January 5, 1983; Union Electric Company correspondence.
9.5.2 Letter BLUE 1285, "Callaway Annual Average X/Q and D/Q Values", J. H. Smith (Bechtel Power Corporation), to D. W. Capone (Union Electric Co. ), dated February 27, 1984.
l 9.5.3 (Reference Deleted) 9.5.4 Letter BLUE 1232, "Callaway Annual Average X/Q Values and "S" Values", J. H. Smith (Bechtel Power Corporation) to D. W. Capone (Union Elecetric Co.), dated February 9, 1984.
9.5.5 Letter BLUE 1358, "Comparison of Callaway Plant offsite Dose Calculations for Routine Effluents", J.H.
Smith (Bechtel Power Corpora-tion) to D.W. Capone (Union Electric Company),
dated March 22, 1934.
l 9.5.6 Privato Communication, H.C.
Lindeman & B.F.
l Holderness, August 6, 1986 R^v.
4 9.6 Union Electric Company Callaway Plant, Unit 1, Final Safety Analysis Report.
9.6.1 Section 11.5.2.2.3.1 9.6.2 Section 11.5.2.2.3.4 9.6.3 Section 11.5.2.1.2 9.6.4 Section 11.5.2.2.3.2 9.6.5 Section 11.5.2.2.3.3 9.6.6 Section 11.2.3.3.4 9.6.7 Section 11.2.3.4.3 9.6.8 Section 11.5.2.3.3.1 9.6.9 Section 11.5.2.3.3.2 9.6.10 Section 11.5.2.3.2.3 9.6.11 Section 11.5.2.3.2.2 9.6.12 Section 2.3.5 9.6.13 Section 2.3.5.1 9.6.14 Section 2.3.5.2.1.2 9.6.15 (Reference Deleted) 9.6.16 (Reference Deleted) 9.6.17 Section 9.2.6 9.6.18 Section 9.2.7.2.1 9.6.19 Section 6.3.2.2 9.6.20 Table 11.1-6 l
l 9.6.21 Table 9.4-6 i
l 9.6.22 Table 9.4-8 L
9.6.23 Table 9.4-11 1
(
- 100 -
Re.v. 4 9.6.24 Table 9.4-12 9.6.25 Table 2.3-66 9.6.26 Table 2. 3-68 9.7 Union Electric Company Callaway Plant Environ-mental Report, Operating License Stage.
9.7.1 Table 2.1-19 9.7.2 Section 2.1.2.3 l 9.7.3 (Reference Deletod) 9.7.4 Section 2.1.3.3.4 l 9.7.5 (Reference Deleted) 9.7.6 Section 5.2.4.1 9.7.7 Table 2.1-19 9.8 U.S. Nuclear Regalatory Commission, "Preparation of Radiological Effluent Techni-cal Specification For Nuclear Power Plants",
USNRC NUREG-0133, Washington, D.C. 20555, oc-tober 1978.
9.8.1 Pages AA-1 through AA-3 9.8.2 Section 5.3.1.3 9.8.3 Section 4.3 9.8.4 Section 4.3.1 9.8.5 Section 5.3.1.5 9.8,6 Section 5.1.1 9.8.7 Section 5.1.2 9.8.8 Section 5.2.1 9.8.9 Section S.2.1.1 9.8.10 Section 5.3.1
- 101 -
o
Rev. 4 9.8.11 Section 3.8 9.8.12 Section 3.3 9.9 U.S. Nuclear Regulatory Commission, "XOQDOQ, Program For the Meterological Evaluation of Routine Effluent Releases At Nuclear Power Stations", USNRC NUREG-0324, Washington, D.C.
20555.
9.9.1 Pages 19-20 Subroutine PURGE 9.10 Regulatory Guide 1.111, "Methods For Estimat-ing Atmospheric Tr~ansport And Dispersion of Gaseous Effluents In Routine Releases From Light-Water-Cooled Reactors", Revision 1, U.S.
Nuclear Regulatory Commission, Washington, D.C.
20555, July, 1977.
9.10.1 Section c.1.b 9.10.2 Figures 3 through 6 9.10.3 Figures 7 through 10 9.10.4 (Reference Deleted) 9.10.5 Section c.4 9.11 Regulatory Guide 1.109, "Calculation of Annual Doses to Man From Routine Releases Of Reactor Effluents For the Purpose Of Evaluating Com-pliance With 10 CFR Part 50, Appendix I",
Revision 1, U.S. Nuclear Regulatory Commis-sion, Washington, D.C.
20555, October 1977.
9.11.1 Appendix C, Section 3.a 9.11.2 Appendix E, Table E-15 9.11.3 Appendix C, Section 1
- 102 -
~-
R9v. 4 9.12 U.S. Nuclear Regulatory Commission, "Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190)", USNRC NUREG-0543, Washington, D.C.
20555, January 1980.
9.12.1 Section-I, Page 2 9.12.2 Section IV, Page 8 9.12.3 Section IV, Page 9 9.12.4 Section III, Page 6 9.13 U.S. Nuclear Regulatory Commission, "Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors", USNRC NUREG-0472, Draft Revision 3, Washington, D.C.
20555, January 1983.
9.13.1 Definition 1.7, Page 1-2 9.14 Management Agreement for the Public Use of Lands, Union Electric Company and the State of Missouri Department of Conservation, December 21, 1982.
9.14.1 Exhibit A l 9.15 (Reference Deleted) 9.16 Miscellaneous-References 9.16.1 Drawing Number M-109-0007-06, Revision 5.
l 9.16.2 HPCI 87-01, "Determination of Annual Average l
Dispersion Parameters at the Owner Controlled l
Area Fence", January 28, 1987.
l 9.16.3 HPCI 87-02, "1986 Land Use Census and Disper-l sion Parameters", January 28, 1987.
l 9.16.4 UENE Safety Analysis Calculation 87-001-00.
- 103 -
r
. ~.
Riv. 4 9.17 U.S. Nuclear Regulatory Commission, *XOQDOQ:
Computer Program for the Meterological Evalua-tion of Routine Effluent Releases at Nuclear Power Stations", USNRC NUREG/CR-2929, Septem-be r, 1982, Washington, D.C. 20555.
.a 9.17.1 Section 4.1, "Subroutine ANNUAL", pages 23-25, 9.17.f' Section 4.1, "Subroutine ANNUAL", page 25.
9.17.3 Section 4.2, "Subroutine DEPOS", page 26, 9.17.4 Section 4, "Subroutine PURGE", pages 27 and 28.
W
/
104 -
J